Sample records for radioactively contaminated sites

  1. RESRAD Computer Code- Evaluation of Radioactively Contaminated Sites

    Broader source: Energy.gov [DOE]

    The evaluation of sites with radioactive contamination was a problem until the RESidual RADioactivity (RESRAD) Computer Code was first released in 1989.

  2. Geochemical information for sites contaminated with low-level radioactive wastes. III. Weldon Spring Storage Site

    SciTech Connect (OSTI)

    Seeley, F.G.; Kelmers, A.D.

    1985-02-01T23:59:59.000Z

    The Weldon Spring Storage Site (WSSS), which includes both the chemical site and the quarry, became radioactively contaminated as the result of wastes that were being stored from operations to recover uranium from pitchblende ores in the 1940s and 1950s. The US Department of Energy (DOE) is considering various remedial action options for the WSSS. This report describes the results of geochemical investigations carried out at Oak Ridge National Laboratory (ORNL) to support these activities and to help quantify various remedial action options. Soil and groundwater samples were characterized, and uranium and radium sorption ratios were measured in site soil/groundwater systems by batch contact methodology. Soil samples from various locations around the raffinate pits were found to contain major amounts of silica, along with illite as the primary clay constituent. Particle sizes of the five soil samples were variable (50% distribution point ranging from 12 to 81 ..mu..m); the surface areas varied from 13 to 62 m/sup 2//g. Elemental analysis of the samples showed them to be typical of sandy clay and silty clay soils. Groundwater samples included solution from Pit 3 and well water from Well D. Anion analyses showed significant concentrations of sulfate and nitrate (>350 and >7000 mg/L, respectively) in the solution from Pit 3. These anions were also present in the well water, but in lower concentrations. Uranium sorption ratios for four of the soil samples contacted with the solution from Pit 3 were moderate to high (approx. 300 to approx. 1000 mL/g). The fifth sample had a ratio of only 12 mL/g. Radium sorption ratios for the five samples were moderate to high (approx. 600 to approx. 1000 mL/g). These values indicate that soil at the WSSS may show favorable retardation of uranium and radium in the groundwater. 13 references, 13 figures, 10 tables.

  3. Radioactive Waste Management and Environmental Contamination Issues at the Chernobyl Site

    SciTech Connect (OSTI)

    Napier, Bruce A.; Schmieman, Eric A.; Voitsekhovitch, Oleg V.

    2007-11-01T23:59:59.000Z

    The destruction of the Unit 4 reactor at the Chernobyl Nuclear Power Plant resulted in the generation of radioactive contamination and radioactive waste at the site and in the surrounding area (referred to as the Exclusion Zone). In the course of remediation activities, large volumes of radioactive waste were generated and placed in temporary near surface waste-storage and disposal facilities. Trench and landfill type facilities were created from 1986 to 1987 in the Chernobyl Exclusion Zone at distances 0.5 to 15 km from the NPP site. This large number of facilities was established without proper design documentation, engineered barriers, or hydrogeological investigations and they do not meet contemporary waste-safety requirements. Immediately following the accident, a Shelter was constructed over the destroyed reactor; in addition to uncertainties in stability at the time of its construction, structural elements of the Shelter have degraded as a result of corrosion. The main potential hazard of the Shelter is a possible collapse of its top structures and release of radioactive dust into the environment. A New Safe Confinement (NSC) with a 100-years service life is planned to be built as a cover over the existing Shelter as a longer-term solution. The construction of the NSC will enable the dismantlement of the current Shelter, removal of highly radioactive, fuel-containing materials from Unit 4, and eventual decommissioning of the damaged reactor. More radioactive waste will be generated during NSC construction, possible Shelter dismantling, removal of fuel containing materials, and decommissioning of Unit 4. The future development of the Exclusion Zone depends on the future strategy for converting Unit 4 into an ecologically safe system, i.e., the development of the NSC, the dismantlement of the current Shelter, removal of fuel containing material, and eventual decommissioning of the accident site. To date, a broadly accepted strategy for radioactive waste management at the reactor site and in the Exclusion Zone, and especially for high-level and long-lived waste, has not been developed.

  4. Geochemical information for sites contaminated with low-level radioactive wastes: II. St. Louis Airport Storage Site

    SciTech Connect (OSTI)

    Seeley, F.G.; Kelmers, A.D.

    1985-01-01T23:59:59.000Z

    The St. Louis Airport Storage Site (SLASS) became radioactively contaminated as a result of wastes that were being stored from operations to recover uranium from pitchblende ores in the 1940s and 1950s. The US Department of Energy is considering various remedial action options for the SLASS under the Formerly Utilized Site Remedial Action Program (FUSRAP). This report describes the results of geochemical investigations, carried out to support the FUSRAP activities and to aid in quantifying various remedial action options. Soil and groundwater samples from the site were characterized, and sorption ratios for uranium and radium and apparent concentration limit values for uranium were measured in soil/groundwater systems by batch contact methodology. The uranium and radium concentrations in soil samples were significantly above background near the old contaminated surface horizon (now at the 0.3/sup -/ to 0.9/sup -/m depth); the maximum values were 1566 ..mu..g/g and 101 pCi/g, respectively. Below about the 6/sup -/m depth, the concentrations appeared to be typical of those naturally present in soils of this area (3.8 +- 1.2 ..mu..g/g and 3.1 +- 0.6 pCi/g). Uranium sorption ratios showed stratigraphic trends but were generally moderate to high (100 to 1000 L/kg). The sorption isotherm suggested an apparent uranium concentration limit of about 200 mg/L. This relatively high solubility can probably be correlated with the carbonate content of the soil/groundwater systems. The lower sorption ratio values obtained from the sorption isotherm may have resulted from changes in the experimental procedure or the groundwater used. The SLASS appears to exhibit generally favorable behavior for the retardation of uranium solubilized from waste in the site. Parametric tests were conducted to estimate the sensitivity of uranium sorption and solubility to the pH and carbonate content of the system.

  5. Radioactive Contamination of Danish Territory

    E-Print Network [OSTI]

    Risø-R-462 Radioactive Contamination of Danish Territory after Core-melt Accidents at the Barsebäck;#12;RIS0-R-462 RADIOACTIVE CONTAMINATION OF DANISH TERRITORY AFTER CORE-MELT ACCIDENTS AT THE BARSEBACK. An assessment is made of the radioactive contamination of Danish territory in the event of a core-melt accident

  6. Radioactive Contamination of Danish Territory

    E-Print Network [OSTI]

    » & Risø-R-462 Radioactive Contamination of Danish Territory after Core-melt Accidents 1982 Risø National Laboratory, DK-4000 Roskilde, Denmark #12;RISØ-R-462 RADIOACTIVE CONTAMINATION contamination of Danish territory in the event of a core-melt accident at the Barseback nuclear power plant

  7. area contamination site: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    and Radium-226 are the predominant radioactive contaminents on Formerly Utilized Sites Remedial Action Plan (FUSRAP) sites. ** The half-life of a radioactive element is the time...

  8. Use of a commercial ranging system in field surveys of radioactively contaminated sites

    SciTech Connect (OSTI)

    Worth, G.M.; Crowell, J.M.; Meddles, A.D.; Jarrett, J.D.; Wolf, M.A.; Umbarger, C.J.; Moyer, C.

    1984-01-01T23:59:59.000Z

    Now, the adaptation of a commercial ranging and tracking system interfaced to these instruments and to an advanced computer graphics system promises another major improvement to the automation of data collection. Contour maps with radiation isopleths and the x-y position of up to eight instrument operators superimposed thereon can be displayed in near real time. A bidirectional data link offers a further improvement in simulation of, and training for, field surveys since previously collected or computer simulated radiation data as a function of position can be transmitted back to the same survey instrument and displayed to the operator in a manner indistinguishable from real-time data. Additionally, simulated instrument malfunctions such as low battery, detector failure, or total failure can be commanded to occur to evaluate operator response to unusual occurrences under the stress of field conditions. This training mode will greatly improve the ability to simulate situations and to train and evaluate operations personnel while eliminating the need to use special sites and potentially hazardous contamination simulants as are used now.

  9. Final report: survey and removal of radioactive surface contamination at environmental restoration sites, Sandia National Laboratories/New Mexico. Volume 1

    SciTech Connect (OSTI)

    Lambert, K.A.; Mitchell, M.M. [Brown and Root Environmental, Albuquerque, NM (United States); Jean, D. [MDM/Lamb, Inc., Albuquerque, NM (United States); Brown, C. [Environmental Dimensions, Inc., Albuquerque, NM 87109 (United States); Byrd, C.S. [Sandia National Labs., Albuquerque, NM (United States)

    1997-09-01T23:59:59.000Z

    This report describes the survey and removal of radioactive surface contamination at Sandia`s Environmental Restoration (ER) sites. Radiological characterization was performed as a prerequisite to beginning the Resource Conservation and Recovery Act (RCRA) corrective action process. The removal of radioactive surface contamination was performed in order to reduce potential impacts to human health and the environment. The predominant radiological contaminant of concern was depleted uranium (DU). Between October 1993 and November 1996 scanning surface radiation surveys, using gamma scintillometers, were conducted at 65 sites covering approximately 908 acres. A total of 9,518 radiation anomalies were detected at 38 sites. Cleanup activities were conducted between October 1994 and November 1996. A total of 9,122 anomalies were removed and 2,072 waste drums were generated. The majority of anomalies not removed were associated with a site that has subsurface contamination beyond the scope of this project. Verification soil samples (1,008 total samples) were collected from anomalies during cleanup activities and confirm that the soil concentration achieved in the field were far below the target cleanup level of 230 pCi/g of U-238 (the primary constituent of DU) in the soil. Cleanup was completed at 21 sites and no further radiological action is required. Seventeen sites were not completed since cleanup activities wee precluded by ongoing site activity or were beyond the original project scope.

  10. Uranium-238, Thorium-230, and Radium-226 are the predominant radioactive contaminents on Formerly Utilized Sites Remedial Action Plan (FUSRAP) sites.

    E-Print Network [OSTI]

    US Army Corps of Engineers

    Uranium-238, Thorium-230, and Radium-226 are the predominant radioactive contaminents on Formerly of time. Uranium-238 decays by alpha emission into thorium-234, which itself decays by beta emission-life* thorium-234 24.1 days protactinium-234m 1.17 minutes uranium-234 244,000 years radon-222 3.82 days

  11. Managing contaminated sites

    SciTech Connect (OSTI)

    Asante-Duah, D.K.

    1997-12-31T23:59:59.000Z

    This book summarizes the generic principles of contaminated site management. The book walks the reader through contaminated site identification, risk assessment and the evaluation of remediation alternatives. The book is divided into two major sections, problem diagnosis and development of site restoration. In problem diagnosis, the general principles of site investigation are discussed, including the objectives and differences between tier 1,2, and 3 investigations. The principles of data collection and analysis are presented. A small quantitative discussion of statistical analysis is presented but in keeping with the objectives of the text is not sufficient comprehensive or detailed to provide much of a guide for the practitioner. Chapters on contaminant fate and transport processes and risk assessment help the reader understand the role of these issues in site investigation and remedial planning. A chapter is also included on elements of a site characterization activity, which summarizes some of the key considerations in conducting a site investigation.

  12. Tracer-level radioactive pilot-scale test of in situ vitrification for the stabilization of contaminated soil sites at ORNL

    SciTech Connect (OSTI)

    Spalding, B.P.; Jacobs, G.K.; Naney, M.T. [Oak Ridge National Lab., TN (United States); Dunbar, N.W. [New Mexico Bureau of Mines and Mineral Resources, Socorro, NM (United States); Tixier, J.S.; Powell, T.D. [Pacific Northwest Lab., Richland, WA (United States)

    1992-11-01T23:59:59.000Z

    A field demonstration of in situ vitrification (ISV) was completed in May 1991, and produced approximately 12 Mg of melted earthen materials containing 12.7 mCi of radioactivity within 500 g of sludge in amodel of an old seepage trench waste disposal unit. Past waste disposal operations at Oak Ridge National Laboratory have left several contaminated seepage sites. In planning for remediation of such sites, ISV technology has been identified as a leading candidate because of the high risks associated with any retrieval option and because of the usual high quality of vitreous waste form. Major isotopes placed in the test trench were {sup 137}Cs and {sup 90}Sr, with lesser amounts of {sup 6O}Co, {sup 241}Am, and {sup 239,240}Pu. A total of 29 MWh of electrical power was delivered to the ground over a 5-day period producing a melt depth of 8.5 ft. During melting, 2.4% of the {sup 137}Cs volatilized from the melt into an off-gas containment hood and was captured quantitatively on a high efficiency particulate air filter. No volatilization of {sup 90}Sr, {sup 241}Am, or {sup 239,240}Pu was detected and > 99.993% retention of these isotopes in the melt was estimated. The use of added rare earth tracers (Ce, La, and Nd), as surrogates for transuranic isotopes, led to estimated melt retentions of >99.9995% during the test. The molten material, composed of the native soil and dolomitic limestone used for filling the test trench, reached a processing temperature of 1500{degrees}C. Standardized leaching procedures using Product Consistency Testing indicated that the ISV product has excellent characteristics relative to other vitreous nuclear waste forms.

  13. Tracer-level radioactive pilot-scale test of in situ vitrification for the stabilization of contaminated soil sites at ORNL

    SciTech Connect (OSTI)

    Spalding, B.P.; Jacobs, G.K.; Naney, M.T. (Oak Ridge National Lab., TN (United States)); Dunbar, N.W. (New Mexico Bureau of Mines and Mineral Resources, Socorro, NM (United States)); Tixier, J.S.; Powell, T.D. (Pacific Northwest Lab., Richland, WA (United States))

    1992-11-01T23:59:59.000Z

    A field demonstration of in situ vitrification (ISV) was completed in May 1991, and produced approximately 12 Mg of melted earthen materials containing 12.7 mCi of radioactivity within 500 g of sludge in amodel of an old seepage trench waste disposal unit. Past waste disposal operations at Oak Ridge National Laboratory have left several contaminated seepage sites. In planning for remediation of such sites, ISV technology has been identified as a leading candidate because of the high risks associated with any retrieval option and because of the usual high quality of vitreous waste form. Major isotopes placed in the test trench were [sup 137]Cs and [sup 90]Sr, with lesser amounts of [sup 6O]Co, [sup 241]Am, and [sup 239,240]Pu. A total of 29 MWh of electrical power was delivered to the ground over a 5-day period producing a melt depth of 8.5 ft. During melting, 2.4% of the [sup 137]Cs volatilized from the melt into an off-gas containment hood and was captured quantitatively on a high efficiency particulate air filter. No volatilization of [sup 90]Sr, [sup 241]Am, or [sup 239,240]Pu was detected and > 99.993% retention of these isotopes in the melt was estimated. The use of added rare earth tracers (Ce, La, and Nd), as surrogates for transuranic isotopes, led to estimated melt retentions of >99.9995% during the test. The molten material, composed of the native soil and dolomitic limestone used for filling the test trench, reached a processing temperature of 1500[degrees]C. Standardized leaching procedures using Product Consistency Testing indicated that the ISV product has excellent characteristics relative to other vitreous nuclear waste forms.

  14. Surface Contamination Surface contamination from radioactive isotopes is a source of background in the Borex-

    E-Print Network [OSTI]

    Chapter 5 Surface Contamination Surface contamination from radioactive isotopes is a source of background in the Borex- ino detector. Surface contaminants can be in the form of macroscopic dust particles contamination is primarily a problem because the radioactive contaminants can be trans- ferred from the surfaces

  15. Environmental remediation of contamination sites at the Hanford Site

    SciTech Connect (OSTI)

    Wittreich, C.D.; Johnson, W.L. [Westinghouse Hanford Co., Richland, WA (United States)

    1993-12-31T23:59:59.000Z

    Efforts currently are under way to remediate the 200 Areas of the US Department of Energy`s (DOE) Hanford Site in Washington State. Because of the complexity and extent of environmental contamination that has resulted from decades of hazardous and radioactive waste disposal practices, an innovative approach to remediating the site was required. A comprehensive study of waste disposal and environmental monitoring data with field investigations, referred to as the 200 Aggregate Area Management Study (AAMS) program, was conducted in 1992 to assess the scope of the remediation effort and to develop a plan to expedite the cleanup progress.

  16. Residual radioactive contamination from decommissioning: Technical basis for translating contamination levels to annual dose

    SciTech Connect (OSTI)

    Kennedy, W.E. Jr.; Peloquin, R.A. (Pacific Northwest Lab., Richland, WA (USA))

    1990-01-01T23:59:59.000Z

    This document describes the generic modeling of the total effective dose equivalent (TEDE) to an individual in a population from a unit concentration of residual radioactive contamination. Radioactive contamination inside buildings and soil contamination are considered. Unit concentration TEDE factors by radionuclide, exposure pathway, and exposure scenario are calculated. Reference radiation exposure scenarios are used to derive unit concentration TEDE factors for about 200 individual radionuclides and parent-daughter mixtures. For buildings, these unit concentration factors list the annual TEDE for volume and surface contamination situations. For soil, annual TEDE factors are presented for unit concentrations of radionuclides in soil during residential use of contaminated land and the TEDE per unit total inventory for potential use of drinking water from a ground-water source. Because of the generic treatment of potentially complex ground-water systems, the annual TEDE factors for drinking water for a given inventory may only indicate when additional site data or modeling sophistication are warranted. Descriptions are provided of the models, exposure pathways, exposure scenarios, parameter values, and assumptions used. An analysis of the potential annual TEDE resulting from reference mixtures of residual radionuclides is provided to demonstrate application of the TEDE factors. 62 refs., 5 figs., 66 tabs.

  17. Portsmouth Site Delivers First Radioactive Waste Shipment to...

    Office of Environmental Management (EM)

    Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal Facility in Texas Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal Facility in Texas...

  18. Distinguishing Between Site Waste, Natural, and Other Sources of Contamination at Uranium and Thorium Contaminated Sites - 12274

    SciTech Connect (OSTI)

    Hays, David C. [United States Army Corps of Engineers, Kansas City, Missouri, 64106 (United States)

    2012-07-01T23:59:59.000Z

    Uranium and thorium processing and milling sites generate wastes (source, byproduct, or technically enhanced naturally occurring material), that contain contaminants that are similar to naturally occurring radioactive material deposits and other industry wastes. This can lead to mis-identification of other materials as Site wastes. A review of methods used by the US Army Corps of Engineers and the Environmental Protection Agency to distinguish Site wastes from potential other sources, enhanced materials, and natural deposits, at three different thorium mills was conducted. Real case examples demonstrate the importance of understanding the methods of distinguishing wastes. Distinguishing between Site wastes and enhanced Background material can be facilitated by establishing and applying a formal process. Significant project cost avoidance may be realized by distinguishing Site wastes from enhanced NORM. Collection of information on other potential sources of radioactive material and physical information related to the potential for other radioactive material sources should be gathered and reported in the Historical Site Assessment. At a minimum, locations of other such information should be recorded. Site decision makers should approach each Site area with the expectation that non site related radioactive material may be present and have a process in place to distinguish from Site and non Site related materials. (authors)

  19. Remote video radioactive process evaluation, Savannah River Site

    SciTech Connect (OSTI)

    Heckendorn, F.M.

    1990-01-01T23:59:59.000Z

    Specialized miniature low cost video equipment has been effectively used in a number of remote, radioactive, and contaminated environments at the Savannah River Site (SRS). The equipment and related techniques have reduced the potential for personnel exposure to both radiation and physical hazards. The valuable process information thus provided would not have otherwise been available for use in improving the quality of operation at SRS.

  20. Remote video radioactive process evaluation, Savannah River Site

    SciTech Connect (OSTI)

    Heckendorn, F.M.

    1990-12-31T23:59:59.000Z

    Specialized miniature low cost video equipment has been effectively used in a number of remote, radioactive, and contaminated environments at the Savannah River Site (SRS). The equipment and related techniques have reduced the potential for personnel exposure to both radiation and physical hazards. The valuable process information thus provided would not have otherwise been available for use in improving the quality of operation at SRS.

  1. Fluvial Placement of Radioactive Contaminants a Weldon Spring Case Study

    SciTech Connect (OSTI)

    Meier, J.

    2002-02-26T23:59:59.000Z

    The operation of the Weldon Spring Uranium Feed Materials Plant in St. Charles, MO between 1958 and 1966 resulted in the migration and emplacement of radioactive contaminants into surface water drainage systems. Multiple drainage systems, receiving from a variety of waste discharge points, combined to create unique and unexpected depositional environment. Discovery and investigation of the depositional environments was a significant technical challenge due to the complex nature of sediment movement and emplacement. The objective of this investigation was to show that application of the knowledge of geomorphic processes is an essential element of a complete stream characterization, pursuant to risk analysis and remediation. This paper sets out to describe many of the expected and unexpected findings of the investigations by the Weldon Spring Site Remedial Action Project (WSSRAP) into the placement and rework of contaminated sediments in stream systems. Information from this paper will be useful to other agencies and contractor personnel faced with the challenge of locating and quantifying contaminated sediments in seemingly haphazard fluvial depositional conditions.

  2. Nevada Test Site 2000 Annual Data Report: Groundwater Monitoring Program Area 5 Radioactive Waste Management Site

    SciTech Connect (OSTI)

    Y. E.Townsend

    2001-02-01T23:59:59.000Z

    This report is a compilation of the calendar year 2000 groundwater sampling results from the Area 5 Radioactive Waste Management Site (RWMS). Contamination indicator data are presented in control chart and tabular form with investigation levels (IL) indicated. Gross water chemistry data are presented in graphical and tabular form. Other information in the report includes, the Cumulative Chronology for Area 5 RWMS Groundwater Monitoring Program, a brief description of the site hydrogeology, and the groundwater sampling procedure.

  3. Complexity of Groundwater Contaminants at DOE Sites

    SciTech Connect (OSTI)

    Hazen, T.C.; Faybishenko, B.; Jordan, P.

    2010-12-03T23:59:59.000Z

    The U.S. Department of Energy (DOE) is responsible for the remediation and long-term stewardship of one of the world's largest groundwater contamination portfolios, with a significant number of plumes containing various contaminants, and considerable total mass and activity. As of 1999, the DOE's Office of Environmental Management was responsible for remediation, waste management, or nuclear materials and facility stabilization at 144 sites in 31 states and one U.S. territory, out of which 109 sites were expected to require long-term stewardship. Currently, 19 DOE sites are on the National Priority List. The total number of contaminated plumes on DOE lands is estimated to be 10,000. However, a significant number of DOE sites have not yet been fully characterized. The most prevalent contaminated media are groundwater and soil, although contaminated sediment, sludge, and surface water also are present. Groundwater, soil, and sediment contamination are present at 72% of all DOE sites. A proper characterization of the contaminant inventory at DOE sites is critical for accomplishing one of the primary DOE missions -- planning basic research to understand the complex physical, chemical, and biological properties of contaminated sites. Note that the definitions of the terms 'site' and 'facility' may differ from one publication to another. In this report, the terms 'site,' 'facility' or 'installation' are used to identify a contiguous land area within the borders of a property, which may contain more than one plume. The term 'plume' is used here to indicate an individual area of contamination, which can be small or large. Even though several publications and databases contain information on groundwater contamination and remediation technologies, no statistical analyses of the contaminant inventory at DOE sites has been prepared since the 1992 report by Riley and Zachara. The DOE Groundwater Data Base (GWD) presents data as of 2003 for 221 groundwater plumes at 60 DOE sites and facilities. Note that Riley and Zachara analyzed the data from only 18 sites/facilities including 91 plumes. In this paper, we present the results of statistical analyses of the data in the GWD as guidance for planning future basic and applied research of groundwater contaminants within the DOE complex. Our analyses include the evaluation of a frequency and ranking of specific contaminants and contaminant groups, contaminant concentrations/activities and total contaminant masses and activities. We also compared the results from analyses of the GWD with those from the 1992 report by Riley and Zachara. The difference between our results and those summarized in the 1992 report by Riley and Zachara could be caused by not only additional releases, but also by the use of modern site characterization methods, which more accurately reveal the extent of groundwater contamination. Contaminated sites within the DOE complex are located in all major geographic regions of the United States, with highly variable geologic, hydrogeologic, soil, and climatic conditions. We assume that the information from the 60 DOE sites included in the GWD are representative for the whole DOE complex. These 60 sites include the major DOE sites and facilities, such as Rocky Flats Environmental Technology Site, Colorado; Idaho National Laboratory, Idaho; Savannah River Site, South Carolina; Oak Ridge Reservation, Tennessee; and Hanford Reservation, Washington. These five sites alone ccount for 71% of the value of the remediation work.

  4. Radioactive contamination of ZnWO4 crystal scintillators

    E-Print Network [OSTI]

    P. Belli; R. Bernabei; F. Cappella; R. Cerulli; F. A. Danevich; A. M. Dubovik; S. d'Angelo; E. N. Galashov; B. V. Grinyov; A. Incicchitti; V. V. Kobychev; M. Laubenstein; L. L. Nagornaya; F. Nozzoli; D. V. Poda; R. B. Podviyanuk; O. G. Polischuk; D. Prosperi; V. N. Shlegel; V. I. Tretyak; I. A. Tupitsyna; Ya. V. Vasiliev; Yu. Ya. Vostretsov

    2010-09-05T23:59:59.000Z

    The radioactive contamination of ZnWO4 crystal scintillators has been measured deep underground at the Gran Sasso National Laboratory (LNGS) of the INFN in Italy with a total exposure 3197 kg x h. Monte Carlo simulation, time-amplitude and pulse-shape analyses of the data have been applied to estimate the radioactive contamination of the ZnWO4 samples. One of the ZnWO4 crystals has also been tested by ultra-low background gamma spectrometry. The radioactive contaminations of the ZnWO4 samples do not exceed 0.002 -- 0.8 mBq/kg (depending on the radionuclide), the total alpha activity is in the range: 0.2 - 2 mBq/kg. Particular radioactivity, beta active 65Zn and alpha active 180W, has been detected. The effect of the re-crystallization on the radiopurity of the ZnWO4 crystal has been studied. The radioactive contamination of samples of the ceramic details of the set-ups used in the crystals growth has been checked by low background gamma spectrometry. A project scheme on further improvement of the radiopurity level of the ZnWO4 crystal scintillators is briefly addressed.

  5. Radioactive contamination of ZnWO4 crystal scintillators

    E-Print Network [OSTI]

    Belli, P; Cappella, F; Cerulli, R; Danevich, F A; Dubovik, A M; d'Angelo, S; Galashov, E N; Grinyov, B V; Incicchitti, A; Kobychev, V V; Laubenstein, M; Nagornaya, L L; Nozzoli, F; Poda, D V; Podviyanuk, R B; Polischuk, O G; Prosperi, D; Shlegel, V N; Tretyak, V I; Tupitsyna, I A; Vasiliev, Ya V; Vostretsov, Yu Ya

    2010-01-01T23:59:59.000Z

    The radioactive contamination of ZnWO4 crystal scintillators has been measured deep underground at the Gran Sasso National Laboratory (LNGS) of the INFN in Italy with a total exposure 3197 kg x h. Monte Carlo simulation, time-amplitude and pulse-shape analyses of the data have been applied to estimate the radioactive contamination of the ZnWO4 samples. One of the ZnWO4 crystals has also been tested by ultra-low background gamma spectrometry. The radioactive contaminations of the ZnWO4 samples do not exceed 0.002 â?? 0.8 mBq/kg (depending on the radionuclide), the total alpha activity is in the range: 0.2 - 2 mBq/kg. Particular radioactivity, beta active 65Zn and alpha active 180W, has been detected. The effect of the re-crystallization on the radiopurity of the ZnWO4 crystal has been studied. The radioactive contamination of samples of the ceramic details of the set-ups used in the crystals growth has been checked by low background gamma spectrometry. A project scheme on further improvement of the radiopur...

  6. DIAGNOSTIC ASSESSMENT 2 OF CONTAMINATED SITE PROBLEMS

    E-Print Network [OSTI]

    Ma, Lena

    in the environment and undergo complex interactions in more than one environmental medium. Contaminated sites should released into the environment will be controlled by a complex set of processes (such as intermedia

  7. Measurement of residual radioactive surface contamination by 2-D laser heated TLD

    SciTech Connect (OSTI)

    Jones, S.C.

    1997-06-01T23:59:59.000Z

    The feasibility of applying and adapting a two-dimensional laser heated thermoluminescence dosimetry system to the problem of surveying for radioactive surface contamination was studied. The system consists of a CO{sub 2} laser-based reader and monolithic arrays of thin dosimeter elements. The arrays consist of 10,201 thermoluminescent phosphor elements of 40 micron thickness, covering a 900 cm{sup 2} area. Array substrates are 125 micron thick polyimide sheets, enabling them to easily conform to regular surface shapes, especially for survey of surfaces that are inaccessible for standard survey instruments. The passive, integrating radiation detectors are sensitive to alpha and beta radiation at contamination levels below release guideline limits. Required contact times with potentially contaminated surfaces are under one hour to achieve detection of transuranic alpha emission at 100 dpm/100 cm{sup 2}. Positional information obtained from array evaluation is useful for locating contamination zones. Unique capabilities of this system for survey of sites, facilities and material include measurement inside pipes and other geometrical configurations that prevent standard surveys, and below-surface measurement of alpha and beta emitters in contaminated soils. These applications imply a reduction of material that must be classified as radioactive waste by virtue of its possibility of contamination, and cost savings in soil sampling at contaminated sites.

  8. Hanford Site radioactive hazardous materials packaging directory

    SciTech Connect (OSTI)

    McCarthy, T.L.

    1995-12-01T23:59:59.000Z

    The Hanford Site Radioactive Hazardous Materials Packaging Directory (RHMPD) provides information concerning packagings owned or routinely leased by Westinghouse Hanford Company (WHC) for offsite shipments or onsite transfers of hazardous materials. Specific information is provided for selected packagings including the following: general description; approval documents/specifications (Certificates of Compliance and Safety Analysis Reports for Packaging); technical information (drawing numbers and dimensions); approved contents; areas of operation; and general information. Packaging Operations & Development (PO&D) maintains the RHMPD and may be contacted for additional information or assistance in obtaining referenced documentation or assistance concerning packaging selection, availability, and usage.

  9. Monitoring Potential Transport of Radioactive Contaminants in Shallow Ephemeral Channels: FY 2012

    SciTech Connect (OSTI)

    Julianne J. Miller, Steve A. Mizell, Greg McCurdy, and Scott A. Campbell

    2012-09-01T23:59:59.000Z

    The US Department of Energy (DOE) National Nuclear Security Administration (NNSA), Nevada Site Office (NSO), Environmental Management’s Soils Activity has authorized the Desert Research Institute (DRI) to conduct field assessments of potential sediment transport of contaminated soil from Corrective Action Unit (CAU) 550, Smoky Contamination Area (CA), during precipitation runoff events. CAU 550 includes Corrective Action Sites (CASs) 08-23-03, 08-23-04, 08-23-06, and 08-23-07; these CASs are associated with tests designated Ceres, Smoky, Oberon, and Titania, respectively. Field measurements at the T-4 Atmospheric Test Site, CAU 370, suggest that radioactive material may have migrated along a shallow ephemeral drainage that traverses the site (NNSA/NSO, 2009). (It is not entirely clear how contaminated soils got into their present location at the T-4 Site, but flow to the channel has been redirected and the contamination does not appear to be migrating at present.) Although DRI initially looked at the CAU 370 site, given that it could not be confirmed that migration of contamination into the channel was natural, an alternate study site was selected at CAU 550. Aerial surveys in selected portions of the Nevada National Security Site (NNSS) also suggest that radioactivity may be migrating along ephemeral channels in Areas 3, 8, 11, 18, and 25 (Colton, 1999). Figure 1 shows the results of a low-elevation aerial survey (Colton, 1999) in Area 8. The numbered markers in Figure 1 identify ground zero for three safety experiments conducted in 1958 [Oberon (number 1), Ceres (number 2), and Titania (number 4)] and a weapons effects test conducted in 1964, Mudpack (number 3). This survey suggests contaminants may be migrating down the ephemeral channels that traverse CAU 550. Note particularly the lobe of higher concentration extending southeastward at the south end of the high concentration area marked as number 3 in Figure 1. CAU 550 in Area 8 of the NNSS was selected for the study because the aerial survey indicates that a channel mapped on the United States Geological Survey topographic map of the area traverses the south end of the area of surface contamination; this channel lies south of the point marked number 3 in Figure 1, and anecdotal information indicates that sediment has been deposited on the road bordering the southeast boundary of the CAU from an adjacent channel (Traynor, J, personal communication, 2011). Because contamination is particularly close to the boundary of CAU 550, Smoky CA, it is important to know if contaminants are moving, what meteorological conditions result in movement of contaminated soils, and what particle size fractions associated with contamination are involved. Closure plans are being developed for the CAUs on the NNSS. The closure plans may include post-closure monitoring for possible release of radioactive contaminants. Determining the potential for transport of contaminated soils under ambient climatic conditions will facilitate an appropriate closure design and post-closure monitoring program.

  10. Monitoring Potential Transport of Radioactive Contaminants in Shallow Ephemeral Channels

    SciTech Connect (OSTI)

    Miller, Julianne J.; Mizell, Steve A.; Nikolich, George; Campbell, Scott A.

    2012-02-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA), Nevada Site Office (NSO), Environmental Restoration Soils Activity has authorized the Desert Research Institute (DRI) to conduct field assessments of potential sediment transport of contaminated soil from Corrective Action Unit (CAU) 550, Area 8 Smoky Contamination Area (CA), during precipitation runoff events. CAU 550 includes Corrective Action Sites (CASs) 08-23-03, 08-23-04, 08-23-06, and 08-23-07; these CASs are associated with tests designated Ceres, Smoky, Oberon, and Titania, respectively.

  11. Hanford Site Solid (Radioactive and Hazardous) Waste Program...

    Office of Environmental Management (EM)

    Office 2 3 TITLE: 4 Revised Draft Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact 5 Statement, Richland, Benton County, Washington (DOE...

  12. Savannah River Site Ingestion Pathway Methodology Manual for Airborne Radioactive Releases

    SciTech Connect (OSTI)

    Vincent, A.W. III

    2001-01-03T23:59:59.000Z

    This manual documents a recommended methodology for determining the ingestion pathway consequences of hypothetical accidental airborne radiological releases from facilities at the Savannah River Site. Both particulate and tritiated radioactive contaminants are addressed. Other approaches should be applied for evaluation of routine releases.

  13. Radioactive contamination of BaF2 crystal scintillator

    E-Print Network [OSTI]

    Polischuk, O G; Bernabei, R; Cappella, F; Caracciolo, V; Cerulli, R; Di Marco, A; Danevich, F A; Incicchitti, A; Poda, D V; Tretyak, V I

    2013-01-01T23:59:59.000Z

    Barium fluoride (BaF$_2$) crystal scintillators are promising detectors to search for double beta decay processes in $^{130}$Ba ($Q_{2{\\beta}}$ = 2619(3) keV) and $^{132}$Ba ($Q_{2{\\beta}}$ = 844(1) keV). The $^{130}$Ba isotope is of particular interest because of the indications on 2${\\beta}$ decay found in two geochemical experiments. The radioactive contamination of BaF$_2$ scintillation crystal with mass of 1.714 kg was measured over 113.4 hours in a low-background DAMA/R&D set-up deep underground (3600 m w.e.) at the Gran Sasso National Laboratories of INFN (LNGS, Italy). The half-life of $^{212}$Po (present in the crystal scintillator due to contamination by radium) was estimated as $T_{1/2}$ = 298.8 $\\pm$ 0.8(stat.) $\\pm$ 1.4(syst.) ns by analysis of the events pulse profiles.

  14. Baseline risk assessment of groundwater contamination at the Uranium Mill Tailings Site near Gunnison, Colorado

    SciTech Connect (OSTI)

    Not Available

    1993-12-01T23:59:59.000Z

    This Baseline Risk Assessment of Groundwater Contamination at the Uranium Mill Tailings Site Near Gunnison, Colorado evaluates potential impacts to public health or the environment resulting from groundwater contamination at the former uranium mill processing site. The tailings and other contaminated material at this site are being placed in an off-site disposal cell by the US Department of Energy`s (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. Currently, the UMTRA Project is evaluating groundwater contamination. This is the second risk assessment of groundwater contamination at this site. The first risk assessment was performed primarily to evaluate existing domestic wells. This risk assessment evaluates the most contaminated monitor wells at the processing site. It will be used to assist in determining what remedial action is needed for contaminated groundwater at the site after the tailings are relocated. This risk assessment follows an approach outlined by the US Environmental Protection Agency (EPA). The first step is to evaluate groundwater data collected from monitor wells at the site. Evaluation of these data showed that the main contaminants in the groundwater are cadmium, cobalt, iron, manganese, sulfate, uranium, and some of the products of radioactive decay of uranium.

  15. Restoration of water environment contaminated by radioactive cesium released from Fukushima Daiichi NPP

    SciTech Connect (OSTI)

    Takeshita, K.; Takahashi, H. [Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, 2-12-1 Ookayama, Meguro-ku, Tokyo 157-8550 (Japan); Jinbo, Y. [CDM Cosulting Co.Ltd., 1-13-13 Tsukiji Chuo-ku Tokyo 104-0045 (Japan); Ishido, A. [Radwaste and Decommissioning Center, 1-7-6 Toranomon, Minato-ku, Tokyo 105-0001 (Japan)

    2013-07-01T23:59:59.000Z

    In the Fukushima Daiichi NPP Accident, large amounts of volatile radioactive nuclides, such as {sup 131}I, {sup 134}Cs and {sup 137}Cs, were released to the atmosphere and huge areas surrounding the nuclear site were contaminated by the radioactive fallout. In this study, a combined process with a hydrothermal process and a coagulation settling process was proposed for the separation of radioactive Cs from contaminated soil and sewage sludge. The coagulation settling operation uses Prussian Blue (Ferric ferrocyanide) and an inorganic coagulant. The recovery of Cs from sewage sludge sampled at Fukushima city (100.000 Bq/kg) and soil at a nearby village (55.000 Bq/kg), was tested. About 96% of Cs in the sewage sludge was removed successfully by combining simple hydrothermal decomposition and coagulation settling. However, Cs in the soil was not removed sufficiently by the combined process (Cs removal is only 56%). The hydrothermal decomposition with blasting was carried out. The Cs removal from the soil was increased to 85%. When these operations were repeated twice, the Cs recovery was over 90%. The combined process with hydrothermal blasting and coagulation settling is applicable to the removal of Cs from highly contaminated soil.

  16. Bioremediation of Petroleum Hydrocarbon Contaminated Sites

    SciTech Connect (OSTI)

    Paul Fallgren

    2009-03-30T23:59:59.000Z

    Bioremediation has been widely applied in the restoration of petroleum hydrocarbon-contaminated. Parameters that may affect the rate and efficiency of biodegradation include temperature, moisture, salinity, nutrient availability, microbial species, and type and concentration of contaminants. Other factors can also affect the success of the bioremediation treatment of contaminants, such as climatic conditions, soil type, soil permeability, contaminant distribution and concentration, and drainage. Western Research Institute in conjunction with TechLink Environmental, Inc. and the U.S. Department of Energy conducted laboratory studies to evaluate major parameters that contribute to the bioremediation of petroleum-contaminated drill cuttings using land farming and to develop a biotreatment cell to expedite biodegradation of hydrocarbons. Physical characteristics such as soil texture, hydraulic conductivity, and water retention were determined for the petroleum hydrocarbon contaminated soil. Soil texture was determined to be loamy sand to sand, and high hydraulic conductivity and low water retention was observed. Temperature appeared to have the greatest influence on biodegradation rates where high temperatures (>50 C) favored biodegradation. High nitrogen content in the form of ammonium enhanced biodegradation as well did the presence of water near field water holding capacity. Urea was not a good source of nitrogen and has detrimental effects for bioremediation for this site soil. Artificial sea water had little effect on biodegradation rates, but biodegradation rates decreased after increasing the concentrations of salts. Biotreatment cell (biocell) tests demonstrated hydrocarbon biodegradation can be enhanced substantially when utilizing a leachate recirculation design where a 72% reduction of hydrocarbon concentration was observed with a 72-h period at a treatment temperature of 50 C. Overall, this study demonstrates the investigation of the effects of environmental parameters on bioremediation is important in designing a bioremediation system to reduce petroleum hydrocarbon concentrations in impacted soils.

  17. Treatment of Mercury Contaminated Oil from the Mound Site

    SciTech Connect (OSTI)

    Klasson, KT

    2000-11-09T23:59:59.000Z

    Over one thousand gallons of tritiated oil, at various contamination levels, are stored in the Main Hill Tritium Facility at the Miamisburg Environmental Management Project (MEMP), commonly referred to as Mound Site. This tritiated oil is to be characterized for hazardous materials and radioactive contamination. Most of the hazardous materials are expected to be in the form of heavy metals, i.e., mercury, silver, lead, chromium, etc, but transuranic materials and PCBs could also be in some oils. Waste oils, found to contain heavy metals as well as being radioactively contaminated, are considered as mixed wastes and are controlled by Resource Conservation and Recovery Act (RCRA) regulations. The SAMMS (Self-Assembled Mercaptan on Mesoporous Silica) technology was developed by the Pacific Northwest National Laboratory (PNNL) for removal and stabilization of RCRA metals (i.e., lead, mercury, cadmium, silver, etc.) and for removal of mercury from organic solvents. The SAMMS material is based on self-assembly of functionalized monolayers on mesoporous oxide surfaces. The unique mesoporous oxide supports provide a high surface area, thereby enhancing the metal-loading capacity. SAMMS material has high flexibility in that it binds with different forms of mercury, including metallic, inorganic, organic, charged, and neutral compounds. The material removes mercury from both organic wastes, such as pump oils, and from aqueous wastes. Mercury-loaded SAMMS not only passes TCLP tests, but also has good long-term durability as a waste form because: (1) the covalent binding between mercury and SAMMS has good resistance in ion-exchange, oxidation, and hydrolysis over a wide pH range and (2) the uniform and small pore size of the mesoporous silica prevents bacteria from solubilizing the bound mercury.

  18. Journey to the Nevada Test Site Radioactive Waste Management Complex

    ScienceCinema (OSTI)

    None

    2014-10-28T23:59:59.000Z

    Journey to the Nevada Test Site Radioactive Waste Management Complex begins with a global to regional perspective regarding the location of low-level and mixed low-level waste disposal at the Nevada Test Site. For decades, the Nevada National Security Site (NNSS) has served as a vital disposal resource in the nation-wide cleanup of former nuclear research and testing facilities. State-of-the-art waste management sites at the NNSS offer a safe, permanent disposal option for U.S. Department of Energy/U.S. Department of Defense facilities generating cleanup-related radioactive waste.

  19. Radioactive contamination of SrI2(Eu) crystal scintillator

    E-Print Network [OSTI]

    Belli, P; Cerulli, R; Danevich, F A; Galenin, E; Gektin, A; Incicchitti, A; Isaienko, V; Kobychev, V V; Laubenstein, M; Nagorny, S S; Podviyanuk, R B; Tkachenko, S; Tretyak, V I

    2011-01-01T23:59:59.000Z

    A strontium iodide crystal doped by europium (SrI2(Eu)) was produced by using the Stockbarger growth technique. The crystal was subjected to characterisation that included relative photoelectron output and energy resolution for gamma quanta. The intrinsic radioactivity of SrI2(Eu) crystal scintillator was tested both in scintillation mode and by using ultra-low background HPGe gamma spectrometry deep underground. The response of the SrI2(Eu) detector to alpha particles (alpha/beta ratio and pulse shape) was estimated by analysing the 226Ra trace contamination internal to the crystal. We have found alpha/beta=0.55 and no difference in scintillation decay for alpha particles and gamma quanta. The application of the obtained results in the search for the double electron capture and electron capture with positron emission in 84Sr has been investigated at a level of sensitivity T_1/2 \\sim 10^15-10^16 yr. The results of these studies demonstrate the potentiality of this material for a variety of scintillation appli...

  20. Packaging, Transportation, and Disposal Logistics for Large Radioactively Contaminated Reactor Decommissioning Components

    SciTech Connect (OSTI)

    Lewis, Mark S. [EnergySolutions: 140 Stoneridge Drive, Columbia, SC 29210 (United States)

    2008-01-15T23:59:59.000Z

    The packaging, transportation and disposal of large, retired reactor components from operating or decommissioning nuclear plants pose unique challenges from a technical as well as regulatory compliance standpoint. In addition to the routine considerations associated with any radioactive waste disposition activity, such as characterization, ALARA, and manifesting, the technical challenges for large radioactively contaminated components, such as access, segmentation, removal, packaging, rigging, lifting, mode of transportation, conveyance compatibility, and load securing require significant planning and execution. In addition, the current regulatory framework, domestically in Titles 49 and 10 and internationally in TS-R-1, does not lend itself to the transport of these large radioactively contaminated components, such as reactor vessels, steam generators, reactor pressure vessel heads, and pressurizers, without application for a special permit or arrangement. This paper addresses the methods of overcoming the technical and regulatory challenges. The challenges and disposition decisions do differ during decommissioning versus component replacement during an outage at an operating plant. During decommissioning, there is less concern about critical path for restart and more concern about volume reduction and waste minimization. Segmentation on-site is an available option during decommissioning, since labor and equipment will be readily available and decontamination activities are routine. The reactor building removal path is also of less concern and there are more rigging/lifting options available. Radionuclide assessment is necessary for transportation and disposal characterization. Characterization will dictate the packaging methodology, transportation mode, need for intermediate processing, and the disposal location or availability. Characterization will also assist in determining if the large component can be transported in full compliance with the transportation and disposal regulations and criteria or if special authorizations must be granted to transport and/or dispose. The U.S. DOT routinely issues special permits for large components where compliance with regulatory or acceptance criteria is impractical or impossible to meet. Transportation and disposal safety must be maintained even under special permits or authorizations. For example, if transported un-packaged, performance analysis must still be performed to assess the ability of the large component's outer steel shell to contain the internal radioactive contamination under normal transportation conditions and possibly incidence normal to transportation. The dimensions and weight of a large component must be considered when determining the possible modes of transportation (rail, water, or highway). At some locations, rail and/or barge access is unavailable. Many locations that once had an active rail spur to deliver new construction materials and components have let the spur deteriorate to the point that repair and upgrade of the spur is no longer economically feasible. Barge slips that have not been used since new plant construction require significant repair and/or dredging. Short on-site haul routes must be assessed for surface and subsurface conditions, as well as longer off-site routes. Off-site routes require clearance approvals from the regulatory authorities or, in the case of rail transport, the rail lines. Significant engineering planning and analysis must be performed during the pre-mobilization. In conclusion, the packaging, transportation, and disposal of large, oversized radioactively contaminated components removed during plant decommissioning is complex. However, over the last 15 years, a 100 or more components have been safely and compliantly packaged and transported for processing and/or disposal.

  1. Bugs boost Cold War clean-up: Bacteria could scrub uranium from sites contaminated decades ago. updated at midnight GMTtoday is friday, november 14

    E-Print Network [OSTI]

    Lovley, Derek

    2003 · Fungus catches radioactive fallout 8 May 2002 · Depleted uranium soils battlefields 12 MarchBugs boost Cold War clean-up: Bacteria could scrub uranium from sites contaminated decades ago boost Cold War clean-up Bacteria could scrub uranium from sites contaminated decades ago. 13 October

  2. Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site near Maybell, Colorado

    SciTech Connect (OSTI)

    NONE

    1995-09-01T23:59:59.000Z

    The US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (Phase I) and the Ground Water Project (Phase II). Under the UMTRA Surface Project, tailings, radioactive contaminated soil, building foundations, and materials associated with the former processing of uranium ore at UMTRA sites are placed into disposal cells. The cells are designed to reduce radon and other radiation emissions and to prevent further contamination of ground water. One UMTRA Project site is near Maybell, Colorado. Surface cleanup at this site is under way and is scheduled for completion in 1996. The tailings are being stabilized in-place at this site. The disposal area has been withdrawn from public use by the DOE and is referred to as the permanent withdrawal area. The Ground Water Project evaluates the nature and extent of ground water contamination resulting from past uranium ore processing activities. The Ground Water Project at this site is in its beginning stages. This report is a site-specific document that will be used to evaluate current and future potential impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site characterization will determine whether any action is needed to protect human health or the environment. Currently, no points of exposure (e.g. a drinking water well); and no receptors of contaminated ground water have been identified at the Maybell site. Therefore, there are no current human health and ecological risks associated with exposure to contaminated ground water. Furthermore, if current site conditions and land- and water-use patterns do not change, it is unlikely that contaminated ground water would reach people or the ecological communities in the future.

  3. Contaminated land and groundwater management at Sellafield, a large operational site with significant legacy and contaminated land challenges

    SciTech Connect (OSTI)

    Reeve, Phil; Eilbeck, Katherine [British Nuclear Group Sellafield Ltd (United Kingdom)

    2007-07-01T23:59:59.000Z

    Sellafield is a former Royal Ordnance Factory used since the 1940's for the production and reprocessing of fissile materials. Leaks and spills from these plants and their associated waste facilities has led to radioactive contaminated ground legacy of up to 20 million m{sup 3}. Consideration of land contamination at Sellafield began in 1976, following discovery of a major leak from a waste storage silo. Over the past three decades there has been a programme of environmental monitoring and several phases of characterization. The latest phase of characterization is a pounds 10 million contract to develop second generation conceptual and numeric models. The Site Licence Company that operates the site has been subject to structural changes due to reorganizations within the British nuclear industry. There has also been a change in emphasis to place an increased importance on accelerated decommissioning. To address these challenges a new contaminated land team and contaminated land and groundwater management plan have been established. Setting and measuring performance against challenging objectives is important. The management plan has to be cognizant of the long timescales (ca. 80 years) for final remediation. Data review, collation, acquisition, analysis, and storage is critical for success. It is equally important to seize opportunities for early environmental gains. It is possible to accelerate the development and delivery of a contaminated land and groundwater management plan by using international experts. (authors)

  4. Fate and transport processes controlling the migration of hazardous and radioactive materials from the Area 5 Radioactive Waste Management Site (RWMS)

    SciTech Connect (OSTI)

    Estrella, R.

    1994-10-01T23:59:59.000Z

    Desert vadose zones have been considered as suitable environments for the safe and long-term isolation of hazardous wastes. Low precipitation, high evapotranspiration and thick unsaturated alluvial deposits commonly found in deserts make them attractive as waste disposal sites. The fate and transport of any contaminant in the subsurface is ultimately determined by the operating retention and transformation processes in the system and the end result of the interactions among them. Retention (sorption) and transformation are the two major processes that affect the amount of a contaminant present and available for transport. Retention processes do not affect the total amount of a contaminant in the soil system, but rather decrease or eliminate the amount available for transport at a given point in time. Sorption reactions retard the contaminant migration. Permanent binding of solute by the sorbent is also possible. These processes and their interactions are controlled by the nature of the hazardous waste, the properties of the porous media and the geochemical and environmental conditions (temperature, moisture and vegetation). The present study summarizes the available data and investigates the fate and transport processes that govern the migration of contaminants from the Radioactive Waste Management Site (RWMS) in Area 5 of the Nevada Test Site (NTS). While the site is currently used only for low-level radioactive waste disposal, past practices have included burial of material now considered hazardous. Fundamentals of chemical and biological transformation processes are discussed subsequently, followed by a discussion of relevant results.

  5. Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site near Naturita, Colorado

    SciTech Connect (OSTI)

    NONE

    1995-08-01T23:59:59.000Z

    The Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (phase I), and the Ground Water Project (phase II). For the UMTRA Project site located near Naturita, Colorado (the Naturita site), phase I involves the removal of radioactively contaminated soils and materials and their transportation to a disposal site at Union Carbide Corporation`s Upper Burbank Repository at Uravan, Colorado, about 13 road miles (mi) (21 kilometers [km]) to the northwest. No uranium mill tailings are involved because the tailings were removed from the Naturita site and placed at Coke Oven, Colorado, during 1977 to 1979. Phase II of the project will evaluate the nature and extent of ground water contamination resulting from uranium processing and its effect on human health or the environment; and will determine site-specific ground water compliance strategies in accordance with the US Environmental Protection Agency (EPA) ground water standards established for the UMTRA Project. Human health risks could occur from drinking water pumped from a hypothetical well drilled in the contaminated ground water area. Environmental risks may result if plants or animals are exposed to contaminated ground water, or surface water that has received contaminated ground water. Therefore, a risk assessment is conducted for the Naturita site. This risk assessment report is the first site-specific document prepared for the Ground Water Project at the Naturita site. What follows is an evaluation of current and possible future impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site characterization will be used to determine whether any action is needed to protect human health or the environment.

  6. Nevada National Security Site 2012 Data Report: Groundwater Monitoring Program Area 5 Radioactive Waste Management Site

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2013-02-11T23:59:59.000Z

    This report is a compilation of the groundwater sampling results from the Area 5 Radioactive Waste Management Site (RWMS). The data have been collected since 1993 and include calendar year 2012 results. During 2012, groundwater samples were collected and static water levels were measured at the three pilot wells surrounding the Area 5 RWMS. Groundwater samples were collected at UE5PW-1, UE5PW-2, and UE5PW-3 on March 21, August 7, August 21, and September 11, 2012, and static water levels were measured at each of the three pilot wells on March 19, June 6, August 2, and October 15, 2012. Groundwater samples were analyzed for the following indicators of contamination: pH, specific conductance, total organic carbon, total organic halides, and tritium. Indicators of general water chemistry (cations and anions) were also measured. Final results from samples collected in 2012 were within the limits established by agreement with the Nevada Division of Environmental Protection for each analyte. These data indicate that there has been no measurable impact to the uppermost aquifer from the Area 5 RWMS. There were no significant changes in measured groundwater parameters compared to previous years. The report contains an updated cumulative chronology for the Area 5 RWMS Groundwater Monitoring Program and a brief description of the site hydrogeology.

  7. Nevada Test Site 2002 Data Report: Groundwater Monitoring Program Area 5 Radioactive Waste Management Site

    SciTech Connect (OSTI)

    Y. E. Townsend

    2003-02-01T23:59:59.000Z

    This report is a compilation of the calendar year 2002 groundwater sampling results from the Area 5 Radioactive Waste Management Site (RWMS). Wells Ue5PW-1, Ue5PW-2, and Ue5PW-3 were sampled semiannually for the required analytes: pH, specific conductance, major cations/anions, metals, tritium, total organic carbon (TOC), and total organic halogen (TOX). Results from all samples collected in 2002 were within established criteria. These data indicate that there has been no measurable impact to the uppermost aquifer from the Resource Conservation and Recovery Act(RCRA) regulated unit within the RWMS-5 and confirm that the detections of TOC and TOX in 2000 were false positives. Contamination indicator data are presented in control chart and tabular form with investigation levels (ILs) indicated. Gross water chemistry data are presented in graphical and tabular form. There were no major changes noted in the monitored groundwater elevation. There continues to be an extremely small gradient to the northeast with an average flow velocity of less than one foot per year. Other information in the report includes, the Cumulative Chronology for Area 5 RWMS Groundwater Monitoring Program, a brief description of the site hydrogeology, and the groundwater sampling procedure.

  8. Nevada Test Site 2001 Data Report: Groundwater Monitoring Program Area 5 Radioactive Waste Management Site

    SciTech Connect (OSTI)

    Y. E. Townsend

    2002-02-01T23:59:59.000Z

    This report is a compilation of the calendar year 2001 groundwater sampling results from the Area 5 Radioactive Waste Management Site (RWMS). Contamination indicator data are presented in control chart and tabular form with investigation levels (ILs) indicated. Gross water chemistry data are presented in graphical and tabular form. Other information in the report includes, the Cumulative Chronology for Area 5 RWMS Groundwater Monitoring Program, a brief description of the site hydrogeology, and the groundwater sampling procedure. Wells Ue5PW-1, Ue5PW-2, and Ue5PW-3 were sampled semiannually for the required analytes: pH, specific conductance, major cations/anions, metals, tritium, total organic carbon (TOC), and total organic halogen (TOX). Due to detections of TOC and TOX in some samples collected in 2000, a plan, as approved by the Nevada Division of Environmental Protection (NDEP), was executed to collect an increased number and type of samples in 2001. Results from all samples collected in 2001 were below ILs. These data indicate that there has been no measurable impact to the uppermost aquifer from the Resource Conservation and Recovery Act (RCRA) regulated unit within the Area 5 RWMS and confirm that the detections of TOC and TOX in 2000 were false positives. There were no major changes noted in the monitored groundwater elevation. There continues to be an extremely small gradient to the northeast with an average flow velocity of less than one foot per year.

  9. Nevada Test Site 2009 Data Report: Groundwater Monitoring Program, Area 5 Radioactive Waste Management Site

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2010-01-19T23:59:59.000Z

    This report is a compilation of the groundwater sampling results from the Area 5 Radioactive Waste Management Site (RWMS). The data have been collected since 1993 and include calendar year 2009 results. During 2009, groundwater at each of the three pilot wells was sampled on March 10, 2009, and August 18, 2009, and water levels at each of the three pilot wells were measured on February 17, May 6, August 17, and November 10, 2009. Groundwater samples were analyzed for the following indicators of contamination: pH, specific conductance, total organic carbon, total organic halides, and tritium. Indicators of general water chemistry (cations and anions) were also measured. Results from all samples collected in 2009 were within the limits established by agreement with the Nevada Division of Environmental Protection for each analyte. These data indicate that there has been no measurable impact to the uppermost aquifer from the Area 5 RWMS. There were no significant changes in measured groundwater parameters compared to previous years. The report contains an updated cumulative chronology for the Area 5 RWMS Groundwater Monitoring Program and a brief description of the site hydrogeology.

  10. Baseline risk assessment of groundwater contamination at the Uranium Mill Tailings Site near Gunnison, Colorado. Revision 1

    SciTech Connect (OSTI)

    Not Available

    1994-04-01T23:59:59.000Z

    This report evaluates potential impacts to public health or the environment resulting from groundwater contamination at the former uranium mill processing site. The tailings and other contaminated material at this site are being placed in an off-site disposal cell by the US Department of Energy`s (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. Currently, the UMTRA Project is evaluating groundwater contamination. This is the second risk assessment of groundwater contamination at this site. The first risk assessment was performed primarily to evaluate existing domestic wells to determine the potential for immediate human health and environmental impacts. This risk assessment evaluates the most contaminated groundwater that flows beneath the processing site towards the Gunnison River. The monitor wells that have consistently shown the highest concentration of most contaminants are used in this risk assessment. This risk assessment will be used in conjunction with additional activities and documents to assist in determining what remedial action is needed for contaminated groundwater at the site after the tailings are relocated. This risk assessment follows an approach outlined by the US Environmental Protection Agency (EPA). The first step is to evaluate groundwater data collected from monitor wells at the site. Evaluation of these data showed that the main contaminants in the groundwater are cadmium, cobalt, iron, manganese, sulfate, uranium, and some of the products of radioactive decay of uranium.

  11. Proposed sale of radioactively contaminated nickel ingots located at the Paducah Gaseous Diffusion Plant, Paducah, Kentucky

    SciTech Connect (OSTI)

    NONE

    1995-10-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) proposes to sell 8,500 radioactively contaminated nickel ingots (9.350 short tons), currently in open storage at the Paducah Gaseous Diffusion Plant (PGDP), to Scientific Ecology Group, Inc. (SEG) for decontamination and resale on the international market. SEG would take ownership of the ingots when they are loaded for transport by truck to its facility in Oak Ridge, Tennessee. SEG would receive approximately 200 short tons per month over approximately 48 months (an average of 180 ingots per month). The nickel decontamination process specified in SEG`s technical proposal is considered the best available technology and has been demonstrated in prototype at SEG. The resultant metal for resale would have contamination levels between 0.3 and 20 becquerel per gram (Bq/g). The health hazards associated with release of the decontaminated nickel are minimal. The activity concentration of the end product would be further reduced when the nickel is combined with other metals to make stainless steel. Low-level radioactive waste from the SEG decontamination process, estimated to be approximately 382 m{sup 3} (12,730 ft), would be shipped to a licensed commercial or DOE disposal facility. If the waste were packaged in 0.23 m{sup 3}-(7.5 ft{sup 3}-) capacity drums, approximately 1,500 to 1,900 drums would be transported over the 48-month contract period. Impacts from the construction of decontamination facilities and the selected site are minimal.

  12. Cesium removal from Savannah River Site radioactive waste using crystalline silicotitanate (IONSIV(R) IE-911)

    SciTech Connect (OSTI)

    Walker, D.D.

    1999-12-15T23:59:59.000Z

    This study measured the ability of crystalline silicotitanate to remove cesium from Savannah River Site radioactive waste.

  13. Baseline risk assessment of ground water contamination at the uranium mill tailings sites near Rifle, Colorado. Revision 1

    SciTech Connect (OSTI)

    NONE

    1995-08-01T23:59:59.000Z

    The US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (Phase 1) and the Ground Water Project (Phase 2). Under the UMTRA Surface Project, tailings, radioactive contaminated soil, equipment, and materials associated with the former uranium ore processing sites are placed into disposal cells. The cells are designed to reduce radon and other radiation emissions and to prevent further ground water contamination. The Ground Water Project evaluates the nature and extent of ground water contamination resulting from the uranium ore processing activities. Two UMTRA Project sites are near Rifle, Colorado: the Old Rifle site and the New Rifle site. Surface cleanup at the two sites is under way and is scheduled for completion in 1996. The Ground Water Project is in its beginning stages. A risk assessment identifies a source of contamination, how that contamination reaches people and the environment, the amount of contamination to which people or the environment may be exposed, and the health or environmental effects that could result from that exposure. This report is a site-specific document that will be used to evaluate current and future impacts to the public and the environment from exposure to contaminated ground water. This evaluation and further site characterization will be used to determine if action is needed to protect human health or the environment.

  14. Registration for the Hanford Site: Sources of radioactive emissions

    SciTech Connect (OSTI)

    Silvia, M.J.

    1993-04-01T23:59:59.000Z

    This Registration Application serves to renew the registration for all Hanford Site sources of radioactive air emissions routinely reported to the State of Washington Department of Health (DOH). The current registration expires on August 15, 1993. The Application is submitted pursuant to the Washington Administrative Code (WAC) Chapter 246--247, and is consistent with guidance provided by DOH for renewal. The Application subdivides the Hanford Site into six major production, processing or research areas. Those six areas are in the 100 Area, 200 East Area, 200 West Area, 300 Area, 400 Area, and 600 Area. Each major group of point sources within the six areas listed above is represented by a Source Registration for Radioactive Air Emissions form. Annual emissions. for the sources are listed in the ``Radionuclide Air Emissions Report for the Hanford Site,`` published annually. It is a requirement that the following Statement of Compliance be provided: ``The radioactive air emissions from the above sources do meet the emissions standards contained in Chapter 173-480-040 WAC, Ambient Air Quality Standards and Emissions Limits for Radionuclides. As the Statement of Compliance pertains to this submittal, the phrase ``above sources`` is to be understood as meaning the combined air emissions from all sources registered by this submittal.

  15. Nevada National Security Site 2011 Data Report: Groundwater Monitoring Program Area 5 Radioactive Waste Management Site

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2012-02-27T23:59:59.000Z

    This report is a compilation of the groundwater sampling results from the Area 5 Radioactive Waste Management Site (RWMS). The data have been collected since 1993 and include calendar year 2011 results. During 2011, groundwater samples were collected and static water levels were measured at the three pilot wells surrounding the Area 5 RWMS. Samples were collected at UE5PW-1 on March 8, August 2, August 24, and October 19, 2011; at UE5PW-2 on March 8, August 2, August 23, and October 19, 2011; and at UE5PW-3 on March 8, August 2, August 23, and October 19, 2011. Static water levels were measured at each of the three pilot wells on March 1, June 7, August 1, and October 17, 2011. Groundwater samples were analyzed for the following indicators of contamination: pH, specific conductance, total organic carbon, total organic halides, and tritium. Indicators of general water chemistry (cations and anions) were also measured. Initial total organic carbon and total organic halides results for samples collected in August 2011 were above previous measurements and, in some cases, above the established investigation limits. However, after field sample pumps and tubing were disinfected with Clorox solution, the results returned to normal levels. Final results from samples collected in 2011 were within the limits established by agreement with the Nevada Division of Environmental Protection for each analyte. These data indicate that there has been no measurable impact to the uppermost aquifer from the Area 5 RWMS. There were no significant changes in measured groundwater parameters compared to previous years. The report contains an updated cumulative chronology for the Area 5 RWMS Groundwater Monitoring Program and a brief description of the site hydrogeology.

  16. Closure End States for Facilities, Waste Sites, and Subsurface Contamination

    SciTech Connect (OSTI)

    Gerdes, Kurt D.; Chamberlain, Grover S.; Wellman, Dawn M.; Deeb, Rula A.; Hawley, Elizabeth L.; Whitehurst, Latrincy; Marble, Justin

    2012-11-21T23:59:59.000Z

    The United States (U.S.) Department of Energy (DOE) manages the largest groundwater and soil cleanup effort in the world. DOE’s Office of Environmental Management (EM) has made significant progress in its restoration efforts at sites such as Fernald and Rocky Flats. However, remaining sites, such as Savannah River Site, Oak Ridge Site, Hanford Site, Los Alamos, Paducah Gaseous Diffusion Plant, Portsmouth Gaseous Diffusion Plant, and West Valley Demonstration Project possess the most complex challenges ever encountered by the technical community and represent a challenge that will face DOE for the next decade. Closure of the remaining 18 sites in the DOE EM Program requires remediation of 75 million cubic yards of contaminated soil and 1.7 trillion gallons of contaminated groundwater, deactivation & decommissioning (D&D) of over 3000 contaminated facilities and thousands of miles of contaminated piping, removal and disposition of millions of cubic yards of legacy materials, treatment of millions of gallons of high level tank waste and disposition of hundreds of contaminated tanks. The financial obligation required to remediate this volume of contaminated environment is estimated to cost more than 7% of the to-go life-cycle cost. Critical in meeting this goal within the current life-cycle cost projections is defining technically achievable end states that formally acknowledge that remedial goals will not be achieved for a long time and that residual contamination will be managed in the interim in ways that are protective of human health and environment. Formally acknowledging the long timeframe needed for remediation can be a basis for establishing common expectations for remedy performance, thereby minimizing the risk of re-evaluating the selected remedy at a later time. Once the expectations for long-term management are in place, remedial efforts can be directed towards near-term objectives (e.g., reducing the risk of exposure to residual contamination) instead of focusing on long-term cleanup requirements. An acknowledgement of the long timeframe for complete restoration and the need for long-term management can also help a site transition from the process of pilot testing different remedial strategies to selecting a final remedy and establishing a long-term management and monitoring approach. This approach has led to cost savings and the more efficient use of resources across the Department of Defense complex and at numerous industrial sites across the U.S. Defensible end states provide numerous benefits for the DOE environmental remediation programs including cost-effective, sustainable long-term monitoring strategies, remediation and site transition decision support, and long-term management of closure sites.

  17. DEMONSTRATION SOLIDIFICATION TESTS CONDUCTED ON RADIOACTIVELY CONTAMINATED ORGANIC LIQUIDS AT THE AECL WHITESHELL LABORATORIES

    SciTech Connect (OSTI)

    Ryz, R. A.; Brunkow, W. G.; Govers, R.; Campbell, D.; Krause, D.

    2002-02-25T23:59:59.000Z

    The AECL, Whiteshell Laboratory (WL) near Pinawa Manitoba, Canada, was established in the early 1960's to carry out AECL research and development activities for higher temperature versions of the CANDU{reg_sign} reactor. The initial focus of the research program was the Whiteshell Reactor-1 (WR-1) Organic Cooled Reactor (OCR) that began operation in 1965. The OCR program was discontinued in the early 1970's in favor of the successful heavy-water-cooled CANDU system. WR-1 continued to operate until 1985 in support of AECL nuclear research programs. A consequence of the Federal government's recent program review process was AECL's business decision to discontinue research programs and operations at the Whiteshell Laboratories and to consolidate its' activities at the Chalk River Laboratories. As a result, AECL received government concurrence in 1998 to proceed to plan actions to achieve closure of WL. The planning actions now in progress address the need to safely and effectively transition the WL site from an operational state, in support of AECL's business, to a shutdown and decommissioned state that meets the regulatory requirements for a licensed nuclear site. The decommissioning program that will be required at WL is unique within AECL and Canada since it will need to address the entire research site rather than individual facilities declared redundant. Accordingly, the site nuclear facilities are being systematically placed in a safe shutdown state and planning for the decommissioning work to place the facilities in a secure monitoring and surveillance state is in progress. One aspect of the shutdown activities is to deal with the legacy of radioactively contaminated organic liquid wastes. Use of a polymer powder to solidify these organic wastes was identified as one possibility for improved interim storage of this material pending final disposition.

  18. REAL-TIME IDENTIFICATION AND CHARACTERIZATION OF ASBESTOS AND CONCRETE MATERIALS WITH RADIOACTIVE CONTAMINATION

    SciTech Connect (OSTI)

    XU, X. George; Zhang, X.C.

    2002-05-10T23:59:59.000Z

    Concrete and asbestos-containing materials were widely used in DOE building construction in the 1940s and 1950s. Over the years, many of these porous materials have been contaminated with radioactive sources, on and below the surface. To improve current practice in identifying hazardous materials and in characterizing radioactive contamination, an interdisciplinary team from Rensselaer has conducted research in two aspects: (1) to develop terahertz time-domain spectroscopy and imaging system that can be used to analyze environmental samples such as asbestos in the field, and (2) to develop algorithms for characterizing the radioactive contamination depth profiles in real-time in the field using gamma spectroscopy. The basic research focused on the following: (1) mechanism of generating of broadband pulsed radiation in terahertz region, (2) optimal free-space electro-optic sampling for asbestos, (3) absorption and transmission mechanisms of asbestos in THz region, (4) the role of asbestos sample conditions on the temporal and spectral distributions, (5) real-time identification and mapping of asbestos using THz imaging, (7) Monte Carlo modeling of distributed contamination from diffusion of radioactive materials into porous concrete and asbestos materials, (8) development of unfolding algorithms for gamma spectroscopy, and (9) portable and integrated spectroscopy systems for field testing in DOE. Final results of the project show that the combination of these innovative approaches has the potential to bring significant improvement in future risk reduction and cost/time saving in DOE's D and D activities.

  19. EIS-0084: Incineration Facility for Radioactively Contaminated PCBs and Other Wastes, Oak Ridge, Tennessee

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy Office of Uranium Enrichment and Assessment prepared this statement to assess the environmental impacts of the construction and operation of the proposed Oak Ridge Gaseous Diffusion Plant, an incineration facility to dispose of radioactively contaminated polychlorinated biophenyls, as well as combustible waste from the Paducah, Portsmouth and Oak Ridge facilities.

  20. Spatial Data Analysis and Modeling of Radioactively-Contaminated Territories: Lessons Learned from Chernobyl

    E-Print Network [OSTI]

    Chernobyl M. Kanevski1 , L. Bolshov2 , V. Demyanov3 , E. Savelieva4 , V. Timonin5 , S. Chernov6 Abstract territories after the Chernobyl accident. The Chernobyl accident resulted in radioactive contamination, concerning environmental spatial data analysis. The spatial patterns of the Chernobyl fallout are very

  1. Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Sites near Rifle, Colorado. Revision 2

    SciTech Connect (OSTI)

    NONE

    1996-02-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (Phase I) and the Ground Water Project (Phase II). Under the UMTRA Surface Project, tailings, radioactive contaminated soil, equipment, and materials associated with the former uranium ore processing sites are placed into disposal cells. The cells are designed to reduce radon and other radiation emissions and to prevent further ground water contamination. The Ground Water Project evaluates the nature and extent of ground water contamination resulting from the uranium ore processing activities. Two UMTRA Project sites are near Rifle, Colorado: the Old Rifle site and the New Rifle site. Surface cleanup at the two sites is under way and is scheduled for completion in 1996. The Ground Water Project is in its beginning stages. A risk assessment identifies a source of contamination, how that contamination reaches people and the environment, the amount of contamination to which people or the environment may be exposed, and the health or environmental effects that could result from that exposure. This report is a site-specific document that will be used to evaluate current and future impacts to the public and the environment from exposure to contaminated ground water. This evaluation and further site characterization will be used to determine if action is needed to protect human health or the environment. Human health risk may result from exposure to ground water contaminated from uranium ore processing. Exposure could occur from drinking water obtained from a well placed in the areas of contamination. Furthermore, environmental risk may result from plant or animal exposure to surface water and sediment that have received contaminated ground water.

  2. 2005 Data Report: Groundwater Monitoring Program Area 5 Radioactive Waste Management Site

    SciTech Connect (OSTI)

    Bechtel Nevada

    2006-02-01T23:59:59.000Z

    This report is a compilation of the calendar year 2005 groundwater sampling results from the Area 5 Radioactive Waste Management Site. In additon to providing groundwater monitoring results, this report also includes information regarding site hydrogeology, well construction, sample collection, and meteorological data measured at the Area 5 Radioactive Waste Management Site at the Nevada Test Site, Ny County, Nevada.

  3. EA-1599: Disposition of Radioactively Contaminated Nickel Located at the

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy China U.S.ContaminationJuly 2011D APPENDIX D9 STAT.BPA's10Y-12 Steam Plant Life 230-kVEast

  4. Analysis of disposition alternatives for radioactively contaminated scrap metal

    SciTech Connect (OSTI)

    Nieves, L.A.; Chen, S.Y.; Kohout, E.J.; Nabelssi, B.; Tilbrook, R.W.; Wilson, S.E.

    1997-01-01T23:59:59.000Z

    Millions of tonnes of slightly radioactive, scrap iron and steel, stainless steel, and copper are likely to become available as nuclear and other facilities and equipment are withdrawn from service. Disposition of this material is an international policy issue under consideration currently. The major alternatives for managing this material are to either develop a regulatory process for decontamination and recycling that will safeguard human health or to dispose of the scrap and replace the metal stocks. To evaluate the alternatives, we estimate quantities of scrap arising from nuclear power plant decommissioning, evaluate potential price impacts of recycling on regional markets, and assess the health and environmental impacts of the management alternatives. We conclude that decontaminating and recycling the scrap is the superior alternative.

  5. Baseline risk assessment of ground water contamination at the uranium mill tailings site near Canonsburg, Pennsylvania. Revision 1

    SciTech Connect (OSTI)

    NONE

    1995-11-01T23:59:59.000Z

    For the UMTRA Project site located near Canonsburg, Pennsylvania (the Canonsburg site), the Surface Project cleanup occurred from 1983 to 1985, and involved removing the uranium processing mill tailings and radioactively contaminated soils and materials from their original locations and placing them in a disposal cell located on the former Canonsburg uranium mill site. This disposal cell is designed to minimize radiation emissions and further contamination of ground water beneath the site. The Ground Water Project will evaluate the nature and the extent of ground water contamination resulting from uranium processing at the former Canonsburg uranium mill site, and will determine a ground water strategy for complying with the US Environmental Protection Agency`s (EPA) ground water standards established for the UMTRA Project. For the Canonsburg site, an evaluation was made to determine whether exposure to ground water contaminated by uranium processing could affect people`s health. This risk assessment report is the first site-specific document prepared for the UMTRA Ground Water Project at the Canonsburg site. The results of this report and further site characterization of the Canonsburg site will be used to determine how to protect public health and the environment, and how to comply with the EPA standards.

  6. Closure Report for Corrective Action Unit 143: Area 25 Contaminated Waste Dumps, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    D. S. Tobiason

    2002-03-01T23:59:59.000Z

    This Closure Report (CR) has been prepared for the Area 25 Contaminated Waste Dumps (CWD), Corrective Action Unit (CAU) 143 in accordance with the Federal Facility Agreement and Consent Order [FFACO] (FFACO, 1996) and the Nevada Division of Environmental Protection (NDEP)-approved Corrective Action Plan (CAP) for CAU 143: Area 25, Contaminated Waste Dumps, Nevada Test Site, Nevada. CAU 143 consists of two Corrective Action Sites (CASs): 25-23-09 CWD No.1, and 25-23-03 CWD No.2. The Area 25 CWDs are historic disposal units within the Area 25 Reactor Maintenance, Assembly, and Disassembly (R-MAD), and Engine Maintenance, Assembly, and Disassembly (E-MAD) compounds located on the Nevada Test Site (NTS). The R-MAD and E-MAD facilities originally supported a portion of the Nuclear Rocket Development Station in Area 25 of the NTS. CWD No.1 CAS 25-23-09 received solid radioactive waste from the R-MAD Compound (East Trestle and West Trench Berms) and 25-23-03 CWD No.2 received solid radioactive waste from the E-MAD Compound (E-MAD Trench).

  7. SRS: Site ranking system for hazardous chemical and radioactive waste

    SciTech Connect (OSTI)

    Rechard, R.P.; Chu, M.S.Y.; Brown, S.L.

    1988-05-01T23:59:59.000Z

    This report describes the rationale and presents instructions for a site ranking system (SRS). SRS ranks hazardous chemical and radioactive waste sites by scoring important and readily available factors that influence risk to human health. Using SRS, sites can be ranked for purposes of detailed site investigations. SRS evaluates the relative risk as a combination of potentially exposed population, chemical toxicity, and potential exposure of release from a waste site; hence, SRS uses the same concepts found in a detailed assessment of health risk. Basing SRS on the concepts of risk assessment tends to reduce the distortion of results found in other ranking schemes. More importantly, a clear logic helps ensure the successful application of the ranking procedure and increases its versatility when modifications are necessary for unique situations. Although one can rank sites using a detailed risk assessment, it is potentially costly because of data and resources required. SRS is an efficient approach to provide an order-of-magnitude ranking, requiring only readily available data (often only descriptive) and hand calculations. Worksheets are included to make the system easier to understand and use. 88 refs., 19 figs., 58 tabs.

  8. Noninvasive Contaminant Site Characterization Using Geophysical Induced Polarization

    SciTech Connect (OSTI)

    Morgan, F.D.; Sogade, J.; Lesmes, D.; Coles, D.; Vichabian, Y.; Scira-Scappuzzo, F.; Shi, W.; Vandiver, A.; Rodi, W.

    2003-03-27T23:59:59.000Z

    Results of aspects of a broad foundational study of time domain IP (TDIP) and spectral IP (SIP) for contaminant site characterization are presented. This ongoing study encompassed laboratory studies of coupled effects of rock/soil microgeometry and contaminant chemistry on induced polarization (IP), an investigation of electromagnetic coupling (EMC) noise and development of 3D modeling and inversion codes. SIP requires extensions to higher frequencies (above the typical 100Hz threshold) and EMC becomes the major limitation for field implementation, because conventional correction methods are inadequate at required higher frequencies. A proposed methodology is outlined, based on a model of all EMC components, that addresses the EMC problem by coupling IP and electromagnetic induction in modeling and inversion. Examples of application of IP and SIP to contaminant mapping and detection for TDIP and SIP will be presented for FS-12 plume at Massachusetts Military Reservation and a suspected DNAPL plume at Savannah River Site.

  9. Prioritization and accelerated remediation of groundwater contamination in the 200 Areas of the Hanford Site, Washington

    SciTech Connect (OSTI)

    Wittreich, C.D.; Ford, B.H.

    1993-04-01T23:59:59.000Z

    The Hanford Site, operated by the US Department of Energy (DOE), occupies about 1,450 km{sup 2} (560 mi{sup 2}) of the southeastern part of Washington State north of the confluence of the Yakima and Columbia Rivers. The Hanford Site is organized into numerically designated operational areas. The 200 Areas, located near the center of the Hanford Site, encompasses the 200 West, East and North Areas and cover an area of over 40 km{sup 2}. The Hanford Site was originally designed, built, and operated to produce plutonium for nuclear weapons using production reactors and chemical reprocessing plants. Operations in the 200 Areas were mainly related to separation of special nuclear materials from spent nuclear fuel and contain related chemical and fuel processing and waste management facilities. Large quantities of chemical and radioactive waste associated with these processes were often disposed to the environment via infiltration structures such as cribs, ponds, ditches. This has resulted in over 25 chemical and radionuclide groundwater plumes, some of which have reached the Columbia River. An Aggregate Area Management Study program was implemented under the Hanford Federal Facility Agreement and Consent Order to assess source and groundwater contamination and develop a prioritized approach for managing groundwater remediation in the 200 Areas. This included a comprehensive evaluation of existing waste disposal and environmental monitoring data and the conduct of limited field investigations (DOE-RL 1992, 1993). This paper summarizes the results of groundwater portion of AAMS program focusing on high priority contaminant plume distributions and the groundwater plume prioritization process. The objectives of the study were to identify groundwater contaminants of concern, develop a conceptual model, refine groundwater contaminant plume maps, and develop a strategy to expedite the remediation of high priority contaminants through the implementation of interim actions.

  10. Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site near Green River, Utah. Revision 1

    SciTech Connect (OSTI)

    NONE

    1995-09-01T23:59:59.000Z

    The Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (phase 1) and the Ground Water Project (phase 2). For the UMTRA Project site located near Green River, Utah, the Surface Project cleanup occurred from 1988 to 1989. The tailings and radioactively contaminated soils and materials were removed from their original locations and placed into a disposal cell on the site. The disposal cell is designed to minimize radiation emissions and minimize further contamination of ground water beneath the site. The UMTRA Project`s second phase, the Ground Water Project, evaluates the nature and extent of ground water contamination resulting from uranium processing and determines a strategy for ground water compliance with the Environmental Protection Agency (EPA) ground water standards established for the UMTRA Project. For the Green River site, the risk assessment helps determine whether human health risks result from exposure to ground water contaminated by uranium processing. This risk assessment report is the first site-specific document prepared for the UMTRA Ground Water Project at the Green River site. What follows is an evaluation of current and possible future impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site characterization will be used to determine what is necessary, if anything, to protect human health and the environment while complying with EPA standards.

  11. Baseline risk assessment of ground water contamination at the Monument Valley uranium mill tailings site Cane Valley, Arizona

    SciTech Connect (OSTI)

    NONE

    1996-03-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (Phase I) and the Ground Water Project (Phase II). Under the UMTRA Surface Project, tailings, radioactive contaminated soil, equipment, and materials associated with the former uranium ore processing at UMTRA Project sites are placed into disposal cells. The cells are designed to reduce radon and other radiation emissions and to minimize further contamination of ground water. Surface cleanup at the Monument Valley UMTRA Project site near Cane Valley, Arizona, was completed in 1994. The Ground Water Project evaluates the nature and extent of ground water contamination that resulted from the uranium ore processing activities. The Ground Water Project is in its beginning stages. Human health may be at risk from exposure to ground water contaminated by uranium ore processing. Exposure could occur by drinking water pumped out of a hypothetical well drilled in the contaminated areas. Adverse ecological and agricultural effects may also result from exposure to contaminated ground water. For example, livestock should not be watered with contaminated ground water. A risk assessment describes a source of contamination, how that contamination reaches people and the environment, the amount of contamination to which people or the ecological environment may be exposed, and the health or ecological effects that could result from that exposure. This risk assessment is a site-specific document that will be used to evaluate current and potential future impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site investigations will be used to determine a compliance strategy to comply with the UMTRA ground water standards.

  12. Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site near Naturita, Colorado. Revision 1

    SciTech Connect (OSTI)

    NONE

    1995-11-01T23:59:59.000Z

    The Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project, and the Ground Water Project. For the UMTRA Project site located near Naturita, Colorado, phase I involves the removal of radioactively contaminated soils and materials and their transportation to a disposal site at Union Carbide Corporation`s Upper Burbank Repository at Uravan, Colorado. The surface cleanup will reduce radon and other radiation emissions from the former uranium processing site and prevent further site-related contamination of ground water. Phase II of the project will evaluate the nature and extent of ground water contamination resulting from uranium processing and its effect on human health and the environment, and will determine site-specific ground water compliance strategies in accordance with the US Environmental Protection Agency (EPA) ground water standards established for the UMTRA Project. Human health risks could occur from drinking water pumped from a hypothetical well drilled in the contaminated ground water area. Environmental risks may result if plants or animals are exposed to contaminated ground water or surface water that has mixed with contaminated ground water. Therefore, a risk assessment was conducted for the Naturita site. This risk assessment report is the first site-specific document prepared for the Ground Water Project at the Naturita site. What follows is an evaluation of current and possible future impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site characterization will be used to determine whether any action is needed to protect human health or the environment.

  13. Baseline risk assessment of ground water contamination at the uranium mill tailings site near Riverton, Wyoming. Revision 1

    SciTech Connect (OSTI)

    NONE

    1995-09-01T23:59:59.000Z

    The Uranium Mill Tailings Remedial Action (UMTRA) Project consists of two phases: the Surface Project and the Ground Water Project. At the UMTRA Project site near Riverton, Wyoming, Surface Project cleanup occurred from 1988 to 1990. Tailings and radioactively contaminated soils and materials were taken from the Riverton site to a disposal cell in the Gas Hills area, about 60 road miles (100 kilometers) to the east. The surface cleanup reduces radon and other radiation emissions and minimizes further ground water contamination. The UMTRA Project`s second phase, the Ground Water Project, will evaluate the nature and extent of ground water contamination at the Riverton site that has resulted from the uranium ore processing activities. Such evaluations are used at each site to determine a strategy for complying with UMTRA ground water standards established by the US Environmental Protection Agency (EPA) and if human health risks could result from exposure to ground water contaminated by uranium ore processing. Exposure could hypothetically occur if drinking water were pumped from a well drilled in an area where ground water contamination might have occurred. Human health and environmental risks may also result if people, plants, or animals are exposed to surface water that has mixed with contaminated ground water.

  14. A Review of Removable Surface Contamination on Radioactive Materials Transportation Containers

    SciTech Connect (OSTI)

    Kennedy, Jr, W. E.; Watson, E. C.; Murphy, D. W.; Harrer, B. J.; Harty, R.; Aldrich, J. M.

    1981-05-01T23:59:59.000Z

    This report contains the results of a study sponsored by the U.S. Nuclear Regulatory Commission (NRC) of removable surface contamination on radioactive materials transportation containers. The purpose of the study is to provide information to the NRC during their review of existing regulations. Data was obtained from both industry and literature on three major topics: 1) radiation doses, 2) economic costs, and 3) contamination frequencies. Containers for four categories of radioactive materials are considered including radiopharmaceuticals, industrial sources, nuclear fuel cycle materials, and low-level radioactive waste. Assumptions made in this study use current information to obtain realistic yet conservative estimates of radiation dose and economic costs. Collective and individual radiation doses are presented for each container category on a per container basis. Total doses, to workers and the public, are also presented for spent fuel cask and low-level waste drum decontamination. Estimates of the additional economic costs incurred by lowering current limits by factors of 10 and 100 are presented. Current contamination levels for each category of container are estimated from the data collected. The information contained in this report is designed to be useful to the NRC in preparing their recommendations for new regulations.

  15. Nevada Test Site 2007 Data Report: Groundwater Monitoring Program Area 5 Radioactive Waste Management Site

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2008-01-01T23:59:59.000Z

    This report is a compilation of the groundwater sampling results from three monitoring wells located near the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS), Nye County, Nevada, for calendar year 2007. The NTS is an approximately 3,561 square kilometer (1,375 square mile) restricted-access federal installation located approximately 105 kilometers (65 miles) northwest of Las Vegas, Nevada (Figure 1). Pilot wells UE5PW-1, UE5PW-2, and UE5PW-3 are used to monitor the groundwater at the Area 5 RWMS (Figure 2). In addition to groundwater monitoring results, this report includes information regarding site hydrogeology, well construction, sample collection, and meteorological data measured at the Area 5 RWMS. The disposal of low-level radioactive waste and mixed low-level radioactive waste at the Area 5 RWMS is regulated by U.S. Department of Energy (DOE) Order 435.1, 'Radioactive Waste Management'. The disposal of mixed low-level radioactive waste is also regulated by the state of Nevada under the Resource Conservation and Recovery Act (RCRA) regulation Title 40 Code of Federal Regulations (CFR) Part 265, 'Interim Status Standards for Owners and Operators of Hazardous Waste Treatment, Storage, and Disposal Facilities' (CFR, 1999). The format of this report was requested by the Nevada Division of Environmental Protection (NDEP) in a letter dated August 12, 1997. The appearance and arrangement of this document have been modified slightly since that date to provide additional information and to facilitate the readability of the document. The objective of this report is to satisfy any Area 5 RWMS reporting agreements between DOE and NDEP.

  16. Ecotoxicity literature review of selected Hanford Site contaminants

    SciTech Connect (OSTI)

    Driver, C.J.

    1994-03-01T23:59:59.000Z

    Available information on the toxicity, food chain transport, and bioconcentration of several Hanford Site contaminants were reviewed. The contaminants included cesium-137, cobalt-60, europium, nitrate, plutonium, strontium-90, technetium, tritium, uranium, and chromium (III and VI). Toxicity and mobility in both aquatic and terrestrial systems were considered. For aquatic systems, considerable information was available on the chemical and/or radiological toxicity of most of the contaminants in invertebrate animals and fish. Little information was available on aquatic macrophyte response to the contaminants. Terrestrial animals such as waterfowl and amphibians that have high exposure potential in aquatic systems were also largely unrepresented in the toxicity literature. The preponderance of toxicity data for terrestrial biota was for laboratory mammals. Bioconcentration factors and transfer coefficients were obtained for primary producers and consumers in representative aquatic and terrestrial systems; however, little data were available for upper trophic level transfer, particularly for terrestrial predators. Food chain transport and toxicity information for the contaminants were generally lacking for desert or sage brush-steppe organisms, particularly plants and reptiles

  17. Contaminant monitoring of biota downstream of a radioactive liquid waste treatment facility, Los Alamos National Laboratory

    SciTech Connect (OSTI)

    Bennett, K.D.; Biggs, J.R.; Fresquez, P.R. [Los Alamos National Lab., NM (United States). Environment, Safety, and Health Div.

    1996-12-31T23:59:59.000Z

    Small mammals, plants, and sediments were sampled at one upstream location (Site 1) and two downstream locations (Site 2 and Site 3) from the National Pollution Discharge Elimination System (NPDES) outfall {number_sign}051-051 in Mortandad Canyon, Los Alamos National Laboratory, Los Alamos, New Mexico. The purpose of the sampling was to identify radionuclides potentially present, to quantitatively estimate and compare the amount of radionuclide uptake at specific locations (Site 2 and Site 3) within Mortandad Canyon to an upstream site (Site 1), and to identify the primary mode (inhalation/ingestion or surface contact) of contamination to small mammals. Three composite samples of at least five animals per sample were collected at each site. The pelt was separated from the carcass of each animal and both were analyzed independently. In addition, three composite samples were also collected for plants and sediments at each site. Samples were analyzed for americium ({sup 241}Am), strontium ({sup 90}Sr), plutonium ({sup 238}Pu and {sup 239}Pu), and total uranium (U). With the exception of total U, all mean radionuclide concentrations in small mammal carcasses and sediments were significantly higher at Site 2 than Site 1 or Site 3. No differences were detected in the mean radionuclide concentration of plant samples between sites. However, some radionuclide concentrations found at all three sites were higher than regional background. No differences were found between mean carcass radionuclide concentrations and mean pelt radionuclide concentrations, indicating that the two primary modes of contamination may be equally occurring.

  18. Concluding Remarks In this work, we have explored in depth many types of radioactive contamination that are

    E-Print Network [OSTI]

    Concluding Remarks In this work, we have explored in depth many types of radioactive contamination!) of 14C per gram of carbon. Sensitivities to uranium and thorium in a 5-kg sample, assuming secular

  19. Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site in Lakeview, Oregon

    SciTech Connect (OSTI)

    Not Available

    1994-10-01T23:59:59.000Z

    This Baseline Risk Assessment of Ground Water Contamination at the Uranium Mill Tailings Site in Lake view, Oregon evaluates potential impacts to public health or the environment resulting from ground water contamination at the former uranium mill processing site.

  20. Four methods for determining the composition of trace radioactive surface contamination of low-radioactivity metal

    E-Print Network [OSTI]

    H. M. O'Keeffe; T. H. Burritt; B. T. Cleveland; G. Doucas; N. Gagnon; N. A. Jelley; C. Kraus; I. T. Lawson; S. Majerus; S. R. McGee; A. W. Myers; A. W. P. Poon; K. Rielage; R. G. H. Robertson; R. C. Rosten; L. C. Stonehill; B. A. VanDevender; T. D. Van Wechel

    2011-03-29T23:59:59.000Z

    Four methods for determining the composition of low-level uranium- and thorium-chain surface contamination are presented. One method is the observation of Cherenkov light production in water. In two additional methods a position-sensitive proportional counter surrounding the surface is used to make both a measurement of the energy spectrum of alpha particle emissions and also coincidence measurements to derive the thorium-chain content based on the presence of short-lived isotopes in that decay chain. The fourth method is a radiochemical technique in which the surface is eluted with a weak acid, the eluate is concentrated, added to liquid scintillator and assayed by recording beta-alpha coincidences. These methods were used to characterize two `hotspots' on the outer surface of one of the He-3 proportional counters in the Neutral Current Detection array of the Sudbury Neutrino Observatory experiment. The methods have similar sensitivities, of order tens of ng, to both thorium- and uranium-chain contamination.

  1. Nevada National Security Site 2013 Data Report: Groundwater Monitoring Program Area 5 Radioactive Waste Management Site

    SciTech Connect (OSTI)

    Hudson, David B

    2014-02-13T23:59:59.000Z

    This report is a compilation of the groundwater sampling results from the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada National Security Site, Nye County, Nevada. Groundwater samples from the aquifer immediately below the Area 5 RWMS have been collected and analyzed and static water levels have been measured in this aquifer since 1993. This report updates these data to include the 2013 results. Beginning with this report, analysis results for leachate collected from the mixed-waste cell at the Area 5 RWMS (Cell 18) are also included.

  2. Converting Limbo Lands to Energy-Generating Stations: Renewable Energy Technologies on Underused, Formerly Contaminated Sites

    SciTech Connect (OSTI)

    Mosey, G.; Heimiller, D.; Dahle, D.; Vimmerstedt, L.; Brady-Sabeff, L.

    2007-10-01T23:59:59.000Z

    This report addresses the potential for using 'Limbo Lands' (underused, formerly contaminated sites, landfills, brownfields, abandoned mine lands, etc. ) as sites for renewable energy generating stations.

  3. Measurement of radioactive contamination in the high-resistivity silicon CCDs of the DAMIC experiment

    E-Print Network [OSTI]

    Aguilar-Arevalo, A; Bertou, X; Bole, D; Butner, M; Cancelo, G; Vázquez, A Castañeda; Chavarria, A E; Neto, J R T de Mello; Dixon, S; D'Olivo, J C; Estrada, J; Moroni, G Fernandez; Torres, K P Hernández; Izraelevitch, F; Kavner, A; Kilminster, B; Lawson, I; Liao, J; López, M; Molina, J; Moreno-Granados, G; Pena, J; Privitera, P; Sarkis, Y; Scarpine, V; Schwarz, T; Haro, M Sofo; Tiffenberg, J; Machado, D Torres; Trillaud, F; You, X; Zhou, J

    2015-01-01T23:59:59.000Z

    We present measurements of radioactive contamination in the high-resistivity silicon charge-coupled devices (CCDs) used by the DAMIC experiment to search for dark matter particles. Novel analysis methods, which exploit the unique spatial resolution of CCDs, were developed to identify $\\alpha$ and $\\beta$ particles. Uranium and thorium contamination in the CCD bulk was measured through $\\alpha$ spectroscopy, with an upper limit on the $^{238}$U ($^{232}$Th) decay rate of 5 (15) kg$^{-1}$ d$^{-1}$ at 95% CL. We also searched for pairs of spatially correlated electron tracks separated in time by up to tens of days, as expected from $^{32}$Si-$^{32}$P or $^{210}$Pb-$^{210}$Bi sequences of $\\beta$ decays. The decay rate of $^{32}$Si was found to be $80^{+110}_{-65}$ kg$^{-1}$ d$^{-1}$ (95% CI). An upper limit of $\\sim$35 kg$^{-1}$ d$^{-1}$ (95% CL) on the $^{210}$Pb decay rate was obtained independently by $\\alpha$ spectroscopy and the $\\beta$ decay sequence search. These levels of radioactive contamination are su...

  4. Building of multilevel stakeholder consensus in radioactive waste repository siting

    SciTech Connect (OSTI)

    Dreimanis, A. [Radiation Safety Centre, Riga LV (Latvia)

    2007-07-01T23:59:59.000Z

    This report considers the problem of multilevel consensus building for siting and construction of shared multinational/regional repositories for radioactive waste (RW) deep disposal. In the siting of a multinational repository there appears an essential innovative component of stakeholder consensus building, namely: to reach consent - political, social, economic, ecological - among international partners, in addition to solving the whole set of intra-national consensus building items. An entire partnering country is considered as a higher-level stakeholder - the national stakeholder, represented by the national government, being faced to simultaneous seeking an upward (international) and a downward (intra-national) consensus in a psychologically stressed environment, possibly being characterized by diverse political, economic and social interests. The following theses as a possible interdisciplinary approach towards building of shared understanding and stakeholder consensus on the international scale of RW disposal are forwarded and developed: a) building of international stakeholder consensus would be promoted by activating and diversifying on the international scale multilateral interactions between intra- and international stakeholders, including web-based networks of the RW disposal site investigations and decision-making, as well as networks for international cooperation among government authorities in nuclear safety, b) gradual progress in intergovernmental consensus and reaching multilateral agreements on shared deep repositories will be the result of democratic dialogue, via observing the whole set of various interests and common resolving of emerged controversies by using advanced synergetic approaches of conflict resolution, c) cross-cultural thinking and world perception, mental flexibility, creativity and knowledge are considered as basic prerogatives for gaining a higher level of mutual understanding and consensus for seeking further consensus, for advancing the preparedness to act together, and ultimately - for achieving desired shared goals. It is proposed that self-organized social learning will make it possible to promote adequate perception of risk and prevent, by diminishing uncertainties and unknown factors, social amplification of an imagined risk, as well as to increase the trust level and facilitate more adequate equity perception. The proposed approach to the multilevel stakeholder consensus building on international scale is extrapolated to the present-day activities of siting of such near-surface RW disposal facilities which supposedly could have non-negligible trans-boundary impact. A multilevel stakeholder interaction process is considered for the case of resolving of emerged problems in site selection for the planned near-surface RW repository in vicinity of the Lithuanian-Latvian border foreseen for disposal of short lived low- and intermediate level waste arising from the decommissioning of the Ignalina Nuclear Power Plant. (authors)

  5. Nuclear Operations Application to Environmental Restoration at Corrective Action Unit 547, Miscellaneous Contaminated Waste Sites, at the Nevada National Security Site

    SciTech Connect (OSTI)

    Kevin Cabble (NSO), Mark Krauss and Patrick Matthews (N-I)

    2011-03-03T23:59:59.000Z

    The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office has responsibility for environmental restoration at the Nevada National Security Site (formerly the Nevada Test Site). This includes remediation at locations where past testing activities have resulted in the release of plutonium to the environment. One of the current remediation efforts involves a site where an underground subcritical nuclear safety test was conducted in 1964. The underground test was vented through a steel pipe to the surface in a closed system where gas samples were obtained. The piping downstream of the gas-sampling apparatus was routed belowground to a location where it was allowed to vent into an existing radioactively contaminated borehole. The length of the pipe above the ground surface is approximately 200 meters. This pipe remained in place until remediation efforts began in 2007, at which time internal plutonium contamination was discovered. Following this discovery, an assessment was conducted to determine the quantity of plutonium present in the pipe. This site has been identified as Corrective Action Unit (CAU) 547, Miscellaneous Contaminated Waste Sites. The quantity of plutonium identified at CAU 547 exceeded the Hazard Category 3 threshold but was below the Hazard Category 2 threshold specified in DOE Standard DOE-STD-1027-92. This CAU, therefore, was initially categorized as a Hazard Category 3 environmental restoration site. A contaminated facility or site that is initially categorized as Hazard Category 3, however, may be downgraded to below Hazard Category 3 if it can be demonstrated through further analysis that the form of the material and the energy available for release support reducing the hazard category. This is an important consideration when performing hazard categorization of environmental restoration sites because energy sources available for release of material are generally fewer at an environmental restoration site than at an operating facility and environmental restoration activities may result in the complete removal of source material.

  6. Performance Assessment Transport Modeling of Uranium at the Area 5 Radioactive Waste Management Site at the Nevada National Security Site

    SciTech Connect (OSTI)

    NSTec Radioactive Waste

    2010-10-12T23:59:59.000Z

    Following is a brief summary of the assumptions that are pertinent to the radioactive isotope transport in the GoldSim Performance Assessment model of the Area 5 Radioactive Waste Management Site, with special emphasis on the water-phase reactive transport of uranium, which includes depleted uranium products.

  7. Single-Pass Flow-Through Test Elucidation of Weathering Behavior and Evaluation of Contaminant Release Models for Hanford Tank Residual Radioactive Waste

    SciTech Connect (OSTI)

    Cantrell, Kirk J.; Carroll, Kenneth C.; Buck, Edgar C.; Neiner, Doinita; Geiszler, Keith N.

    2013-01-01T23:59:59.000Z

    Contaminant release models are required to evaluate and predict long-term environmental impacts of even residual amounts of high-level radioactive waste after cleanup and closure of radioactively contaminated sites such as the DOE’s Hanford Site. More realistic and representative models have been developed for release of uranium, technetium, and chromium from Hanford Site tanks C-202, C-203, and C-103 residual wastes using data collected with a single-pass flow-through test (SPFT) method. These revised models indicate that contaminant release concentrations from these residual wastes will be considerably lower than previous estimates based on batch experiments. For uranium, a thermodynamic solubility model provides an effective description of uranium release, which can account for differences in pore fluid chemistry contacting the waste that could occur through time and as a result of different closure scenarios. Under certain circumstances in the SPFT experiments various calcium rich precipitates (calcium phosphates and calcite) form on the surfaces of the waste particles, inhibiting dissolution of the underlying uranium phases in the waste. This behavior was not observed in previous batch experiments. For both technetium and chromium, empirical release models were developed. In the case of technetium, release from all three wastes was modeled using an equilibrium Kd model. For chromium release, a constant concentration model was applied for all three wastes.

  8. Physical countermeasures to sustain acceptable living and working conditions in radioactively contaminated residential areas

    E-Print Network [OSTI]

    Andersson, K G; Roed, J

    2003-01-01T23:59:59.000Z

    The Chernobyl accident highlighted the need in nuclear preparedness for robust, effective and sustainable countermeasure strategies for restoration of radioactively contaminated residential areas. Under the EC-supporter STRATEGY project a series of investigations were made of countermeasures that were deemed potentially applicable for implementation in such events in European Member States. The findings are presented in this report, in a standardised data sheet format to clarify the features of the individual methods and facilitate intercomparison. The aspects of averted doses and management of wastes generated by countermeasures had to be described separately to provide room for the required level of detail. The information is mainly intended as a tool for decision makers and planners and constitutes of basis for the STRATEGY decision framework for remediation of contaminated urban areas. (au)

  9. Native Plant Uptake Model for Radioactive Waste Disposal Areas at the Nevada Test Site

    SciTech Connect (OSTI)

    BROWN,THERESA J.; WIRTH,SHARON

    1999-09-01T23:59:59.000Z

    This report defines and defends the basic framework, methodology, and associated input parameters for modeling plant uptake of radionuclides for use in Performance Assessment (PA) activities of Radioactive Waste Management Sites (RWMS) at the Nevada Test Site (NTS). PAs are used to help determine whether waste disposal configurations meet applicable regulatory standards for the protection of human health, the environment, or both. Plants adapted to the arid climate of the NTS are able to rapidly capture infiltrating moisture. In addition to capturing soil moisture, plant roots absorb nutrients, minerals, and heavy metals, transporting them within the plant to the above-ground biomass. In this fashion, plant uptake affects the movement of radionuclides. The plant uptake model presented reflects rooting characteristics important to plant uptake, biomass turnover rates, and the ability of plants to uptake radionuclides from the soil. Parameters are provided for modeling plant uptake and estimating surface contaminant flux due to plant uptake under both current and potential future climate conditions with increased effective soil moisture. The term ''effective moisture'' is used throughout this report to indicate the soil moisture that is available to plants and is intended to be inclusive of all the variables that control soil moisture at a site (e.g., precipitation, temperature, soil texture, and soil chemistry). Effective moisture is a concept used to simplify a number of complex, interrelated soil processes for which there are too little data to model actual plant available moisture. The PA simulates both the flux of radionuclides across the land surface and the potential dose to humans from that flux. Surface flux is modeled here as the amount of soil contamination that is transferred from the soil by roots and incorporated into aboveground biomass. Movement of contaminants to the surface is the only transport mechanism evaluated with the model presented here. Parameters necessary for estimating surface contaminant flux due to native plants expected to inhabit the NTS RWMSS are developed in this report. The model is specific to the plant communities found at the NTS and is designed for both short-term (<1,000 years) and long-term (>1,000 years) modeling efforts. While the model has been crafted for general applicability to any NTS PA, the key radionuclides considered are limited to the transuranic (TRU) wastes disposed of at the NTS.

  10. alcatraz disposal site: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    and Radium-226 are the predominant radioactive contaminents on Formerly Utilized Sites Remedial Action Plan (FUSRAP) sites. Engineering Websites Summary: by the nearby disposal...

  11. A field strategy to monitor radioactivity associated with investigation derived wastes returned from deep drilling sites

    SciTech Connect (OSTI)

    Rego, J.H.; Smith, D.K.; Friensehner, A.V.

    1995-05-26T23:59:59.000Z

    The U.S. Department of Energy, Nevada Operations Office, Underground Test Area Operable Unit (UGTA) is drilling deep (>1500m) monitoring wells that penetrate both unsaturated (vadose) and saturated zones potentially contaminated by sub-surface nuclear weapons testing at the Nevada Test Site, Nye County, Nevada. Drill site radiological monitoring returns data on drilling effluents to make informed management decisions concerning fluid management. Because of rapid turn-around required for on-site monitoring, a representative sample will be analyzed simultaneously for {alpha}, {beta} and {gamma} emitters by instrumentation deployed on-site. For the purposes of field survey, accurate and precise data is returned, in many cases, with minimal sample treatment. A 30% efficient high purity germanium detector and a discriminating liquid scintillation detector are being evaluated for {gamma} and {alpha}/{beta} monitoring respectively. Implementation of these detector systems complements a successful on-site tritium monitoring program. Residual radioactivity associated with underground nuclear tests include tritium, activation products, fission products and actinides. Pulse shape discrimination (PSD) is used in {alpha}/{beta} liquid scintillation counting and is a function of the time distribution of photon emission. In particular, we hope to measure {sup 241}Am produced from {sup 241}Pu by {beta} decay. Because {sup 241}Pu is depleted in fissile bomb fuels, maximum PSD resolution will be required. The high purity germanium detector employs a multichannel analyzer to count gamma emitting radionuclides; we will designate specific window configurations to selectively monitor diagnostic fission product radionuclides (i.e., {sup 137}Cs).

  12. Closure Plan for the Area 5 Radioactive Waste Management Site at the Nevada Test Site

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2008-09-01T23:59:59.000Z

    The Area 5 Radioactive Waste Management Site (RMWS) at the Nevada Test Site (NTS) is managed and operated by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This document is the first update of the preliminary closure plan for the Area 5 RWMS at the NTS that was presented in the Integrated Closure and Monitoring Plan (DOE, 2005a). The major updates to the plan include a new closure schedule, updated closure inventory, updated site and facility characterization data, the Title II engineering cover design, and the closure process for the 92-Acre Area of the RWMS. The format and content of this site-specific plan follows the Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans (DOE, 1999a). This interim closure plan meets closure and post-closure monitoring requirements of the order DOE O 435.1, manual DOE M 435.1-1, Title 40 Code of Federal Regulations (CFR) Part 191, 40 CFR 265, Nevada Administrative Code (NAC) 444.743, and Resource Conservation and Recovery Act (RCRA) requirements as incorporated into NAC 444.8632. The Area 5 RWMS accepts primarily packaged low-level waste (LLW), low-level mixed waste (LLMW), and asbestiform low-level waste (ALLW) for disposal in excavated disposal cells.

  13. Integrated Closure and Monitoring Plan for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site

    SciTech Connect (OSTI)

    Bechtel Nevada

    2005-06-01T23:59:59.000Z

    This document is an integrated plan for closing and monitoring two low-level radioactive waste disposal sites at the Nevada Test Site.

  14. IN-SITU, LONG-TERM MONITORING SYSTEM FOR RADIOACTIVE CONTAMINANTS

    SciTech Connect (OSTI)

    James S. Durham; Stephen W.S. McKeever; Mark S. Akselrod

    2002-10-01T23:59:59.000Z

    This report presents the results of the first phase of the project entitled ''In-situ, Long-term Monitoring System for Radioactive Contaminants.'' Phase one of this effort included four objectives, each with specific success criteria. The first objective was to produce dosimetry grade fibers and rods of aluminum oxide. The success criterion for this milestone was the production of aluminum oxide rods and fibers that have a minimum measurable dose (MMD) of 100 mrem or less. This milestone was completed and the MMD for the rods was measured to be 1.53 mrem. Based on the MMD, the ability of the sensor to measure {sup 137}Cs, {sup 90}Sr/{sup 90}Y, and {sup 99}Tc was evaluated. It was determined that the sensor can measure the release limit of these radionuclides (50 pCi/cm{sup 3}) in 150 h, 200 h, and 54,000 h, respectively. The monitor is adequate for measuring {sup 137}Cs and {sup 90}Sr/{sup 90}Y but is unsuitable for measuring {sup 99}Tc in soil. The second objective was to construct a prototype sensor (dosimeter and fiber optic channel). There were three success criteria for this milestone: (1) Perform measurements with the sensor for both gamma and beta radiation with a standard deviation of 10% or less; (2) Demonstrate the ability of the sensor to discriminate between gamma and beta radiation; and (3) Obtain similar or relatable results for differing lengths of fiber optic cable. These milestones were met. The sensor was able to measure gamma radiation repeatedly with a standard deviation of 3.15% and beta radiation with a standard deviation of 2.85%. Data is presented that demonstrates that an end cap can be used to discriminate between beta plus gamma radiation using beta radiation from a {sup 90}Sr/{sup 90}Y source, and gamma radiation alone. It is shown that some amount of attenuation occurs in longer fiber optic cables, but it is unclear if the attenuation is due to poor alignment of the dosimeter and the cable. This issue will be investigated further when more dosimeters are available so that the dosimeters can be permanently attached to the longer cables. The third objective was to identify a demonstration site. The success criterion for this milestone was to obtain a written agreement from a DOE site to host the demonstration of the monitor during the third phase. Because of uncertainties in funding of the second and third phases of this effort, a written agreement was not obtained. Instead, verbal agreements were reached with both Hanford and the Nevada Test Site. It is believed that the verbal agreements meet the intent of the objective. The final objective was to prepare the Draft Phase I Topical Report. The success criterion for this milestone was to have the report accepted by NETL. It is anticipated that this objective will be met.

  15. IN-SITU, LONG-TERM MONITORING SYSTEM FOR RADIOACTIVE CONTAMINANTS

    SciTech Connect (OSTI)

    James S. Durham; Stephen W.S. McKeever; Mark S. Akselrod

    2002-10-01T23:59:59.000Z

    This report presents the results of the first phase of the project entitled ''In-situ, Long-term Monitoring System for Radioactive Contaminants.'' Phase one of this effort included four objectives, each with specific success criteria. The first objective was to produce dosimetry grade fibers and rods of aluminum oxide. The success criterion for this milestone was the production of aluminum oxide rods and fibers that have a minimum measureable dose (MMD) of 100 mrem or less. This milestone was completed and the MMD for the rods was measured to be 1.53 mrem. Based on the MMD, the ability of the sensor to measure {sup 137}Cs, {sup 90}Sr/{sup 90}Y, and {sup 99}Tc was evaluated. It was determined that the sensor can measure the release limit of these radionuclides (50 pCi/cm{sup 3}) in 150 h, 200 h, and 54,000 h, respectively. The monitor is adequate for measuring {sup 137}Cs and {sup 90}Sr/{sup 90}Y but is unsuitable for measuring {sup 99}Tc in soil. The second objective was to construct a prototype sensor (dosimeter and fiber optic channel). There were three success criteria for this milestone: (1) Perform measurements with the sensor for both gamma and beta radiation with a standard deviation of 10% or less; (2) Demonstrate the ability of the sensor to discriminate between gamma and beta radiation; and (3) Obtain similar or relatable results for differing lengths of fiber optic cable. These milestones were met. The sensor was able to measure gamma radiation repeatedly with a standard deviation of 3.15% and beta radiation with a standard deviation of 2.85%. Data is presented that demonstrates that an end cap can be used to discriminate between beta plus gamma and gamma radiation. It is shown that some amount of attenuation occurs in longer fiber optic cables, but it is unclear if the attenuation is due to poor alignment of the dosimeter and the cable. This issue will be investigated further when more dosimeters are available so that the dosimeters can be permanently attached to the longer cables. The third objective was to identify a demonstration site. The success criterion for this milestone was to obtain a written agreement from a DOE site to host the demonstration of the monitor during the third phase. Because of uncertainties in funding of the second and third phases of this effort, a written agreement was not obtained. Instead, verbal agreements were reached with both Hanford and the Nevada Test Site. It is believed that the verbal agreements meet the intent of the objective. The final objective was to prepare the Draft Phase I Topical Report. The success criterion for this milestone was to have the report accepted by NETL. It is anticipated that this objective will be met.

  16. The Radioactivity Characteristics of the NPP Charcoal Sample Contaminated by Carbon-14 - 13531

    SciTech Connect (OSTI)

    Kim, Hee Reyoung [Ulsan National Institute of Science and Technology, UNIST-gil 50, Eonyang-eup, Ulju-gun, Ulsan, 689-798 (Korea, Republic of)] [Ulsan National Institute of Science and Technology, UNIST-gil 50, Eonyang-eup, Ulju-gun, Ulsan, 689-798 (Korea, Republic of)

    2013-07-01T23:59:59.000Z

    The radioactivity of {sup 14}C-contaminated charcoal sample was analyzed by using a high temperature oxidation and liquid scintillation counting method. The radioactivity of the sample was monotonically increased according to the increase of the combustion time at each temperature where the experimental uncertainty was calculated in the 95 % confidence level. It showed that the {sup 14}C radioactivity was not completely extracted from the sample by simply increasing the combustion time unless the combustion temperature was high enough. The higher the combustion temperature was, the higher the recovery during the first 30 minutes was. The first 30 minute recoveries were 100 % at a temperature equal to or greater than 450 deg. C. The ratios of the recovery during the first 30 minutes to the total recovery during whole duration were more than 90 % at each experiment temperature. It was understood that the temperature was a critical factor for the complete removal of the {sup 14}C from the waste sample. (authors)

  17. Corrective Action Investigation Plan for Corrective Action Unit 573: Alpha Contaminated Sites, Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Matthews, Patrick

    2014-05-01T23:59:59.000Z

    Corrective Action Unit (CAU) 573 is located in Area 5 of the Nevada National Security Site, which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 573 is a grouping of sites where there has been a suspected release of contamination associated with non-nuclear experiments and nuclear testing. This document describes the planned investigation of CAU 573, which comprises the following corrective action sites (CASs): • 05-23-02, GMX Alpha Contaminated Area • 05-45-01, Atmospheric Test Site - Hamilton These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives.

  18. 1999 data report: Groundwater monitoring program Area 5 Radioactive Waste Management Site

    SciTech Connect (OSTI)

    Yvonne Townsend

    2000-03-01T23:59:59.000Z

    This report is a compilation of the annual 1999 groundwater sampling results from the Area 5 Radioactive Waste Management Site (RWMS). Contamination indicator data are presented in control chart and tabular form with investigation levels indicated. Gross water chemistry data are presented in graphical and tabular form. Other information in the report includes, the Cumulative Chronology for Area 5 RWMS Groundwater Monitoring Program, a brief description of the site hydrogeology and the groundwater sampling procedure. Wells Ue5PW-1, Ue5PW-2, and Ue5PW-3 were sampled semiannually for pH, specific conductance, major cations/anions, metals, tritium, total organic carbon (TOC), and total organic halogen (TOX). Results indicate that there has been no measurable impact to the uppermost aquifer from the Resource Conservation and Recovery Act (RCRA) regulated unit within the Area 5 RWMS. Groundwater elevation was monitored quarterly with no major changes noted. There continues to be an extremely small gradient to the northeast with a flow velocity less than one foot per year; however, this is subject to change because the wells have a similar groundwater elevation.

  19. IMPACT OF TARGET MATERIAL ACTIVATION ON PERSONNEL EXPOSURE AND RADIOACTIVE CONTAMINATION IN THE NATIONAL IGNITION FACILITY

    SciTech Connect (OSTI)

    Khater, H; Epperson, P; Thacker, R; Beale, R; Kohut, T; Brereton, S

    2009-06-30T23:59:59.000Z

    Detailed activation analyses are performed for the different materials under consideration for use in the target capsules and hohlraums used during the ignition campaign on the National Ignition Facility. Results of the target material activation were additionally used to estimate the levels of contamination within the NIF target chamber and the workplace controls necessary for safe operation. The analysis examined the impact of using Be-Cu and Ge-doped CH capsules on the external dose received by workers during maintenance activities. Five days following a 20 MJ shot, dose rates inside the Target Chamber (TC) due to the two proposed capsule materials are small ({approx} 1 {micro}rem/h). Gold and depleted-uranium (DU) are considered as potential hohlraum materials. Following a shot, gold will most probably get deposited on the TC first wall. On the other hand, while noble-gas precursors from the DU are expected to stay in the TC, most of the noble gases are pumped out of the chamber and end up on the cryopumps. The dose rates inside the TC due to activated gold or DU, at 5 days following a 20 MJ shot, are about 1 mrem/h. Dose rates in the vicinity of the cryo-pumps (containing noble 'fission' gases) drop-off to about 1 mrem/h during the first 12 hours following the shot. Contamination from activation of NIF targets will result in the NIF target chamber exceeding DOE surface contamination limits. Objects removed from the TC will need to be managed as radioactive material. However, the results suggest that airborne contamination from resuspension of surface contamination will not be significant and is at levels that can be managed by negative ventilation when accessing the TC attachments.

  20. Hanford Site annual dangerous waste report: Volume 4, Waste Management Facility report, Radioactive mixed waste

    SciTech Connect (OSTI)

    NONE

    1994-12-31T23:59:59.000Z

    This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, handling method and containment vessel, waste number, waste designation and amount of waste.

  1. Hanford Site annual dangerous waste report: Volume 2, Generator dangerous waste report, radioactive mixed waste

    SciTech Connect (OSTI)

    NONE

    1994-12-31T23:59:59.000Z

    This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, waste number, waste designation, weight, and waste designation.

  2. Siting of low-level radioactive waste disposal facilities in Texas

    E-Print Network [OSTI]

    Isenhower, Daniel Bruce

    1982-01-01T23:59:59.000Z

    University property was evaluated for suitability for disposal of low-level radioactive waste. This site was evaluated to demonstrate, briefly, the site characterization process and to determine the ability of the statewide study to accurately predict... these boreholes. Literature review was an additional method employed to characterize the site. The results of this site characterization reveal that a more extensive investigation would be necessary to completely evaluate the site and that the state- wide...

  3. Radioactive contamination of the Arctic Region, Baltic Sea, and the Sea of Japan from activities in the former Soviet Union

    SciTech Connect (OSTI)

    Bradley, D.J.

    1992-09-01T23:59:59.000Z

    Contamination of the Arctic regions of northern Europe and Russia, as well as the Sea of Japan, may become a potential major hazard to the ecosystem of these large areas. Widespread poor radioactive waste management practices from nuclear fuel cycle activities in the former Soviet Union have resulted in direct discharges to this area as well as multiple sources that may continue to release additional radioactivity. Information on the discharges of radioactive materials has become more commonplace in the last year, and a clearer picture is emerging of the scale of the contamination. Radioactivity in the Arctic oceans is now reported to be four times higher than would be derived from fallout from weapons tests. Although the characteristics and extent of the contamination are not well known, it has been stated that the contamination in the Arctic may range from 1 to 3.5 billion curies. As yet, no scientific sampling or measurement program has occurred that can verify the amount or extent of the contamination, or its potential impact on the ecosystem.

  4. Analysis of potential groundwater contamination in the vicinity of the Weldon Spring Raffinate Pits site, Weldon Spring, Missouri

    SciTech Connect (OSTI)

    Tsai, S.Y.; Peterson, J.M.; Winters, M.C.B.

    1984-08-01T23:59:59.000Z

    Results of the analysis of contaminant migration beneath the raffinate pits at the Weldon Spring Raffinate Pits site indicate that during a 10,000-year time period, the maximum concentrations in the water immediately beneath the pit bottoms would be about 4600 pCi/L of radium-226 (Pit 3) and about 12,000 pCi/L of uranium-238 (Pit 1); these concentrations would occur at the centers of the pit bottoms. Based on the assumptions used in this study, the radioactive contaminants in the pits would migrate no more than 2 m (7 ft) below the pit bottoms. Because 6 to 12 m (20 to 40 ft) of silty clays underlie the raffinate pits, the radioactive contaminants would take several tens of thousands of years to reach nearby groundwater supplies. Although the results of these analyses indicate that a high degree of confinement is provided by the four raffinate pits, it should be noted that the validity of such analyses rests on the quality of the parameter values utilized. Due to a lack of current site-specific data for some physical parameters, it has been necessary to use historical and regional data for these values. The values cited are at times inconsistent and contradictory, e.g., the wide range of values indicated for the permeability of clays underlying the pits. However, these were the only data available. The analysis reported herein indicates that within the limitations of the available data, use of the Raffinate Pits site for long-term management of radioactive materials such as those currently being stored in the four pits appears to be feasible. 24 references, 14 figures, 7 tables.

  5. Global samples from nuclear contamination sites reveal unpredicted...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    elements, weather and heat is essential in determining whether that chemical is hazardous. This is especially important when that chemical is radioactive. In a...

  6. Reading contamination : an environmental education center at the Wells G&H Superfund Site

    E-Print Network [OSTI]

    Berry, Rebecca Lynn, 1973-

    1999-01-01T23:59:59.000Z

    This thesis proposes and architectural and programmatic methodology which makes legible the processes and consequences of site contamination. This methodology is chiefly demonstrated through a plan for the site which emerges ...

  7. Baseline risk assessment of ground water contamination at the uranium mill tailings site near Durango, Colorado

    SciTech Connect (OSTI)

    Not Available

    1995-02-01T23:59:59.000Z

    This risk assessment evaluates the possibility of health and environmental risks from contaminated ground water at the uranium mill tailings site near Durango, Colorado. The former uranium processing site`s contaminated soil and material were removed and placed at a disposal site located in Body Canyon, Colorado, during 1986--1991 by the US Departments of Energy`s Uranium Mill Tailings Remedial Action (UMTRA) Project. Currently, the UMTRA Project is evaluating the nature and extent of ground water contamination at the site. This risk assessment follows an approach similar to that used by the US Environmental Protection Agency. The first step is to determine what site-related contaminants are found in ground water samples. The next step in the risk assessment is to determine how much of these contaminants people might ingest if they got their drinking water from a well on the site. In accordance with standard practice for this type of risk assessment, the highest contaminant concentrations from the most contaminated wells are used. The risk assessment then explains the possible health problems that could result from this amount of contamination.

  8. Hanford Site Shares Lessons Learned in Retrieving Highly Radioactive...

    Energy Savers [EERE]

    Company (CH2M HILL), welcomed staff from the Oak Ridge Office of Environmental Management Transuranic (TRU) waste processing team in Tennessee to the Hanford site...

  9. Operational Strategies for Low-Level Radioactive Waste Disposal Site in Egypt - 13513

    SciTech Connect (OSTI)

    Mohamed, Yasser T. [Hot Laboratories and Waste Management Center, Atomic Energy Authority, 3 Ahmed El-Zomor St., El-Zohour District, Naser City, 11787, Cairo (Egypt)] [Hot Laboratories and Waste Management Center, Atomic Energy Authority, 3 Ahmed El-Zomor St., El-Zohour District, Naser City, 11787, Cairo (Egypt)

    2013-07-01T23:59:59.000Z

    The ultimate aims of treatment and conditioning is to prepare waste for disposal by ensuring that the waste will meet the waste acceptance criteria of a disposal facility. Hence the purpose of low-level waste disposal is to isolate the waste from both people and the environment. The radioactive particles in low-level waste emit the same types of radiation that everyone receives from nature. Most low-level waste fades away to natural background levels of radioactivity in months or years. Virtually all of it diminishes to natural levels in less than 300 years. In Egypt, The Hot Laboratories and Waste Management Center has been established since 1983, as a waste management facility for LLW and ILW and the disposal site licensed for preoperational in 2005. The site accepts the low level waste generated on site and off site and unwanted radioactive sealed sources with half-life less than 30 years for disposal and all types of sources for interim storage prior to the final disposal. Operational requirements at the low-level (LLRW) disposal site are listed in the National Center for Nuclear Safety and Radiation Control NCNSRC guidelines. Additional procedures are listed in the Low-Level Radioactive Waste Disposal Facility Standards Manual. The following describes the current operations at the LLRW disposal site. (authors)

  10. Corrective Action Decision Document/Closure Report for Corrective Action Unit 545: Dumps, Waste Disposal Sites, and Buried Radioactive Materials Nevada Test Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Alfred Wickline

    2008-04-01T23:59:59.000Z

    This Corrective Action Decision Document (CADD)/Closure Report (CR) has been prepared for Corrective Action Unit (CAU) 545, Dumps, Waste Disposal Sites, and Buried Radioactive Materials, in Areas 2, 3, 9, and 20 of the Nevada Test Site, Nevada, in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management (1996, as amended February 2008). Corrective Action Unit 545 is comprised of the following eight Corrective Action Sites (CASs): • 02-09-01, Mud Disposal Area • 03-08-03, Mud Disposal Site • 03-17-01, Waste Consolidation Site 3B • 03-23-02, Waste Disposal Site • 03-23-05, Europium Disposal Site • 03-99-14, Radioactive Material Disposal Area • 09-23-02, U-9y Drilling Mud Disposal Crater • 20-19-01, Waste Disposal Site While all eight CASs are addressed in this CADD/CR, sufficient information was available for the following three CASs; therefore, a field investigation was not conducted at these sites: • For CAS 03-08-03, though the potential for subsidence of the craters was judged to be extremely unlikely, the data quality objective (DQO) meeting participants agreed that sufficient information existed about disposal and releases at the site and that a corrective action of close in place with a use restriction is recommended. Sampling in the craters was not considered necessary. • For CAS 03-23-02, there were no potential releases of hazardous or radioactive contaminants identified. Therefore, the Corrective Action Investigation Plan for CAU 545 concluded that: “Sufficient information exists to conclude that this CAS does not exist as originally identified. Therefore, there is no environmental concern associated with CAS 03-23-02.” This CAS is closed with no further action. • For CAS 03-23-05, existing information about the two buried sources and lead pig was considered to be sufficient, and safety concerns existed about the stability of the crater component. Therefore, a corrective action of close in place with a use restriction is recommended, and sampling at the site was not considered necessary. The purpose of this CADD/CR is to provide justification and documentation to support the recommendation for closure of CAU 545 with no further corrective action. To achieve this, corrective action investigation (CAI) activities were performed from August 20 through November 02, 2007, as set forth in the CAU 545 Corrective Action Investigation Plan. The purpose of the CAI was to fulfill the following data needs as defined during the DQO process: • Determine whether contaminants of concern (COCs) are present. • If COCs are present, determine their nature and extent. • Provide sufficient information and data to complete appropriate corrective actions. The CAU 545 dataset from the investigation results was evaluated based on the data quality indicator parameters. This evaluation demonstrated the quality and acceptability of the dataset for use in fulfilling the DQO data needs. Analytes detected during the CAI were evaluated against final action levels established in this CADD/CR. The results of the CAI identified no COCs at the five CASs investigated in CAU 545. As a best management practice, repair of the fence enclosing CAS 03-08-03 has been completed. Therefore, the DOE, National Nuclear Security Administration Nevada Site Office provides the following recommendations: • Close in place COCs at CASs 03-08-03 and 03-23-05 with use restrictions. • No further corrective action for CAU 545. • No Corrective Action Plan. • Corrective Action Unit 545 should be moved from Appendix III to Appendix IV of the Federal Facility Agreement and Consent Order. • A Notice of Completion to the DOE, National Nuclear Security Administration Nevada Site Office is requested from the Nevada Division of Environmental Protection for closure of CAU 545.

  11. Closure Report for Corrective Action Unit 547: Miscellaneous Contaminated Waste Sites, Nevada National Security Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2012-07-17T23:59:59.000Z

    This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 547, Miscellaneous Contaminated Waste Sites, and provides documentation supporting the completed corrective actions and confirmation that closure objectives for CAU 547 were met. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; the U.S. Department of Energy (DOE), Environmental Management; the U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996 as amended). CAU 547 consists of the following three Corrective Action Sites (CASs), located in Areas 2, 3, and 9 of the Nevada National Security Site: (1) CAS 02-37-02, Gas Sampling Assembly; (2) CAS 03-99-19, Gas Sampling Assembly; AND (3) CAS 09-99-06, Gas Sampling Assembly Closure activities began in August 2011 and were completed in June 2012. Activities were conducted according to the Corrective Action Decision Document/Corrective Action Plan (CADD/CAP) for CAU 547 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2011). The recommended corrective action for the three CASs in CAU 547 was closure in place with administrative controls. The following closure activities were performed: (1) Open holes were filled with concrete; (2) Steel casings were placed over vertical expansion joints and filled with cement; (3) Engineered soil covers were constructed over piping and exposed sections of the gas sampling system components; (4) Fencing, monuments, Jersey barriers, radiological postings, and use restriction (UR) warning signs were installed around the perimeters of the sites; (5) Housekeeping debris was picked up from around the sites and disposed; and (6) Radiological surveys were performed to confirm final radiological postings. UR documentation is included in Appendix D. The post-closure plan was presented in detail in the CADD/CAP for CAU 547 and is included as Appendix F of this report. The requirements are summarized in Section 5.2 of this report. The proposed post-closure requirements consist of visual inspections to determine the condition of postings and radiological surveys to verify contamination has not migrated. NNSA/NSO requests the following: (1) A Notice of Completion from the Nevada Division of Environmental Protection to NNSA/NSO for closure of CAU 547; and (2) The transfer of CAU 547 from Appendix III to Appendix IV, Closed Corrective Action Units, of the FFACO.

  12. Waste Disposal Site and Radioactive Waste Management (Iowa)

    Broader source: Energy.gov [DOE]

    This section describes the considerations of the Commission in determining whether to approve the establishment and operation of a disposal site for nuclear waste. If a permit is issued, the...

  13. Baseline risk assessment of ground water contamination at the uranium mill tailings site near Canonsburg, Pennsylvania

    SciTech Connect (OSTI)

    Not Available

    1994-09-01T23:59:59.000Z

    This baseline risk assessment evaluates potential impacts to public health and the environment resulting from ground water contamination from past activities at the former uranium processing site in Canonsburg, Pennsylvania. The US Department of Energy Uranium Mill Tailings Remedial Action (UMTRA) Project has placed contaminated material from this site in an on-site disposal cell. Currently, the UMTRA Project is evaluating ground water contamination. This risk assessment is the first document specific to this site for the UMTRA Ground Water Project. Currently, no domestic or drinking water well tap into contaminated ground water of the two distinct ground water units: the unconsolidated materials and the bedrock. Because there is no access, no current health or environmental risks are associated with the direct use of the contaminated ground water. However, humans and ecological organisms could be exposed to contaminated ground water if a domestic well were to be installed in the unconsolidated materials in that part of the site being considered for public use (Area C). The first step is evaluating ground water data collected from monitor wells at the site. For the Canonsburg site, this evaluation showed the contaminants in ground water exceeding background in the unconsolidated materials in Area C are ammonia, boron, calcium, manganese, molybdenum, potassium, strontium, and uranium.

  14. Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site near Riverton, Wyoming

    SciTech Connect (OSTI)

    Not Available

    1994-09-01T23:59:59.000Z

    This Risk Assessment evaluated potential impacts to public health or the environment caused by ground water contamination at the former uranium mill processing site. In the first phase of the U.S. Department of Energy`s Uranium Mill Tailings Remedial Action (UMTRA) Project, the tailing and other contaminated material at this site were placed in a disposal cell near the Gas Hills Plant in 1990. The second phase of the UMTRA Project is to evaluate ground water contamination. This risk assessment is the first site-specific document to evaluate potential health and environmental risks for the Riverton site under the Ground Water Project; it will help determine whether remedial actions are needed for contaminated ground water at the site.

  15. Special Analysis of the Area 3 Radioactive Waste Management Site at the Nevada National Security Site, Nye County, Nevada

    SciTech Connect (OSTI)

    National Security Technologies, LLC, Environmental Management

    2012-09-30T23:59:59.000Z

    This report describes the methods and results of a special analysis (SA) of the Area 3 Radioactive Waste Management Site (RWMS) on the Nevada National Security Site (NNSS). The purpose of the SA is to determine if the approved performance assessment (PA) and composite analysis (CA) (Shott et al., 2001) remain valid. The Area 3 RWMS PA and CA were prepared as a single document and received conditional approval on October 6, 1999. A conditional Disposal Authorization Statement (DAS) for the Area 3 RWMS was issued on October 20, 1999. Since preparation of the approved PA and CA, new information and additional environmental monitoring data have been used to update the PA and CA. At the same time, continual advancements in computer processors and software have allowed improvement to the PA and CA models. Annual reviews of the PA and CA required by U.S. Department of Energy (DOE) Order DOE O 435.1 have documented multiple changes occurring since preparation of the PA and CA. Potentially important changes include: Development of a new and improved baseline PA and CA model implemented in the probabilistic GoldSim simulation platform. A significant increase in the waste inventory disposed at the site. Revision and updating of model parameters based on additional years of site monitoring data and new research and development results. Although changes have occurred, many important PA/CA issues remain unchanged, including the site conceptual model, important features, events, and processes, and the points of compliance. The SA is performed to document the current status of the PA/CA model and to quantitatively assess the impact of cumulative changes on the PA and CA results. The results of the SA are used to assess the validity of the approved PA/CA and make a determination if revision of the PA or CA is necessary. The SA was performed using the Area 3 RWMS, version 2.102, GoldSim model, the current baseline PA/CA model. Comparison of the maximum SA results with the PA performance objectives indicates that there continues to be a reasonable expectation of compliance. The resident exposure scenario was evaluated for compliance with the air pathway and all-pathways annual total effective dose (TED) performance objectives. The maximum mean air pathway TED, 7E-6 millisievert (mSv) at 1,000 years (y) has decreased relative to the approved PA and is significantly less than the 0.1 mSv limit. The maximum mean all-pathways annual TED, 7E-5 mSv at 1,000 y has increased but remains a small fraction of the 0.25 mSv limit. The SA maximum mean radon-222 (222Rn) flux density, 0.03 becquerel per square meter per second (Bq m-2 s-1), has increased relative to the PA results but is significantly less than the 0.74 Bq m-2 s-1 limit. The SA results continue to support a conclusion that the disposed waste inventory is protective of intruders and groundwater resources. The maximum mean intruder TED, 0.01 mSv for an acute construction scenario at the U-3ah/at disposal unit, was less than the 5 mSv performance measure. Site monitoring data and research results continue to support a conclusion that a groundwater pathway will not exist within the 1,000 y compliance period. Projected releases to the environment are a small fraction of the performance objectives. Cost-effective options for reducing releases further are unlikely to exist. Therefore, releases from the Area 3 RWMS are judged to be as low as reasonably achievable. Comparison of the maximum CA result with the 0.3 mSv CA dose constraint indicates that no action is required to reduce the dose from the Area 3 RWMS and all interacting sources of residual radioactive contamination. The SA maximum mean CA annual TED, 0.02 mSv at 1,000 y, has increased from the approved CA result but remains less than 10% of the dose constraint. The CA TED continues to be due predominantly to inhalation of plutonium-239 resuspended from soils contaminated by nuclear weapons tests conducted near the Area 3 RWMS. The SA results estimated with the Area 3 RWMS version 2.102 model indicate that changes to the PA and CA do not

  16. Characterization of the National Petroleum Reserve No. 3 (NPR-3) Site for Naturally Occurring Radioactive Material(NORM)

    SciTech Connect (OSTI)

    White, G.J; Rood, A.S.

    1999-01-21T23:59:59.000Z

    The National Petroleum Reserve No. 3 site (NPR-3) near Casper, Wyoming is being prepared for transfer to private industry. Remediation of the NPR-3 site has already begun in anticipation of this transfer. This document describes the characterization of the NPR-3 site for Naturally Occurring Radioactive Materials (NORM). Data generated on radionuclide concentrations and radon emanation may be used to determine disposal options and the need for remediation at this site. A preliminary gamma survey of the NPR-3 site was conducted to identify areas of potential NORM contamination. Based on these gamma surveys, two general areas of NORM contamination were found: the North Water Flood area and the BTP-10 produced water discharge steam. A maximum surface exposure rate of 120 {micro}R h{sup -1} was observed in the North Water Flood area, with the highest readings found along the drainage channel from the area. Exposure rates dropped to background quickly with increasing distance from the center of the drainage. The maximum observed exposure rate in the BTP-10 produced water drainage was 40 {micro}R h{sup -1}. Soil and sediment sampling were concentrated in these two areas. All samples were analyzed for concentration of {sup 226}Ra, {sup 228}Ra, and {sup 40}K. Maximum {sup 226}Ra concentrations observed in the samples collected were 46 pCi g{sup -1} for soil and 78 pCi g{sup -1} for sediment. Concentrations in most samples were considerably lower than these values. Radon emanation fraction was also measured for a randomly selected fraction of the samples. The mean Rn emanation fraction measured was 0.10, indicating that on average only 10 percent of the Rn produced is released from the medium. Based on the results of these analyses, NORM contamination at the NPR-3 site is minimal, and appears to be restricted to the two general areas sampled. Concentrations of NORM radionuclides found soils and sediments in these two locations do not justify remedial actions at present. However, continued discharge of NORM-contaminated produced waters from the BTP-10 area will likely result in the continued accumulation of NORM in sediment. It is therefore recommended that the sediments in the BTP-10 discharge stream be monitored periodically for NORM.

  17. Electrosorption on carbon aerogel electrodes as a means of treating low-level radioactive wastes and remediating contaminated ground water

    SciTech Connect (OSTI)

    Tran, Tri Duc; Farmer, Joseph C.; DePruneda, Jean H.; Richardson, Jeffery H.

    1997-07-01T23:59:59.000Z

    A novel separation process based upon carbon aerogel electrodes has been recently developed for the efficient removal of ionic impurities from aqueous streams. This process can be used as an electrical y- regenerated alternative to ion exchange, thereby reducing-the need for large quantities of chemical regenerants. Once spent (contaminated), these regenerants contribute to the waste that must be disposed of in landfills. The elimination of such wastes is especially beneficial in situations involving radioactive contaminants, and pump and treat processing of massive volumes of ground water. A review and analysis of potential applications will be presented.

  18. Composite Analysis for the Area 5 Radioactive Waste Management Site at the Nevada Test Site, Nye County, Nevada

    SciTech Connect (OSTI)

    V. Yucel

    2001-09-01T23:59:59.000Z

    This report summarizes the results of a Composite Analysis (CA) for the Area 5 Radioactive Waste Management Site (RWMS). The Area 5 RWMS is a US Department of Energy (DOE)-operated low-level radioactive waste (LLW) management site located in northern Frenchman Flat on the Nevada Test Site (NTS). The Area 5 RWMS has disposed of low-level radioactive waste in shallow unlined pits and trenches since 1960. Transuranic waste (TRU) and high-specific activity waste was disposed in Greater Confinement Disposal (GCD) boreholes from 1983 to 1989. The purpose of this CA is to determine if continuing operation of the Area 5 RWMS poses an acceptable or unacceptable risk to the public considering the total waste inventory and all other interacting sources of radioactive material in the vicinity. Continuing operation of the Area 5 RWMS will be considered acceptable if the total effective dose equivalent (TEDE) is less than 100 mrem in a year. If the TEDE exceeds 30 mrem in a year, a cost-benefit options analysis must be performed to determine if cost-effective management options exist to reduce the dose further. If the TEDE is found to be less than 30 mrem in a year, an analysis may be performed if warranted to determine if doses are as low as reasonably achievable (ALARA).

  19. Corrective Action Investigation Plan for Corrective Action Unit 365: Baneberry Contamination Area, Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Patrick Matthews

    2010-12-01T23:59:59.000Z

    Corrective Action Unit 365 comprises one corrective action site (CAS), CAS 08-23-02, U-8d Contamination Area. This site is being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for the CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The site will be investigated based on the data quality objectives (DQOs) developed on July 6, 2010, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for the Baneberry site. The primary release associated with Corrective Action Unit 365 was radiological contamination from the Baneberry nuclear test. Baneberry was an underground weapons-related test that vented significant quantities of radioactive gases from a fissure located in close proximity to ground zero. A crater formed shortly after detonation, which stemmed part of the flow from the fissure. The scope of this investigation includes surface and shallow subsurface (less than 15 feet below ground surface) soils. Radionuclides from the Baneberry test with the potential to impact groundwater are included within the Underground Test Area Subproject. Investigations and corrective actions associated with the Underground Test Area Subproject include the radiological inventory resulting from the Baneberry test.

  20. Dismantling of alpha contaminated obsolete installations and glove boxes on the IRMM site in Geel (Belgium)

    SciTech Connect (OSTI)

    Cretskens, Pieter; Lenie, Koen [Tecnubel NV, Gravenstraat 77, B-2480 Dessel (Belgium); Melis, Gustaaf [IRMM JRC, Retieseweg 111, B-2440 Geel (Belgium)

    2007-07-01T23:59:59.000Z

    At the Institute for Reference Materials and Measurements (European commission, Joint Research Centre, IRMM) a dismantling campaign of obsolete installations and glove boxes has been carried out in 2005. There were various reasons for their removal. Some large installations did not meet modern safety standards, other installations were worn out and expected to cause a radioactive contamination risk in the future. The main goal was to create as less waste as possible by extensive contamination checks and by decontamination if necessary. For the glove boxes, decontamination was not possible. A controlled area was set up around the installation to be dismantled in order to prevent spreading of contamination from dust and dirt. This was only possible for the 'minor' contaminated installations. The dismantling campaign of the glove boxes was carried out by using tents of two types depending the contamination inside the glove boxes. The most common glove boxes were dismantled in a tent constructed with hard surfaced polycarbonate plates (ventilated cell). For glove boxes with higher contamination, the same principle was used but with a second 'glove box tent' inside (ventilated glove tent). The purpose of this project was to learn from the experience of this campaign which gave the ability to make estimates of future radioactive waste or classic waste that could be expected from dismantled installations. (authors)

  1. Comparative approaches to siting low-level radioactive waste disposal facilities

    SciTech Connect (OSTI)

    Newberry, W.F.

    1994-07-01T23:59:59.000Z

    This report describes activities in nine States to select site locations for new disposal facilities for low-level radioactive waste. These nine States have completed processes leading to identification of specific site locations for onsite investigations. For each State, the status, legal and regulatory framework, site criteria, and site selection process are described. In most cases, States and compact regions decided to assign responsibility for site selection to agencies of government and to use top-down mapping methods for site selection. The report discusses quantitative and qualitative techniques used in applying top-down screenings, various approaches for delineating units of land for comparison, issues involved in excluding land from further consideration, and different positions taken by the siting organizations in considering public acceptance, land use, and land availability as factors in site selection.

  2. The risk implications of approaches to setting soil remediation goals at hazardous waste contaminated sites

    SciTech Connect (OSTI)

    Labieniec, P.A.

    1994-08-01T23:59:59.000Z

    An integrated exposure and carcinogenic risk assessment model for organic contamination in soil, SoilRisk, was developed and used for evaluating the risk implications of both site-specific and uniform-concentration approaches to setting soil remediation goals at hazardous-waste-contaminated sites. SoilRisk was applied to evaluate the uncertainty in the risk estimate due to uncertainty in site conditions at a representative site. It was also used to evaluate the variability in risk across a region of sites that can occur due to differences in site characteristics that affect contaminant transport and fate when a uniform concentration approach is used. In evaluating regional variability, Ross County, Ohio and the State of Ohio were used as examples. All analyses performed considered four contaminants (benzene, trichloroethylene (TCE), chlordane, and benzo[a]pyrene (BAP)) and four exposure scenarios (commercial, recreational and on- and offsite residential). Regardless of whether uncertainty in risk at a single site or variability in risk across sites was evaluated, the exposure scenario specified and the properties of the target contaminant had more influence than variance in site parameters on the resulting variance and magnitude of the risk estimate. In general, variance in risk was found to be greater for the relatively less degradable and more mobile of the chemicals studied (TCE and chlordane) than for benzene which is highly degradable and BAP which is very immobile in the subsurface.

  3. Overview of Nevada Test Site Radioactive and Mixed Waste Disposal Operations

    SciTech Connect (OSTI)

    J.T. Carilli; S.K. Krenzien; R.G. Geisinger; S.J. Gordon; B. Quinn

    2009-03-01T23:59:59.000Z

    The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office Environmental Management Program is responsible for carrying out the disposal of on-site and off-site generated low-level radioactive waste (LLW) and low-level radioactive mixed waste (MW) at the Nevada Test Site (NTS). Core elements of this mission are ensuring safe and cost-effective disposal while protecting workers, the public, and the environment. This paper focuses on the impacts of new policies, processes, and opportunities at the NTS related to LLW and MW. Covered topics include: the first year of direct funding for NTS waste disposal operations; zero tolerance policy for non-compliant packages; the suspension of mixed waste disposal; waste acceptance changes; DOE Consolidated Audit Program (DOECAP) auditing; the 92-Acre Area closure plan; new eligibility requirements for generators; and operational successes with unusual waste streams.

  4. Characterization Report for the 92-Acre Area of the Area 5 Radioactive Waste Management Site, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    Bechtel Nevada; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

    2006-06-01T23:59:59.000Z

    The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office manages two low-level Radioactive Waste Management Sites at the Nevada Test Site. The Area 5 RWMS uses engineered shallow-land burial cells to dispose of packaged waste. This report summarizes characterization and monitoring work pertinent to the 92-Acre Area in the southeast part of the Area 5 Radioactive Waste Management Sites. The decades of characterization and assessment work at the Area 5 RWMS indicate that the access controls, waste operation practices, site design, final cover design, site setting, and arid natural environment contribute to a containment system that meets regulatory requirements and performance objectives for the short- and long-term protection of the environment and public. The available characterization and Performance Assessment information is adequate to support design of the final cover and development of closure plans. No further characterization is warranted to demonstrate regulatory compliance. U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office is proceeding with the development of closure plans for the six closure units of the 92-Acre Area.

  5. BIOREMEDIATION OF CONTAMINATED SITES* Karl J. Rockne and Krishna R. Reddy

    E-Print Network [OSTI]

    Rockne, Karl J.

    1 BIOREMEDIATION OF CONTAMINATED SITES* Karl J. Rockne and Krishna R. Reddy University of Illinois ABSTRACT Bioremediation is a process in which microorganisms metabolize contaminants either through are bioremediated through reductive processes that remove the electrophilic halogens or nitro groups. Bioremediation

  6. Remediation of a Former USAF Radioactive Material Disposal Site

    SciTech Connect (OSTI)

    Hoffman, D. E.; Cushman, M; Tupyi, B.; Lambert, J.

    2003-02-25T23:59:59.000Z

    This paper describes the remediation of a low-level radiological waste burial site located at the former James Connally Air Force Base in Waco, Texas. Burial activities at the site occurred during the 1950's when the property was under the ownership of the United States Air Force. Included is a discussion of methods and strategies that were used to successfully exhume and characterize the wastes for proper disposal at offsite disposal facilities. Worker and environmental protection measures are also described. Information gained from this project may be used at other similar project sites. A total of nine burial tubes had been identified for excavation, characterization, and removal from the site. The disposal tubes were constructed of 4-ft lengths of concrete pipe buried upright with the upper ends flush with ground surface. Initial ground level observations of the burial tubes indicated that some weathering had occurred; however, the condition of the subsurface portions of the tubes was unknown. Soil excavation occurred in 1-foot lifts in order that the tubes could be inspected and to allow for characterization of the soils at each stage of the excavation. Due to the weight of the concrete pipe and the condition of the piping joints it was determined that special measures would be required to maintain the tubes intact during their removal. Special tube anchoring and handling methods were required to relocate the tubes from their initial positions to a staging area where they could be further characterized. Characterization of the disposal tubes was accomplished using a combination of gamma spectroscopy and activity mapping methods. Important aspects of the project included the use of specialized excavation and disposal tube reinforcement measures to maintain the disposal tubes intact during excavation, removal and subsequent characterization. The non-intrusive gamma spectroscopy and data logging methods allowed for effective characterization of the wastes while minimizing disposal costs. In addition, worker exposures were maintained ALARA as a result of the removal and characterization methods employed.

  7. Result Summary for the Area 5 Radioactive Waste Management Site Performance Assessment Model Version 4.113

    SciTech Connect (OSTI)

    Shott, G. J.

    2012-04-15T23:59:59.000Z

    Preliminary results for Version 4.113 of the Nevada National Security Site Area 5 Radioactive Waste Management Site performance assessment model are summarized. Version 4.113 includes the Fiscal Year 2011 inventory estimate.

  8. Birds prefer to breed in sites with low radioactivity in Chernobyl

    E-Print Network [OSTI]

    Mousseau, Timothy A.

    Birds prefer to breed in sites with low radioactivity in Chernobyl A. P. Møller1,* and T. A. 1988). Likewise, a recent report on the biological consequences of the accident at the Chernobyl predicted after the accident (Chernobyl Forum 2005). However, the main conclusion remaining after 20 years

  9. Erace--an integrated system for treating organic-contaminated sites

    SciTech Connect (OSTI)

    Caley, S.M.; Heath, W.O.; Bergsman, T.M.; Gauglitz, P.A.; Pillay, C.; Moss, R.W.; Shah, R.R.; Goheen, S.C.; Camiaoni, D.M.

    1994-11-01T23:59:59.000Z

    The U.S. Department of Energy`s (DOE) Pacific Northwest Laboratory (PNL) is developing a suite of electrical technologies for treating sites contaminated with hazardous organic compounds. These include: (1) Six-Phase Soil Heating (SPSH) to remove volatile and semi-volatile organic compounds from soils; (2) In Situ Corona (ISC) to decompose nonvolatile and bound organic contaminants in soils; (3) High-Energy Corona (HEC) to treat contaminated off-gases; and (4) Liquid Corona (LC) to treat contaminated liquids. These four technologies comprise ERACE (Electrical Remediation at Contaminated Environments), an integrated system for accomplishing site remediation with little or no secondary wastes produced that would require off-site treatment or disposal. Each ERACE technology can be employed individually as a stand-alone treatment process, or combined as a system for total site remediation. For example, an ERACE system for treating sites contaminated with volatile organics would integrate SPSH to remove the contaminants from the soil, LC to continuously treat an aqueous stream condensed out of the soil off-gas, and HEC to treat non-condensibles remaining in the off-gas, before atmospheric release.

  10. Investigation of gas-phase decontamination of internally radioactively contaminated gaseous diffusion process equipment and piping

    SciTech Connect (OSTI)

    Bundy, R.D.; Munday, E.B.

    1991-01-01T23:59:59.000Z

    Construction of the gaseous diffusion plants (GDPs) was begun during World War 2 to produce enriched uranium for defense purposes. These plants, which utilized UF{sub 6} gas, were used primarily for this purpose through 1964. From 1959 through 1968, production shifted primarily to uranium enrichment to supply the nuclear power industry. Additional UF{sub 6}-handling facilities were built in feed and fuel-processing plants associated with the uranium enrichment process. Two of the five process buildings at Oak ridge were shut down in 1964. Uranium enrichment activities at Oak Ridge were discontinued altogether in 1985. In 1987, the Department of Energy (DOE) decided to proceed with a permanent shutdown of the Oak Ridge Gaseous Diffusion Plant (ORGDP). DOE intends to begin decommissioning and decontamination (D D) of ORGDP early in the next century. The remaining two GDPs are expected to be shut down during the next 10 to 40 years and will also require D D, as will the other UF{sub 6}-handling facilities. This paper presents an investigation of gas- phase decontamination of internally radioactively contaminated gaseous diffusion process equipment and piping using powerful fluorinating reagents that convert nonvolatile uranium compounds to volatile UF{sub 6}. These reagents include ClF{sub 3}, F{sub 2}, and other compounds. The scope of D D at the GDPs, previous work of gas-phase decontamination, four concepts for using gas-phase decontamination, plans for further study of gas-phase decontamination, and the current status of this work are discussed. 13 refs., 15 figs.

  11. Release of Radioactive Scrap Metal/Scrap Metal (RSM/SM) at Nevada Test Site (NTS)

    SciTech Connect (OSTI)

    Not Available

    1993-07-01T23:59:59.000Z

    Reynolds Electrical and Engineering Company, Inc. (REECo) is the prime contractor to the US Department of Energy (DOE) in providing service and support for NTS operations. Mercury Base Camp is the main control point for the many forward areas at NTS, which covers 1,350 square miles. The forward areas are where above-ground and underground nuclear tests have been performed over the last 41 years. No metal (or other material) is returned to Mercury without first being tested for radioactivity. No radioactive metals are allowed to reenter Mercury from the forward areas, other than testing equipment. RAMATROL is the monitor check point. They check material in various ways, including swipe tests, and have a large assortment of equipment for testing. Scrap metal is also checked to address Resource Conservation and Recovery Act concerns. After addressing these issues, the scrap metals are categorized. Federal Property Management Regulations (FPMR) are followed by REECo. The nonradioactive scrap material is sold through the GSA on a scheduled basis. Radioactive scrap metal are presently held in forward areas where they were used. REECo has gained approval of their Nevada Test Site Defense Waste Acceptance Criteria, Certification, and Transfer Requirements, NVO-325 application, which will allow disposal on site, when RSM is declared a waste. The guideline that REECo uses for release limits is DOE Order 5480.11, Radiation Protection for Occupational Works, Attachment 2, Surface Radioactivity Guides, of this order, give release limits for radioactive materials. However, the removal of radioactive materials from NTS require approval by DOE Nevada Operations Office (DOE/NV) on a case-by-case basis. Requirements to consider before removal are found in DOE Order 5820.2A, Radioactive Waste Management.

  12. Modelling of contaminant release from a uranium mine tailings site

    SciTech Connect (OSTI)

    Kahnt, Rene [G.E.O.S. Freiberg Ingenieurgesellschaft mbH, P.O.Box 1162. D-09581 Freiberg (Germany); Metschies, Thomas [Wismut GmbH, Jagdschaenkenstrasse 29. D-09117 Chemnitz (Germany)

    2007-07-01T23:59:59.000Z

    Available in abstract form only. Full text of publication follows: Uranium mining and milling continuing from the early 1960's until 1990 close to the town of Seelingstaedt in Eastern Germany resulted in 4 tailings impoundments with a total tailings volume of about 105 Mio. m{sup 3}. Leakage from these tailings impoundments enters the underlying aquifers and is discharged into surface water streams. High concentration of salts, uranium and several heavy metals are released from the tailings. At present the tailings impoundments are reshaped and covered. For the identification of suitable remediation options predictions of the contaminant release for different remediation scenarios have to be made. A compartment model representing the tailings impoundments and the surrounding aquifers for the calculation of contaminant release and transport was set up using the software GOLDSIM. This compartment model describes the time dependent hydraulic conditions within the tailings and the surrounding aquifers taking into account hydraulic and geotechnical processes influencing the hydraulic properties of the tailings material. A simple geochemical approach taking into account sorption processes as well as retardation by applying a k{sub d}-approach was implemented to describe the contaminant release and transport within the hydraulic system. For uranium as the relevant contaminant the simple approach takes into account additional geochemical conditions influencing the mobility. Alternatively the model approach allows to include the results of detailed geochemical modelling of the individual tailings zones which is than used as source term for the modelling of the contaminant transport in the aquifer and to the receiving streams. (authors)

  13. Closure Plan for the Area 3 Radioactive Waste Management Site at the Nevada Test Site

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2007-09-01T23:59:59.000Z

    The Area 3 Radioactive Waste Management Site (RMWS) at the Nevada Test Site (NTS) is managed and operated by National Security Technologies, LLC (NSTec) for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This document is the first update of the interim closure plan for the Area 3 RWMS, which was presented in the Integrated Closure and Monitoring Plan (ICMP) (DOE, 2005). The format and content of this plan follows the Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans (DOE, 1999a). The major updates to the plan include a new closure date, updated closure inventory, the new institutional control policy, and the Title II engineering cover design. The plan identifies the assumptions and regulatory requirements, describes the disposal sites and the physical environment in which they are located, presents the design of the closure cover, and defines the approach and schedule for both closing and monitoring the site. The Area 3 RWMS accepts low-level waste (LLW) from across the DOE Complex in compliance with the NTS Waste Acceptance Criteria (NNSA/NSO, 2006). The Area 3 RWMS accepts both packaged and unpackaged unclassified bulk LLW for disposal in subsidence craters that resulted from deep underground tests of nuclear devices in the early 1960s. The Area 3 RWMS covers 48 hectares (119 acres) and comprises seven subsidence craters--U-3ax, U-3bl, U-3ah, U-3at, U-3bh, U-3az, and U-3bg. The area between craters U-3ax and U-3bl was excavated to form one large disposal unit (U-3ax/bl); the area between craters U-3ah and U-3at was also excavated to form another large disposal unit (U-3ah/at). Waste unit U-3ax/bl is closed; waste units U-3ah/at and U-3bh are active; and the remaining craters, although currently undeveloped, are available for disposal of waste if required. This plan specifically addresses the closure of the U-3ah/at and the U-3bh LLW units. A final closure cover has been placed on unit U-3ax/bl (Corrective Action Unit 110) at the Area 3 RWMS. Monolayer-evapotranspirative closure cover designs for the U-3ah/at and U-3bh units are provided in this plan. The current-design closure cover thickness is 3 meters (10 feet). The final design cover will have an optimized cover thickness, which is expected to be less than 3 m (10 ft). Although waste operations at the Area 3 RWMS have ceased at the end of June 2006, disposal capacity is available for future disposals at the U-3ah/at and U-3bh units. The Area 3 RWMS is expected to start closure activities in fiscal year 2025, which include the development of final performance assessment and composite analysis documents, closure plan, closure cover design for construction, cover construction, and initiation of the post-closure care and monitoring activities. Current monitoring at the Area 3 RWMS includes monitoring the cover of the closed mixed waste unit U-3ax/bl as required by the Nevada Department of Environmental Protection, and others required under federal regulations and DOE orders. Monitoring data, collected via sensors and analysis of samples, are needed to evaluate radiation doses to the general public, for performance assessment maintenance, to demonstrate regulatory compliance, and to evaluate the actual performance of the RWMSs. Monitoring provides data to ensure the integrity and performance of waste disposal units. The monitoring program is designed to forewarn management and regulators of any failure and need for mitigating actions. The plan describes the program for monitoring direct radiation, air, vadose zone, biota, groundwater, meteorology, and subsidence. The requirements of post-closure cover maintenance and monitoring will be determined in the final closure plan.

  14. Derivation of uranium residual radioactive material guidelines for the Shpack site

    SciTech Connect (OSTI)

    Cheng, J.J.; Yu, C.; Monette, F.; Jones, L.

    1991-08-01T23:59:59.000Z

    Residual radioactive material guidelines for uranium were derived for the Shpack site in Norton, Massachusetts. This site has been identified for remedial action under the Formerly Utilized Sites Remedial Action Program (FUSRAP) of the US Department of Energy (DOE). The uranium guidelines were derived on the basis of the requirement that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works in the immediate vicinity of the Shpack site should not exceed a dose of 100 mrem/yr following decontamination. The DOE residual radioactive material guideline computer code, RESRAD, which implements the methodology described in the DOE manual for implementing residual radioactive material guidelines, was used in this evaluation. Three potential scenarios were considered for the site; the scenarios vary with regard to time spent at the site, sources of water used, and sources of food consumed. The results of the evaluation indicate that the basic dose limit of 100 mrem/yr will not be exceeded for uranium (including uranium-234, uranium-235, and uranium-238) within 1000 years, provided that the soil concentration of combined uranium (uranium-234 and uranium-238) at the Shpack site does not exceed the following levels: 2500 pCi/g for Scenario A (recreationist: the expected scenario); 1100 pCi/g for Scenario B (industrial worker: a plausible scenario); and 53 pCi/g for Scenario C (resident farmer using a well water as the only water source: a possible but unlikely scenario). The uranium guidelines derived in this report apply to the combined activity concentration of uranium-234 and uranium-238 and were calculated on the basis of a dose of 100 mrem/yr. In setting the actual uranium guidelines for the Shpack site, DOE will apply the as low as reasonably achievable (ALARA) policy to the decision-making process, along with other factors, such as whether a particular scenario is reasonable and appropriate. 8 refs., 2 figs., 8 tabs.

  15. Carbon tetrachloride contamination, 200 West Area, Hanford Site: Arid Site Integrated Demonstration for remediation of volatile organic compounds

    SciTech Connect (OSTI)

    Last, G.V. [Pacific Northwest Lab., Richland, WA (United States); Rohay, V.J. [Westinghouse Hanford Co., Richland, WA (United States)

    1991-05-06T23:59:59.000Z

    The Arid State Integrated Demonstration is a US Department of Energy (DOE) program targeted at the acquisition, development, demonstration, and deployment of technologies for evaluation and cleanup of volatile organic and associated contaminants in soils and ground waters. Several DOE laboratories, universities, and industry will participate in the program. Candidate technologies will be demonstrated in the areas of site characterization; performance prediction, monitoring, and evaluations; contaminant extraction and ex situ treatment; in situ remediations; and site closure and monitoring. The performance of these demonstrated technologies will be compared to baseline technologies and documented to promote the transfer of new technologies to industry for use at DOE facilities. The initial host site is the Hanford Site`s 200 West Area. The location of the demonstration contains primarily carbon tetrachloride (CCl{sub 4}), chloroform, and a variety of associated mixed waste contaminants. Chemical processes used to recover and purify plutonium at Hanford`s plutonium finishing plant (Z Plant) resulted in the production of actinide-bearing waste liquid. Both aqueous and organic liquid wastes were generated, and were routinely discharged to subsurface disposal facilities. The primary radionuclide in the waste streams was plutonium, and the primary organic was CCl{sub 4}. This paper contains brief descriptions of the principal CCl{sub 4} waste disposal facilities in Hanford`s 200 West Area, associated hydrogeology, existing information on the extent of soil and ground-water contamination, and a conceptual outline of suspected subsurface CCl{sub 4} distributions.

  16. Descriptions of representative contaminated sites and facilities within the DOE complex

    SciTech Connect (OSTI)

    Short, S.M.; Buck, J.W.; Clark, L.L.; Fletcher, J.F.; Glantz, C.S.; Holdren, G.R.; Huesties, L.R.; Williams, M.D. [Pacific Northwest Lab., Richland, WA (United States); Oates, L. [ICF, Richland, WA (United States)] [and others

    1994-10-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) has initiated efforts to prepare a Programmatic Environmental Impact Statement (PEIS) that will analyze the existing environmental restoration and waste management program and evaluate alternatives for an integrated program. The alternatives being evaluated include (1) a {open_quotes}No Action{close_quotes} alternative as required by the National Environmental Policy Act (NEPA), (2) an Applicable, Relevant, and Appropriate Requirements (ARAR)-driven alternative, (3) a land-use-driven alternative, (4) a health-risk-driven alternative, and (5) a combination land-use and health-risk-driven alternative. The analytical approach being taken to evaluate each of these alternatives is to perform a remedial engineering analysis and human health and ecosystem effects analyses on every contaminated site and facility in the DOE complex. One of Pacific Northwest Laboratory`s (PNL) roles in this approach has been to compile the source term and environmental setting data needed to drive each of these analyses. To date, over 10,000 individual contaminated sites and facilities located throughout the DOE complex of installations have been identified and at least some minimal data compiled on each. The PEIS analyses have been appreciably simplified by categorizing all of these contaminated sites and facilities into six broad categories: (1) contaminated buildings, (2) contaminated soils, (3) solid waste sites (e.g., burial grounds), (4) liquid containment structures (e.g., tanks), (5) surface water sites, and (6) contaminated groundwater sites. A report containing a complete description of each of these thousands of contaminated sites and facilities would be tremendously large and unwildy, as would separate reports describing the application of the analytical methodologies to each.

  17. Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Sites near Slick Rock, Colorado. Revision 1

    SciTech Connect (OSTI)

    NONE

    1995-09-01T23:59:59.000Z

    Two UMTRA (Uranium Mill Tailings Remedial Action) Project sites are near Slick Rock, Colorado: the North Continent site and the Union Carbide site. Currently, no one uses the contaminated ground water at either site for domestic or agricultural purposes. However, there may be future land development. This risk assessment evaluates possible future health problems associated with exposure to contaminated ground water. Since some health problems could occur, it is recommended that the contaminated ground water not be used as drinking water.

  18. Bioremediation of ground water contaminants at a uranium mill tailings site

    SciTech Connect (OSTI)

    Barton, L.L.; Nuttall, H.E.; Thomson, B.M.; Lutze, W. [Univ. of New Mexico, Albuquerque, NM (United States)

    1995-12-31T23:59:59.000Z

    Ground water contaminated with uranium from milling operations must be remediated to reduce the migration of soluble toxic compounds. At the mill tailings site near Tuba City, Arizona (USA) the approach is to employ bioremediation for in situ immobilization of uranium by bacterial reduction of uranyl, U(VI), compounds to uraninite, U(IV). In this initial phase of remediation, details are provided to indicate the magnitude of the contamination problem and to present preliminary evidence supporting the proposition that bacterial immobilization of uranium is possible. Additionally, consideration is given to contaminating cations and anions that may be at toxic levels in ground water at this uranium mill tailing site and detoxification strategies using bacteria are addressed. A model concept is employed so that results obtained at the Tuba City site could contribute to bioremediation of ground water at other uranium mill tailings sites.

  19. Radioactive contamination of fish, shellfish, and waterfowl exposed to Hanford effluents: Annual summaries, 1945--1972

    SciTech Connect (OSTI)

    Hanf, R.W.; Dirkes, R.L.; Duncan, J.P.

    1992-07-01T23:59:59.000Z

    The objective of the Hanford Environmental Dose Reconstruction Project (HEDR) is to estimate the potential radiation doses received by people living within the sphere of influence of the Hanford Site. A potential critical pathway for human radiation exposure is through the consumption of waterfowl that frequent onsite waste-water ponds or through eating of fish, shellfish, and waterfowl that reside in/on the Columbia River and its tributaries downstream of the reactors. This document summarizes information on fish, shellfish, and waterfowl radiation contamination for samples collected by Hanford monitoring personnel and offsite agencies for the period 1945 to 1972. Specific information includes the types of organisms sampled, the kinds of tissues and organs analyzed, the sampling locations, and the radionuclides reported. Some tissue concentrations are also included. We anticipate that these yearly summaries will be helpful to individuals and organizations interested in evaluating aquatic pathway information for locations impacted by Hanford operations and will be useful for planning the direction of future HEDR studies.

  20. Nevada National Security Site 2013 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Site

    SciTech Connect (OSTI)

    Hudson, D. B.

    2014-08-19T23:59:59.000Z

    Environmental monitoring data are collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) within the Nevada National Security Site (NNSS). These data are associated with radiation exposure, air, groundwater, meteorology, and vadose zone. This report summarizes the 2013 environmental data to provide an overall evaluation of RWMS performance and to support environmental compliance and performance assessment (PA) activities. Some of these data (e.g., radiation exposure, air, and groundwater) are presented in other reports (National Security Technologies, LLC, 2013; 2014a; 2014b). Direct radiation monitoring data indicate exposure levels at the RWMSs are within the range of background levels measured at the NNSS. Slightly elevated exposure levels outside the Area 3 RWMS are attributed to nearby historical aboveground nuclear weapons tests. Air monitoring data show tritium concentrations in water vapor and americium and plutonium concentrations in air particles are close to detection limits and background levels. The measured levels of radionuclides in air particulates and moisture are below Derived Concentration Standards for these radionuclides. Groundwater monitoring data indicate the groundwater in the uppermost aquifer beneath the Area 5 RWMS is not impacted by RWMS operations. Results of groundwater analysis from wells around the Area 5 RWMS were all below established investigation levels. Leachate samples collected from the leachate collection system at the mixed low-level waste cell were below established contaminant regulatory limits. The 105.8 millimeters (mm) (4.17 inches [in.]) of precipitation at the Area 3 RWMS during 2013 is 30% below the average of 150.3 mm (5.92 in.), and the 117.5 mm (4.63 in.) of precipitation at the Area 5 RWMS during 2013 is 5% below the average of 123.6 mm (4.86 in.). Water balance measurements indicate that evapotranspiration from the vegetated weighing lysimeter dries the soil and prevents downward percolation of precipitation more effectively than evaporation from the bare-soil weighing lysimeter. Automated vadose zone monitoring on Area 5 and Area 3 RWMS cell covers show no evidence of precipitation percolating through the cover to the waste. Moisture from precipitation did not percolate below 60 centimeters (cm) (2 feet [ft]) in the vegetated final cover on the U-3ax/bl disposal unit at the Area 3 RWMS, and moisture from precipitation and irrigation did not percolate below 45 cm (1.5 ft) on the 92-Acre Area final cover. Irrigation was applied to this cover for seed germination and plant growth. During 2013, there was no drainage through 2.4 meters (8 ft) of soil from the Area 3 drainage lysimeters that received only natural precipitation. Twenty percent of the applied precipitation and irrigation drained from the bare-soil drainage lysimeter that received 3-times natural precipitation. All 2013 monitoring data indicate that the Area 3 and Area 5 RWMSs are performing within expectations of the model and parameter assumptions for the facility PAs.

  1. Nevada National Security Site 2012 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Site

    SciTech Connect (OSTI)

    Hudson, David B.

    2013-09-10T23:59:59.000Z

    Environmental monitoring data are collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada National Security Site (NNSS). These data are associated with radiation exposure, air, groundwater, meteorology, and vadose zone. This report summarizes the 2012 environmental data to provide an overall evaluation of RWMS performance and to support environmental compliance and performance assessment (PA) activities. Some of these data (e.g., radiation exposure, air, and groundwater) are presented in other reports (National Security Technologies, LLC, 2012; 2013a; 2013b). Direct radiation monitoring data indicate exposure levels at the RWMSs are within the range of background levels measured at the NNSS. Slightly elevated exposure levels outside the Area 3 RWMS are attributed to nearby historical aboveground nuclear weapons tests. Air monitoring data show tritium concentrations in water vapor and americium and plutonium concentrations in air particles are only slightly above detection limits and background levels. The measured levels of radionuclides in air particulates and moisture are below Derived Concentration Standards for these radionuclides. Groundwater monitoring data indicate the groundwater in the uppermost aquifer beneath the Area 5 RWMS is not impacted by RWMS operations. Results of groundwater analysis from wells around the Area 5 RWMS were all below established investigation levels. Leachate samples collected from the leachate collection system at the mixed low-level waste cell were below established contaminant regulatory limits. The 133.9 millimeters (mm) (5.27 inches [in.]) of precipitation at the Area 3 RWMS during 2012 is 12% below the average of 153.0 mm (6.02 in.), and the 137.6 mm (5.42 in.) of precipitation at the Area 5 RWMS during 2012 is 11% below the average of 122.4 mm (4.82 in.). Water balance measurements indicate that evapotranspiration from the vegetated weighing lysimeter dries the soil and prevents downward percolation of precipitation more effectively than evaporation from the bare-soil weighing lysimeter. Automated vadose zone monitoring on Area 5 and Area 3 RWMS cell covers show no evidence of precipitation percolating through the cover to the waste. Moisture from precipitation did not percolate below 60 centimeters (cm) (2 feet [ft]) in the vegetated final cover on the U-3ax/bl disposal unit at the Area 3 RWMS, and moisture from precipitation and irrigation did not percolate below 45 cm (1.5 ft) on the 92-Acre Area final cover. Irrigation was applied to this cover for seed germination and plant growth. During 2012, there was no drainage through 2.4 meters (8 ft) of soil from the Area 3 drainage lysimeters that received only natural precipitation. Twenty percent of the applied precipitation and irrigation drained from the bare-soil drainage lysimeter that received 3 times natural precipitation. All 2012 monitoring data indicate that the Area 3 and Area 5 RWMSs are performing within expectations of the model and parameter assumptions for the facility PAs.

  2. ADVANCES IN SE-79 ANALYSES ON SAVANNAH RIVER SITE RADIOACTIVE WASTE MATRICES

    SciTech Connect (OSTI)

    Diprete, D; C Diprete, C; Ned Bibler, N; Cj Bannochie, C; Michael Hay, M

    2009-03-16T23:59:59.000Z

    Waste cleanup efforts underway at the United States Department of Energy's (DOE) Savannah River Site (SRS) in South Carolina, as well as other DOE nuclear sites, have created a need to characterize {sup 79}Se in radioactive waste inventories. Successful analysis of {sup 79}Se in high activity waste matrices is challenging for a variety of reasons. As a result of these unique challenges, the successful quantification of {sup 79}Se in the types of matrices present at SRS requires an extremely efficient and selective separation of {sup 79}Se from high levels of interfering radionuclides. A robust {sup 79}Se radiochemical separation method has been developed at the Savannah River National Laboratory (SRNL) which is routinely capable of successfully purifying {sup 79}Se from a wide range of interfering radioactive species. In addition to a dramatic improvements in the Kd, ease, and reproducibility of the analysis, the laboratory time has been reduced from several days to only 6 hours.

  3. Carbon tetrachloride contamination, 200 West Area, Hanford Site: Arid Site Integrated Demonstration for remediation of volatile organic compounds

    SciTech Connect (OSTI)

    Last, G.V. (Pacific Northwest Lab., Richland, WA (United States)); Rohay, V.J. (Westinghouse Hanford Co., Richland, WA (United States))

    1991-05-06T23:59:59.000Z

    The Arid State Integrated Demonstration is a US Department of Energy (DOE) program targeted at the acquisition, development, demonstration, and deployment of technologies for evaluation and cleanup of volatile organic and associated contaminants in soils and ground waters. Several DOE laboratories, universities, and industry will participate in the program. Candidate technologies will be demonstrated in the areas of site characterization; performance prediction, monitoring, and evaluations; contaminant extraction and ex situ treatment; in situ remediations; and site closure and monitoring. The performance of these demonstrated technologies will be compared to baseline technologies and documented to promote the transfer of new technologies to industry for use at DOE facilities. The initial host site is the Hanford Site's 200 West Area. The location of the demonstration contains primarily carbon tetrachloride (CCl{sub 4}), chloroform, and a variety of associated mixed waste contaminants. Chemical processes used to recover and purify plutonium at Hanford's plutonium finishing plant (Z Plant) resulted in the production of actinide-bearing waste liquid. Both aqueous and organic liquid wastes were generated, and were routinely discharged to subsurface disposal facilities. The primary radionuclide in the waste streams was plutonium, and the primary organic was CCl{sub 4}. This paper contains brief descriptions of the principal CCl{sub 4} waste disposal facilities in Hanford's 200 West Area, associated hydrogeology, existing information on the extent of soil and ground-water contamination, and a conceptual outline of suspected subsurface CCl{sub 4} distributions.

  4. Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site near Tuba City, Arizona

    SciTech Connect (OSTI)

    Not Available

    1994-06-01T23:59:59.000Z

    This document evaluates potential public health or environmental impacts resulting from ground water contamination at the former uranium mill site. The tailings and other contaminated material at this site were placed in a disposal cell on the site in 1990 by the US Department of Energy`s Uranium Mill Tailings Remedial Action (UMTRA) Project. The second phase of the UMTRA Project is to evaluate ground water contamination. This risk assessment is the first site-specific document under the Ground Water Project. It will help determine what remedial actions are necessary for contaminated ground water at the site.

  5. Closure End States for Facilities, Waste Sites, and Subsurface Contamination - 12543

    SciTech Connect (OSTI)

    Gerdes, Kurt; Chamberlain, Grover; Whitehurst, Latrincy; Marble, Justin [Office of Groundwater and Soil Remediation, U.S. Department of Energy, Washington, DC 20585 (United States); Wellman, Dawn [Pacific Northwest National Laboratory, Richland, Washington 99352 (United States); Deeb, Rula; Hawley, Elisabeth [ARCADIS U.S., Inc., Emeryville, CA 94608 (United States)

    2012-07-01T23:59:59.000Z

    The United States (U.S.) Department of Energy (DOE) manages the largest groundwater and soil cleanup effort in the world. DOE's Office of Environmental Management (EM) has made significant progress in its restoration efforts at sites such as Fernald and Rocky Flats. However, remaining sites, such as Savannah River Site, Oak Ridge Site, Hanford Site, Los Alamos, Paducah Gaseous Diffusion Plant, Portsmouth Gaseous Diffusion Plant, and West Valley Demonstration Project possess the most complex challenges ever encountered by the technical community and represent a challenge that will face DOE for the next decade. Closure of the remaining 18 sites in the DOE EM Program requires remediation of 75 million cubic yards of contaminated soil and 1.7 trillion gallons of contaminated groundwater, deactivation and decommissioning (D and D) of over 3000 contaminated facilities and thousands of miles of contaminated piping, removal and disposition of millions of cubic yards of legacy materials, treatment of millions of gallons of high level tank waste and disposition of hundreds of contaminated tanks. The financial obligation required to remediate this volume of contaminated environment is estimated to cost more than 7% of the to-go life-cycle cost. Critical in meeting this goal within the current life-cycle cost projections is defining technically achievable end states that formally acknowledge that remedial goals will not be achieved for a long time and that residual contamination will be managed in the interim in ways that are protective of human health and environment. Formally acknowledging the long timeframe needed for remediation can be a basis for establishing common expectations for remedy performance, thereby minimizing the risk of re-evaluating the selected remedy at a later time. Once the expectations for long-term management are in place, remedial efforts can be directed towards near-term objectives (e.g., reducing the risk of exposure to residual contamination) instead of focusing on long-term cleanup requirements. An acknowledgement of the long timeframe for complete restoration and the need for long-term management can also help a site transition from the process of pilot testing different remedial strategies to selecting a final remedy and establishing a long-term management and monitoring approach. This approach has led to cost savings and the more efficient use of resources across the Department of Defense complex and at numerous industrial sites across the U.S. Defensible end states provide numerous benefits for the DOE environmental remediation programs including cost-effective, sustainable long-term monitoring strategies, remediation and site transition decision support, and long-term management of closure sites. (authors)

  6. Uranium Contamination in the Subsurface Beneath the 300 Area, Hanford Site, Washington

    SciTech Connect (OSTI)

    Peterson, Robert E.; Rockhold, Mark L.; Serne, R. Jeffrey; Thorne, Paul D.; Williams, Mark D.

    2008-02-29T23:59:59.000Z

    This report provides a description of uranium contamination in the subsurface at the Hanford Site's 300 Area. The principal focus is a persistence plume in groundwater, which has not attenuated as predicted by earlier remedial investigations. Included in the report are chapters on current conditions, hydrogeologic framework, groundwater flow modeling, and geochemical considerations. The report is intended to describe what is known or inferred about the uranium contamination for the purpose of making remedial action decisions.

  7. Techniques and equipment used in contaminant detection at Hoe Creek underground coal gasification experimental site

    SciTech Connect (OSTI)

    Davidson, S.C.

    1984-01-01T23:59:59.000Z

    Data obtained from existing monitoring wells at an experimental coal gasification site indicated that local groundwater supplies were under risk from organic contaminants, particularly phenols. A more extensive monitoring system was installed. A drilling and open-hole sampling programme was devised to locate the edge of the contaminated area and indicate where additional monitoring wells were required. Geophysical logging was employed to determine the optimal position of gas-driven groundwater samplers/piezometers. The system successfully delineated the extent of the contaminant plume on 3 sides, but further work is required on the fourth side.

  8. Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site near Maybell, Colorado

    SciTech Connect (OSTI)

    NONE

    1996-03-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (Phase I) and the Ground Water Project (Phase II). Under the UMTRA Surface Project, tailings, contaminated soil, building foundations, and materials associated with the former processing of uranium ore at UMTRA Project sites are placed into disposal cells. The cells are designed to reduce radon and other radiation emissions and to prevent further contamination of ground water. One UMTRA Project site is near Maybell, Colorado. Surface cleanup at this site began in 1995 and is scheduled for completion in 1996. The tailings are being stabilized in place at this site. The disposal area has been withdrawn from public use by the DOE and is referred to as the permanent withdrawal area. The Ground Water Project evaluates the nature and extent of ground water contamination resulting from past uranium ore processing activities. The Ground Water Project at this site is in its beginning stages. This report is a site-specific document that will be used to evaluate current and future potential impacts to the public and the environment from exposure to contaminated ground water. The results presented in this document and other evaluations will determine whether any action is needed to protect human health or the environment.

  9. Preliminary evaluation of selected in situ remediation technologies for Volatile Organic Compound contamination at Arid sites

    SciTech Connect (OSTI)

    Lenhard, R.J.; Gerber, M.A.; Amonette, J.E.

    1992-10-01T23:59:59.000Z

    To support the Volatile Organic Compounds-Arid Site (VOC-Arid) Integrated Demonstration (ID) in its technical, logistical, institutional, and economical testing of emerging environmental management and restoration technologies. Pacific Northwest Laboratory(a) is evaluating several in situ remediation technologies for possible inclusion in the demonstration. The evaluations are made with respect to the initial focus of the VOC-Arid ID: the carbon tetrachloride contamination at the Hanford Site, where it was disposed to the vadose zone along with other volatile and nonvolatile organic wastes. heavy metals, acids. and radionuclides. The purposes of this report are (1) to identify candidate in situ technologies for inclusion in the program, (2) to evaluate the candidate technologies based on their potential applicability to VOC contamination at arid sites and geologic conditions representative of the ID host site (i.e., Hanford Site), and (3) to prioritize those technologies for future US Department of Energy (DOE) support.

  10. Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site at Grand Junction, Colorado. Revision 1

    SciTech Connect (OSTI)

    Not Available

    1994-09-01T23:59:59.000Z

    This risk assessment evaluates potential impacts to public health or the environment resulting from ground water contamination at the former uranium mill processing site. The tailings and other contaminated material at this site were placed in an off-site disposal cell by the US Department of Energy`s (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. The remedial activities at the site were conducted from 1989 to 1993. Currently, the UMTRA Project is evaluating ground water contamination. This risk assessment evaluates the most contaminated ground water that flows beneath the processing site toward the Colorado River. The monitor wells that have consistently shown the highest concentrations of most contaminants are used to assess risk. This risk assessment will be used in conjunction with additional activities and documents to determine what remedial action may be needed for contaminated ground water at the site.

  11. Baseline risk assessment for exposure to contaminants at the St. Louis Site, St. Louis, Missouri

    SciTech Connect (OSTI)

    Not Available

    1993-11-01T23:59:59.000Z

    The St. Louis Site comprises three noncontiguous areas in and near St. Louis, Missouri: the St. Louis Downtown Site (SLDS), the St. Louis Airport Storage Site (SLAPS), and the Latty Avenue Properties. The main site of the Latty Avenue Properties includes the Hazelwood Interim Storage Site (HISS) and the Futura Coatings property, which are located at 9200 Latty Avenue. Contamination at the St. Louis Site is the result of uranium processing and disposal activities that took place from the 1940s through the 1970s. Uranium processing took place at the SLDS from 1942 through 1957. From the 1940s through the 1960s, SLAPS was used as a storage area for residues from the manufacturing operations at SLDS. The materials stored at SLAPS were bought by Continental Mining and Milling Company of Chicago, Illinois, in 1966, and moved to the HISS/Futura Coatings property at 9200 Latty Avenue. Vicinity properties became contaminated as a result of transport and movement of the contaminated material among SLDS, SLAPS, and the 9200 Latty Avenue property. This contamination led to the SLAPS, HISS, and Futura Coatings properties being placed on the National Priorities List (NPL) of the US Environmental Protection Agency (EPA). The US Department of Energy (DOE) is responsible for cleanup activities at the St. Louis Site under its Formerly Utilized Sites Remedial Action Program (FUSRAP). The primary goal of FUSRAP is the elimination of potential hazards to human health and the environment at former Manhattan Engineer District/Atomic Energy Commission (MED/AEC) sites so that, to the extent possible, these properties can be released for use without restrictions. To determine and establish cleanup goals for the St. Louis Site, DOE is currently preparing a remedial investigation/feasibility study-environmental impact statement (RI/FS-EIS). This baseline risk assessment (BRA) is a component of the process; it addresses potential risk to human health and the environment associated wi

  12. Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site near Green River, Utah

    SciTech Connect (OSTI)

    Not Available

    1994-09-01T23:59:59.000Z

    This document evaluates potential impacts to public health and the environment resulting from ground water contamination at the former uranium mill processing site. The tailings and other contaminated material at this site were placed in a disposal cell on the site in 1989 by the US DOE`s Uranium Mill Tailings Remedial Action (UMTRA) Project. Currently, UMTRA Project is evaluating ground water contamination in this risk assessment.

  13. EIS-0109: Long-Term Management of the Existing Radioactive Wastes and Residues at the Niagara Falls Storage Site

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy developed this statement to evaluate the environmental impacts of several alternatives for management and control of the radioactive wastes and residues at the Niagara Falls Storage Site, including a no action alternative, an alternative to manage wastes on-site, and two off-site management alternatives.

  14. Baseline risk assessment of ground water contamination at the inactive uriniferous lignite ashing site near Belfield, North Dakota

    SciTech Connect (OSTI)

    NONE

    1994-08-01T23:59:59.000Z

    This Baseline Risk Assessment of Ground Water Contamination at the Inactive Uraniferous Lignite Ashing Site Near Belfield, North Dakota, evaluates potential impacts to public health or the environment resulting from ground water contamination at the site where coal containing uranium was burned to produce uranium. The US Department of Energy`s Uranium Mill Tailings Remedial Action (UMTRA) Project is evaluating plans to remedy soil and ground water contamination at the site. Phase I of the UMTRA Project consists of determining the extent of soil contamination. Phase II of the UMTRA Project consists of evaluating ground water contamination. Under Phase II, results of this risk assessment will help determine what remedial actions may be necessary for contaminated ground water at the site. This risk assessment evaluates the potential risks to human health and the environment resulting from exposure to contaminated ground water as it relates to historic processing activities at the site. Potential risk is quantified for constituents introduced from the processing activities, and not for those constituents naturally occurring in water quality in the site vicinity. Background ground water quality has the potential to cause adverse health effects from exposure through drinking. Any risks associated with contaminants attributable to site activities are incremental to these risks from background ground water quality. This incremental risk from site-related contaminants is quantified in this risk assessment. The baseline risk from background water quality is incorporated only into the assessment of potential chemical interactions and the definition of the overall site condition.

  15. Baseline risk assessment of ground water contamination at the inactive uraniferous lignite ashing site near Bowman, North Dakota

    SciTech Connect (OSTI)

    Not Available

    1994-11-01T23:59:59.000Z

    This baseline risk assessment of ground water contamination at the inactive uraniferous lignite ashing site near Bowman, North Dakota, evaluates the potential impacts to public health or the environment from contaminated ground water at this site. This contamination is a result of the uraniferous lignite ashing process, when coal containing uranium was burned to produce uranium. Potential risk is quantified only for constituents introduced by the processing activities and not for the constituents naturally occurring in background ground water in the site vicinity. Background ground water, separate from any site-related contamination, imposes a percentage of the overall risk from ground water ingestion in the Bowman site vicinity. The US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project is developing plans to address soil and ground water contamination at the site. The UMTRA Surface Project involves the determination of the extent of soil contamination and design of an engineered disposal cell for long-term storage of contaminated materials. The UMTRA Ground Water Project evaluates ground water contamination. Based on results from future site monitoring activities as defined in the site observational work plan and results from this risk assessment, the DOE will propose an approach for managing contaminated ground water at the Bowman site.

  16. Baseline risk assessment of ground water contamination at the uranium mill tailings site Salt Lake City, Utah

    SciTech Connect (OSTI)

    Not Available

    1994-09-01T23:59:59.000Z

    This baseline risk assessment of groundwater contamination at the uranium mill tailings site near Salt Lake City, Utah, evaluates potential public health or environmental impacts resulting from ground water contamination at the former uranium ore processing site. The tailings and other contaminated material at this site were placed in a disposal cell located at Clive, Utah, in 1987 by the US Department of Energy`s Uranium Mill Tailings Remedial Action (UMTRA) Project. The second phase of the UMTRA Project is to evaluate residual ground water contamination at the former uranium processing site, known as the Vitro processing site. This risk assessment is the first site-specific document under the Ground Water Project. It will help determine the appropriate remedial action for contaminated ground water at the site.

  17. Operations of the LR56 radioactive liquid cask transport system at U.S. Department of Energy sites

    SciTech Connect (OSTI)

    Davidson, J.S. [Lockheed Martin Energy Systems, Oak Ridge, TN (United States); Hornstra, D.J. [Performance Development Corp., Oak Ridge, TN (United States); Sazawal, V.K. [NUMATEC, Inc., Bethesda, MD (United States); Clement, G. [SGN, St. Quentin en Yvelines (France)

    1996-06-01T23:59:59.000Z

    The LR56 cask system is licensed for use in France under Certificate of Compliance F/309/B(U)F for transport of 4,000-liter volumes of radioactive liquids. Three LR56 cask systems (with modifications for use at Department of Energy (DOE) sites) have been purchased for delivery at the Hanford Site, Oak Ridge National Laboratory (ORNL), and Savannah River Site (SRS). The LR56 cask systems will be used for on-site transfers of Type B quantities of radioactive liquid waste. The ORNL unit will also be used as a Type A packaging for transfers of radioactive liquids between DOE sites. This paper discusses LR56 operating features and the use of the cask system at the three DOE sites.

  18. Radioactive Waste Management

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1984-02-06T23:59:59.000Z

    To establish policies and guidelines by which the Department of Energy (DOE) manages tis radioactive waste, waste byproducts, and radioactively contaminated surplus facilities.

  19. Soil washing as a potential remediation technology for contaminated DOE sites

    SciTech Connect (OSTI)

    Devgun, J.S.; Beskid, N.J. (Argonne National Lab., IL (United States)); Natsis, M.E. (Princeton Univ., NJ (United States)); Walker, J.S. (USDOE, Washington, DC (United States))

    1993-01-01T23:59:59.000Z

    Frequently detected contaminants at US Department of Energy (DOE) sites include radionuclides, heavy metals, and chlorinated hydrocarbons. Remediation of these sites requires application of several technologies used in concert with each other, because no single technology is universally applicable. Special situations, such as mixed waste, generally require innovative technology development. This paper, however, focuses on contaminated soils, for which soil washing and vitrification technologies appear to have wide ranging application potential. Because the volumes of contaminated soils around the DOE complex are so large, soil washing can offer a potentially inexpensive way to effect remediation or to attain waste volume reduction. As costs for disposal of low-level and mixed wastes continue to rise, it is likely that volume-reduction techniques and in-situ containment techniques will become increasingly important. This paper reviews the status of the soil washing technology, examines the systems that are currently available, and discusses the potential application of this technology to some DOE sites, with a focus on radionuclide contamination and, primarily, uranium-contaminated soils

  20. Soil washing as a potential remediation technology for contaminated DOE sites

    SciTech Connect (OSTI)

    Devgun, J.S.; Beskid, N.J. [Argonne National Lab., IL (United States); Natsis, M.E. [Princeton Univ., NJ (United States); Walker, J.S. [USDOE, Washington, DC (United States)

    1993-03-01T23:59:59.000Z

    Frequently detected contaminants at US Department of Energy (DOE) sites include radionuclides, heavy metals, and chlorinated hydrocarbons. Remediation of these sites requires application of several technologies used in concert with each other, because no single technology is universally applicable. Special situations, such as mixed waste, generally require innovative technology development. This paper, however, focuses on contaminated soils, for which soil washing and vitrification technologies appear to have wide ranging application potential. Because the volumes of contaminated soils around the DOE complex are so large, soil washing can offer a potentially inexpensive way to effect remediation or to attain waste volume reduction. As costs for disposal of low-level and mixed wastes continue to rise, it is likely that volume-reduction techniques and in-situ containment techniques will become increasingly important. This paper reviews the status of the soil washing technology, examines the systems that are currently available, and discusses the potential application of this technology to some DOE sites, with a focus on radionuclide contamination and, primarily, uranium-contaminated soils

  1. Radioactively Contaminated Scrap Metal An International Approach to Monitoring, Interception & Managing

    E-Print Network [OSTI]

    Customs Organization (WCO) · Scrap processing consultant · International Atomic Energy Agency (IAEARadioactively Contaminated Scrap Metal An International Approach to Monitoring, Interception of monitoring requirements and procedures Standardization of monitoring of scrap metal and response to alarms

  2. A data base for low-level radioactive waste disposal sites

    SciTech Connect (OSTI)

    Daum, M.L.; Moskowitz, P.D.

    1989-07-01T23:59:59.000Z

    A computerized database was developed to assist the US Environmental Protection Agency (EPA) in evaluating methods and data for characterizing health hazards associated with land and ocean disposal options for low-level radioactive wastes. The data cover 1984 to 1987. The types of sites considered include Nuclear Regulatory Commission (NRC) licensed commercial disposal sites, EPA National Priority List (NPL) sites, US Department of Energy (DOE) Formerly Utilized Sites Remedial Action Project (FUSRAP) and DOE Surplus Facilities Management Program (SFMP) sites, inactive US ocean disposal sites, and DOE/Department of Defense facilities. Sources of information include reports from EPA, the US Department of Energy (DOE) and the Nuclear Regulatory Commission (NRC), as well as direct communication with individuals associated with specific programs. The data include site descriptions, waste volumes and activity levels, and physical and radiological characterization of low-level wastes. Additional information on mixed waste, packaging forms, and disposal methods were compiled, but are not yet included in the database. 55 refs., 4 figs., 2 tabs.

  3. Integrated system for gathering, processing, and reporting data relating to site contamination

    DOE Patents [OSTI]

    Long, D.D.; Goldberg, M.S.; Baker, L.A.

    1997-11-11T23:59:59.000Z

    An integrated screening system comprises an intrusive sampling subsystem, a field mobile laboratory subsystem, a computer assisted design/geographical information subsystem, and a telecommunication linkup subsystem, all integrated to provide synergistically improved data relating to the extent of site soil/groundwater contamination. According to the present invention, data samples related to the soil, groundwater or other contamination of the subsurface material are gathered and analyzed to measure contaminants. Based on the location of origin of the samples in three-dimensional space, the analyzed data are transmitted to a location display. The data from analyzing samples and the data from the locating the origin are managed to project the next probable sample location. The next probable sample location is then forwarded for use as a guide in the placement of ensuing sample location, whereby the number of samples needed to accurately characterize the site is minimized. 10 figs.

  4. Integrated system for gathering, processing, and reporting data relating to site contamination

    DOE Patents [OSTI]

    Long, Delmar D. (Oak Ridge, TN); Goldberg, Mitchell S. (Lenior City, TN); Baker, Lorie A. (Oak Ridge, TN)

    1997-01-01T23:59:59.000Z

    An integrated screening system comprises an intrusive sampling subsystem, a field mobile laboratory subsystem, a computer assisted design/geographical information subsystem, and a telecommunication linkup subsystem, all integrated to provide synergistically improved data relating to the extent of site soil/groundwater contamination. According to the present invention, data samples related to the soil, groundwater or other contamination of the subsurface material are gathered and analyzed to measure contaminants. Based on the location of origin of the samples in three-dimensional space, the analyzed data are transmitted to a location display. The data from analyzing samples and the data from the locating the origin are managed to project the next probable sample location. The next probable sample location is then forwarded for use as a guide in the placement of ensuing sample location, whereby the number of samples needed to accurately characterize the site is minimized.

  5. Radionuclide contaminant analysis of rodents at a waste burial site, Los Alamos National Laboratory

    SciTech Connect (OSTI)

    Biggs, J.R.; Bennett, K.D.; Fresquez, P.R. [Los Alamos National Lab., NM (United States). Environment, Safety, and Health Div.

    1996-12-31T23:59:59.000Z

    Small mammals were sampled at two waste burial sites (Sites 1 and 2) at Area G, TA-54, and a control site outside Area G (Site 3) to identify radionuclides that are present within surface and subsurface soils at waste burial sites, to compare the amount of radionuclide uptake by small mammals at waste burial sites to a control site, and to identify the primary mode of contamination to small mammals, either through surface contact or ingestion/inhalation. Three composite samples of at least five animals per sample were collected at each site. Pelts and carcasses of each animal were separated and analyzed independently. Samples were analyzed for americium ({sup 241}Am), strontium ({sup 90}Sr), plutonium ({sup 238}Pu and {sup 239}Pu), total uranium (U), and examined by gamma spectroscopy (including cesium [{sup 137}Cs]). Significantly higher (parametric t-test at p = 0.05) levels of total U, {sup 241}Am, {sup 238}Pu, and potassium ({sup 40}K) were detected in pelts as compared to the carcasses of small mammals at TA-54. Concentrations of other measured radionuclides in carcasses were nearly equal to or exceeded the mean concentrations in the pelts. The results show higher concentrations in pelts compared to carcasses which is similar to what has been found at waste burial/contaminated sites outside of Los Alamos National Laboratory. Site 1 had significantly higher (alpha = 0.05, P = 0.0095) total U concentrations in carcasses than Sites 2 and 3. Site 2 had significantly higher (alpha = 0.05, P = 0.0195) {sup 239}Pu concentrations in carcasses than either Site 1 or Site 3.

  6. Roundtable on Long-Term Management In The Cleanup of Contaminated Sites

    SciTech Connect (OSTI)

    Aimee Houghton

    2002-06-28T23:59:59.000Z

    The Center for Public Environmental Oversight (CPEO) convened a roundtable in Washington, DC on June 28, 2002 to discuss innovative approaches to long-term management in the cleanup of contaminated property. Twenty participants attended the meeting, including representatives of federal agencies, local government, state regulatory agencies, environmental organizations, and thinking tanks, as well as private consultants with experience in site remediation and redevelopment.

  7. DECHEM: A remedial planning tool for metallic contaminants in soil at UMTRA Project sites

    SciTech Connect (OSTI)

    Not Available

    1989-03-01T23:59:59.000Z

    The DECHEM (DEcontamination of CHEMicals) method was developed for the Uranium Mill Tailings Remedial Action (UMTRA) Project to guide characterization and remedial planning for metals contamination in soils. This is necessary because non-radiological hazardous constituents may be more mobile than radium-226 (Ra-226), and hence may migrate more deeply into subpile soils (beneath tailings that are to be relocated) or into adjacent contaminated soils at UMTRA Project sites. The result is that remedial action to the Ra-226 excavation limit, as specified in the US Environmental Protection Agency (EPA) standards, may not adequately remove hazardous non-radiological contamination. Unmitigated, these contaminants in soil may cause health risks because of their presence in resuspended particles, their uptake by crops or fodder their seepage into aquifers used for drinking water or other possible exposure pathways. The DECHEM method was developed in response to the need for advanced planning for the remediation of chemical contaminants at UMTRA Project sites, and includes the following elements: Establishment of acceptable exposure rates for humans to chemicals, based on EPA guidelines or other toxicological literature. Modeling of chemical migration through environmental pathways from a remediated UMTRA Project site to humans. Determination of allowable residual concentrations (i.e., cleanup guidelines) for chemicals in soils that results in doses to humans that are below established acceptable exposure rates. The initial development and application of the DECHEM method has focused upon hazardous metallic contaminants such as arsenic, lead, molybdenum, and selenium, which are known to occur in elevated concentrations at some UMTRA Project sites.

  8. Annual Transportation Report for Radioactive Waste Shipments to and from the Nevada Test Site, Fiscal Year 2009

    SciTech Connect (OSTI)

    U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

    2010-02-01T23:59:59.000Z

    In February 1997, the U.S. Department of Energy (DOE), Nevada Operations Office (now known as the Nevada Site Office) issued the Mitigation Action Plan which addressed potential impacts described in the “Final Environmental Impact Statement for the Nevada Test Site and Off-Site Locations in the State of Nevada” (DOE/EIS 0243). The DOE, Nevada Operations Office committed to several actions, including the preparation of an annual report, which summarizes waste shipments to and from the Nevada Test Site (NTS) Radioactive Waste Management Site (RWMS) at Area 5 and Area 3. Since 2006, the Area 3 RWMS has been in cold stand-by. This document satisfies requirements regarding low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) transported to and from the NTS during FY 2009. In addition, this document provides shipment, volume, and route information on transuranic (TRU) waste shipped from the NTS to the Idaho National Laboratory, near Idaho Falls, Idaho.

  9. Assessment of microbial processes on gas production at radioactive low-level waste disposal sites

    SciTech Connect (OSTI)

    Weiss, A.J.; Tate, R.L. III; Colombo, P.

    1982-05-01T23:59:59.000Z

    Factors controlling gaseous emanations from low level radioactive waste disposal sites are assessed. Importance of gaseous fluxes of methane, carbon dioxide, and possible hydrogen from the site, stems from the inclusion of tritium and/or carbon-14 into the elemental composition of these compounds. In that the primary source of these gases is the biodegradation of organic components of the waste material, primary emphasis of the study involved an examination of the biochemical pathways producing methane, carbon dioxide, and hydrogen, and the environmental parameters controlling the activity of the microbial community involved. Initial examination of the data indicates that the ecosystem is anaerobic. As the result of the complexity of the pathway leading to methane production, factors such as substrate availability, which limit the initial reaction in the sequence, greatly affect the overall rate of methane evolution. Biochemical transformations of methane, hydrogen and carbon dioxide as they pass through the soil profile above the trench are discussed. Results of gas studies performed at three commercial low level radioactive waste disposal sites are reviewed. Methods used to obtain trench and soil gas samples are discussed. Estimates of rates of gas production and amounts released into the atmosphere (by the GASFLOW model) are evaluated. Tritium and carbon-14 gaseous compounds have been measured in these studies; tritiated methane is the major radionuclide species in all disposal trenches studied. The concentration of methane in a typical trench increases with the age of the trench, whereas the concentration of carbon dioxide is similar in all trenches.

  10. Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site near Shiprock, New Mexico. Revision 1

    SciTech Connect (OSTI)

    Not Available

    1994-04-01T23:59:59.000Z

    This baseline risk assessment at the former uranium mill tailings site near Shiprock, New Mexico, evaluates the potential impact to public health or the environment resulting from ground water contamination at the former uranium mill processing site. The tailings and other contaminated material at this site were placed in an on-site disposal cell in 1986 through the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. Currently, the UMTRA Project is evaluating ground water contamination. This risk assessment is the first document specific to this site for the Ground Water Project. There are no domestic or drinking water wells in the contaminated ground water of the two distinct ground water units: the contaminated ground water in the San Juan River floodplain alluvium below the site and the contaminated ground water in the terrace alluvium area where the disposal cell is located. Because no one is drinking the affected ground water, there are currently no health or environmental risks directly associated with the contaminated ground water. However, there is a potential for humans, domestic animals, and wildlife to the exposed to surface expressions of ground water in the seeps and pools in the area of the San Juan River floodplain below the site. For these reasons, this risk assessment evaluates potential exposure to contaminated surface water and seeps as well as potential future use of contaminated ground water.

  11. Corrosion Control Measures For Liquid Radioactive Waste Storage Tanks At The Savannah River Site

    SciTech Connect (OSTI)

    Wiersma, B. J.; Subramanian, K. H.

    2012-11-27T23:59:59.000Z

    The Savannah River Site has stored radioactive wastes in large, underground, carbon steel tanks for approximately 60 years. An assessment of potential degradation mechanisms determined that the tanks may be vulnerable to nitrate- induced pitting corrosion and stress corrosion cracking. Controls on the solution chemistry and temperature of the wastes are in place to mitigate these mechanisms. These controls are based upon a series of experiments performed using simulated solutions on materials used for construction of the tanks. The technical bases and evolution of these controls is presented in this paper.

  12. Revised Draft Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement, Richland, Washington

    SciTech Connect (OSTI)

    N /A

    2003-04-11T23:59:59.000Z

    This ''Revised Draft Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement'' (HSW EIS) covers three primary aspects of waste management at Hanford--waste treatment, storage, and disposal. It also addresses four kinds of solid waste--low-level waste (LLW), mixed (radioactive and chemically hazardous) low-level waste (MLLW), transuranic (TRU) waste, and immobilized low-activity waste (ILAW). It fundamentally asks the question: how should we manage the waste we have now and will have in the future? This EIS analyzes the impacts of the LLW, MLLW, TRU waste, and ILAW we currently have in storage, will generate, or expect to receive at Hanford. The HSW EIS is intended to help us determine what specific facilities we will continue to use, modify, or construct to treat, store, and dispose of these wastes (Figure S.1). Because radioactive and chemically hazardous waste management is a complex, technical, and difficult subject, we have made every effort to minimize the use of acronyms (making an exception for our four waste types listed above), use more commonly understood words, and provide the ''big picture'' in this summary. An acronym list, glossary of terms, and conversions for units of measure are provided in a readers guide in Volume 1 of this EIS.

  13. Innovative technology for expedited site remediation of extensive surface and subsurface contamination

    SciTech Connect (OSTI)

    Audibert, J.M.E.; Lew, L.R.

    1994-12-31T23:59:59.000Z

    Large scale surface and subsurface contamination resulted from numerous releases of feed stock, process streams, waste streams, and final product at a major chemical plant. Soil and groundwater was contaminated by numerous compounds including lead, tetraethyl lead, ethylene dibromide, ethylene dichloride, and toluene. The state administrative order dictated that the site be investigated fully, that remedial alternative be evaluated, and that the site be remediated within a year period. Because of the acute toxicity and extreme volatility of tetraethyl lead and other organic compounds present at the site and the short time frame ordered by the regulators, innovative approaches were needed to carry out the remediation while protecting plant workers, remediation workers, and the public.

  14. Surface and subsurface characterization of uranium contamination at the Fernald environmental management site

    SciTech Connect (OSTI)

    Schilk, A.J.; Perkins, R.W.; Abel, K.H.; Brodzinski, R.L.

    1993-04-01T23:59:59.000Z

    The past operations of uranium production and support facilities at several Department of Energy (DOE) sites have occasionally resulted in the local contamination of some surface and subsurface soils, and the three-dimensional distribution of the uranium at these sites must be thoroughly characterized before any effective remedial protocols can be established. To this end, Pacific Northwest Laboratory (PNL) has been tasked by the DOE`s Office of Technology Development with adapting, developing, and demonstrating technologies for the measurement of uranium in surface and subsurface soils at the Fernald Uranium in Soils Integrated Demonstration site. These studies are detailed in this report.

  15. Baseline risk assessment of ground water contamination at the uranium mill tailings sites near Slick Rock, Colorado

    SciTech Connect (OSTI)

    Not Available

    1994-11-01T23:59:59.000Z

    This baseline risk assessment of ground water contamination at the uranium mill tailings sites near Slick Rock, Colorado, evaluates potential public health and environmental impacts resulting from ground water contamination at the former North Continent (NC) and Union Carbide (UC) uranium mill processing sites. The tailings at these sites will be placed in a disposal cell at the proposed Burro Canyon, Colorado, site. The US Department of Energy (DOE) anticipates the start of the first phase remedial action by the spring of 1995 under the direction of the DOE`s Uranium Mill Tailings Remedial Action (UMTRA) Project. The second phase of the UMTRA Project will evaluate ground water contamination. This baseline risk assessment is the first site-specific document for these sites under the Ground Water Project. It will help determine the compliance strategy for contaminated ground water at the site. In addition, surface water and sediment are qualitatively evaluated in this report.

  16. Changes in major organic contaminants in the groundwater at the Hoe Creek underground coal gasification site

    SciTech Connect (OSTI)

    Wang, F.; Mead, W.

    1985-08-01T23:59:59.000Z

    The results of groundwater analysis at the Hoe Creek underground coal gasification (UCG) site have indicated that, after gasification, the phenolic compounds and neutral aromatic hydrocarbons decrease more slowly than expected on the basis of our laboratory studies. The field data also fail to confirm the expected inverse relationship between a contaminant's water solubility and the extent to which it is sorbed by surrounding coal. The authors described a mechanism for the deposition of coal pyrolysis products that may help to elucidate the observed behavior of these organic contaminants. 7 refs., 7 figs.

  17. Sulfur Polymer Stabilization/Solidification Treatability Study of Mercury Contaminated Soil from the Y-12 Site

    SciTech Connect (OSTI)

    Kalb P.; Milian, L.; Yim, S. P.

    2012-11-30T23:59:59.000Z

    As a result of past operations, the Department of Energy’s (DOE) Oak Ridge Y-12 National Security Complex (Y-12 Plant) has extensive mercury-contamination in building structures, soils, storm sewer sediments, and stream sediments, which are a source of pollution to the local ecosystem. Because of mercury’s toxicity and potential impacts on human health and the environment, DOE continues to investigate and implement projects to support the remediation of the Y-12 site.URS and #9122;CH2M Oak Ridge LLC (UCOR) under its prime contract with DOE has cleanup responsibilities on the DOE Oak Ridge Reservation and is investigating potential mercury-contaminated soil treatment technologies through an agreement with Babcock and Wilcox (B and W) Y-12, the Y-12 operating contractor to DOE. As part of its investigations, UCOR has subcontracted with Brookhaven National Laboratory (BNL) to conduct laboratory-scale studies evaluating the applicability of the Sulfur Polymer Stabilization/Solidification (SPSS) process using surrogate and actual mixed waste Y-12 soils containing mercury (Hg) at 135, 2,000, and 10,000 ppm.SPSS uses a thermoplastic sulfur binder to convert Hg to stable mercury sulfide (HgS) and solidifies the chemically stable product in a monolithic solid final waste form to reduce dispersion and permeability. Formulations containing 40 – 60 dry wt% Y-12 soil were fabricated and samples were prepared in triplicate for Environmental Protection Agency Toxicity Characteristic Leaching Procedure (TCLP) testing by an independent laboratory. Those containing 50 and 60 wt% soil easily met the study criteria for maximum allowable Hg concentrations (47 and 1 ppb, respectively compared with the TCLP limit of 200 ppb Hg). The lowest waste loading of 40 wt% yielded TCLP Hg concentrations slightly higher (240 ppb) than the allowable limit. Since the Y-12 soil tended to form clumps, the improved leaching at higher waste loadings was probably due to reduction in particle size from friction of the soil mixing, which creates more surface area for chemical conversion. This was corroborated by the fact that the same waste loading pre-treated by ball milling to reduce particle size prior to SPSS processing yielded TCLP concentrations almost 30 times lower, and at 8.5 ppb Hg was well below EPA limits. Pre-treatment by ball milling also allowed a reduction in the time required for stabilization, thus potentially reducing total process times by 30%.Additional performance testing was conducted including measurement of compressive strength to confirm mechanical integrity and immersion testing to determine the potential impacts of storage or disposal under saturated conditions. For both surrogate and actual Y-12 treated soils, waste form compressive strengths ranged between 2,300 and 6,500 psi, indicating very strong mechanical integrity (a minimum of greater than 40 times greater than the NRC guidance for low-level radioactive waste). In general, compressive strength increases with waste loading as the soil acts as an aggregate in the sulfur concrete waste forms. No statistically significant loss in strength was recorded for the 30 and 40 wt% surrogate waste samples and only a minor reduction in strength was measured for the 43 wt% waste forms. The 30 wt% Y-12 soil did not show a significant loss in strength but the 50 wt% samples were severely degraded in immersion due to swelling of the clay soil. The impact on Hg leaching, if any, was not determined.

  18. Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site near Grand Junction, Colorado

    SciTech Connect (OSTI)

    Not Available

    1994-06-01T23:59:59.000Z

    This Baseline Risk Assessment of Ground Water Contamination at the Uranium Mill Tailings Site Near Grand Junction, Colorado evaluates potential impacts to public health or the environment resulting from ground water contamination at the former uranium mill processing site. The tailings and other contaminated material at this site were placed in an off-site disposal cell by the US Department of Energy`s (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. The remedial activities at the site were conducted from 1989 to 1993. Currently, the UMTRA Project is evaluating ground water contamination. This risk assessment is the first document specific to this site for the Ground Water Project. This risk assessment evaluates the most contaminated ground water that flows beneath the processing site toward the Colorado River. The monitor wells that have consistently shown the highest concentrations of most contaminants are used to assess risk. This risk assessment will be used in conjunction with additional activities and documents to determine what remedial action may be needed for contaminated ground water at the site. This risk assessment follows an approach outlined by the EPA. the first step is to evaluate ground water data collected from monitor wells at the site. Evaluation of these data showed that the contaminants of potential concern in the ground water are arsenic, cadmium, cobalt, fluoride, iron, manganese, molybdenum, nickel, sulfate, uranium, vanadium, zinc, and radium-226. The next step in the risk assessment is to estimate how much of these contaminants people would be exposed to if they drank from a well installed in the contaminated ground water at the former processing site.

  19. Surficial geology and performance assessment for a Radioactive Waste Management Facility at the Nevada Test Site

    SciTech Connect (OSTI)

    Snyder, K.E. [Lockheed Environmental Systems and Technologies, Co., Las Vegas, NV (United States); Gustafson, D.L.; Huckins-Gang, H.E.; Miller, J.J.; Rawlinson, S.E. [Raytheon Services Nevada, Las Vegas, NV (United States)

    1995-02-01T23:59:59.000Z

    At the Nevada Test Site, one potentially disruptive scenario being evaluated for the Greater Confinement Disposal (GCD) Facility Performance Assessment is deep post-closure erosion that would expose buried radioactive waste to the accessible environment. The GCD Facility located at the Area 5 Radioactive Waste Management Site (RWMS) lies at the juncture of three alluvial fan systems. Geomorphic surface mapping in northern Frenchman Flat indicates that reaches of these fans where the RWMS is now located have been constructional since at least the middle Quaternary. Mapping indicates a regular sequence of prograding fans with entrenchment of the older fan surfaces near the mountain fronts and construction of progressively younger inset fans farther from the mountain fronts. At the facility, the oldest fan surfaces are of late Pleistocene and Holocene age. More recent geomorphic activity has been limited to erosion and deposition along small channels. Trench and pit wall mapping found maximum incision in the vicinity of the RWMS to be less than 1.5 m. Based on collected data, natural geomorphic processes are unlikely to result in erosion to a depth of more than approximately 2 m at the facility within the 10,000-year regulatory period.

  20. On-Site Decontamination System for Liquid Low Level Radioactive Waste - 13010

    SciTech Connect (OSTI)

    OSMANLIOGLU, Ahmet Erdal [Cekmece Nuclear Research and Training Center, Kucukcekmece Istanbul (Turkey)] [Cekmece Nuclear Research and Training Center, Kucukcekmece Istanbul (Turkey)

    2013-07-01T23:59:59.000Z

    This study is based on an evaluation of purification methods for liquid low-level radioactive waste (LLLW) by using natural zeolite. Generally the volume of liquid low-level waste is relatively large and the specific activity is rather low when compared to other radioactive waste types. In this study, a pilot scale column was used with natural zeolite as an ion exchanger media. Decontamination and minimization of LLLW especially at the generation site decrease operational cost in waste management operations. Portable pilot scale column was constructed for decontamination of LLW on site. Effect of temperature on the radionuclide adsorption of the zeolite was determined to optimize the waste solution temperature for the plant scale operations. In addition, effect of pH on the radionuclide uptake of the zeolite column was determined to optimize the waste solution pH for the plant scale operations. The advantages of this method used for the processing of LLLW are discussed in this paper. (authors)

  1. The Assessment of Future Human Actions at Radioactive Waste Disposal Sites: An international perspective

    SciTech Connect (OSTI)

    Anderson, D.R. [Sandia National Labs., Albuquerque, NM (United States); Galson, D.A. [Galson Sciences Ltd., (United Kindgom); Patera, E.S. [Nuclear Energy Agency, 75 - Paris (France)

    1994-04-01T23:59:59.000Z

    For some deep geological disposal systems, the level of confinement provided by the natural and engineered barriers is considered to be so high that the greatest long-term risks associated with waste disposal may arise from the possibility of future human actions breaching the natural and/or engineered barrier systems. Following a Workshop in 1989, the OECD Nuclear Energy Agency established a Working Group on Assessment of Future Human Actions (FHA) a Radioactive Waste Disposal Sites. This Group met four times in the period 1991--1993, and has extensively reviewed approaches to and experience of incorporating the effects of FHA into long-term performance assessments (PAs). The Working Group`s report reviews the main issues concerning the treatment of FHA, presents a general framework for the quantitative, consideration of FHA in radioactive waste disposal programmes, and discusses means in reduce the risks associated with FHA. The Working Group concluded that FHA must be considered in PAs, although FHA where the actors were cognizant of the risks could be ignored. Credit can be taken for no more than several hundred years of active site control; additional efforts should therefore be taken to reduce the risks associated with FHA. International agreement on principles for the construction of FHA scenarios would build confidence, as would further discussion concerning regulatory policies for judging risks associated with FHA.

  2. CLOSURE WELDING RADIOACTIVE MATERIALS CONTAINERS AT THE DEPARTMENT OF ENERGY (DOE) HANFORD SITE

    SciTech Connect (OSTI)

    CANNELL, G.R.

    2006-09-01T23:59:59.000Z

    The Department of Energy's (DOE) responsibility for the disposition of radioactive materials has given rise to several unique welding applications. Many of these materials require packaging into containers for either Interim or long-term storage. It is not uncommon that final container fabrication, i.e., closure welding, is performed with these materials already placed into the container. Closure welding is typically performed remote to the container, and routine post-weld testing and nondestructive examination (NDE) are often times not feasible. Fluor Hanford has packaged many such materials in recent years as park of the Site's cleanup mission. In lieu of post-weld testing and NDE, the Fluor-Hanford approach has been to establish weld quality through ''upfront'' development and qualification of welding parameters, and then ensure parameter compliance during welding. This approach requires a rigor not usually afforded to typical welding development activities, and may involve statistical analysis and extensive testing, including burst, drop, sensitive leak testing, etc. This paper provides an instructive review of the development and qualification activities associated with the closure of radioactive materials containers, including a brief report on activities for closure welding research reactor, spent nuclear fuel (SNF) overpacks at the Hanford Site.

  3. Radioactive contamination of cistern waters along the Croatian coast of the Adriatic Sea by [sup 90]Sr

    SciTech Connect (OSTI)

    Franic, Z.; Lokobauer, N.; Marovic, G. (Inst. for Medical Research and Occupational Health, Zagreb (Croatia). Radiation Protection Unit)

    1999-07-01T23:59:59.000Z

    Measurements of radioactive contamination of water samples from cisterns collecting rainwater containing fission products from roofs and other surfaces have been carried out along the Croatian coast of the Adriatic sea since 1968. An exponential decline of radioactivity followed the nuclear moratorium. After the nuclear accident at Chernobyl, higher levels of [sup 137]Cs and [sup 90]Sr were detected again, with cistern waters being the only environmental samples in Croatia in which elevated [sup 90]Sr activities persisted for several years. For the pre-Chernobyl period, the observed mean residence time of [sup 90]Sr in cistern waters, estimated to be 6.2 [+-] 1.9 y, was similar to that calculated for fallout. Contrary, for the post-Chernobyl time, observed [sup 90]Sr mean residence time was calculated to be considerably shorter, reflecting the tropospheric mean residence time. The annual dose for the critical adult population received from [sup 90]Sr and [sup 137]Cs by drinking cistern water was estimated to be very small, in the 1990's less than few [micro]Sv y[sup [minus]1].

  4. Organic contaminants in groundwater mar an underground coal gasification site in northeastern Wyoming

    SciTech Connect (OSTI)

    Stuermer, D.H.

    1982-09-01T23:59:59.000Z

    Three groundwater samples collected near two underground coal gasification (UCG) sites 15 months after the end of gasification were analysed for dissolved organic contaminants. The contaminants consisted of phenols, aromatic carboxylic acids, aromatic hydrocarbons, ketones, aldehydes, pyridines, quinolines, isoquinolines, and aromatic amines. Concentrations ranged up to about 50 ppm with large variations both in the relative concentrations of acidic, neutral, and basic constituents and in the concentrations of individual compounds. Naphthalene o-xylene, 2-methylpyridine, and o-cresol were consistently present in high concentrations and were identified as UCG contaminant-indicator compounds that appear to be particularly useful for monitoring purposes. A simplified method of analysis for these compounds was developed.

  5. Organic contaminants in groundwater near an underground coal gasification site in northeastern Wyoming

    SciTech Connect (OSTI)

    Stuermer, D.H.; Ng, D.J.; Morris, C.J.

    1982-09-01T23:59:59.000Z

    Three groundwater samples collected near two underground coal gasification (UCG) sites 15 months after the end of gasification were analyzed for dissolved organic contaminants. The contaminants consisted of phenols, aromatic carboxylic acids, aromatic hydrocarbons, ketones, aldehydes, pyridines, quinolines, isoquinolines, and aromatic amines. Concentrations ranged up to about 50 ppm with large variations both in the relative concentrations of acidic, neutral, and basic constituents and in the concentrations of individual compounds. Naphthalene, o-xylene, 2-methylpyridine, and o-cresol were consistently present in high concentrations and were identified as UCG contaminant-indicator compounds that appear to be particularly useful for monitoring purposes. A simplified method of analysis for these compounds was developed.

  6. Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Sites near Rifle, Colorado

    SciTech Connect (OSTI)

    NONE

    1995-05-01T23:59:59.000Z

    The ground water project evaluates the nature and extent of ground water contamination resulting from the uranium ore processing activities. This report is a site specific document that will be used to evaluate current and future impacts to the public and the environment from exposure to contaminated ground water. Currently, no one is using the ground water and therefore, no one is at risk. However, the land will probably be developed in the future and so the possibility of people using the ground water does exist. This report examines the future possibility of health hazards resulting from the ingestion of contaminated drinking water, skin contact, fish ingestion, or contact with surface waters and sediments.

  7. Baseline risk assessment of ground water contamination at the uranium mill tailings site near Durango, Colorado. Revision 1

    SciTech Connect (OSTI)

    NONE

    1995-09-01T23:59:59.000Z

    For the UMTRA Project site located near Durango, Colorado (the Durango site), the Surface Project cleanup occurred from 1986 to 1991. An evaluation was made to determine whether exposure to ground water contaminated by uranium processing could affect people`s health. Exposure could occur from drinking water pumped from a hypothetical well drilled in the contaminated ground water area. In addition, environmental risks may result if plants or animals are exposed to contaminated ground water, or surface water that has mixed with contaminated ground water. This risk assessment report is the first site-specific document prepared for the UMTRA Ground Water Project at the Durango site. The results of this report and further site characterization of the Durango site will be used to determine what is necessary to protect public health and the environment, and to comply with the EPA standards.

  8. Characterization ReportOperational Closure Covers for the Area 5 Radioactive Waste Management Site at the Nevada Test Site

    SciTech Connect (OSTI)

    Bechtel Nevada Geotechnical Sciences

    2005-06-01T23:59:59.000Z

    Bechtel Nevada (BN) manages two low-level Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site (NTS) for the U.S. Department of Energy (DOE) National Nuclear Security Administration Nevada Site Office (NNSA/NSO). The Area 3 RWMS is located in south-central Yucca Flat and the Area 5 RWMS is located about 15 miles south, in north-central Frenchman Flat. Though located in two separate topographically closed basins, they are similar in climate and hydrogeologic setting. The Area 5 RWMS uses engineered shallow-land burial cells to dispose of packaged waste, while the Area 3 RWMS uses subsidence craters formed from underground testing of nuclear weapons for the disposal of packaged and unpackaged bulk waste. Over the next several decades, most waste disposal units at both the Area 3 and Area 5 RWMSs are anticipated to be closed. Closure of the Area 3 and Area 5 RWMSs will proceed through three phases: operational closure, final closure, and institutional control. Many waste disposal units at the Area 5RWMS are operationally closed and final closure has been placed on one unit at the Area 3 RWMS (U-3ax/bl). Because of the similarities between the two sites (e.g., type of wastes, environmental factors, operational closure cover designs, etc.), many characterization studies and data collected at the Area 3 RWMS are relevant and applicable to the Area 5 RWMS. For this reason, data and closure strategies from the Area 3 RWMS are referred to as applicable. This document is an interim Characterization Report – Operational Closure Covers, for the Area 5 RWMS. The report briefly describes the Area 5 RWMS and the physical environment where it is located, identifies the regulatory requirements, reviews the approach and schedule for closing, summarizes the monitoring programs, summarizes characterization studies and results, and then presents conclusions and recommendations.

  9. Radiological Survey of Contaminated Installations of Research Reactor before Dismantling in High Dose Conditions with Complex for Remote Measurements of Radioactivity - 12069

    SciTech Connect (OSTI)

    Danilovich, Alexey; Ivanov, Oleg; Lemus, Alexey; Smirnov, Sergey; Stepanov, Vyacheslav; Volkovich, Anatoly [National Research Centre 'Kurchatov Institute', Moscow (Russian Federation)

    2012-07-01T23:59:59.000Z

    Decontamination and decommissioning of the research reactors MR (Testing Reactor) and RFT (Reactor of Physics and Technology) has recently been initiated in the National Research Center (NRC) 'Kurchatov institute', Moscow. These research reactors have a long history and many installations - nine loop facilities for experiments with different kinds of fuel. When decommissioning nuclear facilities it is necessary to measure the distribution of radioactive contamination in the rooms and at the equipment at high levels of background radiation. At 'Kurchatov Institute' some special remote control measuring systems were developed and they are applied during dismantling of the reactors MR and RFT. For a survey of high-level objects a radiometric system mounted on the robotic Brokk vehicle is used. This system has two (4? and collimated) dose meters and a high resolution video camera. Maximum measured dose rate for this system is ?8.5 Sv/h. To determine the composition of contaminants, a portable spectrometric system is used. It is a remotely controlled, collimated detector for scanning the distribution of radioactive contamination. To obtain a detailed distribution of contamination a remote-controlled gamma camera is applied. For work at highly contaminated premises with non-uniform background radiation, another camera is equipped with rotating coded mask (coded aperture imaging). As a result, a new system of instruments for remote radioactivity measurements with wide range of sensitivity and angular resolution was developed. The experience and results of measurements in different areas of the reactor and at its loop installations, with emphasis on the radioactive survey of highly-contaminated samples, are presented. These activities are conducted under the Federal Program for Nuclear and Radiation Safety of Russia. Adaptation of complex remote measurements of radioactivity and survey of contaminated installations of research reactor before dismantling in high dose conditions has proven successful. The radioactivity measuring devices for operation at high, non-uniform dose background were tested in the field and a new data of measurement of contamination distribution in the premises and installations were obtained. (authors)

  10. Response of PCB contamination in stream fish to abatement actions at an industrial site

    SciTech Connect (OSTI)

    Southworth, G.R.; Peterson, M.J.; McCarthy, J.F. [Oak Ridge National Lab., TN (United States); Milne, G. [Paducah Gaseous Diffusion Plant, KY (United States)

    1995-12-31T23:59:59.000Z

    The Paducah Gaseous Diffusion Plant (PGDP) in Paducah, Kentucky, used large quantities of PCBs in equipment associated with the great electric power requirements of isotopic enrichment of uranium. Historic losses of PCBs in the 1950s and 1960s have left a legacy of contamination at the site. A biological monitoring program implemented in 1987 found PCBs in PGDP effluents and in fish downstream from facility discharges. As a consequence, a fish consumption advisory was posted on Little Bayou Creek by the Commonwealth of Kentucky in 1987, and regulatory discharge limits for PCBs at PGDP were reduced. Monitoring at multiple locations in receiving streams indicated that PGDP discharges were more important than in stream sediment contamination as sources of PCBs to fish. Environmental management and compliance staff at PGDP led an effort to reduce PCB discharges and monitor the effects of those actions. The active discharge of uncontaminated process water to historically PCB-contaminated drainage systems was found to mobilize PCBs into KPDES (Clean Water Act) regulated effluents. Efforts to locate PCB sources within the plant, coupled with improvements in management practices and remedial actions, appear to have been successful in reducing PCB discharges from these sources. Actions included emplacing passive monitors in the plant drainage system to identify this as a chronic source, and consolidating and re-routing effluents to minimize flow through PCB-contaminated channels. As a consequence, PCB contamination in fish in small streams receiving plant discharges decreased 75% over from 1992--1995.

  11. CLOSURE REPORT FOR CORRECTIVE ACTION UNIT 528: POLYCHLORINATED BIPHENYLS CONTAMINATION NEVADA TEST SITE, NEVADA

    SciTech Connect (OSTI)

    BECHTEL NEVADA

    2006-09-01T23:59:59.000Z

    This Closure Report (CR) describes the closure activities performed at CAU 528, Polychlorinated Biphenyls Contamination, as presented in the Nevada Division of Environmental Protection (NDEP)-approved Corrective Action Plan (CAP) (US. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSAINSO], 2005). The approved closure alternative was closure in place with administrative controls. This CR provides a summary of the completed closure activities, documentation of waste disposal, and analytical data to confirm that the remediation goals were met.

  12. Corrective Action Decision Document for Corrective Action Unit 168: Area 25 and 26 Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada, Rev. No.: 2 with Errata Sheet

    SciTech Connect (OSTI)

    Wickline, Alfred

    2006-12-01T23:59:59.000Z

    This Corrective Action Decision Document has been prepared for Corrective Action Unit (CAU) 168: Area 25 and 26, Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada. The purpose of this Corrective Action Decision Document is to identify and provide a rationale for the selection of a recommended corrective action alternative for each corrective action site (CAS) within CAU 168. The corrective action investigation (CAI) was conducted in accordance with the ''Corrective Action Investigation Plan for Corrective Action Unit 168: Area 25 and 26, Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada'', as developed under the ''Federal Facility Agreement and Consent Order'' (1996). Corrective Action Unit 168 is located in Areas 25 and 26 of the Nevada Test Site, Nevada and is comprised of the following 12 CASs: CAS 25-16-01, Construction Waste Pile; CAS 25-16-03, MX Construction Landfill; CAS 25-19-02, Waste Disposal Site; CAS 25-23-02, Radioactive Storage RR Cars; CAS 25-23-13, ETL - Lab Radioactive Contamination; CAS 25-23-18, Radioactive Material Storage; CAS 25-34-01, NRDS Contaminated Bunker; CAS 25-34-02, NRDS Contaminated Bunker; CAS 25-99-16, USW G3; CAS 26-08-01, Waste Dump/Burn Pit; CAS 26-17-01, Pluto Waste Holding Area; and CAS 26-19-02, Contaminated Waste Dump No.2. Analytes detected during the CAI were evaluated against preliminary action levels (PALs) to determine contaminants of concern (COCs) for CASs within CAU 168. Radiological measurements of railroad cars and test equipment were compared to unrestricted (free) release criteria. Assessment of the data generated from the CAI activities revealed the following: (1) Corrective Action Site 25-16-01 contains hydrocarbon-contaminated soil at concentrations exceeding the PAL. The contamination is at discrete locations associated with asphalt debris. (2) No COCs were identified at CAS 25-16-03. Buried construction waste is present in at least two disposal cells contained within the landfill boundaries. (3) No COCs were identified at CAS 25-19-02. (4) Radiological surveys at CAS 25-23-02 identified 13 railroad cars that exceeded the NV/YMP Radiological Control Manual limits for free release. Six railroad cars were below these limits and therefore met the free-release criteria. (5) An In-Situ Object Counting System survey taken at CAS 25-23-02 identified two railroad cars possibly containing fuel fragments; both exceeded the NV/YMP Radiological Control Manual free release criteria. (6) Corrective Action Site 25-23-18 contains total petroleum hydrocarbons-diesel-range organics, Aroclor-1260, uranium-234, uranium-235, strontium-90, and cesium-137 that exceed PALs. (7) Radiological surveys at CAS 25-34-01 indicate that there were no total contamination readings that exceeded the NV/YMP Radiological Control Manual limits for free release. (8) Radiological surveys at CAS 25-34-02 indicate that there were no total contamination readings that exceeded the NV/YMP Radiological Control Manual limits for free release. (9) Radiological surveys at CAS 25-23-13 identified six pieces of equipment that exceed the NV/YMP Radiological Control Manual limits for free release. (10) Corrective Action Site 25-99-16 was not investigated. A review of historical documentation and current site conditions showed that no further characterization was required to select the appropriate corrective action. (11) Corrective Action Site 26-08-01 contains hydrocarbon-contaminated soil at concentrations exceeding the PAL. The contamination is at discrete locations associated with asphalt debris. (12) Corrective Action Site 26-17-01 contains total petroleum hydrocarbons-diesel-range organics and Aroclor-1260 exceeding the PALs. (13) Radiological surveys at CAS 26-19-02 identified metallic debris that exceeded the NV/YMP Radiological Control Manual limits for free release. Concentrations of radiological or chemical constituents in soil did not exceed PALs.

  13. Baseline risk assessment of ground water contamination at the inactive uriniferous lignite ashing site near Belfield, North Dakota. Revision 1

    SciTech Connect (OSTI)

    NONE

    1994-09-01T23:59:59.000Z

    This risk assessment evaluates the potential for impacts to public health or the environment from contaminated ground water at this site caused by the burning of coal containing uranium to produce uranium. Potential risk is quantified for constituents introduced from the processing activities and not for those constituents naturally occurring in background ground water in the site vicinity. Because background ground water quality has the potential to cause adverse health effects from exposure through drinking, any risks associated with contaminants attributable to site activities are incremental to these risks from background. The incremental risk from site-related contaminants is quantified in this risk assessment. The baseline risk from background water quality is incorporated only into the assessment of potential chemical interactions and the definition of the overall site condition. The US Department of Energy`s (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project is developing plans to remedy soil and ground water contamination at the site. The UMTRA Surface Project consists of determining the extent of soil contamination and disposing of the contaminated soils in an engineered disposal cell. The UMTRA Ground Water Project consists of evaluating ground water contamination. Under the UMTRA Ground Water Project, results of this risk assessment will help determine what ground water compliance strategy may be applied at the site.

  14. Contamination of the Northern Oceans from Releases of Radioactivity from the Former Soviet Union

    SciTech Connect (OSTI)

    Gomez, Leo S.

    1999-06-04T23:59:59.000Z

    During the Cold War the handling of Soviet military nuclear wastes was a classified topic--kept secret to hide the status and readiness of Soviet military forces. Following the end of the Cold War information about the handling of nuclear wastes by agencies of the Former Soviet Union (FSU) became available. The US Government response to the disclosure of disposal of radioactive wastes into the Arctic Ocean and into rivers that drain into the Arctic Ocean was the finding of the Arctic Nuclear Waste Assessment Program (ANWAP) in the Office of Naval Research (ONR). Projects were aided by ANWAP to study the behavior, transport, and fate of radionuclides in the Arctic Ocean. One of the research teams, the Risk Assessment Integration Group (RAIG) assessed the potential risks to humans and to the environment, particularly in the US Alaskan Arctic.

  15. Baseline risk assessment of ground water contamination at the Monument Valley Uranium Mill Tailings Site, Cane Valley, Arizona. Revision 1

    SciTech Connect (OSTI)

    Not Available

    1994-08-01T23:59:59.000Z

    This baseline risk assessment evaluates potential impact to public health or the environment from ground water contamination at the former uranium mill processing site in Cane Valley near Monument Valley, Arizona. The US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project has relocated and stabilized this site`s tailings and other contaminated material in a disposal cell at Mexican Hat, Utah. The second phase of the UMTRA Project is to evaluate ground water contamination. This risk assessment is the first document specific to this site for the Ground Water Project that evaluates potential health and environmental risks. It will help determine the approach required to address contaminated ground water at the site.

  16. Corrective Action Investigation Plan for Corrective Action Unit 190: Contaminated Waste Sites Nevada Test Site, Nevada, Rev. No.: 0

    SciTech Connect (OSTI)

    Wickline, Alfred

    2006-12-01T23:59:59.000Z

    Corrective Action Unit (CAU) 190 is located in Areas 11 and 14 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 190 is comprised of the four Corrective Action Sites (CASs) listed below: (1) 11-02-01, Underground Centrifuge; (2) 11-02-02, Drain Lines and Outfall; (3) 11-59-01, Tweezer Facility Septic System; and (4) 14-23-01, LTU-6 Test Area. These sites are being investigated because existing information is insufficient on the nature and extent of potential contamination to evaluate and recommend corrective action alternatives. Additional information will be obtained before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS by conducting a corrective action investigation (CAI). The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on August 24, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture, and National Security Technologies, LLC. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 190. The scope of the CAU 190 CAI includes the following activities: (1) Move surface debris and/or materials, as needed, to facilitate sampling; (2) Conduct radiological and geophysical surveys; (3) Perform field screening; (4) Collect and submit environmental samples for laboratory analysis to determine whether contaminants of concern (COCs) are present; (5) If COCs are present, collect additional step-out samples to define the lateral and vertical extent of the contamination; (6) Collect samples of source material, if present, to determine the potential for a release; (7) Collect samples of investigation-derived waste, as needed, for waste management and minimization purposes; and (8) Collect quality control samples. This Corrective Action Investigation Document (CAIP) has been developed in accordance with the Federal Facility Agreement and Consent Order (FFACO) agreed to by the State of Nevada, U.S. Department of Energy, and U.S. Department of Defense. Under the FFACO, this CAIP will be submitted to the Nevada Division of Environmental Protection for approval. Field work will be conducted following approval.

  17. Nevada Test 1999 Waste Management Monitoring Report, Area 3 and Area 5 radioactive waste management sites

    SciTech Connect (OSTI)

    Yvonne Townsend

    2000-05-01T23:59:59.000Z

    Environmental monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site (NTS). These monitoring data include radiation exposure, air, groundwater, meteorology, vadose zone, and biota data. Although some of these media (radiation exposure, air, and groundwater) are reported in detail in other Bechtel Nevada reports (Annual Site Environmental Report [ASER], the National Emissions Standard for Hazardous Air Pollutants [NESHAP] report, and the Annual Groundwater Monitoring Report), they are also summarized in this report to provide an overall evaluation of RWMS performance and environmental compliance. Direct radiation monitoring data indicate that exposure at and around the RWMSs is not above background levels. Air monitoring data indicate that tritium concentrations are slightly above background levels, whereas radon concentrations are not above background levels. Groundwater monitoring data indicate that the groundwater in the alluvial aquifer beneath the Area 5 RWMS has not been affected by the facility. Meteorology data indicate that 1999 was a dry year: rainfall totaled 3.9 inches at the Area 3 RWMS (61 percent of average) and 3.8 inches at the Area 5 RWMS (75 percent of average). Vadose zone monitoring data indicate that 1999 rainfall infiltrated less than one foot before being returned to the atmosphere by evaporation. Soil-gas tritium data indicate very slow migration, and tritium concentrations in biota were insignificant. All 1999 monitoring data indicate that the Area 3 and Area 5 RWMSs are performing as expected at isolating buried waste.

  18. Projected environmental impacts of radioactive material transportation to the first US repository site

    SciTech Connect (OSTI)

    Neuhauser, K.S.; Cashwell, J.W.; Reardon, P.C.; Ostmeyer, R.M.; McNair, G.W.

    1986-12-31T23:59:59.000Z

    This paper discusses the relative national environmental impacts of transporting nuclear wastes to each of the nine candidate repository sites in the United States. Several of the potential sites are closely clustered and, for the purpose of distance and routing calculations, are treated as a single location. These are: Cypress Creek Dome and Richton Dome in Mississippi (Gulf Interior Region), Deaf Smith County and Swisher County sites in Texas (Permian Basin), and Davis Canyon and Lavender Canyon site in Utah (Paradox Basin). The remaining sites are: Vacherie Dome, Louisiana; Yucca Mountain, Nevada; and Hanford Reservation, Washington. For compatibility with both the repository system authorized by the NWPA and with the MRS option, two separate scenarios were analyzed. In belief, they are (1) shipment of spent fuel and high-level wastes (HLW) directly from waste generators to a repository (Reference Case) and (2) shipment of spent fuel to a Monitored Retrievable Storage (MRS) facility and then to a repository. Between 17 and 38 truck accident fatalities, between 1.4 and 7.7 rail accident fatalities, and between 0.22 and 12 radiological health effects can be expected to occur as a result of radioactive material transportation during the 26-year operating period of the first repository. During the same period in the United States, about 65,000 total deaths from truck accidents and about 32,000 total deaths from rail accidents would occur; also an estimated 58,300 cancer fatalities are predicted to occur in the United States during a 26-year period from exposure to background radiation alone (not including medical and other manmade sources). The risks reported here are upper limits and are small by comparison with the "natural background" of risks of the same type. 3 refs., 6 tabs.

  19. Researchers at Montana State University and Idaho National Lab have developed a process to effectively and efficiently clean natural and man-made porous material of radioactive contamination. The system eliminates

    E-Print Network [OSTI]

    Maxwell, Bruce D.

    to effectively and efficiently clean natural and man-made porous material of radioactive contamination. The system eliminates the practice of full demolition and removal of contaminated objects and can address contaminated substrate. Thus, building walls (interior or exterior), floors and ceilings can be remediated

  20. Subsurface contaminants focus area

    SciTech Connect (OSTI)

    NONE

    1996-08-01T23:59:59.000Z

    The US Department of Enregy (DOE) Subsurface Contaminants Focus Area is developing technologies to address environmental problems associated with hazardous and radioactive contaminants in soil and groundwater that exist throughout the DOE complex, including radionuclides, heavy metals; and dense non-aqueous phase liquids (DNAPLs). More than 5,700 known DOE groundwater plumes have contaminated over 600 billion gallons of water and 200 million cubic meters of soil. Migration of these plumes threatens local and regional water sources, and in some cases has already adversely impacted off-site rsources. In addition, the Subsurface Contaminants Focus Area is responsible for supplying technologies for the remediation of numerous landfills at DOE facilities. These landfills are estimated to contain over 3 million cubic meters of radioactive and hazardous buried Technology developed within this specialty area will provide efective methods to contain contaminant plumes and new or alternative technologies for development of in situ technologies to minimize waste disposal costs and potential worker exposure by treating plumes in place. While addressing contaminant plumes emanating from DOE landfills, the Subsurface Contaminants Focus Area is also working to develop new or alternative technologies for the in situ stabilization, and nonintrusive characterization of these disposal sites.

  1. Encapsulation of mixed radioactive and hazardous waste contaminated incinerator ash in modified sulfur cement

    SciTech Connect (OSTI)

    Kalb, P.D.; Heiser, J.H. III; Colombo, P.

    1990-01-01T23:59:59.000Z

    Some of the process waste streams incinerated at various Department of Energy (DOE) facilities contain traces of both low-level radioactive (LLW) and hazardous constituents, thus yielding ash residues that are classified as mixed waste. Work is currently being performed at Brookhaven National Laboratory (BNL) to develop new and innovative materials for encapsulation of DOE mixed wastes including incinerator ash. One such material under investigation is modified sulfur cement, a thermoplastic developed by the US Bureau of Mines. Monolithic waste forms containing as much as 55 wt % incinerator fly ash from Idaho national Engineering Laboratory (INEL) have been formulated with modified sulfur cement, whereas maximum waste loading for this waste in hydraulic cement is 16 wt %. Compressive strength of these waste forms exceeded 27.6 MPa. Wet chemical and solid phase waste characterization analyses performed on this fly ash revealed high concentrations of soluble metal salts including Pb and Cd, identified by the Environmental Protection Agency (EPA) as toxic metals. Leach testing of the ash according to the EPA Toxicity Characteristic Leaching Procedure (TCLP) resulted in concentrations of Pb and Cd above allowable limits. Encapsulation of INEL fly ash in modified sulfur cement with a small quantity of sodium sulfide added to enhance retention of soluble metal salts reduced TCLP leachate concentrations of Pb and Cd well below EPA concentration criteria for delisting as a toxic hazardous waste. 12 refs., 4 figs., 2 tabs.

  2. Characteristics of radionuclide-contaminated soils from the Sedan crater area at the Nevada test site

    SciTech Connect (OSTI)

    Lee, S.Y.; Tamura, T.; Larsen, I.L.; Essington, E.H.

    1987-08-01T23:59:59.000Z

    The distribution of radionuclides in selected soil profiles and the characteristics of contaminated ejecta in the Sedan crater area (site of a nuclear excavation test conducted in 19862) were investigated in an attempt to define the physicochemical parameters controlling the redistribution of radionuclides required to assess the environmental and health hazards of the contaminated area. The results showed that concentrations of /sup 239,240/Pu, /sup 241/Am, /sup 155/Eu, /sup 137/Cs, /sup 102m/Rh, /sup 90/Sr, and /sup 60/Co decreased with depth and with increasing distance from ground zero. The contaminated particles occurred as moderately porous calcium aluminosilicate glass, predominantly and size (2-0.1 mm in diameter), in the loamy sand or sandy loam soil. Differences in distribution patterns and concentration ratios among the radionuclides indicted a that a significant fraction of the /sup 137/Cs and /sup 90/Sr present in contaminated overburden materials had moved downward during the past 22 years, under arid environmental conditions, into the buried soil.

  3. Factors Affecting Indoor Air Concentrations of Volatile Organic Compounds at a Site of Subsurface Gasoline Contamination

    E-Print Network [OSTI]

    Fischer, M.L.

    2011-01-01T23:59:59.000Z

    OF SUBSURFACE GASOLINE CONTAMINATION Marc L. Fischer, AbraOF SUBSURFACE GASOLINE CONTAMINATION Marc L. Fischer, Abrareporting indoor air contamination (6,7). Estimation of

  4. 2010 Annual Summary Report for the Area 3 and Area 5 Radioactive Management Sites at the Nevada National Security Site, Nye County, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2011-03-01T23:59:59.000Z

    The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office performed an annual review of the Area 3 and Area 5 Radioactive Waste Management Site (RWMS) Performance Assessments (PAs) and Composite Analyses (CAs) in fiscal year (FY) 2010. This annual summary report presents data and conclusions from the FY 2010 review, and determines the adequacy of the PAs and CAs. Operational factors (e.g., waste forms and containers, facility design, and waste receipts), closure plans, monitoring results, and research and development (R&D) activities were reviewed to determine the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada National Security Site (NNSS) (formerly the Nevada Test Site) relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R&D activities were reviewed to determine the adequacy of the CAs.

  5. Flood Assessment at the Area 5 Radioactive Waste Management Site and the Proposed Hazardous Waste Storage Unit, DOE/Nevada Test Site, Nye County, Nevada

    SciTech Connect (OSTI)

    Schmeltzer, J. S., Millier, J. J., Gustafson, D. L.

    1993-01-01T23:59:59.000Z

    A flood assessment at the Radioactive Waste Management Site (RWMS) and the proposed Hazardous Waste Storage Unit (HWSU) in Area 5 of the Nevada Test Site (NTS) was performed to determine the 100-year flood hazard at these facilities. The study was conducted to determine whether the RWMS and HWSU are located within a 100-year flood hazard as defined by the Federal Emergency Management Agency, and to provide discharges for the design of flood protection.

  6. Remaining Sites Verification Package for the 600-243 Petroleum-Contaminated Soil Bioremediation Pad, Waste Site Reclassification Form 2007-033

    SciTech Connect (OSTI)

    J. M. Capron

    2008-11-07T23:59:59.000Z

    The 600-243 waste site consisted of a bioremediation pad for petroleum-contaminated soils resulting from the 1100 Area Underground Storage Tank (UST) upgrades in 1994. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

  7. Analytical Electron Microscopy examination of uranium contamination at the DOE Fernald operation site

    SciTech Connect (OSTI)

    Buck, E.C.; Dietz, N.L.; Bates, J.K.; Cunnane, J.C.

    1993-02-01T23:59:59.000Z

    Analytical Electron Microscopy (AEM) has been used to identify uranium-bearing phases present in contaminated soils from the DOE Fernald operation site. A combination of optical microscopy, scanning electron microscopy with backscattered electron detection (SEM/BSE), and AEM was used in isolating and characterizing uranium-rich regions of the contaminated soils. Soil samples were prepared for transmission electron microscopy (TEM) by ultramicrotomy using an embedding resin previously employed for aquatic colloids and biological samples. This preparation method allowed direct comparison between SEM and TEM images. At the macroscopic level much of the uranium appears to be associated with clays in the soils; however, electron beam analysis revealed that the uranium is present as discrete phases, including iron oxides, silicates (soddyite), phosphates (autunites), and fluorite. Only low levels of uranium were actually within the clay minerals. The distribution of uranium phases was inhomogeneous at the submicron level.

  8. EIS-0063: Waste Management Operations, Double-Shell Tanks for Defense High Level Radioactive Waste Storage, Hanford Site, Richland, Washington

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy developed this statement to evaluate the existing tank design and consider additional specific design and safety feature alternatives for the thirteen tanks being constructed for storage of defense high-level radioactive liquid waste at the Hanford Site in Richland, Washington. This statement supplements ERDA-1538, "Final Environmental Statement on Waste Management Operation."

  9. Evaluation of technologies for volume reduction of plutonium-contaminated soils from the Nevada Test Site

    SciTech Connect (OSTI)

    Papelis, C.; Jacobson, R.L.; Miller, F.L.; Shaulis, L.K.

    1996-06-01T23:59:59.000Z

    Nuclear testing at and around the Nevada Test Site (NTS) resulted in plutonium (Pu) contamination of the soil over an area of several thousands of acres. The objective of this project was to evaluate the potential of five different processes to reduce the volume of Pu-contaminated soil from three different areas, namely Areas 11, 13, and 52. Volume reduction was to be accomplished by concentrating the Pu into a small but highly contaminated soil fraction, thereby greatly reducing the volume of soil requiring disposal. The processes tested were proposed by Paramag Corp. (PARAMAG), Advanced Processing Technologies Inc. (APT), Lockheed Environmental Systems and Technologies (LESAT), Nuclear Remediation Technologies (NRT), and Scientific Ecology Group (SEG). Because of time and budgetary restraints, the NRT and SEG processes were tested with soil from Area 11 only. These processes typically included a preliminary soil conditioning step (e.g., attrition scrubbing, wet sieving), followed by a more advanced process designed to separate Pu from the soil, based on physiochemical properties of Pu compounds (e.g., magnetic susceptibility, specific gravity). Analysis of the soil indicates that a substantial fraction of the total Pu contamination is typically confined in a relatively narrow and small particle size range. Processes which were able to separate this highly contaminated soil fraction (using physical methods, e.g., attrition scrubbing, wet sieving), from the rest of the soil achieved volume (mass) reductions on the order of 70%. The advanced, more complex processes tested did not enhance volume reduction. The primary reason why processes that rely on the dependence of settling velocity on density differences failed was the very fine grain size of the Pu-rich particles.

  10. RESRAD-BUILD: A computer model for analyzing the radiological doses resulting from the remediation and occupancy of buildings contaminated with radioactive material

    SciTech Connect (OSTI)

    Yu, C.; LePoire, D.J.; Jones, L.G. [and others

    1994-11-01T23:59:59.000Z

    The RESRAD-BUILD computer code is a pathway analysis model designed to evaluate the potential radiological dose incurred by an individual who works or lives in a building contaminated with radioactive material. The transport of radioactive material inside the building from one compartment to another is calculated with an indoor air quality model. The air quality model considers the transport of radioactive dust particulates and radon progeny due to air exchange, deposition and resuspension, and radioactive decay and ingrowth. A single run of the RESRAD-BUILD code can model a building with up to: three compartments, 10 distinct source geometries, and 10 receptor locations. A shielding material can be specified between each source-receptor pair for external gamma dose calculations. Six exposure pathways are considered in the RESRAD-BUILD code: (1) external exposure directly from the source; (2) external exposure to materials deposited on the floor; (3) external exposure due to air submersion; (4) inhalation of airborne radioactive particulates; (5) inhalation of aerosol indoor radon progeny; and (6) inadvertent ingestion of radioactive material, either directly from the sources or from materials deposited on the surfaces of the building compartments. 4 refs., 23 figs., 4 tabs.

  11. A Multiattribute Utility Analysis of Sites Nominated For Characterization For the First Radioactive Waste Repository- A Decision Aiding Methodology

    Broader source: Energy.gov [DOE]

    In December 1984, the Department of Energy (DOE) published draft environmental assessments (EAs) to support the proposed nomination of five sites and the recommendation of three sites for characterization for the first radioactive-waste repository. A chapter common to all the draft EAs (Chapter 7) presented rankings of the five sites against the postclosure and the preclosure technical siting guidelines. To determine which three sites appeared most favorable for recommendation for characterization, three simple quantitative methods were used to aggregate the rankings assigned to each site for the various technical guidelines. In response to numerous comments on the methods, the DOE has undertaken a formal application of one of them (hereafter referred to as the decision-aiding methodology) for the purpose of obtaining a more rigorous evaluation of the nominated sites.

  12. Baseline risk assessment of ground water contamination at the uranium mill tailings site near Lakeview, Oregon. Revision 1

    SciTech Connect (OSTI)

    NONE

    1995-12-01T23:59:59.000Z

    Surface cleanup at the Uranium Mill Tailings Remedial Action (UMTRA) Project site near Lakeview, Oregon was completed in 1989. The Ground Water Project evaluates the nature and extent of ground water contamination that resulted from the uranium ore processing activities. The Ground Water Project is in its beginning stages. Human health may be at risk from exposure to ground water contaminated by uranium ore processing. Exposure could occur by drinking water pumped out of a hypothetical well drilled in the contaminated areas. Ecological risks to plants or animals may result from exposure to surface water and sediment that have received contaminated ground water. A risk assessment describes a source of contamination, how that contamination reaches people and the environment, the amount of contamination to which people or the ecological environment may be exposed, and the health or ecological effects that could result from that exposure. This risk assessment is a site-specific document that will be used to evaluate current and potential future impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site characterization will determine whether any action is needed to protect human health or the ecological environment.

  13. Canada Geese at the Hanford Site – Trends in Reproductive Success, Migration Patterns, and Contaminant Concentrations

    SciTech Connect (OSTI)

    Simmons, Mary Ann; Poston, Ted M.; Tiller, Brett L.; Stegen, Amanda; Hand, Kristine D.; Brandenberger, Jill M.

    2010-05-25T23:59:59.000Z

    Pacific Northwest National Laboratory (PNNL) has conducted several studies for the U.S. Department of Energy (DOE) to evaluate the status and condition of Canada geese on the Hanford Reach of the Columbia River. This report summarizes results of studies of Canada geese (Branta canadensis moffitti) at the Hanford Site dating back to the 1950s. Results include information on the nesting (reproductive) success of Canada geese using the Hanford Reach, review of the local and regional migration of this species using data from bird banding studies, and summary data describing monitoring and investigations of the accumulation of Hanford-derived and environmental contaminants by resident goose populations.

  14. 2002 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Sites

    SciTech Connect (OSTI)

    Y. E. Townsend

    2003-06-01T23:59:59.000Z

    Environmental, subsidence, and meteorological monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site (NTS)(refer to Figure 1). These monitoring data include radiation exposure, air, groundwater,meteorology, vadose zone, subsidence, and biota data. Although some of these media (radiation exposure, air, and groundwater) are reported in detail in other Bechtel Nevada (BN) reports (Annual Site Environmental Report [ASER], the National Emissions Standard for Hazardous Air Pollutants [NESHAP] report, and the Annual Groundwater Monitoring Report), they are also summarized in this report to provide an overall evaluation of RWMS performance and environmental compliance. Direct radiation monitoring data indicate that exposure at and around the RWMSs is not above background levels. Air monitoring data indicate that tritium concentrations are slightly above background levels. Groundwater monitoring data indicate that the groundwater in the uppermost aquifer beneath the Area 5 RWMS has not been affected by the facility. Meteorological data indicate that 2002 was a dry year: rainfall totaled 26 mm (1.0 in) at the Area 3 RWMS and 38 mm (1.5 in) at the Area 5 RWMS. Vadose zone monitoring data indicate that 2002 rainfall infiltrated less than 30 cm (1 ft) before being returned to the atmosphere by evaporation. Soil-gas tritium monitoring data indicate slow subsurface migration, and tritium concentrations in biota were lower than in previous years. Special investigations conducted in 2002 included: a comparison between waste cover water contents measured by neutron probe and coring; and a comparison of four methods for measuring radon concentrations in air. All 2002 monitoring data indicate that the Area 3 and Area 5 RWMSs are performing within expectations of the model and parameter assumptions for the facility Performance Assessments (PAs).

  15. Final Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement Richland, Washington

    SciTech Connect (OSTI)

    N /A

    2004-02-13T23:59:59.000Z

    This Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement (HSW EIS) provides environmental and technical information concerning U.S. Department of Energy (DOE) ongoing and proposed waste management practices at the Hanford Site in Washington State. The HSW EIS updates some analyses of environmental consequences from previous documents and provides evaluations for activities that may be implemented consistent with the Waste Management Programmatic Environmental Impact Statement (WM PEIS; DOE 1997c) Records of Decision (RODs). The draft HSW EIS was initially issued in April 2002 for public comment (DOE 2002b). A revised draft HSW EIS was issued in March 2003 to address new waste management alternatives that had been proposed since the initial draft HSW EIS was prepared, and to address comments received during the public review period for the first draft (DOE 2003d). The revised draft HSW EIS also incorporated alternatives for disposal of immobilized low-activity waste (ILAW) from treatment of Hanford Site tank waste in the waste treatment plant (WTP) currently under construction, an activity that was not included in the first draft (68 FR 7110). This final HSW EIS describes the DOE preferred alternative, and in response to public comments received on the March 2003 revised draft, provides additional analyses for some environmental consequences associated with the preferred alternative, with other alternatives, and with cumulative impacts. Public comments on the revised draft HSW EIS are addressed in the comment response document (Volume III of this final EIS). This HSW EIS describes the environmental consequences of alternatives for constructing, modifying, and operating facilities to store, treat, and/or dispose of low-level (radioactive) waste (LLW), transuranic (TRU) waste, ILAW, and mixed low-level waste (MLLW) including WTP melters at Hanford. In addition, the potential long-term consequences of LLW, MLLW, and ILAW disposal on groundwater and surface water are evaluated for a 10,000-year period, although the DOE performance standards only require assessment for the first 1000 years after disposal (DOE 2001f). This document does not address non-radioactive waste that contains ''hazardous'' or ''dangerous'' waste, as defined under the Resource Conservation and Recovery Act (RCRA) of 1976 (42 USC 6901) and Washington State Dangerous Waste regulations (WAC 173-303). Following a previous National Environmental Policy Act (NEPA, 42 USC 4321) review (DOE 1997d), DOE decided to dispose of TRU waste in New Mexico at the Waste Isolation Pilot Plant (WIPP), a repository that meets the requirements of 40 CFR 191 (63 FR 3623). This HSW EIS has been prepared in accordance with NEPA, the DOE implementing procedures for NEPA 10 CFR 1021, and the Council on Environmental Quality (CEQ) Regulations for Implementing the Procedural Provisions of NEPA (40 CFR 1500-1508).

  16. Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site near Lakeview, Oregon. Revision 2

    SciTech Connect (OSTI)

    NONE

    1996-03-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (Phase I) and the Ground Water Project (Phase II). Under the UMTRA Surface Project, tailings, contaminated soil, equipment, and materials associated with the former uranium ore processing at UMTRA Project sites are placed into disposal cells. The cells are designed to reduce radon and other radiation emissions and to minimize further contamination of ground water. Surface cleanup at the UMTRA Project site near Lakeview, Oregon, was completed in 1989. The mill operated from February 1958 to November 1960. The Ground Water Project evaluates the nature and extent of ground water contamination that resulted from the uranium ore processing activities. The Ground Water Project is in its beginning stages. Human health may be at risk from exposure to ground water contaminated by uranium ore processing. Exposure could occur by drinking water pumped out of a hypothetical well drilled in the contaminated areas. Ecological risks to plants or animals may result from exposure to surface water and sediment that have received contaminated ground water. A risk assessment describes a source of contamination, how that contamination reaches people and the environment, the amount of contamination to which people or the ecological environment may be exposed, and the health or ecological effects that could result from that exposure. This risk assessment is a site-specific document that will be used to evaluate current and potential future impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site characterization will determine whether any action is needed to protect human health or the ecological environment.

  17. Baseline risk assessment of groundwater contamination at the uranium mill tailings site near Shiprock, New Mexico. Draft

    SciTech Connect (OSTI)

    Not Available

    1993-09-01T23:59:59.000Z

    This report evaluates potential impact to public health or the environment resulting from groundwater contamination at the former uranium mill processing site. The tailings and other contaminated material at this site were placed in a disposal cell on the site in 1986 by the US Department of Energy`s (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. Currently, the UMTRA Project is evaluating groundwater contamination. This risk assessment is the first document specific to this site for the Groundwater Project. This risk assessment follows the approach outlined by the US Environmental Protection Agency (EPA). The first step is to evaluate groundwater data collected from monitor wells at the site. Evaluation of these data showed that the main contaminants in the floodplain groundwater are arsenic, magnesium, manganese, nitrate, sodium, sulfate, and uranium. The complete list of contaminants associated with the terrace groundwater could not be determined due to the lack of the background groundwater quality data. However, uranium, nitrate, and sulfate are evaluated since these chemicals are clearly associated with uranium processing and are highly elevated compared to regional waters. It also could not be determined if the groundwater occurring in the terrace is a usable water resource, since it appears to have originated largely from past milling operations. The next step in the risk assessment is to estimate how much of these contaminants people would be exposed to if a drinking well were installed in the contaminated groundwater or if there were exposure to surface expressions of contaminated water. Potential exposures to surface water include incidental contact with contaminated water or sediments by children playing on the floodplain and consumption of meat and milk from domestic animals grazed and watered on the floodplain.

  18. Final Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement Richland, Washington

    SciTech Connect (OSTI)

    M.S. Collins C.M. Borgstrom

    2004-01-01T23:59:59.000Z

    The Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement (HSW EIS) provides environmental and technical information concerning U.S. Department of Energy (DOE) proposed waste management practices at the Hanford Site. The HSW EIS updates analyses of environmental consequences from previous documents and provides evaluations for activities that may be implemented consistent with the Waste Management Programmatic Environmental Impact Statement (WM PEIS) Records of Decision (RODs). Waste types considered in the HSW EIS include operational low-level radioactive waste (LLW), mixed low-level waste (MLLW), immobilized low-activity waste (ILAW), and transuranic (TRU) waste (including TRU mixed waste). MLLW contains chemically hazardous components in addition to radionuclides. Alternatives for management of these wastes at the Hanford Site, including the alternative of No Action, are analyzed in detail. The LLW, MLLW, and TRU waste alternatives are evaluated for a range of waste volumes, representing quantities of waste that could be managed at the Hanford Site. A single maximum forecast volume is evaluated for ILAW. The No Action Alternative considers continuation of ongoing waste management practices at the Hanford Site and ceasing some operations when the limits of existing capabilities are reached. The No Action Alternative provides for continued storage of some waste types. The other alternatives evaluate expanded waste management practices including treatment and disposal of most wastes. The potential environmental consequences of the alternatives are generally similar. The major differences occur with respect to the consequences of disposal versus continued storage and with respect to the range of waste volumes managed under the alternatives. DOE's preferred alternative is to dispose of LLW, MLLW, and ILAW in a single, modular, lined facility near PUREX on Hanford's Central Plateau; to treat MLLW using a combination of onsite and offsite facilities; and to certify TRU waste onsite using a combination of existing, upgraded, and mobile facilities. DOE issued the Notice of Intent to prepare the HSW EIS on October 27, 1997, and held public meetings during the scoping period that extended through January 30, 1998. In April 2002, DOE issued the initial draft of the EIS. During the public comment period that extended from May through August 2002, DOE received numerous comments from regulators, tribal nations, and other stakeholders. In March 2003, DOE issued a revised draft of the HSW EIS to address those comments, and to incorporate disposal of ILAW and other alternatives that had been under consideration since the first draft was published. Comments on the revised draft were received from April 11 through June 11, 2003. This final EIS responds to comments on the revised draft and includes updated analyses to incorporate information developed since the revised draft was published. DOE will publish the ROD(s) in the ''Federal Register'' no sooner than 30 days after publication of the Environmental Protection Agency's Notice of Availability of the final HSW EIS.

  19. Analyzing remediation technologies for Department of Energy sites contaminated with DNAPL pollutants. Master`s thesis

    SciTech Connect (OSTI)

    Papatyi, A.F.

    1997-03-01T23:59:59.000Z

    The Department of Energy is in the process of conducting a Remedial Investigation/Feasibility Study for a site contaminated with Dense Non-Aqueous Phase Liquid (DNAPL) pollutants at their Paducah Kentucky facility. This thesis effort focuses on acquiring insight into a number of remediation technology trains that are candidates for the Paducah site. This insight is used to recommend and justify the screening of candidate technology trains. The research makes use of two decision analysis models (one is deterministic, the other is probabilistic) built to provide a quantitative assessment of the candidate technology trains. Dominance considerations and multi-attribute utility theory are utilized to make the quantitative assessments and to gain insight into each candidate technology train. The results of the analysis provide the DOE with a rational justification for screening 55 of the 58 candidate technology trains from further consideration.

  20. AN EVALUATION OF HANFORD SITE TANK FARM SUBSURFACE CONTAMINATION FY2007

    SciTech Connect (OSTI)

    MANN, F.M.

    2007-07-10T23:59:59.000Z

    The Tank Farm Vadose Zone (TFVZ) Project conducts activities to characterize and analyze the long-term environmental and human health impacts from tank waste releases to the vadose zone. The project also implements interim measures to mitigate impacts, and plans the remediation of waste releases from tank farms and associated facilities. The scope of this document is to report data needs that are important to estimating long-term human health and environmental risks. The scope does not include technologies needed to remediate contaminated soils and facilities, technologies needed to close tank farms, or management and regulatory decisions that will impact remediation and closure. This document is an update of ''A Summary and Evaluation of Hanford Site Tank Farm Subsurface Contamination''. That 1998 document summarized knowledge of subsurface contamination beneath the tank farms at the time. It included a preliminary conceptual model for migration of tank wastes through the vadose zone and an assessment of data and analysis gaps needed to update the conceptual model. This document provides a status of the data and analysis gaps previously defined and discussion of the gaps and needs that currently exist to support the stated mission of the TFVZ Project. The first data-gaps document provided the basis for TFVZ Project activities over the previous eight years. Fourteen of the nineteen knowledge gaps identified in the previous document have been investigated to the point that the project defines the current status as acceptable. In the process of filling these gaps, significant accomplishments were made in field work and characterization, laboratory investigations, modeling, and implementation of interim measures. The current data gaps are organized in groups that reflect Components of the tank farm vadose zone conceptual model: inventory, release, recharge, geohydrology, geochemistry, and modeling. The inventory and release components address residual wastes that will remain in the tanks and tank-farm infrastructure after closure and potential losses from leaks during waste retrieval. Recharge addresses the impacts of current conditions in the tank farms (i.e. gravel covers that affect infiltration and recharge) as well as the impacts of surface barriers. The geohydrology and geochemistry components address the extent of the existing subsurface contaminant inventory and drivers and pathways for contaminants to be transported through the vadose zone and groundwater. Geochemistry addresses the mobility of key reactive contaminants such as uranium. Modeling addresses conceptual models and how they are simulated in computers. The data gaps will be used to provide input to planning (including the upcoming C Farm Data Quality Objective meetings scheduled this year).

  1. An inverse analytical technique applied to a chloride contamination of groundwater at Indian School and Levering sites, Michigan

    E-Print Network [OSTI]

    Shumway, Helen

    1992-01-01T23:59:59.000Z

    and the Indian River Site. were used to store road salt. Seepage from precipitation on these road salt piles has resulted in chloride contamination of the groundwater down gradient of the storage areas. The resulting chloride plumes were examined using two... Descriptions. 3. 1. 1. Indian River Site, 3. 1. 2. Levering Site 3. 2. Modeling Results for the Michigan Sites . . . . . . . . 3. 2. 1. Modeling Results for the Indian River Site, 3. 2. 2, MOdeling Results for the Levering Site. . 20 20 22 23 34 4...

  2. Low-level radioactive waste management: transitioning to off-site disposal at Los Alamos National Laboratory

    SciTech Connect (OSTI)

    Dorries, Alison M [Los Alamos National Laboratory

    2010-11-09T23:59:59.000Z

    Facing the closure of nearly all on-site management and disposal capability for low-level radioactive waste (LLW), Los Alamos National Laboratory (LANL) is making ready to ship the majority of LLW off-site. In order to ship off-site, waste must meet the Treatment, Storage, and Disposal Facility's (TSDF) Waste Acceptance Criteria (WAC). In preparation, LANL's waste management organization must ensure LANL waste generators characterize and package waste compliantly and waste characterization documentation is complete and accurate. Key challenges that must be addressed to successfully make the shift to off-site disposal of LLW include improving the detail, accuracy, and quality of process knowledge (PK) and acceptable knowledge (AK) documentation, training waste generators and waste management staff on the higher standard of data quality and expectations, improved WAC compliance for off-site facilities, and enhanced quality assurance throughout the process. Certification of LANL generators will allow direct off-site shipping of LLW from their facilities.

  3. Product consistency leach tests of Savannah River Site radioactive waste glasses

    SciTech Connect (OSTI)

    Bibler, N.E. (Westinghouse Savannah River Co., Aiken, SC (United States)); Bates, J.K. (Argonne National Lab., IL (United States))

    1989-01-01T23:59:59.000Z

    The Product Consistency Test (PCT) is a glass leach test that was developed at the Savannah River Site (SRS) to routinely confirm the durability of nuclear waste glasses that will be produced in the Defense Waste Processing Facility. The PCT is a 7 day, crushed glass leach test in deionized water at 90{degree}C. Final leachates are filtered and acidified prior to analysis. To demonstrate the reproducibility of the PCT when performed remotely, SRS and Argonne National Laboratory have performed the PCT on samples of two radioactive glasses. The tests were also performed to compare the releases of the radionuclides with the major nonradioactive glass components and to determine if radiation from the glass was affecting the results of the PCT. The test was performed in triplicate at each laboratory. For the major soluble elements, B, Li, Na, and Si, in the glass, each investigator obtained relative precisions in the range 2--5% in the triplicate tests. This range indicates good precision for the PCT when performed remotely with master slave manipulators in a shielded cell environment.

  4. Engineering study of 50 miscellaneous inactive underground radioactive waste tanks located at the Hanford Site, Washington

    SciTech Connect (OSTI)

    Freeman-Pollard, J.R.

    1994-03-02T23:59:59.000Z

    This engineering study addresses 50 inactive underground radioactive waste tanks. The tanks were formerly used for the following functions associated with plutonium and uranium separations and waste management activities in the 200 East and 200 West Areas of the Hanford Site: settling solids prior to disposal of supernatant in cribs and a reverse well; neutralizing acidic process wastes prior to crib disposal; receipt and processing of single-shell tank (SST) waste for uranium recovery operations; catch tanks to collect water that intruded into diversion boxes and transfer pipeline encasements and any leakage that occurred during waste transfer operations; and waste handling and process experimentation. Most of these tanks have not been in use for many years. Several projects have, been planned and implemented since the 1970`s and through 1985 to remove waste and interim isolate or interim stabilize many of the tanks. Some tanks have been filled with grout within the past several years. Responsibility for final closure and/or remediation of these tanks is currently assigned to several programs including Tank Waste Remediation Systems (TWRS), Environmental Restoration and Remedial Action (ERRA), and Decommissioning and Resource Conservation and Recovery Act (RCRA) Closure (D&RCP). Some are under facility landlord responsibility for maintenance and surveillance (i.e. Plutonium Uranium Extraction [PUREX]). However, most of the tanks are not currently included in any active monitoring or surveillance program.

  5. Assessment of unsaturated zone radionuclide contamination in the 200 areas of the Hanford site, Washington

    SciTech Connect (OSTI)

    Brodeur, J.R.; Wittreich, C.D.

    1993-03-01T23:59:59.000Z

    The 200 East and 200 West Areas at the Department of Energy`s Hanford site in southeastern Washington, contain chemical and nuclear fuel processing facilities that disposed of large volumes of chemical and radionuclide effluents to the ground via various structures such as ponds, cribs and ditches. A geophysical logging investigation was implemented in 1992 to assess the nature and extent of contamination beneath select liquid disposal sites in the 200 Areas. The borehole geophysical logging was accomplished with a recently developed spectral gamma-ray logging system called the Radionuclide Logging System (RLS). This system has a high-resolution, intrinsic germanium detector mounted in a downhole probe and is calibrated and operated specifically for use in a borehole environment. It provides a means to develop in-situ, gamma-emitting radioelement concentration profiles. Approximately 50 boreholes were logged in this study. The RLS log data provided information about the migration and deposition patterns of specific radionuclides in the unsaturated zone and their impacts on the groundwater. Approximately 10 radionuclide species were detected and quantified. Results of the field investigation are being used to refine site specific conceptual models, support Hanford Site remediation decisions and focus future characterization activities.

  6. SAVANNAH RIVER SITE INCIPIENT SLUDGE MIXING IN RADIOACTIVE LIQUID WASTE STORAGE TANKS DURING SALT SOLUTION BLENDING

    SciTech Connect (OSTI)

    Leishear, R.; Poirier, M.; Lee, S.; Steeper, T.; Fowley, M.; Parkinson, K.

    2011-01-12T23:59:59.000Z

    This paper is the second in a series of four publications to document ongoing pilot scale testing and computational fluid dynamics (CFD) modeling of mixing processes in 85 foot diameter, 1.3 million gallon, radioactive liquid waste, storage tanks at Savannah River Site (SRS). Homogeneous blending of salt solutions is required in waste tanks. Settled solids (i.e., sludge) are required to remain undisturbed on the bottom of waste tanks during blending. Suspension of sludge during blending may potentially release radiolytically generated hydrogen trapped in the sludge, which is a safety concern. The first paper (Leishear, et. al. [1]) presented pilot scale blending experiments of miscible fluids to provide initial design requirements for a full scale blending pump. Scaling techniques for an 8 foot diameter pilot scale tank were also justified in that work. This second paper describes the overall reasons to perform tests, and documents pilot scale experiments performed to investigate disturbance of sludge, using non-radioactive sludge simulants. A third paper will document pilot scale CFD modeling for comparison to experimental pilot scale test results for both blending tests and sludge disturbance tests. That paper will also describe full scale CFD results. The final paper will document additional blending test results for stratified layers in salt solutions, scale up techniques, final full scale pump design recommendations, and operational recommendations. Specifically, this paper documents a series of pilot scale tests, where sludge simulant disturbance due to a blending pump or transfer pump are investigated. A principle design requirement for a blending pump is UoD, where Uo is the pump discharge nozzle velocity, and D is the nozzle diameter. Pilot scale test results showed that sludge was undisturbed below UoD = 0.47 ft{sup 2}/s, and that below UoD = 0.58 ft{sup 2}/s minimal sludge disturbance was observed. If sludge is minimally disturbed, hydrogen will not be released. Installation requirements were also determined for a transfer pump which will remove tank contents, and which is also required to not disturb sludge. Testing techniques and test results for both types of pumps are presented.

  7. C-1 1999 SITE ENVIRONMENTAL REPORT APPENDIX C: CONCEPTS OF RADIOACTIVITY

    E-Print Network [OSTI]

    Man-made Medical, 39 Nuclear Medicine, 14 Consumer Products, 10 SOURCES OF RADIATION Radioactivity as radiation. The three most important types of radiation are described below. COMMON TYPES OF RADIATION ALPHA occurring radioactive elements such as radon emit alpha radiation. BETA Beta radiation is composed

  8. Nevada National Security Site 2011 Waste Management Monitoring Report, Area 3 and Area 5 Radioactive Waste Management Site

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2012-07-31T23:59:59.000Z

    Environmental monitoring data are collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada National Security Site (NNSS). These data are associated with radiation exposure, air, groundwater, meteorology, and vadose zone. This report summarizes the 2011 environmental data to provide an overall evaluation of RWMS performance and to support environmental compliance and performance assessment (PA) activities. Some of these data (e.g., radiation exposure, air, and groundwater) are presented in other reports. Direct radiation monitoring data indicate exposure levels at the RWMSs are within the range of background levels measured at the NNSS. Slightly elevated exposure levels outside the Area 3 RWMS are attributed to nearby historical aboveground nuclear weapons tests. Air monitoring data show tritium concentrations in water vapor and americium and plutonium concentrations in air particles are only slightly above detection limits and background levels. The measured levels of radionuclides in air particulates and moisture are below derived concentration guides for these radionuclides. During the last 2 weeks of March 2011, gamma spectroscopy results for air particles showed measurable activities of iodine-131 (131I), cesium-134 (134Cs), and cesium-137 (137Cs). These results are attributed to the release of fission products from the damaged Fukushima Daiichi power plant in Japan. The remaining gamma spectroscopy results for air particulates collected at the Area 3 and Area 5 RWMS were below minimum detectable concentrations. Groundwater monitoring data indicate the groundwater in the uppermost aquifer beneath the Area 5 RWMS is not impacted by RWMS operations. Results of groundwater analysis from wells around the Area 5 RWMS were all below established investigation levels. The 86.3 millimeters (mm) (3.40 inches [in.]) of precipitation at the Area 3 RWMS during 2011 is 44% below the average of 154.1 mm (6.07 in.), and the 64.8 mm (2.55 in.) of precipitation at the Area 5 RWMS during 2011 is 47% below the average of 122.4 mm (4.82 in.). Water balance measurements indicate that evapotranspiration from the vegetated weighing lysimeter dries the soil and prevents downward percolation of precipitation more effectively than evaporation from the bare-soil weighing lysimeter. Automated vadose zone monitoring on Area 5 RWMS operational waste covers was not done during 2011 due to construction of the final evapotranspiration cover at these monitoring locations. Moisture from precipitation did not percolate below 122 centimeters (4 feet) in the vegetated final mono-layer cover on the U-3ax/bl disposal unit at the Area 3 RWMS before being removed by evapotranspiration. During 2011, there was no drainage through 2.4 meters (8 feet) of soil from the Area 3 drainage lysimeters that received only natural precipitation. Ten percent of the applied precipitation and irrigation drained from the bare-soil drainage lysimeter that received 3 times natural precipitation. All 2011 monitoring data indicate that the Area 3 and Area 5 RWMSs are performing within expectations of the model and parameter assumptions for the facility PAs.

  9. Impact Assessment of Existing Vadose Zone Contamination at the Hanford Site SX Tank Farm

    SciTech Connect (OSTI)

    Khaleel, Raziuddin; White, Mark D.; Oostrom, Martinus; Wood, Marcus I.; Mann, Frederick M.; Kristofzski, John G.

    2007-11-01T23:59:59.000Z

    The USDOE has initiated an impact assessment of existing vadose zone contamination at the Hanford Site SX tank farm in southeastern Washington State. The assessment followed the Resource Conservation and Recovery Act (RCRA) Corrective Action process to address the impacts of past tank waste releases to the vadose zone at the single-shell tank farm. Numerical models were developed that consider the extent of contamination presently within the vadose zone and predict contaminant movement through the vadose zone to groundwater. The transport of representative mobile (technetium-99) and immobile (cesium-137) constituents was evaluated in modeling. The model considered the accelerated movement of moisture around and beneath single-shell tanks that is attributed to bare, gravel surfaces resulting from the construction of the underground storage tanks. Infiltration, possibly nearing 100 mm yr–1, is further amplified in the tank farm because of the umbrella effect created by percolating moisture being diverted by the impermeable, sloping surface of the large, 24-m-diameter, buried tank domes. For both the base case (no-action alternative) simulation and a simulation that considered placement of an interim surface barrier to minimize infiltration, predicted groundwater concentrations for technetium-99 at the SX tank farm boundary were exceedingly high, on the order of 106 pCi L–1. The predicted concentrations are, however, somewhat conservative because of our use of two-dimensional modeling for a three-dimensional problem. A series of simulations were performed, using recharge rates of 50, 30, and 10 mm yr–1, and compared to the base case (100 mm yr–1) results. As expected, lowering meteoric recharge delayed peak arrival times and reduced peak concentrations at the tank farm boundary.

  10. IMPACT ASSESSMENT OF EXISTING VADOSE ZONE CONTAMINATION AT THE HANFORD SITE SX TANK FARM

    SciTech Connect (OSTI)

    KHALEEL R

    2007-11-01T23:59:59.000Z

    The USDOE has initiated an impact assessment of existing vadose zone contamination at the Hanford Site SX tank farm in southeastern Washington State. The assessment followed the Resource Conservation and Recovery Act (RCRA) Corrective Action process to address the impacts of past tank waste releases to the vadose zone at the single-shell tank farm. Numerical models were developed that consider the extent of contamination presently within the vadose zone and predict contaminant movement through the vadose zone to groundwater. The transport of representative mobile (technetium-99) and immobile (cesium-137) constituents was evaluated in modeling. The model considered the accelerated movement of moisture around and beneath single-shell tanks that is attributed to bare, gravel surfaces resulting from the construction of the underground storage tanks. Infiltration, possibly nearing 100 mm yr{sup -1}, is further amplified in the tank farm because of the umbrella effect created by percolating moisture being diverted by the impermeable, sloping surface of the large, 24-m-diameter, buried tank domes. For both the base case (no-action alternative) simulation and a simulation that considered placement of an interim surface barrier to minimize infiltration, predicted, groundwater concentrations for technetium-99 at the SX tank farm boundary were exceedingly high, on the order of 10{sup 6} pCi L{sup -1}. The predicted concentrations are, however, somewhat conservative because of our use of two-dimensional modeling for a three-dimensional problem. A series of simulations were performed, using recharge rates of 50, 30, and 10 mm yr{sup -1}, and compared to the basecase(100 mm yr{sup -1}) results. As expected, lowering meteoric recharge delayed peak arrival times and reduced peak concentrations at the tank farm boundary.

  11. Baseline risk assessment of ground water contamination at the uranium mill tailings site near Salt Lake City, Utah. Revision 1

    SciTech Connect (OSTI)

    NONE

    1995-09-01T23:59:59.000Z

    The Uranium Mill Tailings Remedial Action (UMTRA) Project consists of two phases: the first is the Surface Project, and the second is the Ground Water Project. For the UMTRA Project site known as the Vitro site, near Salt Lake City, Utah, Surface Project cleanup occurred from 1985 to 1987. The UMTRA Project`s second phase, the Ground Water Project, evaluates the nature and extent of ground water contamination resulting from uranium processing and determines a strategy for ground water compliance with the Environmental Protection Agency (EPA) ground water standards established for the UMTRA Project. A risk assessment is the process of describing a source of contamination and showing how that contamination may reach people and the environment. The amount of contamination people or the environment may be exposed to is calculated and used to characterize the possible health or environmental effects that may result from this exposure. This risk assessment report is the first site-specific document prepared for the UMTRA Ground Water Project at the Vitro site. The results of this report and further site characterization of the Vitro site will be used to determine what is necessary, if anything, to protect human health and the environment while complying with EPA standards.

  12. Baseline risk assessment of ground water contamination at the uranium mill tailings site near Falls City, Texas: Revision 1

    SciTech Connect (OSTI)

    Not Available

    1994-09-01T23:59:59.000Z

    This baseline risk assessment of ground water contamination of the uranium mill tailings site near Falls City, Texas, evaluates potential impact to public health and the environment resulting from ground water contamination at the former Susquehanna Western, Inc. (SWI), uranium mill processing site. This document fulfills the following objectives: determine if the site presents immediate or potential future health risks, determine the need for interim institutional controls, serve as a key input to project planning and prioritization, and recommend future data collection efforts to more fully characterize risk. The Uranium Mill Tailings Remedial Action (UMTRA) Project has begun its evaluation of ground water contamination at the Falls City site. This risk assessment is one of the first documents specific to this site for the Ground Water Project. The first step is to evaluate ground water data collected from monitor wells at or near the site. Evaluation of these data show the main contaminants in the Dilworth ground water are cadmium, cobalt, fluoride, iron, nickel, sulfate, and uranium. The data also show high levels of arsenic and manganese occur naturally in some areas.

  13. Use of engineered soils and other site modifications for low-level radioactive waste disposal

    SciTech Connect (OSTI)

    Not Available

    1994-08-01T23:59:59.000Z

    The U.S. Nuclear Regulatory Commission requires that low-level radioactive waste (LLW) disposal facilities be designed to minimize contact between waste and infiltrating water through the use of site design features. The purpose of this investigation is to identify engineered barriers and evaluate their ability to enhance the long-term performance of an LLW disposal facility. Previously used barriers such as concrete overpacks, vaults, backfill, and engineered soil covers, are evaluated as well as state-of-the-art barriers, including an engineered sorptive soil layer underlying a facility and an advanced design soil cover incorporating a double-capillary layer. The purpose of this investigation is also to provide information in incorporating or excluding specific engineered barriers as part of new disposal facility designs. Evaluations are performed using performance assessment modeling techniques. A generic reference disposal facility design is used as a baseline for comparing the improvements in long-term performance offered by designs incorporating engineered barriers in generic and humid environments. These evaluations simulate water infiltration through the facility, waste leaching, radionuclide transport through the facility, and decay and ingrowth. They also calculate a maximum (peak annual) dose for each disposal system design. A relative dose reduction factor is calculated for each design evaluated. The results of this investigation are presented for concrete overpacks, concrete vaults, sorptive backfill, sorptive engineered soil underlying the facility, and sloped engineered soil covers using a single-capillary barrier and a double-capillary barrier. Designs using combinations of barriers are also evaluated. These designs include a vault plus overpacks, sorptive backfill plus overpacks, and overpack with vault plus sorptive backfill, underlying sorptive soil, and engineered soil cover.

  14. Closure Report for Corrective Action Unit 166: Storage Yards and Contaminated Materials, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2009-08-01T23:59:59.000Z

    Corrective Action Unit (CAU) 166 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Storage Yards and Contaminated Materials' and consists of the following seven Corrective Action Sites (CASs), located in Areas 2, 3, 5, and 18 of the Nevada Test Site: CAS 02-42-01, Condo Release Storage Yd - North; CAS 02-42-02, Condo Release Storage Yd - South; CAS 02-99-10, D-38 Storage Area; CAS 03-42-01, Conditional Release Storage Yard; CAS 05-19-02, Contaminated Soil and Drum; CAS 18-01-01, Aboveground Storage Tank; and CAS 18-99-03, Wax Piles/Oil Stain. Closure activities were conducted from March to July 2009 according to the FF ACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 166 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action and Clean Closure. Closure activities are summarized. CAU 166, Storage Yards and Contaminated Materials, consists of seven CASs in Areas 2, 3, 5, and 18 of the NTS. The closure alternatives included No Further Action and Clean Closure. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 166 as documented in this CR: (1) At CAS 02-99-10, D-38 Storage Area, approximately 40 gal of lead shot were removed and are currently pending treatment and disposal as MW, and approximately 50 small pieces of DU were removed and disposed as LLW. (2) At CAS 03-42-01, Conditional Release Storage Yard, approximately 7.5 yd{sup 3} of soil impacted with lead and Am-241 were removed and disposed as LLW. As a BMP, approximately 22 ft{sup 3} of asbestos tile were removed from a portable building and disposed as ALLW, approximately 55 gal of oil were drained from accumulators and are currently pending disposal as HW, the portable building was removed and disposed as LLW, and accumulators, gas cylinders, and associated debris were removed and are currently pending treatment and disposal as MW. (3) At CAS 05-19-02, Contaminated Soil and Drum, as a BMP, an empty drum was removed and disposed as sanitary waste. (4) At CAS 18-01-01, Aboveground Storage Tank, approximately 165 gal of lead-impacted liquid were removed and are currently pending disposal as HW, and approximately 10 gal of lead shot and 6 yd{sup 3} of wax embedded with lead shot were removed and are currently pending treatment and disposal as MW. As a BMP, approximately 0.5 yd{sup 3} of wax were removed and disposed as hydrocarbon waste, approximately 55 gal of liquid were removed and disposed as sanitary waste, and two metal containers were grouted in place. (5) At CAS 18-99-03, Wax Piles/Oil Stain, no further action was required; however, as a BMP, approximately l.5 yd{sup 3} of wax were removed and disposed as hydrocarbon waste, and one metal container was grouted in place.

  15. Remote Sensing Analysis of the Sierra Blanca (Faskin Ranch) Low-Level Radioactive Waste Disposal Site, Hudspeth County, Texas

    SciTech Connect (OSTI)

    LeMone, D. V.; Dodge, R.; Xie, H.; Langford, R. P.; Keller, G. R.

    2002-02-26T23:59:59.000Z

    Remote sensing images provide useful physical information, revealing such features as geological structure, vegetation, drainage patterns, and variations in consolidated and unconsolidated lithologies. That technology has been applied to the failed Sierra Blanca (Faskin Ranch) shallow burial low-level radioactive waste disposal site selected by the Texas Low-Level Radioactive Waste Disposal Authority. It has been re-examined using data from LANDSAT satellite series. The comparison of the earlier LANDSAT V (5/20/86) (30-m resolution) with the later new, higher resolution ETM imagery (10/23/99) LANDSAT VII data (15-m resolution) clearly shows the superiority of the LANDSAT VII data. The search for surficial indications of evidence of fatal flaws at the Sierra Blanca site utilizing was not successful, as it had been in the case of the earlier remote sensing analysis of the failed Fort Hancock site utilizing LANDSAT V data. The authors conclude that the tectonic activity at the Sierra Blanca site is much less recent and active than in the previously studied Fort Hancock site. The Sierra Blanca site failed primarily on the further needed documentation concerning a subsurface fault underneath the site and environmental justice issues. The presence of this fault was not revealed using the newer LANDSAT VII data. Despite this fact, it must be remembered that remote sensing provides baseline documentation for determining future physical and financial remediation responsibilities. On the basis of the two sites examined by LANDSAT remote sensing imaging, it is concluded that it is an essential, cost-effective tool that should be utilized not only in site examination but also in all nuclear-related facilities.

  16. The Performance of Underground Radioactive Waste Storage Tanks at the Savannah River Site: A 60-Year Historical Perspective

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Wiersma, Bruce J.

    2014-03-01T23:59:59.000Z

    The Savannah River Site produced weapons-grade materials for nearly 35 years between 1953 and 1988. The legacy of this production is nearly 37 million gallons of radioactive waste. Since the 1950s, the liquid waste has been stored in large, underground carbon steel waste tanks. During the past 20 years, the site has begun to process the waste so that it may be stored in vitrified and grout forms, which are more suitable for long-term storage. Over the history of the site, some tanks have experienced leakage of the waste to the secondary containment. This article is a review of themore »instances of leakage and corrosion degradation that the tanks and associated equipment have experienced since the first tanks were built. Furthermore, the activities that the site has taken to mitigate the degradation and manage the service life of the tank for its anticipated lifetime are reviewed.« less

  17. TECHNICAL EVALUATION OF REMEDIATION TECHNOLOGIES FOR PLUTONIUM-CONTAMINATED SOILS AT THE NEVADA TEST SITE (NTS)

    SciTech Connect (OSTI)

    Steve Hoeffner

    2003-12-31T23:59:59.000Z

    The Clemson Environmental Technologies Laboratory (CETL) was contracted by the National Energy Technology Center to evaluate technologies that might be used to reduce the volume of plutonium-contaminated soil at the Nevada Test Site. The project has been systematically approached. A thorough review and summary was completed for: (1) The NTS soil geological, geochemical and physical characteristics; (2) The characteristics and chemical form of the plutonium that is in these soils; (3) Previous volume reduction technologies that have been attempted on the NTS soils; (4) Vendors with technology that may be applicable; and (5) Related needs at other DOE sites. Soils from the Nevada Test Site were collected and delivered to the CETL. Soils were characterized for Pu-239/240, Am-241 and gross alpha. In addition, wet sieving and the subsequent characterization were performed on soils before and after attrition scrubbing to determine the particle size distribution and the distribution of Pu-239/240 and gross alpha as a function of particle size. Sequential extraction was performed on untreated soil to provide information about how tightly bound the plutonium was to the soil. Magnetic separation was performed to determine if this could be useful as part of a treatment approach. Using the information obtained from these reviews, three vendors were selected to demonstration their volume reduction technologies at the CETL. Two of the three technologies, bioremediation and soil washing, met the performance criteria. Both were able to significantly reduce the concentration plutonium in the soil from around 1100 pCi/g to 200 pCi/g or less with a volume reduction of around 95%, well over the target 70%. These results are especially encouraging because they indicate significant improvement over that obtained in these earlier pilot and field studies. Additional studies are recommended.

  18. Mitigative techniques and analysis of generic site conditions for ground-water contamination associated with severe accidents

    SciTech Connect (OSTI)

    Shafer, J.M.; Oberlander, P.L.; Skaggs, R.L.

    1984-04-01T23:59:59.000Z

    The purpose of this study is to evaluate the feasibility of using ground-water contaminant mitigation techniques to control radionuclide migration following a severe commercial nuclear power reactor accident. The two types of severe commercial reactor accidents investigated are: (1) containment basemat penetration of core melt debris which slowly cools and leaches radionuclides to the subsurface environment, and (2) containment basemat penetration of sump water without full penetration of the core mass. Six generic hydrogeologic site classifications are developed from an evaluation of reported data pertaining to the hydrogeologic properties of all existing and proposed commercial reactor sites. One-dimensional radionuclide transport analyses are conducted on each of the individual reactor sites to determine the generic characteristics of a radionuclide discharge to an accessible environment. Ground-water contaminant mitigation techniques that may be suitable, depending on specific site and accident conditions, for severe power plant accidents are identified and evaluated. Feasible mitigative techniques and associated constraints on feasibility are determined for each of the six hydrogeologic site classifications. The first of three case studies is conducted on a site located on the Texas Gulf Coastal Plain. Mitigative strategies are evaluated for their impact on contaminant transport and results show that the techniques evaluated significantly increased ground-water travel times. 31 references, 118 figures, 62 tables.

  19. Integrated Closure and Monitoring Plan for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site

    SciTech Connect (OSTI)

    S. E. Rawlinson

    2001-09-01T23:59:59.000Z

    Bechtel Nevada (BN) manages two low-level Radioactive Waste Management Sites (RWMSs) (one site is in Area 3 and the other is in Area 5) at the Nevada Test Site (NTS) for the U.S. Department of Energy's (DOE's) National Nuclear Security Administration Nevada Operations Office (NNSA/NV). The current DOE Order governing management of radioactive waste is 435.1. Associated with DOE Order 435.1 is a Manual (DOE M 435.1-1) and Guidance (DOE G 435.1-1). The Manual and Guidance specify that preliminary closure and monitoring plans for a low-level waste (LLW) management facility be developed and initially submitted with the Performance Assessment (PA) and Composite Analysis (CA) for that facility. The Manual and Guidance, and the Disposal Authorization Statement (DAS) issued for the Area 3 RWMS further specify that the preliminary closure and monitoring plans be updated within one year following issuance of a DAS. This Integrated Closure and Monitoring Plan (ICMP) fulfills both requirements. Additional updates will be conducted every third year hereafter. This document is an integrated plan for closing and monitoring both RWMSs, and is based on guidance issued in 1999 by the DOE for developing closure plans. The plan does not follow the format suggested by the DOE guidance in order to better accommodate differences between the two RWMSs, especially in terms of operations and site characteristics. The modification reduces redundancy and provides a smoother progression of the discussion. The closure and monitoring plans were integrated because much of the information that would be included in individual plans is the same, and integration provides efficient presentation and program management. The ICMP identifies the regulatory requirements, describes the disposal sites and the physical environment where they are located, and defines the approach and schedule for both closing and monitoring the sites.

  20. Commencement Bay nearshore/tideflats Superfund site, Tacoma, Washington remedial investigations. Evaluation of alternative dredging methods and equipment, disposal methods and sites, and site control and treatment practices for contaminated sediments. Final report

    SciTech Connect (OSTI)

    Phillips, K.E.; Malek, J.F.; Hammer, W.B.

    1985-06-01T23:59:59.000Z

    Alternative technologies and techniques for dredging, disposal, and treatment of contaminated sediments are reviewed. Implications of alternative technologies for management of contaminated sediments are discussed. Selection of appropriate technologies for contaminated sediments management depends on the physical and chemical profile of the sediments, and particularly on the physical state (liquid, solid, or gaseous) of contaminants of concern and changes in state that may occur at different phases of dredging, disposal, control, and treatment. Determination of acceptable criteria governing concentrations of contaminants in water, sediments, and soils, and air is the major requirement for selecting specific technologies for managing contaminated sediments. Technologies should be used which ensure that criteria will be met at all phases in the handling operations. Cost is most variable for disposal-site effluent-treatment options.

  1. DECHEM: A remedial planning tool for metallic contaminants in soil at UMTRA Project sites. Final report and users` guide

    SciTech Connect (OSTI)

    Not Available

    1989-03-01T23:59:59.000Z

    The DECHEM (DEcontamination of CHEMicals) method was developed for the Uranium Mill Tailings Remedial Action (UMTRA) Project to guide characterization and remedial planning for metals contamination in soils. This is necessary because non-radiological hazardous constituents may be more mobile than radium-226 (Ra-226), and hence may migrate more deeply into subpile soils (beneath tailings that are to be relocated) or into adjacent contaminated soils at UMTRA Project sites. The result is that remedial action to the Ra-226 excavation limit, as specified in the US Environmental Protection Agency (EPA) standards, may not adequately remove hazardous non-radiological contamination. Unmitigated, these contaminants in soil may cause health risks because of their presence in resuspended particles, their uptake by crops or fodder their seepage into aquifers used for drinking water or other possible exposure pathways. The DECHEM method was developed in response to the need for advanced planning for the remediation of chemical contaminants at UMTRA Project sites, and includes the following elements: Establishment of acceptable exposure rates for humans to chemicals, based on EPA guidelines or other toxicological literature. Modeling of chemical migration through environmental pathways from a remediated UMTRA Project site to humans. Determination of allowable residual concentrations (i.e., cleanup guidelines) for chemicals in soils that results in doses to humans that are below established acceptable exposure rates. The initial development and application of the DECHEM method has focused upon hazardous metallic contaminants such as arsenic, lead, molybdenum, and selenium, which are known to occur in elevated concentrations at some UMTRA Project sites.

  2. INDEPENDENT TECHNICAL EVALUATION AND RECOMMENDATIONS FOR CONTAMINATED GROUNDWATER AT THE DEPARTMENT OF ENERGY OFFICE OF LEGACY MANAGEMENT RIVERTON PROCESSING SITE

    SciTech Connect (OSTI)

    Looney, B.; Denham, M.; Eddy-Dilek, C.

    2014-05-06T23:59:59.000Z

    The U.S. Department of Energy Office of Legacy Management (DOE-LM) manages the legacy contamination at the Riverton, WY, Processing Site – a former uranium milling site that operated from 1958 to 1963. The tailings and associated materials were removed in 1988-1989 and contaminants are currently flushing from the groundwater. DOE-LM commissioned an independent technical team to assess the status of the contaminant flushing, identify any issues or opportunities for DOE-LM, and provide key recommendations. The team applied a range of technical frameworks – spatial, temporal, hydrological and geochemical – in performing the evaluation. In each topic area, an in depth evaluation was performed using DOE-LM site data (e.g., chemical measurements in groundwater, surface water and soil, water levels, and historical records) along with information collected during the December 2013 site visit (e.g., plant type survey, geomorphology, and minerals that were observed, collected and evaluated). A few of the key findings include: ? Physical removal of the tailings and associated materials reduced contaminant discharges to groundwater and reduced contaminant concentrations in the near-field plume. ? In the mid-field and far-field areas, residual contaminants are present in the vadose zone as a result of a variety of factors (e.g., evaporation/evapotranspiration from the capillary fringe and water table, higher water levels during tailings disposal, and geochemical processes). ? Vadose zone contaminants are widely distributed above the plume and are expected to be present as solid phase minerals that can serve as “secondary sources” to the underlying groundwater. The mineral sample collected at the site is consistent with thermodynamic predictions. ? Water table fluctuations, irrigation, infiltration and flooding will episodically solubilize some of the vadose zone secondary source materials and release contaminants to the groundwater for continued down gradient migration – extending the overall timeframe for flushing. ? Vertical contaminant stratification in the vadose zone and surficial aquifer will vary from location to location. Soil and water sampling strategies and monitoring well construction details will influence characterization and monitoring data. ? Water flows from the Wind River, beneath the Riverton Processing Site and through the plume toward the Little Wind River. This base flow pattern is influenced by seasonal irrigation and other anthropogenic activities, and by natural perturbations (e.g., flooding). ? Erosion and reworking of the sediments adjacent to the Little Wind River results in high heterogeneity and complex flow and geochemistry. Water flowing into oxbow lakes (or through areas where oxbow lakes were present in the past) will be exposed to localized geochemical conditions that favor chemical reduction (i.e., “naturally reduced zones”) and other attenuation processes. This attenuation is not sufficient to fully stabilize the plume or to reduce contaminant concentrations in the groundwater to target levels. Consistent with these observations, the team recommended increased emphasis on collecting data in the zones where secondary source minerals are projected to accumulate (e.g., just above the water table) using low cost methods such as x-ray fluorescence. The team also suggested several low cost nontraditional sources of data that have the potential to provide supplemental data (e.g., multispectral satellite imagery) to inform and improve legacy management decisions. There are a range of strategies for management of the legacy contamination in the groundwater and vadose zone near the Riverton Processing Site. These range from the current strategy, natural flushing, to intrusive remedies such as plume scale excavation of the vadose zone and pump & treat. Each option relates to the site specific conditions, issues and opportunities in a unique way. Further, each option has advantages and disadvantages that need to be weighed. Scoping evaluation was performed for three major classes

  3. Corrective Action Investigation Plan for Corrective Action Unit 545: Dumps, Waste Disposal Sites, and Buried Radioactive Materials Nevada Test Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Alfred Wickline

    2007-06-01T23:59:59.000Z

    Corrective Action Unit 545, Dumps, Waste Disposal Sites, and Buried Radioactive Materials, consists of seven inactive sites located in the Yucca Flat area and one inactive site in the Pahute Mesa area. The eight CAU 545 sites consist of craters used for mud disposal, surface or buried waste disposed within craters or potential crater areas, and sites where surface or buried waste was disposed. The CAU 545 sites were used to support nuclear testing conducted in the Yucca Flat area during the 1950s through the early 1990s, and in Area 20 in the mid-1970s. This Corrective Action Investigation Plan has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Under the Federal Facility Agreement and Consent Order, this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Fieldwork will be conducted following approval.

  4. Guidance on the application of quality assurance for characterizing a low-level radioactive waste disposal site

    SciTech Connect (OSTI)

    Pittiglio, C.L. Jr.; Starmer, R.J.; Hedges, D.

    1990-10-01T23:59:59.000Z

    This document provides the Nuclear Regulatory Commission's staff guidance to an applicant on meeting the quality control (QC) requirements of Title 10 of the Code of Federal Regulations, Part 61, Section 61.12 (10 CFR 61.12), for a low-level waste disposal facility. The QC requirements combined with the requirements for managerial controls and audits are the basis for developing a quality assurance (QA) program and for the guidance provided herein. QA guidance is specified for site characterization activities necessary to meet the performance objectives of 10 CFR Part 61 and to limit exposure to or the release of radioactivity. 1 tab.

  5. Corrective Action Investigation Plan for Corrective Action Unit 528: Polychlorinated Biphenyls Contamination, Nevada Test Site, Nevada, Rev. 0

    SciTech Connect (OSTI)

    U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

    2003-05-08T23:59:59.000Z

    This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 528, Polychlorinated Biphenyls Contamination (PCBs), Nevada Test Site (NTS), Nevada, under the Federal Facility Agreement and Consent Order. Located in the southwestern portion of Area 25 on the NTS in Jackass Flats (adjacent to Test Cell C [TCC]), CAU 528 consists of Corrective Action Site 25-27-03, Polychlorinated Biphenyls Surface Contamination. Test Cell C was built to support the Nuclear Rocket Development Station (operational between 1959 and 1973) activities including conducting ground tests and static firings of nuclear engine reactors. Although CAU 528 was not considered as a direct potential source of PCBs and petroleum contamination, two potential sources of contamination have nevertheless been identified from an unknown source in concentrations that could potentially pose an unacceptable risk to human health and/or the environment. This CAU's close proximity to TCC prompted Shaw to collect surface soil samples, which have indicated the presence of PCBs extending throughout the area to the north, east, south, and even to the edge of the western boundary. Based on this information, more extensive field investigation activities are being planned, the results of which are to be used to support a defensible evaluation of corrective action alternatives in the corrective action decision document.

  6. Corrective Action Decision Document for Corrective Action Unit 366: Area 11 Plutonium Valley Dispersion Sites Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Patrick Matthews

    2012-09-01T23:59:59.000Z

    CAU 366 comprises six corrective action sites (CASs): • 11-08-01, Contaminated Waste Dump #1 • 11-08-02, Contaminated Waste Dump #2 • 11-23-01, Radioactively Contaminated Area A • 11-23-02, Radioactively Contaminated Area B • 11-23-03, Radioactively Contaminated Area C • 11-23-04, Radioactively Contaminated Area D The purpose of this CADD is to identify and provide the rationale for the recommendation of corrective action alternatives (CAA) for the six CASs within CAU 366. Corrective action investigation (CAI) activities were performed from October 12, 2011, to May 14, 2012, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 366: Area 11 Plutonium Valley Dispersion Sites.

  7. Corrective Action Investigation Plan for Corrective Action Unit 550: Smoky Contamination Area Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Grant Evenson

    2012-05-01T23:59:59.000Z

    Corrective Action Unit (CAU) 550 is located in Areas 7, 8, and 10 of the Nevada National Security Site, which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 550, Smoky Contamination Area, comprises 19 corrective action sites (CASs). Based on process knowledge of the releases associated with the nuclear tests and radiological survey information about the location and shape of the resulting contamination plumes, it was determined that some of the CAS releases are co-located and will be investigated as study groups. This document describes the planned investigation of the following CASs (by study group): (1) Study Group 1, Atmospheric Test - CAS 08-23-04, Atmospheric Test Site T-2C; (2) Study Group 2, Safety Experiments - CAS 08-23-03, Atmospheric Test Site T-8B - CAS 08-23-06, Atmospheric Test Site T-8A - CAS 08-23-07, Atmospheric Test Site T-8C; (3) Study Group 3, Washes - Potential stormwater migration of contaminants from CASs; (4) Study Group 4, Debris - CAS 08-01-01, Storage Tank - CAS 08-22-05, Drum - CAS 08-22-07, Drum - CAS 08-22-08, Drums (3) - CAS 08-22-09, Drum - CAS 08-24-03, Battery - CAS 08-24-04, Battery - CAS 08-24-07, Batteries (3) - CAS 08-24-08, Batteries (3) - CAS 08-26-01, Lead Bricks (200) - CAS 10-22-17, Buckets (3) - CAS 10-22-18, Gas Block/Drum - CAS 10-22-19, Drum; Stains - CAS 10-22-20, Drum - CAS 10-24-10, Battery. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each study group. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 31, 2012, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 550. The potential contamination sources associated with the study groups are from nuclear testing activities conducted at CAU 550. The DQO process resulted in an assumption that the total effective dose (TED) within the default contamination boundary of CAU 550 exceeds the final action level and requires corrective action. The presence and nature of contamination outside the default contamination boundary at CAU 550 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the TED at sample locations to the dose-based final action level. The TED will be calculated as the total of separate estimates of internal and external dose. Results from the analysis of soil samples will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at the center of each sample location will be used to measure external radiological dose. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each group of CASs.

  8. Quinoline and derivatives at a tar oil contaminated site: hydroxylated products as indicator for natural attenuation?

    SciTech Connect (OSTI)

    Anne-Kirsten Reineke; Thomas Goeen; Alfred Preiss; Juliane Hollender [RWTH Aachen, Aachen (Germany). Institute of Hygiene and Environmental Medicine

    2007-08-01T23:59:59.000Z

    LC-MS-MS analysis of groundwater of a tar oil contaminated site (a former coal mine and coking plant in Castrop-Rauxel, Germany) showed the occurrence of the N-heterocycles quinoline and isoquinoline as well as their hydroxylated and hydrogenated metabolites. The concentrations of the hydroxylated compounds, 2(1H)-quinolinone and 1(2H)-isoquinolinone, were significantly higher than those of the nonsubstituted parent compounds. Therefore, exclusive quantification of the parent compounds leads to an underestimation of the amount of N-heterocycles present in the groundwater. Microbial degradation experiments of quinoline and isoquinoline with aquifer material of the site as inocculum showed the formation of hydroxylated and hydrogenated products under sulfate-reducing conditions, the prevailing conditions in the field. However, since analyses of seven tar products showed that these compounds are also primary constituents, their detection in groundwater is found to be a nonsufficient indicator for the occurrence of biological natural attenuation processes. Instead, the ratio of hydroxylated to parent compound (R{sub metabolite}) is proposed as a useful indicator. We found that 65-83% of all groundwater samples showed R{sub metabolite} for 2(1H)-quinolinone, 1(2H)-isoquinolinone, 3,4-dihydro-2(1H)-quinolinone, and 3,4-dihydro-1(2H)-isoquinolinone, which was higher than the highest ratio found in tar products. With respect to the observed partition coefficient between tar oil and water of 3.5 for quinoline and isoquinoline and 0.3 for 2(1H)-quinolinone and 1(2H)-isoquinolinone, the ratio in groundwater would be approximately 10 times higher than the ratio in tar oil. When paying attention to these two parameters, 19-31% of groundwater samples exceed the highest tar oil ratio. This indicates that biological processes take place in the aquifer of the site and R{sub metabolite} is an applicable indicator for natural attenuation. 42 refs., 6 figs., 2 tabs.

  9. GEOPHYSICS AND SITE CHARACTERIZATION AT THE HANFORD SITE THE SUCCESSFUL USE OF ELECTRICAL RESISTIVITY TO POSITION BOREHOLES TO DEFINE DEEP VADOSE ZONE CONTAMINATION - 11509

    SciTech Connect (OSTI)

    GANDER MJ; LEARY KD; LEVITT MT; MILLER CW

    2011-01-14T23:59:59.000Z

    Historic boreholes confirmed the presence of nitrate and radionuclide contaminants at various intervals throughout a more than 60 m (200 ft) thick vadose zone, and a 2010 electrical resistivity survey mapped the known contamination and indicated areas of similar contaminants, both laterally and at depth; therefore, electrical resistivity mapping can be used to more accurately locate characterization boreholes. At the Hanford Nuclear Reservation in eastern Washington, production of uranium and plutonium resulted in the planned release of large quantities of contaminated wastewater to unlined excavations (cribs). From 1952 until 1960, the 216-U-8 Crib received approximately 379,000,000 L (100,000,000 gal) of wastewater containing 25,500 kg (56,218 lb) uranium; 1,029,000 kg (1,013 tons) of nitrate; 2.7 Ci of technetium-99; and other fission products including strontium-90 and cesium-137. The 216-U-8 Crib reportedly holds the largest inventory of waste uranium of any crib on the Hanford Site. Electrical resistivity is a geophysical technique capable of identifying contrasting physical properties; specifically, electrically conductive material, relative to resistive native soil, can be mapped in the subsurface. At the 216-U-8 Crib, high nitrate concentrations (from the release of nitric acid [HNO{sub 3}] and associated uranium and other fission products) were detected in 1994 and 2004 boreholes at various depths, such as at the base of the Crib at 9 m (30 ft) below ground surface (bgs) and sporadically to depths in excess of 60 m (200 ft) bgs. These contaminant concentrations were directly correlative with the presence of observed low electrical resistivity responses delineated during the summer 2010 geophysical survey. Based on this correlation and the recently completed mapping of the electrically conductive material, additional boreholes are planned for early 2011 to identify nitrate and radionuclide contamination: (a) throughout the entire vertical length of the vadose zone (i.e., 79 m [260 ft] bgs) within the footprint of the Crib, and (b) 15 to 30 m (50 to 100 ft) east of the Crib footprint, where contaminants are inferred to have migrated through relatively permeable soils. Confirmation of the presence of contamination in historic boreholes correlates well with mapping from the 2010 survey, and serves as a basis to site future characterization boreholes that will likely intersect contamination both laterally and at depth.

  10. Rooting Characteristics of Vegetation Near Areas 3 and 5 Radioactive Waste Management Sites at the Nevada Test Site--Part 1

    SciTech Connect (OSTI)

    D. J. Hansen

    2003-09-30T23:59:59.000Z

    The U.S. Department of Energy emplaced high-specific-activity low-level radioactive wastes and limited quantities of classified transuranic wastes in Greater Confinement Disposal (GCD) boreholes from 1984 to 1989. The boreholes are located at the Area 5 Radioactive Waste Management Site (RWMS) on the Nevada Test Site (NTS) in southern Nevada. The boreholes were backfilled with native alluvium soil. The surface of these boreholes and trenches is expected to be colonized by native vegetation in the future. Considering the long-term performance of the disposal facilities, bioturbation (the disruption of buried wastes by biota) is considered a primary release mechanism for radionuclides disposed in GCD boreholes as well as trenches at both Areas 3 and 5 RWMSs. This report provides information about rooting characteristics of vegetation near Areas 3 and 5 RWMSs. Data from this report are being used to resolve uncertainties involving parameterization of performance assessment models used to characterize the biotic mixing of soils and radionuclide transport processes by biota. The objectives of this study were to: (1) survey the prior ecological literature on the NTS and identify pertinent information about the vegetation, (2) conduct limited field studies to describe the current vegetation in the vicinity of Areas 3 and 5 RWMSs so as to correlate findings with more extensive vegetation data collected at Yucca Mountain and the NTS, ( 3 ) review prior performance assessment documents and evaluate model assumptions based on current ecological information, and (4) identify data deficiencies and make recommendations for correcting such deficiencies.

  11. DOE issues Finding of No Significant Impact on Environmental Assessment for Replacement Capability for Disposal of Remote-Handled Low Level Radioactive Waste Generated at Idaho Site

    Broader source: Energy.gov [DOE]

    Idaho Falls, ID – After completing a careful assessment, the U.S. Department of Energy has determined that building a new facility at its Idaho National Laboratory site for continued disposal of remote-handled low level radioactive waste generated by operations at the site will not have a significant impact on the environment.

  12. Evaluation of Recent Trailer Contamination and Supersack Integrity Issues

    SciTech Connect (OSTI)

    Gordon, S.

    2012-09-17T23:59:59.000Z

    During the period from fiscal year (FY) 2009 to FY 2011, there were a total of 21 incidents involving radioactively contaminated shipment trailers and 9 contaminated waste packages received at the Nevada National Security Site (NNSS) Area 5 Radioactive Waste Management Site (RWMS). During this time period, the EnergySolutions (ES) Clive, Utah, disposal facility had a total of 18 similar incidents involving trailer and package contamination issues. As a result of the increased occurrence of such incidents, DOE Environmental Management Headquarters (EM/HQ) Waste Management organization (EM-30) requested that the Energy Facility Contractors’ Group (EFCOG) Waste Management Working Group (WMWG) conduct a detailed review of these incidents and report back to EM-30 regarding the results of this review, including providing any recommendations formulated as a result of the evaluation of current site practices involving handling and management of radioactive material and waste shipments.

  13. Relative yields of U-235 fission products measured in a high level radioactive sludge at Savannah River Site

    SciTech Connect (OSTI)

    Bibler, N.E.; Coleman, C.J. [Westinghouse Savannah River Co., Aiken, SC (United States); Kinard, W.F. [Charleston Coll., SC (United States). Dept. of Chemistry

    1992-10-01T23:59:59.000Z

    This paper presents measurements of the concentrations of 42 of the long-lived U-235 fission products in a high-level radioactive waste sludge stored at Savannah River Site. The 42 fision products make up 98% of the waste sludge. We used inductively coupled plasma-mass spectroscopy for the analysis. The relative yields for most of the fission products are in complete agreement with the known relative yields for the beta decay chains of the two asymmetric branches of the slow neutron fission of U-235. Disagreements can be reconciled based on the chemistry of the fission products in the caustic waste sludges, the neutron fluences in SRS reactors, or interferences in the ICP-MS analyses. This paper presents measurements of the concentrations of 42 (98%) of the long-lived U-235 fission products in a high-level radioactive waste sludge stored at the Savannah River Site. We analyzed the sludge with inductively coupled plasma-mass spectroscopy. The relative yields for most of the fission products agree completely with the known relative vields for the beta decay chains of the two asymmetric: branches of the slow neutron fission of U-235. The chemistry of the fission products in the caustic waste sludges, the neutron fluences in SRS reactors, or interferences in the ICP-MS analyses explain the differences in the measured and calculated results.

  14. Relative yields of U-235 fission products measured in a high level radioactive sludge at Savannah River Site

    SciTech Connect (OSTI)

    Bibler, N.E.; Coleman, C.J. (Westinghouse Savannah River Co., Aiken, SC (United States)); Kinard, W.F. (Charleston Coll., SC (United States). Dept. of Chemistry)

    1992-01-01T23:59:59.000Z

    This paper presents measurements of the concentrations of 42 of the long-lived U-235 fission products in a high-level radioactive waste sludge stored at Savannah River Site. The 42 fision products make up 98% of the waste sludge. We used inductively coupled plasma-mass spectroscopy for the analysis. The relative yields for most of the fission products are in complete agreement with the known relative yields for the beta decay chains of the two asymmetric branches of the slow neutron fission of U-235. Disagreements can be reconciled based on the chemistry of the fission products in the caustic waste sludges, the neutron fluences in SRS reactors, or interferences in the ICP-MS analyses. This paper presents measurements of the concentrations of 42 (98%) of the long-lived U-235 fission products in a high-level radioactive waste sludge stored at the Savannah River Site. We analyzed the sludge with inductively coupled plasma-mass spectroscopy. The relative yields for most of the fission products agree completely with the known relative vields for the beta decay chains of the two asymmetric: branches of the slow neutron fission of U-235. The chemistry of the fission products in the caustic waste sludges, the neutron fluences in SRS reactors, or interferences in the ICP-MS analyses explain the differences in the measured and calculated results.

  15. Addendum to the Corrective Action Decision Document/Closure Report for Corrective Action Unit 34: Area 3 Contaminated Waste Sites, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    Lynn Kidman

    2008-10-01T23:59:59.000Z

    This document constitutes an addendum to the April 2002, Corrective Action Decision Document/Closure Report for Corrective Action Unit 34: Area 3 Contaminated Waste Sites as described in the document Recommendations and Justifications for Modifications for Use Restrictions Established under the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office Federal Facility Agreement and Consent Order (UR Modification document) dated February 2008. The UR Modification document was approved by NDEP on February 26, 2008. The approval of the UR Modification document constituted approval of each of the recommended UR modifications.

  16. Remaining Sites Verification Package for the 600-111, P-11 Critical Mass Laboratory Crib, and UPR-600-16, Fire and Contamination Spread Waste Sites, Waste Site Reclassification Form 2008-045

    SciTech Connect (OSTI)

    J. M. Capron

    2008-10-28T23:59:59.000Z

    The UPR-600-16, Fire and Contamination Spread waste site is an unplanned release that occurred on December 4, 1951, when plutonium contamination was spread by a fire that ignited inside the 120 Experimental Building. The 120 Experimental Building was a laboratory building that was constructed in 1949 and used for plutonium criticality studies as part of the P-11 Project. In November 1951, a criticality occurred in the 120 Experimental Building that resulted in extensive plutonium contamination inside the building. The confirmatory evaluation supports a reclassification of this site to Interim Closed Out. The current site conditions achieve the remedial action objectives and the corresponding remedial action goals established in the Remaining Sites ROD. The results of the extensive radiological survey of the surface soil and the confirmatory and verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

  17. Design and performance verification of a soil-bentonite slurry wall for the hydraulic isolation of contaminated sites

    SciTech Connect (OSTI)

    Hollenweger, R.; Martinenghi, L. [Swiss Federal Inst. of Tech., Zurich (Switzerland). Inst. of Geotechnical Engineering

    1995-12-31T23:59:59.000Z

    The polluted ground of contaminated sites is often encapsulated by diaphragm walls, with concrete or concrete-stabilized earth being common construction materials in Europe. At the Institute of Geotechnical Engineering at the Swiss Federal Institute of Technology Zurich, new material mixtures that contain a high percentage of clay minerals have been developed over the past few years. Two experimental diaphragm walls, one in Switzerland and one in Germany, were constructed using such materials. A diaphragm wall 55 m deep using this mixture is currently being placed to encapsulate a contaminated landfill site in Germany. In this paper, an evaluation of the new mixture and results from both the experimental and full-scale walls, as well as complementary laboratory investigations, are presented and examined.

  18. Addendum to the East Tennessee Technology Park Site-Wide Residual Contamination Remedial Investigation Work Plan Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    SAIC

    2011-04-01T23:59:59.000Z

    The East Tennessee Technology Park Site-Wide Residual Contamination Remedial Investigation Work Plan (DOE 2004) describes the planned fieldwork to support the remedial investigation (RI) for residual contamination at the East Tennessee Technology Park (ETTP) not addressed in previous Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) decisions. This Addendum describes activities that will be conducted to gather additional information in Zone 1 of the ETTP for groundwater, surface water, and sediments. This Addendum has been developed from agreements reached in meetings held on June 23, 2010, August 25, 2010, October 13, 2010, November 13, 2010, December 1, 2010, and January 13, 2011, with representatives of the U. S. Department of Energy (DOE), U. S. Environmental Protection Agency (EPA), and Tennessee Department of Environment and Conservation (TDEC). Based on historical to recent groundwater data for ETTP and the previously completed Sitewide Remedial Investigation for the ETTP (DOE 2007a), the following six areas of concern have been identified that exhibit groundwater contamination downgradient of these areas above state of Tennessee and EPA drinking water maximum contaminant levels (MCLs): (1) K-720 Fly Ash Pile, (2) K-770 Scrap Yard, (3) Duct Island, (4) K-1085 Firehouse Burn/J.A. Jones Maintenance Area, (5) Contractor's Spoil Area (CSA), and (6) Former K-1070-A Burial Ground. The paper presents a brief summary of the history of the areas, the general conceptual models for the observed groundwater contamination, and the data gaps identified.

  19. Corrective Action Decision Document/Closure Report for Corrective Action Unit 190: Contaminated Waste Sites, Nevada Test Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Alfred Wickline

    2008-03-01T23:59:59.000Z

    This Corrective Action Decision Document/Closure Report has been prepared for Corrective Action Unit (CAU) 190, Contaminated Waste Sites, Nevada Test Site, Nevada, in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; U.S. Department of Energy, Environmental Management; U.S. Department of Defense; and DOE, Legacy Management (1996, as amended January 2007). Corrective Action Unit 190 is comprised of the following four corrective action sites (CASs): • 11-02-01, Underground Centrifuge • 11-02-02, Drain Lines and Outfall • 11-59-01, Tweezer Facility Septic System • 14-23-01, LTU-6 Test Area The purpose of this Corrective Action Decision Document/Closure Report is to provide justification and documentation supporting the recommendation for closure of CAU 190 with no further corrective action. To achieve this, corrective action investigation (CAI) activities were performed from March 21 through June 26, 2007. All CAI activities were conducted as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 190: Contaminated Waste Sites, Nevada Test Site, Nevada (NNSA/NSO, 2006). The purpose of the CAI was to fulfill the following data needs as defined during the data quality objective process: • Determine whether contaminants of concern (COCs) are present. • If COCs are present, determine their nature and extent. • Provide sufficient information and data to complete appropriate corrective actions. The CAU 190 dataset from the investigation results was evaluated based on the data quality indicator parameters. This evaluation demonstrated the quality and acceptability of the dataset for use in fulfilling the data quality objective data needs.

  20. Hydrologic evaluation methodology for estimating water movement through the unsaturated zone at commercial low-level radioactive waste disposal sites

    SciTech Connect (OSTI)

    Meyer, P.D.; Rockhold, M.L.; Nichols, W.E.; Gee, G.W. [Pacific Northwest Lab., Richland, WA (United States)

    1996-01-01T23:59:59.000Z

    This report identifies key technical issues related to hydrologic assessment of water flow in the unsaturated zone at low-level radioactive waste (LLW) disposal facilities. In addition, a methodology for incorporating these issues in the performance assessment of proposed LLW disposal facilities is identified and evaluated. The issues discussed fall into four areas: estimating the water balance at a site (i.e., infiltration, runoff, water storage, evapotranspiration, and recharge); analyzing the hydrologic performance of engineered components of a facility; evaluating the application of models to the prediction of facility performance; and estimating the uncertainty in predicted facility performance. To illustrate the application of the methodology, two examples are presented. The first example is of a below ground vault located in a humid environment. The second example looks at a shallow land burial facility located in an arid environment. The examples utilize actual site-specific data and realistic facility designs. The two examples illustrate the issues unique to humid and arid sites as well as the issues common to all LLW sites. Strategies for addressing the analytical difficulties arising in any complex hydrologic evaluation of the unsaturated zone are demonstrated.

  1. National survey of crystalline rocks and recommendations of regions to be explored for high-level radioactive waste repository sites

    SciTech Connect (OSTI)

    Smedes, H.W.

    1983-04-01T23:59:59.000Z

    A reconnaissance of the geological literature on large regions of exposed crystalline rocks in the United States provides the basis for evaluating if any of those regions warrant further exploration toward identifying potential sites for development of a high-level radioactive waste repository. The reconnaissance does not serve as a detailed evaluation of regions or of any smaller subunits within the regions. Site performance criteria were selected and applied insofar as a national data base exists, and guidelines were adopted that relate the data to those criteria. The criteria include consideration of size, vertical movements, faulting, earthquakes, seismically induced ground motion, Quaternary volcanic rocks, mineral deposits, high-temperature convective ground-water systems, hydraulic gradients, and erosion. Brief summaries of each major region of exposed crystalline rock, and national maps of relevant data provided the means for applying the guidelines and for recommending regions for further study. It is concluded that there is a reasonable likelihood that geologically suitable repository sites exist in each of the major regions of crystalline rocks. The recommendation is made that further studies first be conducted of the Lake Superior, Northern Appalachian and Adirondack, and the Southern Appalachian Regions. It is believed that those regions could be explored more effectively and suitable sites probably could be found, characterized, verified, and licensed more readily there than in the other regions.

  2. Population dose commitments due to radioactive releases from nuclear power plant sites in 1985

    SciTech Connect (OSTI)

    Baker, D.A.

    1988-08-01T23:59:59.000Z

    Population radiation dose commitments have been estimated from reported radionuclide releases from commericial power reactors operating during 1985. Fifty-year dose commitments from a one-year exposure were calculated from both liquid and atmospheric releases for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 61 sites. This report tabulates the results of these calculations, showing the dose commitments for both liquid and airborne pathways for each age group and organ. Also included for each of the sites is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 73 person-rem to a low of 0.011 person-rem for the sites with plants operating throughout the year with an arithmetic mean of 3 person-rem. The total population dose for all sites was estimated at 200 person-rem for the 110 million people considered at risk. The site average individual dose commitment from all pathways ranged from a low of 5 /times/ 10/sup /minus/6/ mrem to a high of 0.02 mrem. No attempt was made in this study to determine the maximum dose commitment received by any one individual from the radionuclides released at any of the sites.

  3. Population dose commitments due to radioactive releases from nuclear power plant sites in 1986

    SciTech Connect (OSTI)

    Baker, D.A. (Pacific Northwest Lab., Richland, WA (USA))

    1989-10-01T23:59:59.000Z

    Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1986. Fifty-year dose commitments for a one-year exposure from both liquid and atmospheric releases were calculated for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 66 reactor sites. This report tabulates the results of these calculations, showing the dose commitments for both water and airborne pathways for each age group and organ. Also included for each of the sites is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 31 person-rem to a low of 0.0007 person-rem for the sites with plants operating throughout the year with an arithmetic mean of 1.7 person-rem. The total population dose for all sites was estimated at 110 person-rem for the 140 million people considered at risk. The site average individual dose commitment from all pathways ranged from a low of 2 {times} 10{sup -6} mrem to a high of 0.02 mrem. No attempt was made in this study to determine the maximum dose commitment received by any one individual from the radionuclides released at any of the sites. 12 refs.

  4. Population dose commitments due to radioactive releases from nuclear power plant sites in 1984

    SciTech Connect (OSTI)

    Baker, D.A.

    1988-01-01T23:59:59.000Z

    Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1984. Fifty-year dose commitments from a one-year exposure were calculated from both liquid and atmospheric releases for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 56 sites. This report tabulates the results of these calculations, showing the dose commitments for both liquid and airborne pathways for each age group and organ. Also included for each of the sites is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 110 person-rem to a low of 0.002 person-rem for the sites with plants operating throughout the year with an arithmetic mean of 5 person-rem. The total population dose for all sites was estimated at 280 person-rem for the 100 million people considered at risk. The site average individual dose commitment from all pathways ranged from a low of 6 x 10/sup -6/ mrem to a high of 0.04 mrem. No attempt was made in this study to determine the maximum dose commitment received by any one individual from the radionuclides released at any of the sites.

  5. Corrective Action Plan for Corrective Action Unit 166: Storage Yards and Contaminated Materials, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2007-10-01T23:59:59.000Z

    Corrective Action Unit (CAU) 166, Storage Yards and Contaminated Materials, is listed in the Federal Facility Agreement and Consent Order (FFACO) of 1996 (FFACO, 1996). CAU 166 consists of seven Corrective Action Sites (CASs) located in Areas 2, 3, 5, and 18 of the Nevada Test Site (NTS), which is located approximately 65 miles northwest of Las Vegas, Nevada (Figure 1). CAU 166 consists of the following CASs: (1) CAS 02-42-01, Cond. Release Storage Yd - North; (2) CAS 02-42-02, Cond. Release Storage Yd - South; (3) CAS 02-99-10, D-38 Storage Area; (4) CAS 03-42-01, Conditional Release Storage Yard; (5) CAS 05-19-02, Contaminated Soil and Drum; (6) CAS 18-01-01, Aboveground Storage Tank; and (7) CAS 18-99-03, Wax Piles/Oil Stain. Details of the site history and site characterization results for CAU 166 are provided in the approved Corrective Action Investigation Plan (CAIP) (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2006) and in the approved Corrective Action Decision Document (CADD) (NNSA/NSO, 2007).

  6. Baseline risk assessment of groundwater contamination at the uranium mill tailings site, near Gunnison, Colorado. Revision 2

    SciTech Connect (OSTI)

    NONE

    1996-06-01T23:59:59.000Z

    This report is the second site-specific risk assessment document prepared for the Ground Water Project at the Gunnison site. A preliminary risk assessment was conducted in 1990 to determine whether long-term use of ground water from private wells near the Gunnison site had the potential for adverse health effects. Due to the results of that preliminary risk assessment, the residents were provided bottled water on an interim basis. In July 1994, the residents and the nearby Valco cement/concrete plant were given the option to connect to anew alternate water supply system, eliminating the bottled water option. This document evaluates current and potential future impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site characterization will be used to determine whether more action is needed to protect human health and the environment and to comply with the EPA standards.

  7. RADIOACTIVE WASTE DISPOSAL IN GRANITE

    E-Print Network [OSTI]

    Witherspoon, P.A.

    2010-01-01T23:59:59.000Z

    RADIOACTIVE WASTE DISPOSAL IN GRANITE Paul A. WitherspoonRADIOACTIVE WASTE DISPOSAL IN GRANITE Paul A. Wither spoona repository site in granite are to evaluate the suitability

  8. Hanford Site Tank 241-C-108 Residual Waste Contaminant Release Models and Supporting Data

    SciTech Connect (OSTI)

    Cantrell, Kirk J.; Krupka, Kenneth M.; Geiszler, Keith N.; Arey, Bruce W.; Schaef, Herbert T.

    2010-06-18T23:59:59.000Z

    This report presents the results of laboratory characterization, testing, and analysis for a composite sample (designated 20578) of residual waste collected from single-shell tank C-108 during the waste retrieval process after modified sluicing. These studies were completed to characterize concentration and form of contaminant of interest in the residual waste; assess the leachability of contaminants from the solids; and develop release models for contaminants of interest. Because modified sluicing did not achieve 99% removal of the waste, it is expected that additional retrieval processing will take place. As a result, the sample analyzed here is not expected to represent final retrieval sample.

  9. ENVIRONMENTAL IMPACTS ASSOCIATED WITH STORAGE, TREATMENT, AND DISPOSAL OF SOLID RADIOACTIVE AND CHEMICALLY HAZARDOUS WASTE AT THE HANFORD SITE, RICHLAND, WASHINGTON

    SciTech Connect (OSTI)

    Johnson, Wayne L.; Nelson, Iral C.; Payson, David R.; Rhoads, Kathleen

    2004-03-01T23:59:59.000Z

    The Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement (HSW EIS) provides environmental and technical information concerning U.S. Department of Energy (DOE) proposed waste management practices for certain solid radioactive wastes at the Hanford Site through the year 2046. The HSW EIS covers four primary aspects of waste management at Hanford – storage, treatment, transportation, and disposal. It also addresses four types of solid waste – low-level waste, mixed low-level waste that contains both radioactive and chemically hazardous constituents, immobilized low-activity waste from processing Hanford tank waste, and transuranic waste. The HSW EIS was prepared to assist DOE in determining which specific Hanford Site facilities will continue to be used, will be modified, or need to be constructed, to safely treat, store, and dispose of these wastes.

  10. 2007 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site, Nye County, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2008-01-01T23:59:59.000Z

    This report summarizes the results of an annual review of conditions affecting the operation of the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) and a determination of the continuing adequacy of the performance assessments (PAs) and composite analyses (CAs). The Area 5 RWMS PA documentation consists of the original PA (Shott et al., 1998), referred to as the 1998 Area 5 RWMS PA and supporting addenda (Bechtel Nevada [BN], 2001b; 2006a). The Area 5 RWMS CA was issued as a single document (BN, 2001a) and has a single addendum (BN, 2001c). The Area 3 PA and CA were issued in a single document (Shott et al., 2000). The Maintenance Plan for the PAs and CAs (National Security Technologies, LLC [NSTec], 2006) and the Disposal Authorization Statements (DASs) for the Area 3 and 5 RWMSs (U.S. Department of Energy [DOE], 2000; 2002) require preparation of an annual summary and a determination of the continuing adequacy of the PAs and CAs. The annual summary report is submitted to DOE Headquarters. Following the annual report format in the DOE PA/CA Maintenance Guide (DOE, 1999), this report presents the annual summary for the PAs in Section 2.0 and the CAs in Section 3.0. The annual summary for the PAs includes the following: Section 2.1 summarizes changes in waste disposal operations; Section 2.1.5 provides an evaluation of the new estimates of the closure inventories derived from the actual disposals through fiscal year (FY) 2007; Section 2.2 summarizes the results of the monitoring conducted under the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's (NNSA/NSO's) Integrated Closure and Monitoring Plan for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site (BN, 2005), and the research and development (R&D) activities; Section 2.4 is a summary of changes in facility design, operation, or expected future conditions; monitoring and R&D activities; and the maintenance program; and Section 2.5 discusses the recommended changes in disposal facility design and operations, monitoring and R&D activities, and the maintenance program. Similarly, the annual summary for the CAs (presented in Section 3.0) includes the following: Section 3.1 presents the assessment of the adequacy of the CAs, with a summary of the relevant factors reviewed in FY 2007; Section 3.2 presents an assessment of the relevant site activities at the Nevada Test Site (NTS) that would impact the sources of residual radioactive material considered in the CAs; Section 3.3 summarizes the monitoring and R&D results that were reviewed in FY 2007; Section 3.4 presents a summary of changes in relevant site programs (including monitoring, R&D, and the maintenance program) that occurred since the CAs were prepared; and Section 3.5 summarizes the recommended changes to these programs.

  11. Population dose commitments due to radioactive releases from nuclear power plant sites in 1988

    SciTech Connect (OSTI)

    Baker, D.A. (Pacific Northwest Lab., Richland, WA (United States))

    1992-01-01T23:59:59.000Z

    Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1988. Fifty-year commitments for a one-year exposure from both liquid and atmospheric releases were calculated for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 71 reactor sites. This report tabulates the results of these calculations, showing the dose commitments for both water and airborne pathways for each age group and organ. Also included for each of the sites is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total collective dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 16 person-rem to a low of 0.0011 person-rem for the sites with plants operating throughout the year with an arithmetic mean of 1.1 person-rem. The total population dose for all sites was estimated at 75 person-rem for the 150 million people considered at risk. The site average individual dose commitment from all pathways ranged from a low of 3 {times} 10{sup {minus}7} mrem to a high of 0.02 mrem. No attempt was made in this study to determine the maximum dose commitment received by any one individual from the radionuclides released at any of the sites. However, licensee calculation of doses to the maximally exposed individual at some sites indicated values of up to approximately 100 times average individual doses (on the order of a few millirem per year).

  12. Population dose commitments due to radioactive releases from nuclear power plant sites in 1988. Volume 10

    SciTech Connect (OSTI)

    Baker, D.A. [Pacific Northwest Lab., Richland, WA (United States)

    1992-01-01T23:59:59.000Z

    Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1988. Fifty-year commitments for a one-year exposure from both liquid and atmospheric releases were calculated for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 71 reactor sites. This report tabulates the results of these calculations, showing the dose commitments for both water and airborne pathways for each age group and organ. Also included for each of the sites is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total collective dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 16 person-rem to a low of 0.0011 person-rem for the sites with plants operating throughout the year with an arithmetic mean of 1.1 person-rem. The total population dose for all sites was estimated at 75 person-rem for the 150 million people considered at risk. The site average individual dose commitment from all pathways ranged from a low of 3 {times} 10{sup {minus}7} mrem to a high of 0.02 mrem. No attempt was made in this study to determine the maximum dose commitment received by any one individual from the radionuclides released at any of the sites. However, licensee calculation of doses to the maximally exposed individual at some sites indicated values of up to approximately 100 times average individual doses (on the order of a few millirem per year).

  13. Technologies Provide High-Resolution Subsurface Imaging of Vadose Zone Contamination at Hanford Site

    Broader source: Energy.gov [DOE]

    RICHLAND, Wash. – Cold War waste disposal practices resulted in both planned and unplanned releases of large amounts of radionuclide and heavy metal contamination into the subsurface throughout the DOE complex.

  14. EA-1146: Radioactive Waste Storage at Rocky Flats Environmental Technology Site, Golden, Colorado

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of the proposal to convert buildings at the U.S. Department of Energy Rocky Flats Environmental Technology Site from their former uses to interim waste...

  15. Special Analysis of Transuranic Waste in Trench T04C at the Area 5 Radioactive Waste Management Site, Nevada Test Site, Nye County, Nevada, Revision 1

    SciTech Connect (OSTI)

    Greg Shott, Vefa Yucel, Lloyd Desotell

    2008-05-01T23:59:59.000Z

    This Special Analysis (SA) was prepared to assess the potential impact of inadvertent disposal of a limited quantity of transuranic (TRU) waste in classified Trench 4 (T04C) within the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS). The Area 5 RWMS is a low-level radioactive waste disposal site in northern Frenchman Flat on the Nevada Test Site (NTS). The Area 5 RWMS is regulated by the U.S. Department of Energy (DOE) under DOE Order 435.1 and DOE Manual (DOE M) 435.1-1. The primary objective of the SA is to evaluate if inadvertent disposal of limited quantities of TRU waste in a shallow land burial trench at the Area 5 RWMS is in compliance with the existing, approved Disposal Authorization Statement (DAS) issued under DOE M 435.1-1. In addition, supplemental analyses are performed to determine if there is reasonable assurance that the requirements of Title 40, Code of Federal Regulations (CFR), Part 191, Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level, and Transuranic Radioactive Wastes, can be met. The 40 CFR 191 analyses provide supplemental information regarding the risk to human health and the environment of leaving the TRU waste in T04C. In 1989, waste management personnel reviewing classified materials records discovered that classified materials buried in trench T04C at the Area 5 RWMS contained TRU waste. Subsequent investigations determined that a total of 102 55-gallon drums of TRU waste from Rocky Flats were buried in trench T04C in 1986. The disposal was inadvertent because unclassified records accompanying the shipment indicated that the waste was low-level. The exact location of the TRU waste in T04C was not recorded and is currently unknown. Under DOE M 435.1-1, Chapter IV, Section P.5, low-level waste disposal facilities must obtain a DAS. The DAS specifies conditions that must be met to operate within the radioactive waste management basis, consisting of a performance assessment (PA), composite analysis (CA), closure plan, monitoring plan, waste acceptance criteria, and a PA/CA maintenance plan. The DOE issued a DAS for the Area 5 RWMS in 2000. The Area 5 RWMS DAS was, in part, based on review of a CA as required under DOE M 435.1-1, Chapter IV, Section P.(3). A CA is a radiological assessment required for DOE waste disposed before 26 September 1988 and includes the radiological dose from all sources of radioactive material interacting with all radioactive waste disposed at the Area 5 RWMS. The approved Area 5 RWMS CA, which includes the inventory of TRU waste in T04C, indicates that the Area 5 RWMS waste inventory and all interacting sources of radioactive material can meet the 0.3 mSv dose constraint. The composite analysis maximum annual dose for a future resident at the Area 5 RWMS was estimated to be 0.01 mSv at 1,000 years. Therefore, the inadvertent disposal of TRU in T04C is protective of the public and the environment, and compliant with all the applicable requirements in DOE M 435.1-1 and the DAS. The U.S. Environmental Protection Agency promulgated 40 CFR 191 to establish standards for the planned disposal of spent nuclear fuel, high level, and transuranic wastes in geologic repositories. Although not required, the National Nuclear Security Administration Nevada Site Office requested a supplemental analysis to evaluate the likelihood that the inadvertent disposal of TRU waste in T04C meets the requirements of 40 CFR 191. The SA evaluates the likelihood of meeting the 40 CFR 191 containment requirements (CRs), assurance requirements, individual protection requirements (IPRs), and groundwater protection standards. The results of the SA indicate that there is a reasonable expectation of meeting all the requirements of 40 CFR 191. The conclusion of the SA is that the Area 5 RWMS with the TRU waste buried in T04C is in compliance with all requirements in DOE M 435.1-1 and the DAS. Compliance with the DAS is demonstrated by the results of the Area 5 RWMS CA. Supplemental analyses in the SA indicate there is a

  16. Population Dose Commitments Due to Radioactive Releases from Nuclear Power Plant Sites in 1977

    SciTech Connect (OSTI)

    Baker, D. A.

    1980-10-01T23:59:59.000Z

    Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1977. Fifty-year dose commitments from a one-year exposure were calculated from both liquid and atmospheric releases for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each site. This report tabulates the results of these calculations, showing the dose commitments for both liquid and airborne pathways for each age group and organ, Also included for each site is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitment from both liquid and airborne pathways ranged from a high of 220 person-rem to a low of 0.003 person-rem with an arithmetic mean of 16 person-rem. The total population dose for all sites was estimated at 700 person-rem for the 92 million people considered at risk. The average individual dose commitment from all pathways on a site basis ranged from a low of 2 x 10{sup -5} mrem to a high of 0.1 mrem. No attempt was made in this study to determine the maximum dose commitment received by any one individual from the radionuclides released at any of the sites.

  17. Population dose commitments due to radioactive releases from Nuclear-Power-Plant Sites in 1979

    SciTech Connect (OSTI)

    Baker, D.A.; Peloquin, R.A.

    1982-12-01T23:59:59.000Z

    Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1979. Fifty-year dose commitments from a one-year exposure were calculated from both liquid and atmospheric releases for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each site. This report tabulates the results of these calculations, showing the dose commitments for both liquid and airborne pathways for each age group and organ. Also included for each site is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitment from both liquid and airborne pathways ranged from a high of 1300 person-rem to a low of 0.0002 person-rem with an arithmetic mean of 38 person-rem. The total population dose for all sites was estimated at 1800 person-rem for the 94 million people considered at risk. The average individual dose commitment from all pathways on a site basis ranged from a low of 2 x 10/sup -6/ mrem to a high of 0.7 mrem. No attempt was made in this study to determine the maximum dose commitment received by any one individual from the radionuclides released at any of the sites.

  18. Dose commitments due to radioactive releases from nuclear power plant sites in 1991. Volume 13

    SciTech Connect (OSTI)

    Baker, D.A. [Pacific Northwest Lab., Richland, WA (United States)

    1995-04-01T23:59:59.000Z

    Population and individual radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1991. Fifty-year dose commitments for a one-year exposure from both liquid and atmospheric releases were calculated for four population groups (infant, child, teenager and adult) residing between 2 and 80 km from each of 72 reactor sites. This report tabulates the results of these calculations, showing the dose commitments for both water and airborne pathways for each age group and organ. Also included for each of the sites is an estimate of individual doses which are compared with 10 CFR Part 50, Appendix 1 design objectives. The total collective dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 22 person-rem to a low of 0.002 person-rem for the sites with plants in operation and producing power during the year. The arithmetic mean was 1.2 person-rem. The total population dose for all sites was estimated at 88 person-rem for the 130 million people considered at risk. The individual dose commitments estimated for all sites were below the Appendix 1 design objectives.

  19. Dose commitments due to radioactive releases from nuclear power plant sites in 1989

    SciTech Connect (OSTI)

    Baker, D.A. (Pacific Northwest Lab., Richland, WA (United States))

    1993-02-01T23:59:59.000Z

    Population and individual radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1989. Fifty-year dose commitments for a one-year exposure from both liquid and atmospheric releases were calculated for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 72 reactor sites. This report tabulates the results of these calculations, showing the dose commitments for both water and airborne pathways for each age group and organ. Also included for each of the sites is an estimate of individual doses which are compared with 10 CFR Part 50, Appendix I design objectives. The total collective dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 14 person-rem to a low of 0.005 person-rem for the sites with plants in operation and producing power during the year. The arithmetic mean was 1.2 person-rem. The total population dose for all sites was estimated at 84 person-rem for the 140 million people considered at risk. The individual dose commitments estimated for all sites were below the Appendix I design objectives.

  20. Population dose commitments due to radioactive releases from nuclear power plant sites in 1983

    SciTech Connect (OSTI)

    Baker, D.A.; Peloquin, R.A.

    1987-04-01T23:59:59.000Z

    Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1983. Fifty-year dose commitments from a one-year exposure were calculated from both liquid and atmospheric releases for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 52 sites. This report tabulates the results of these calculations, showing the dose commitments for both liquid and airborne pathways for each age group and organ. Also included for each of the sites is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 45 person-rem to a low of 0.002 person-rem for the sites with plants operating throughout the year with an arithmetic mean of 3 person-rem. The total population dose for all sites was estimated at 170 person-rem for the 100 million people considered at risk.

  1. Dose commitments due to radioactive releases from nuclear power plant sites in 1992. Volume 14

    SciTech Connect (OSTI)

    Aaberg, R.L.; Baker, D.A.

    1996-03-01T23:59:59.000Z

    Population and individual radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1992. Fifty-year dose commitments for a 1-year exposure from both liquid and atmospheric releases were calculated for four population groups (infant, child, teenager, and adult) residing between 2 and 80 km from each of 72 reactor sites. This report tabulates the results of these calculations, showing the dose commitments for both water and airborne pathways for each age group and organ. Also included for each of the sites is an estimate of individual doses, which are compared with 10 CFR Part 50, Appendix I, design objectives. The total collective dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 3.7 person-rem to a low of 0.0015 person-rem for the sites with plants in operation and producing power during the year. The arithmetic mean was 0.66 person-rem. The total population dose for all sites was estimated at 47 person-rem for the 130-million people considered at risk. The individual dose commitments estimated for all sites were below the 10 CFR 50, Appendix I, design objectives.

  2. Population dose commitments due to radioactive releases from nuclear power plant sites in 1987

    SciTech Connect (OSTI)

    Baker, D.A. (Pacific Northwest Lab., Richland, WA (USA))

    1990-08-01T23:59:59.000Z

    Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1987. Fifty-year dose commitments for a one-year exposure from both liquid and atmospheric releases were calculated for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 70 reactor sites. This report tabulates the results of these calculations, showing the dose commitments for both water and airborne pathways for each age group and organ. Also included for reach of the sites is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The site average individual dose commitment from all pathways ranged from a low of 2 {times} 10{sup {minus}6} mrem to a high of 0.009 mrem. No attempt was made in this study to determine the maximum dose commitment received by any one individual from the radionuclides released at any of the sites. However, licensee calculation of doses to the maximally exposed individual at some sites indicated values of up to approximately 100 times average individual doses (on the order of a few millirem per year). 2 refs., 2 figs., 7 tabs.

  3. EA-1599: Disposition of Radioactively Contaminated Nickel Located at the East Tennessee Technology Park, Oak Ridge, Tennessee, and the Paducah Gaseous Diffusion Plant, Paducah, Kentucky, for Controlled Radiological Applications

    Broader source: Energy.gov [DOE]

    This EA was being prepared to evaluate potential environmental impacts of a proposal to dispose of nickel scrap that is volumetrically contaminated with radioactive materials and that DOE recovered from equipment it had used in uranium enrichment. This EA is on hold.

  4. FULL-SCALE TESTING OF A CAUSTIC SIDE SOLVENT EXTRACTION SYSTEM TO REMOVE CESIUM FROM SAVANNAH RIVER SITE RADIOACTIVE WASTE

    SciTech Connect (OSTI)

    Poirier, M; Thomas Peters, T; Earl Brass, E; Stanley Brown, S; Mark Geeting, M; Lcurtis Johnson, L; Charles02 Coleman, C; S Crump, S; Mark Barnes, M; Samuel Fink, S

    2007-10-15T23:59:59.000Z

    Savannah River Site (SRS) personnel have completed construction and assembly of the Modular Caustic Side Solvent Extraction Unit (MCU) facility. Following assembly, they conducted testing to evaluate the ability of the process to remove non-radioactive cesium and to separate the aqueous and organic phases. They conducted tests at salt solution flow rates of 3.5, 6.0, and 8.5 gpm. During testing, the MCU Facility collected samples and submitted them to Savannah River National Laboratory (SRNL) personnel for analysis of cesium, Isopar{reg_sign} L, and Modifier [1-(2,2,3,3-tetrafluoropropoxy)-3-(4-sec-butylphenoxy)-2-propanol]. SRNL personnel analyzed the aqueous samples for cesium by Inductively-Coupled Plasma Mass Spectroscopy (ICP-MS) and the solvent samples for cesium using a Parr Bomb Digestion followed by ICP-MS. They analyzed aqueous samples for Isopar{reg_sign} L and Modifier by gas chromatography (GC).

  5. Population dose commitments due to radioactive releases from nuclear-power-plant sites in 1978

    SciTech Connect (OSTI)

    Peloquin, R.A.; Schwab, J.D.; Baker, D.A.

    1982-06-01T23:59:59.000Z

    Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1978. Fifty-year dose commitments from a one-year exposure were calculated from both liquid and atmospheric releases for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each site. This report tabulates the results of these calculations, showing the dose commitments for both liquid and airborne pathways for each age group and organ. Also included for each site is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitment from both liquid and airborne pathways ranged from a high of 200 person-rem to a low of 0.0004 person-rem with an arithmetic mean of 14 person-rem. The total population dose for allsites was estimated at 660 person-rem for the 93 million people considered at risk. The average individual dose commitment from all pathways on a site basis ranged from a low of 3 x 10/sup -6/ mrem to a high of 0.08 mrem. No attempt was made in this study to determine the maximum dose commitment received by any one individual from the radionuclides released at any of the sites.

  6. Population dose commitments due to radioactive releases from nuclear power plant sites in 1981. Volume 3

    SciTech Connect (OSTI)

    Baker, D.A.; Peloquin, R.A.

    1985-01-01T23:59:59.000Z

    Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1981. Fifty-year dose commitments from a one-year exposure were calculated from both liquid and atmospheric releases for four population groups (infant, child, teenager and adult) residing between 2 and 80 km from each site. This report tabulates the results of these calculations, showing the dose commitments for both liquid and airborne pathways for each age group and organ. Also included for each site is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitment from both liquid and airborne pathways from 48 sites ranged from a high of 20 person-rem to a low of 0.008 person-rem with an arithmetic mean of 3 person-rem. The total population dose for all sites was estimated at 160 person-rem for the 98 million people considered at risk.

  7. Population dose commitments due to radioactive releases from nuclear power plant sites in 1980

    SciTech Connect (OSTI)

    Baker, D.A.; Peloquin, R.A.

    1983-08-01T23:59:59.000Z

    Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1980. In addition doses derived from the shutdown reactors at the Three Mile Island site were included. Fifty-year dose commitments from a one-year exposure were calculated from both liquid and atmospheric releases for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each site. This report tabulates the results of these calculations, showing the dose commitments for both liquid and airborne pathways for each age group and organ. Also included for each site is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitment from both liquid and airborne pathways ranged from a high of 40 person-rem to a low of 0.02 person-rem with an arithmetic mean of 4 person-rem. The total population dose for all sites was estimated at 180 person-rem for the 96 million people considered at risk.

  8. Enhanced bioremediation process: A case study of effectiveness on PAH contamination in soils at a former wood-treating site

    SciTech Connect (OSTI)

    Mills, W.F. [Miltech Environmental, Inc., Tucker, GA (United States); Matens, B.L. [Dames and Moore, Baton Rouge, LA (United States); Buchalter, D.S. [EMCON, Norcross, GA (United States); Montgomery, D.N. [Georgia Dept. of Transportation, Forest Park, GA (United States). Office of Materials and Research

    1997-12-31T23:59:59.000Z

    The Enhanced Bioremediation Process (EBP) technology is an exsitu biodegradation process that utilizes bacterial and fungal inoculants to effectively oxidize and bioremediate persistent hard to degrade organics in contaminated soils. The EBP fungal inoculants produce highly reactive extracellular peroxidase enzymes that can oxidize and degrade lignin, a complex, natural polymer composed of phenylpropane units that is resistant to decay. The lignin peroxidase enzymes are highly nonspecific because of their ability to oxidize the heterogenic lignin molecule, and are capable of degrading a wide variety of complex organic compounds. Because the chemical sub-structure of lignin (1,2-aryl diethers, alkyl sidechains and connected aryl systems) resembles that of many persistent organic compounds, the EBP inoculants are very effective in biodegrading similar hazardous organic pollutants in contaminated soils. As an inadvertent by-product of these biochemical processes, the EBP organisms reduce the organic constituents to a soluble form. In a soluble form, the indigenous organisms can further degrade the contaminants. The technology is applied in such a manner as to maximize the activity of the indigenous organisms by establishing optimum growth conditions. The efficacy of the EBP technology in degrading persistent environmental pollutants has been documented at both the bench scale and pilot demonstration levels. A recently completed field pilot demonstration was conducted at a creosote contaminated site. The demonstration entailed the treatment of approximately 700 tons of soil contaminated with PAH constituents. Laboratory analyses of pre and post-treated soils indicate that total average PAH concentrations in many samples were reduced by greater than 91 percent over a two month treatment period.

  9. Quantification of in situ polycyclic aromatic hydrocarbon biodegradation at a petroleum contaminated site

    E-Print Network [OSTI]

    Conti, Enzo Mario

    1994-01-01T23:59:59.000Z

    hydrocarbons (PAHS) at a Bunker C contaminated soil. The effectiveness of EPA Seal Beach treatment with a consortium of biosurfactant bacteria in relation of a control is compared. using an EPA Seal Beach consortium of biosurfactant organisms in relation to PAH...

  10. Corrective Action Investigation Plan for Corrective Action Unit 34: Area 3 Contaminated Waste Site, Nevada Test Site, Nevada (Rev. 0, March 2001)

    SciTech Connect (OSTI)

    U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office

    2001-03-27T23:59:59.000Z

    This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 34 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 34 consists of four Corrective Action Sites (CASs). The CAU is located within the Area 3 Compound at the Nevada Test Site (NTS) in the vicinity of the Mud Plant Facility in Yucca Valley. Historically, CAS 03-09-07, Mud Pit, was used for disposal of excess mud from washing drilling equipment from 1968 to 1974, at which time it began to be used for excess mud disposal (currently inactive); CAS 03-44-01, Chromium Contamination Spill, was used to store additives used in the formulation of drilling mud from the early 1960s to the mid-1990s; CAS 03-47-02, Area 3 Mud Plant Pond, was used as a freshwater storage reservoir for the mud plant as well as supplied water for a number of activities including the mixing of mud, the rinsing and cleaning of tanks, and various washdowns from the 1960s through 1990s; and CAS 03-09-06, Mud Disposal Crater, was created in 1962 by an underground nuclear detonation (i.e., Chinchilla test) and was used to mix and store mud, dispose of receiving waste from the mud plant floor drains and excess drilling mud, and clean/flush mix tanks through the mid-1990s. Based on site history, the scope of this plan is to identify potentially contaminated ground soil at each of the four CASs and determine the quantity, nature, and extent of contaminants of potential concern (COPCs). The investigation will include systematic and biased surface and subsurface soil and mud sampling using hand-auguring and direct-push techniques; visual, video, and/or electromagnetic surveys of pipes; field screening for volatile organic compounds (VOCs) and alpha/beta-emitting radionuclides; and laboratory analysis to characterize any investigation-derived waste for disposal both on site at NTS and at off-site locations. Historical information provided by former NTS employees indicates that COPCs include VOCs, semivolatile organic compounds, Resource Conservation and Recovery Act metals, petroleum hydrocarbons, gamma-emitting radionuclides, isotopic plutonium, and strontium-90. The results of this field investigation will support a defensible evaluation of corrective action alternatives in the corrective action decision document.

  11. Radioactive Waste Radioactive Waste

    E-Print Network [OSTI]

    Slatton, Clint

    form · Separate liquid from solid · Radionuclide · Separate all but H3/C14 #12;#12;Radioactive Waste;Radioactive Waste H3/C14 solids Type B (non-incinerable) metal glass hazardous materials #12;#12;Radioactive#12;Radioactive Waste at UF Bldg 831 392-8400 #12;Radioactive Waste · Program is designed to

  12. Comparative analyses of soil contaminant levels and plant species diversity at developing and disused oil well sites in Qianjiang oilfield, China

    SciTech Connect (OSTI)

    Xiong, Z.T.; Hu, H.X.; Wang, Y.X. [Wuhan Univ., Hubei (China)] [and others] [Wuhan Univ., Hubei (China); and others

    1997-04-01T23:59:59.000Z

    Oilfield development contaminates soils and waters with crude oil, brine and heavy metals. Oil well sites are probably the most contaminated places in oilfields. During drilling and crude oil extraction from underground stores, a significant amount of oil and brine discharges into soils at oil well sites by blowouts, container spillages and pipeline ruptures. In oilfields in China, it was estimated that about 0.77 - 1.85% crude oil discharged into soils at oil well sites during oilfield development. Exposure to oil and salt contaminants could evoke toxicological effects in plants. Responses of plants to the contaminant exposure include inhibition of photosynthesis and nitrogen fixation, cessation of growth, reduced reproductive success and mortality. These harmful impacts on plants would be expected to result in remarkable loss of biodiversity. Qianjiang oilfield has been developed for about thirty-five years. Oil well sites in it have long been contaminated with oil and brine since, and plants at the well sites are rare. In the last three years however some wells have fallen into disuse. In result, a few plant species have intruded into the disuse well sites and formed new populations, and plant species diversity in these places has increased thereby. For benefit of restoration of the disuse well sites, it is interesting to know the relationships between contaminant levels and plant biodiversity. The present paper focuses the attention on comparative analyses of soil contaminations by crude oil, salt and some heavy metals and plant species diversity at developing and disuse oil well sites. 15 refs., 3 tabs.

  13. Spectroscopic and Diffraction Study of Uranium Speciation in Contaminated Vadose Zone Sediments from the Hanford Site, Washington State

    SciTech Connect (OSTI)

    Catalano, Jeffrey G.; Heald, Steve M.; Zachara, John M.; Brown Jr., G E.

    2004-05-15T23:59:59.000Z

    Contamination of vadose zone sediments under tank BX-102 at the Hanford site, Washington, resulted from the accidental release of 7-8 metric tons of uranium dissolved in caustic aqueous sludge in 1951. We have applied synchrotron-based X-ray spectroscopic and diffraction techniques to characterize the speciation of uranium in samples of these contaminated sediments. U LIII-edge X-ray absorption fine structure (XAFS) spectroscopic studies demonstrate that uranium occurs predominantly as a uranium-(VI) silicate from the uranophane group of minerals. XAFS cannot distinguish between the members of this mineral group due to the near identical local coordination environments of uranium in these phases. However, these phases differ crystallographically, and can be distinguished using X-ray diffraction (XRD) methods. As the concentration of uranium was too low for conventional XRD to detect these phases, X-ray microdiffraction (?XRD) was used to collect diffraction patterns on {approx}20 ?m diameter areas of localized high uranium concentration found using microscanning X-ray fluorescence (?SXRF). Only sodium boltwoodite, Na(UO2)(SiO3OH)?1.5H2O, was observed; no other uranophane group minerals were present. Sodium boltwoodite formation has effectively sequestered uranium in these sediments under the current geochemical and hydrologic conditions. Attempts to remediate the uranium contamination will likely face significant difficulties because of the speciation and distribution of uranium in the sediments.

  14. New Approach to Assess Volatile Contamination in Vadose Zone Provides Path Forward for Site Closure

    Broader source: Energy.gov [DOE]

    RICHLAND, Wash. and LOS ALAMOS, N.M. – Through the Deep Vadose Zone-Applied Field Research Initiative (DVZ-AFRI), scientists and engineers from Pacific Northwest National Laboratory, CH2M HILL Plateau Remediation Company, federal agencies, and the scientific community are collaborating to develop effective, science-based solutions for remediating, characterizing, monitoring, and predicting the behavior and fate of deep vadose zone contamination.

  15. Subsurface Contamination Control

    SciTech Connect (OSTI)

    Y. Yuan

    2001-12-12T23:59:59.000Z

    There are two objectives of this report, ''Subsurface Contamination Control''. The first is to provide a technical basis for recommending limiting radioactive contamination levels (LRCL) on the external surfaces of waste packages (WP) for acceptance into the subsurface repository. The second is to provide an evaluation of the magnitude of potential releases from a defective WP and the detectability of the released contents. The technical basis for deriving LRCL has been established in ''Retrieval Equipment and Strategy for Wp on Pallet'' (CRWMS M and O 2000g, 6.3.1). This report updates the derivation by incorporating the latest design information of the subsurface repository for site recommendation. The derived LRCL on the external surface of WPs, therefore, supercede that described in CRWMS M and O 2000g. The derived LRCL represent the average concentrations of contamination on the external surfaces of each WP that must not be exceeded before the WP is to be transported to the subsurface facility for emplacement. The evaluation of potential releases is necessary to control the potential contamination of the subsurface repository and to detect prematurely failed WPs. The detection of failed WPs is required in order to provide reasonable assurance that the integrity of each WP is intact prior to MGR closure. An emplaced WP may become breached due to manufacturing defects or improper weld combined with failure to detect the defect, by corrosion, or by mechanical penetration due to accidents or rockfall conditions. The breached WP may release its gaseous and volatile radionuclide content to the subsurface environment and result in contaminating the subsurface facility. The scope of this analysis is limited to radioactive contaminants resulting from breached WPs during the preclosure period of the subsurface repository. This report: (1) documents a method for deriving LRCL on the external surfaces of WP for acceptance into the subsurface repository; (2) provides a table of derived LRCL for nuclides of radiological importance; (3) Provides an as low as is reasonably achievable (ALARA) evaluation of the derived LRCL by comparing potential onsite and offsite doses to documented ALARA requirements; (4) Provides a method for estimating potential releases from a defective WP; (5) Provides an evaluation of potential radioactive releases from a defective WP that may become airborne and result in contamination of the subsurface facility; and (6) Provides a preliminary analysis of the detectability of a potential WP leak to support the design of an airborne release monitoring system.

  16. The advancement of a technique using principal component analysis for the non-intrusive depth profiling of radioactive contamination

    SciTech Connect (OSTI)

    Adams, J. C.; Joyce, M. J. [Engineering Dept., Lancaster Univ., Lancaster. LA1 4YR (United Kingdom); Mellor, M. [Createc Ltd., Derwent Mills Commercial Park, Cockermouth, Cumbria. CA13 0HT (United Kingdom)

    2011-07-01T23:59:59.000Z

    A non-intrusive technique using principal component analysis, to infer the depth of the fission fragment caesium-137, when it is buried under silica sand has been described. Using energy variances within different {gamma}-ray spectra, a complete depth model was produced for a single caesium-137 source buried under 1 mm depths ranging between 5-50 mm. This was achieved using a cadmium telluride detector and a bespoke phantom. In this paper we describe the advancement of the technique by further validating it using blind tests for applications outside of the laboratory, where not only the depth (z) but also the surface (x, y) location of {gamma}-ray emitting contamination is often poorly characterised. At present the technique has been tested at the point of maximum activity above the entrained {gamma}-ray emitting source (where the optimal x, y location is known). This is not usually practical in poorly characterized environments where the detector cannot be conveniently placed at such an optimal location to begin with and scanning at multiple points around the region of interest is often required. Using a uniform scanning time, the point of maximum intensity can be located by sampling in terms of total count rate, and converging on this optimal point of maximum intensity. (authors)

  17. Summary of Natural Resources that Potentially Influence Human Intrusion at the Area 5 Radioactive Waste Management Site, Nevada Test Site, Nye County, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2007-06-01T23:59:59.000Z

    In 1993, Raytheon Services Nevada completed a review of natural resource literature and other sources to identify potentially exploitable resources and potential future land uses near the Area 5 Radioactive Waste Management Site (RWMS) of the Nevada Test Site (NTS), Nye County, Nevada, that could lead to future inadvertent human intrusion and subsequent release of radionuclides to the accessible environment. National Security Technologies, LLC, revised the original limited-distribution document to conform to current editorial standards and U.S. Department of Energy requirements for public release. The researchers examined the potential for future development of sand, gravel, mineral, petroleum, water resources, and rural land uses, such as agriculture, grazing, and hunting. The study was part of the performance assessment for Greater Confinement Disposal boreholes. Sand and gravel are not considered exploitable site resources because the materials are common throughout the area and the quality at the Area 5 RWMS is not ideal for typical commercial uses. Site information also indicates a very low mineral potential for the area. None of the 23 mining districts in southern Nye County report occurrences of economic mineral deposits in unconsolidated alluvium. The potential for oil and natural gas is low for southern Nye County. No occurrences of coal, tar sand, or oil shale on the NTS are reported in available literature. Several potential future uses of water were considered. Agricultural irrigation is impractical due to poor soils and existing water supply regulations. Use of water for geothermal energy development is unlikely because temperatures are too low for typical commercial applications using current technology. Human consumption of water has the most potential for cause of intrusion. The economics of future water needs may create a demand for the development of deep carbonate aquifers in the region. However, the Area 5 RWMS is not an optimal location for extraction of groundwater from the deep carbonate aquifer. Grazing and hunting are unlikely to be potential causes for inadvertent human intrusion into waste areas because of vegetation characteristics and lack of significant game animal populations.

  18. Remaining Sites Verification Package for the 600-111, P-11 Critical Mass Laboratory Crib, and UPR-600-16, Fire and Contamination Spread Waste Sites, Waste Site Reclassification Form 2004-065

    SciTech Connect (OSTI)

    J. M. Capron

    2008-10-28T23:59:59.000Z

    The 600-111, P-11 Critical Mass Laboratory Crib waste site, also referred to as the P-11 Facility, included the 120 Experimental Building, the 123 Control Building, and the P-11 Crib. The facility was constructed in 1949 and was used as a laboratory for plutonium criticality studies. In accordance with this evaluation, the confirmatory and verification sampling results support a reclassification of this site to Interim Closed Out. The results of confirmatory and verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

  19. How to deal with radiologically contaminated vegetation

    SciTech Connect (OSTI)

    Wilde, E.W.; Murphy, C.E.; Lamar, R.T.; Larson, M.J.

    1996-12-31T23:59:59.000Z

    This report describes the findings from a literature review conducted as part of a Department of Energy, Office of Technology Development Biomass Remediation Task. The principal objective of this project is to develop a process or group of processes to treat radiologically contaminated vegetation in a manner that minimizes handling, processing, and treatment costs. Contaminated, woody vegetation growing on waste sites at SRS poses a problem to waste site closure technologies that are being considered for these sites. It is feared that large sections of woody vegetation (logs) can not be buried in waste sites where isolation of waste is accomplished by capping the site. Logs or large piles of woody debris have the potential of decaying and leaving voids under the cap. This could lead to cap failure and entrance of water into the waste. Large solid objects could also interfere with treatments like in situ mixing of soil with grout or other materials to encapsulate the contaminated sediments and soils in the waste sites. Optimal disposal of the wood includes considerations of volume reduction, treatment of the radioactive residue resulting from volume reduction, or confinement without volume reduction. Volume reduction consists primarily of removing the carbon, oxygen, and hydrogen in the wood, leaving an ash that would contain most of the contamination. The only contaminant that would be released by volume reduction would by small amounts of the radioactive isotope of hydrogen, tritium. The following sections will describe the waste sites at SRS which contain contaminated vegetation and are potential candidates for the technology developed under this proposal. The description will provide a context for the magnitude of the problem and the logistics of the alternative solutions that are evaluated later in the review. 76 refs.

  20. Site decommissioning management plan

    SciTech Connect (OSTI)

    Fauver, D.N.; Austin, J.H.; Johnson, T.C.; Weber, M.F.; Cardile, F.P.; Martin, D.E.; Caniano, R.J.; Kinneman, J.D.

    1993-10-01T23:59:59.000Z

    The Nuclear Regulatory Commission (NRC) staff has identified 48 sites contaminated with radioactive material that require special attention to ensure timely decommissioning. While none of these sites represent an immediate threat to public health and safety they have contamination that exceeds existing NRC criteria for unrestricted use. All of these sites require some degree of remediation, and several involve regulatory issues that must be addressed by the Commission before they can be released for unrestricted use and the applicable licenses terminated. This report contains the NRC staff`s strategy for addressing the technical, legal, and policy issues affecting the timely decommissioning of the 48 sites and describes the status of decommissioning activities at the sites.

  1. DEEP VADOSE ZONE CONTAMINATION DUE TO RELEASES FROM HANFORD SITE TANKS

    SciTech Connect (OSTI)

    JARAYSI MN

    2008-01-22T23:59:59.000Z

    CH2M HILL Hanford Group, Inc. (the Hanford Tank Farm Operations contractor) and the Department of Energy's Office of River Protection have just completed the first phase of the Hanford Single-Shell Tank RCRA Corrective Action Program. The focus of this first phase was to characterize the nature and extent of past Hanford single-shell tank releases and to characterize the resulting fate and transport of the released contaminants. Most of these plumes are below 20 meters, with some reaching groundwater (at 60 to 120 meters below ground surface [bgs]).

  2. Post-Closure Evaluation of the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada National Security Site in Support of the Site-Wide Environmental Impact Statement

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2011-04-26T23:59:59.000Z

    The post-closure performance of the Area 3 Radioactive Waste Management Site (RWMS) and Area 5 RWMS are evaluated for the Site-Wide Environmental Impact Statement using current performance assessment and composite analysis methods and models. Two alternatives with different future waste volumes and inventories are evaluated. The No Action Alternative evaluates the inventory disposed through fiscal year (FY) 2010 plus an additional 4.5E5 cubic meters (m3) (1.59E7 cubic feet [ft3]) of waste disposed at the Area 5 RWMS. The Expanded Operations Alternative evaluates the FY 2010 inventory plus an additional 1.42E6 m3 (5.03E7 ft3) of waste disposed at the Area 5 RWMS and 4.93E4 m3 (1.74E6 ft3) disposed at the Area 3 RWMS. Both the No Action and Expanded Operations Alternatives have a reasonable expectation of meeting all performance objectives of U.S. Department of Energy Order DOE O 435.1, “Radioactive Waste Management.” No significant difference between the two alternatives was found because the waste concentrations are similar. The performance assessment model assesses radiological risk for residents at the RWMS boundary where risk is more closely related to waste concentration than total waste inventory. Results for the composite analysis also indicate that the dose constraint and dose limit can be met for both alternatives.

  3. Effectiveness of in site biodegradation for the remediation of polycyclic aromatic hydrocarbons at a contaminated oil refinery, Port Arthur, Texas

    E-Print Network [OSTI]

    Moffit, Alfred Edward

    2000-01-01T23:59:59.000Z

    The effectiveness of bioremediation for the removal of polycyclic aromatic hydrocarbons (PAHs) from sediments contaminated with highly weathered petroleum was evaluated at a contaminated oil refinery. The sediments were chronically contaminated...

  4. ASSESSING EXPOSURE TO THE PUBLIC FROM LOW LEVEL RADIOACTIVE WASTE (LLW) TRANSPORTATION TO THE NEVADA TEST SITE.

    SciTech Connect (OSTI)

    Miller, J.J.; Campbell, S.; Church, B.W.; Shafer, D. S.; Gillespie, D.; Sedano, S.; Cebe, J.J.

    2003-02-27T23:59:59.000Z

    The United States (U.S.) Department of Energy (DOE) Nevada Test Site (NTS) is one of two regional sites where low-level radioactive waste (LLW) from approved DOE and U.S. DOD generators across the United States is disposed. In federal fiscal year (FY) 2002, over 57,000 cubic meters of waste was transported to and disposed at the NTS. DOE and U.S. Department of Transportation (DOT) regulations ensure that radiation exposure from truck shipments to members of the public is negligible. Nevertheless, particularly in rural communities along transportation routes in Utah and Nevada, there is perceived risk from members of the public about incremental exposure from LLW trucks, especially when ''Main Street'' and the LLW transportation route are the same. To better quantify the exposure to gamma radiation, a stationary monitoring array of four pressurized ion chambers (PICs) have been set up in a pullout just before LLW trucks reach the entrance to the NTS. The PICs are positioned at a distance of one meter from the sides of the truck trailer and at a height appropriate for the design of the trucks that will be used in FY2003 to haul LLW to the NTS. The use of four PICs (two on each side of the truck) is to minimize and to correct for non-uniformity where radiation levels from waste packages vary from side to side, and from front to back in the truck trailer. The PIC array is being calibrated by collecting readings from each PIC exposed to a known 137Cs source that was positioned at different locations on a flatbed stationed in the PIC array, along with taking secondary readings from other known sources. Continuous data collection using the PICs, with and without a truck in the array, is being used to develop background readings. In addition, acoustic sensors are positioned on each side of the PIC array to record when a large object (presumably a truck) enters the array. In FY2003, PIC surveys from as many incoming LLW trucks as possible will be made and survey data recorded automatically by dataloggers that will be periodically downloaded. Solar panels provide power for the batteries to run both the dataloggers and PICs. Truck drivers have been asked to park their truck within the PIC array for only the time it takes to complete an information log before moving on to one of two Radioactive Waste Management Sites (RWMS) on the NTS. On the log, the truck drivers record their shipment identification number, the time of day, where the waste originated, and information on the route they used to reach the NTS. This data will facilitate comparison of PIC readings with waste manifests and other waste disposal operations data collected at the RWMSs. Gamma radiation measurements collected from the PICs will be analyzed using standard health physics and statistical methods for comparison to DOT standards, but with the added benefit of obtaining an improved understanding of the variability of readings that can occur in the near vicinity of a LLW truck. The data collected will be combined with measurements of street width and other information about transportation routes through towns to develop realistic dose scenarios for citizens in Nevada and Utah towns.

  5. Improved Radiation Dosimetry/Risk Estimates to Facilitate Environmental Management of Plutonium-Contaminated Sites

    SciTech Connect (OSTI)

    Scott, Bobby R.; Tokarskaya, Zoya B.; Zhuntova, Galina V.; Osovets, Sergey V.; Syrchikov, Victor A., Belyaeva, Zinaida D.

    2007-12-14T23:59:59.000Z

    This report summarizes 4 years of research achievements in this Office of Science (BER), U.S. Department of Energy (DOE) project. The research described was conducted by scientists and supporting staff at Lovelace Respiratory Research Institute (LRRI)/Lovelace Biomedical and Environmental Research Institute (LBERI) and the Southern Urals Biophysics Institute (SUBI). All project objectives and goals were achieved. A major focus was on obtaining improved cancer risk estimates for exposure via inhalation to plutonium (Pu) isotopes in the workplace (DOE radiation workers) and environment (public exposures to Pu-contaminated soil). A major finding was that low doses and dose rates of gamma rays can significantly suppress cancer induction by alpha radiation from inhaled Pu isotopes. The suppression relates to stimulation of the body's natural defenses, including immunity against cancer cells and selective apoptosis which removes precancerous and other aberrant cells.

  6. 2008 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site, Nye County, Nevada: Review of the Performance Assessments and Composite Analyses

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2009-03-30T23:59:59.000Z

    The Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site requires an annual review to assess the adequacy of the Performance Assessments (PAs) and Composite Analyses (CAs) for each of the facilities, with the results submitted annually to U.S. Department of Energy (DOE) Headquarters. The Disposal Authorization Statements for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) also require that such reviews be made and that secondary or minor unresolved issues be tracked and addressed as part of the maintenance plan. The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) performed an annual review in fiscal year (FY) 2008 by evaluating operational factors and research results that impact the continuing validity of the PAs and CAs. This annual summary report presents data and conclusions from the FY 2008 review, and determines the adequacy of the PAs and CAs. Operational factors (e.g., waste forms and containers, facility design, and waste receipts), closure plans, monitoring results, and research and development (R&D) activities were reviewed to determine the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada Test Site relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R&D activities were reviewed to determine the adequacy of the CAs.

  7. 2009 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site, Nye County, Nevada: Review of the Performance Assessments and Composite Analysis

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2010-03-15T23:59:59.000Z

    The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office performed an annual review of the Area 3 and Area 5 Radioactive Wate Management Site (RWMS) Performance Assessments (PAs) and Composite Analyses (CAs) in fiscal year (FY) 2009. This annual summary report presents data and conclusions from the FY 2009 review, and determines the adequacy of the PAs and CAs. Operational factors (e.g., waste forms and containers, facility design, and waste receipts), closure plans, monitoring results, and research and development (R&D) activities were reviewed to determine the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada Test Site relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R&D activities were reviewed to determine the adequacy of the CAs.

  8. Corrective Action Investigation Plan for Corrective Action Unit 529: Area 25 Contaminated Materials, Nevada Test Site, Nevada, Rev. 0, Including Record of Technical Change No. 1

    SciTech Connect (OSTI)

    U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

    2003-02-26T23:59:59.000Z

    This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 529, Area 25 Contaminated Materials, Nevada Test Site (NTS), Nevada, under the Federal Facility Agreement and Consent Order. CAU 529 consists of one Corrective Action Site (25-23-17). For the purpose of this investigation, the Corrective Action Site has been divided into nine parcels based on the separate and distinct releases. A conceptual site model was developed for each parcel to address the translocation of contaminants from each release. The results of this investigation will be used to support a defensible evaluation of corrective action alternatives in the corrective action decision document.

  9. Corrective Action Decision Document/Corrective Action Plan for Corrective Action Unit 547: Miscellaneous Contaminated Waste Sites, Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Mark Krauss

    2011-09-01T23:59:59.000Z

    The purpose of this CADD/CAP is to present the corrective action alternatives (CAAs) evaluated for CAU 547, provide justification for selection of the recommended alternative, and describe the plan for implementing the selected alternative. Corrective Action Unit 547 consists of the following three corrective action sites (CASs): (1) CAS 02-37-02, Gas Sampling Assembly; (2) CAS 03-99-19, Gas Sampling Assembly; and(3) CAS 09-99-06, Gas Sampling Assembly. The gas sampling assemblies consist of inactive process piping, equipment, and instrumentation that were left in place after completion of underground safety experiments. The purpose of these safety experiments was to confirm that a nuclear explosion would not occur in the case of an accidental detonation of the high-explosive component of the device. The gas sampling assemblies allowed for the direct sampling of the gases and particulates produced by the safety experiments. Corrective Action Site 02-37-02 is located in Area 2 of the Nevada National Security Site (NNSS) and is associated with the Mullet safety experiment conducted in emplacement borehole U2ag on October 17, 1963. Corrective Action Site 03-99-19 is located in Area 3 of the NNSS and is associated with the Tejon safety experiment conducted in emplacement borehole U3cg on May 17, 1963. Corrective Action Site 09-99-06 is located in Area 9 of the NNSS and is associated with the Player safety experiment conducted in emplacement borehole U9cc on August 27, 1964. The CAU 547 CASs were investigated in accordance with the data quality objectives (DQOs) developed by representatives of the Nevada Division of Environmental Protection (NDEP) and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to determine and implement appropriate corrective actions for CAU 547. Existing radiological survey data and historical knowledge of the CASs were sufficient to meet the DQOs and evaluate CAAs without additional investigation. As a result, further investigation of the CAU 547 CASs was not required. The following CAAs were identified for the gas sampling assemblies: (1) clean closure, (2) closure in place, (3) modified closure in place, (4) no further action (with administrative controls), and (5) no further action. Based on the CAAs evaluation, the recommended corrective action for the three CASs in CAU 547 is closure in place. This corrective action will involve construction of a soil cover on top of the gas sampling assembly components and establishment of use restrictions at each site. The closure in place alternative was selected as the best and most appropriate corrective action for the CASs at CAU 547 based on the following factors: (1) Provides long-term protection of human health and the environment; (2) Minimizes short-term risk to site workers in implementing corrective action; (3) Is easily implemented using existing technology; (4) Complies with regulatory requirements; (5) Fulfills FFACO requirements for site closure; (6) Does not generate transuranic waste requiring offsite disposal; (7) Is consistent with anticipated future land use of the areas (i.e., testing and support activities); and (8) Is consistent with other NNSS site closures where contamination was left in place.

  10. Software Quality Assurance Plan for GoldSim Models Supporting the Area 3 and Area 5 Radioactive Waste Management Sites Performance Assessment Program

    SciTech Connect (OSTI)

    Gregory J. Shott, Vefa Yucel

    2007-01-03T23:59:59.000Z

    This Software Quality Assurance Plan (SQAP) applies to the development and maintenance of GoldSim models supporting the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) performance assessments (PAs) and composite analyses (CAs). Two PA models have been approved by the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) as of November 2006 for the PA maintenance work undertaken by National Security Technologies, LLC (NSTec). NNSA/NSO asked NSTec to assume the custodianship of the models for future development and maintenance. The models were initially developed by Neptune and Company (N&C).

  11. Understanding the Subsurface Reactive Transport of Transuranic Contaminants at DOE Sites

    SciTech Connect (OSTI)

    Barnett, Mark O. [Auburn University] [Auburn University; Albrecht-Schmitt, Thomas E. [University of Notre Dame] [University of Notre Dame; Saiers, James E. [Yale University] [Yale University; Shuh, David K. [Lawrence Berkeley National Laboratory] [Lawrence Berkeley National Laboratory

    2013-12-20T23:59:59.000Z

    Our primary hypothesis is that actinides can interact with surfaces in fundamentally different ways than other metals, metalloids, and oxyanions and that this fundamental difference requires new approaches to studying and modeling transuranic sorption to minerals and geomedia. This project supports a key mission of the SBR program to develop sufficient scientific understanding such that DOE sites will be able to incorporate coupled physical, chemical, and biological processes into decision making for environmental management and long-term stewardship, while also supporting DOE’s commitment to education, training, and collaboration with DOE user facilities.

  12. Health physics and public health activities at hazardous wastes sites

    SciTech Connect (OSTI)

    Charp, P.A. [Agency for Toxic Substances and Disease Registry, Atlanta, GA (United States)

    1995-12-31T23:59:59.000Z

    The Agency for Toxic Substances and Disease Registry (ATSDR) has worked with the U.S. Environmental Protection Agency (EPA) at several sites contaminated with radioactive materials. The Navajo Brown Vandever (B-V) uranium mine site near Bluewater, New Mexico, and the Austin Avenue Radiation Site (AAR) in Lansdowne, Pennsylvania were the subject of ATSDR health advisories. The sites were contamined with uranium or uranium byproducts but the identification of potential health effects and actions taken to prevent or reduce exposures were approached from different perspectives. At B-V contaminants included uranium and mine tailings, radium, and radon. Contaminants at the site and physical hazards were removed. At AAR, radium and radon were located in residential settings. Residents who might have had annual exposures greater than accepted standards or recommendations were relocated and contaminated building demolished.

  13. Life-Cycle Cost and Risk Analysis of Alternative Configurations for Shipping Low-Level Radioactive Waste to the Nevada Test Site

    SciTech Connect (OSTI)

    PM Daling; SB Ross; BM Biwer

    1999-12-17T23:59:59.000Z

    The Nevada Test Site (NTS) is a major receiver of low-level radioactive waste (LLW) for disposal. Currently, all LLW received at NTS is shipped by truck. The trucks use highway routes to NTS that pass through the Las Vegas Valley and over Hoover Dam, which is a concern of local stakeholder groups in the State of Nevada. Rail service offers the opportunity to reduce transportation risks and costs, according to the Waste Management Programmatic Environmental Impact Statement (WM-PEIS). However, NTS and some DOE LLW generator sites are not served with direct rail service so intermodal transport is under consideration. Intermodal transport involves transport via two modes, in this case truck and rail, from the generator sites to NTS. LLW shipping containers would be transferred between trucks and railcars at intermodal transfer points near the LLW generator sites, NTS, or both. An Environmental Assessment (EA)for Intermodal Transportation of Low-Level Radioactive Waste to the Nevada Test Site (referred to as the NTSIntermodal -M) has been prepared to determine whether there are environmental impacts to alterations to the current truck routing or use of intermodal facilities within the State of Nevada. However, an analysis of the potential impacts outside the State of Nevada are not addressed in the NTS Intermodal EA. This study examines the rest of the transportation network between LLW generator sites and the NTS and evaluates the costs, risks, and feasibility of integrating intermodal shipments into the LLW transportation system. This study evaluates alternative transportation system configurations for NTS approved and potential generators based on complex-wide LLW load information. Technical judgments relative to the availability of DOE LLW generators to ship from their sites by rail were developed. Public and worker risk and life-cycle cost components are quantified. The study identifies and evaluates alternative scenarios that increase the use of rail (intermodal where needed) to transport LLW from generator sites to NTS.

  14. Result Summary for the Area 5 Radioactive Waste Management Site Performance Assessment Model Version 4.110

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2011-07-20T23:59:59.000Z

    Results for Version 4.110 of the Area 5 Radioactive Waste Management Site (RWMS) performance assessment (PA) model are summarized. Version 4.110 includes the fiscal year (FY) 2010 inventory estimate, including a future inventory estimate. Version 4.110 was implemented in GoldSim 10.11(SP4). The following changes have been implemented since the last baseline model, Version 4.105: (1) Updated the inventory and disposal unit configurations with data through the end of FY 2010. (1) Implemented Federal Guidance Report 13 Supplemental CD dose conversion factors (U.S. Environmental Protection Agency, 1999). Version 4.110 PA results comply with air pathway and all-pathways annual total effective dose (TED) performance objectives (Tables 2 and 3, Figures 1 and 2). Air pathways results decrease moderately for all scenarios. The time of the maximum for the air pathway open rangeland scenario shifts from 1,000 to 100 years (y). All-pathways annual TED increases for all scenarios except the resident scenario. The maximum member of public all-pathways dose occurs at 1,000 y for the resident farmer scenario. The resident farmer dose was predominantly due to technetium-99 (Tc-99) (82 percent) and lead-210 (Pb-210) (13 percent). Pb-210 present at 1,000 y is produced predominantly by radioactive decay of uranium-234 (U-234) present at the time of disposal. All results for the postdrilling and intruder-agriculture scenarios comply with the performance objectives (Tables 4 and 5, Figures 3 and 4). The postdrilling intruder results are similar to Version 4.105 results. The intruder-agriculture results are similar to Version 4.105, except for the Pit 6 Radium Disposal Unit (RaDU). The intruder-agriculture result for the Shallow Land Burial (SLB) disposal units is a significant fraction of the performance objective and exceeds the performance objective at the 95th percentile. The intruder-agriculture dose is due predominantly to Tc-99 (75 percent) and U-238 (9.5 percent). The acute intruder scenario results comply with all performance objectives (Tables 6 and 7, Figures 5 and 6). The acute construction result for the SLB disposal units decreases significantly with this version. The maximum acute intruder dose occurs at 1,000 y for the SLB disposal units under the acute construction scenario. The acute intruder dose is caused by multiple radionuclides including U-238 (31 percent), Th-229 (28 percent), plutonium-239 (8.6 percent), U-233 (7.8 percent), and U-234 (6.7 percent). All results for radon-222 (Rn-222) flux density comply with the performance objective (Table 8, Figure 7). The mean Pit 13 RaDU flux density is close to the 0.74 Bq m{sup -2} s{sup -1} limit.

  15. Microscale Controls on the Fate of Contaminant Uranium in the Vadose Zone, Hanford Site, Washington

    SciTech Connect (OSTI)

    McKinley, James P.; Zachara, John M.; Liu, Chongxuan; Heald, Steve M.; Prenitzer, Brenda I.; Kempshall, Brian

    2006-04-15T23:59:59.000Z

    An alkaline brine containing uranyl (UO22+) leaked to the thick unsaturated zone at the Hanford Site. X-ray and electron microprobe imaging showed that the uranium was associated with a minority of clasts, specifically granitic clasts occupying less than four percent of the sediment volume. XANES analysis at micron resolution showed the uranium to be hexavalent. The uranium was precipitated in microfractures as radiating clusters of uranyl silicates, and sorbed uranium was not observed on other surfaces. Compositional determinations of the 1-3 µm precipitates were difficult, but indicated a sodium potassium uranyl silicate, likely sodium boltwoodite. Observations suggested that uranyl was removed from pore waters by diffusion and precipitation in microfractures, where dissolved silica within the granite-equilibrated solution would cause supersaturation with respect to sodium boltwoodite. This hypothesis was tested using a diffusion reaction model operating at microscale. Conditions favoring precipitation were simulated to be transient, and driven by the compositional contrast between pore and fracture space. Pore-space conditions, including alkaline pH, were eventually imposed on the microfracture environment. However, conditions favoring precipitation were prolonged within the microfracture by reaction at the silicate mineral surface to buffer pH in a solubility limiting acidic state, and to replenish dissolved silica. During this time, uranyl was additionally removed to the fracture space by diffusion from pore space. Uranyl is effectively immobilized within the microfracture environment within the presently unsaturated vadose zone.

  16. Chemical and biological methods for the analysis and remediation of environmental contaminants frequently identified at Superfund sites

    E-Print Network [OSTI]

    Wiles, Melinda Christine

    2004-11-15T23:59:59.000Z

    Substantial environmental contamination has occurred from coal tar creosote and pentachlorophenol (C5P) in wood preserving solutions. The present studies focused on the characterization and remediation of these contaminants. The first objective...

  17. EM's $500,000 Investment in Contaminant Remediation Leads to Hanford Site Strategy Providing $6.35 Million in Cost Savings

    Broader source: Energy.gov [DOE]

    Through a collaborative approach between the EM Headquarters’ Office of Groundwater and Soil Remediation, the Richland Operations Office and the Pacific Northwest National Laboratory (PNNL), investments are being leveraged and integrated in applied research and site operations to provide scientifically defensible end states for environmental remediation of volatile organic contaminants in the vadose zone.

  18. Special Analysis for the Disposal of the Neutron Products Incorporated Sealed Source Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

    SciTech Connect (OSTI)

    Shott, Gregory

    2014-08-31T23:59:59.000Z

    The purpose of this special analysis (SA) is to determine if the Neutron Products Incorporated (NPI) Sealed Sources waste stream (DRTK000000056, Revision 0) is suitable for disposal by shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS). The NPI Sealed Sources waste stream consists of 850 60Co sealed sources (Duratek [DRTK] 2013). The NPI Sealed Sources waste stream requires a special analysis (SA) because the waste stream 60Co activity concentration exceeds the Nevada National Security Site (NNSS) Waste Acceptance Criteria (WAC) Action Levels.

  19. Radioactive contamination of fish, shellfish, and waterfowl exposed to Hanford effluents: Annual summaries, 1945--1972. Hanford Environmental Dose Reconstruction Project

    SciTech Connect (OSTI)

    Hanf, R.W.; Dirkes, R.L.; Duncan, J.P.

    1992-07-01T23:59:59.000Z

    The objective of the Hanford Environmental Dose Reconstruction Project (HEDR) is to estimate the potential radiation doses received by people living within the sphere of influence of the Hanford Site. A potential critical pathway for human radiation exposure is through the consumption of waterfowl that frequent onsite waste-water ponds or through eating of fish, shellfish, and waterfowl that reside in/on the Columbia River and its tributaries downstream of the reactors. This document summarizes information on fish, shellfish, and waterfowl radiation contamination for samples collected by Hanford monitoring personnel and offsite agencies for the period 1945 to 1972. Specific information includes the types of organisms sampled, the kinds of tissues and organs analyzed, the sampling locations, and the radionuclides reported. Some tissue concentrations are also included. We anticipate that these yearly summaries will be helpful to individuals and organizations interested in evaluating aquatic pathway information for locations impacted by Hanford operations and will be useful for planning the direction of future HEDR studies.

  20. Annotated bibliography of literature relating to wind transport of plutonium-contaminated soils at the Nevada Test Site

    SciTech Connect (OSTI)

    Lancaster, N.; Bamford, R.

    1993-12-01T23:59:59.000Z

    During the period from 1954 through 1963, a number of tests were conducted on the Nevada Test Site (NTS) and Tonopah Test Range (TTR) to determine the safety of nuclear devices with respect to storage, handling, transport, and accidents. These tests were referred to as ``safety shots.`` ``Safety`` in this context meant ``safety against fission reaction.`` The safety tests were comprised of chemical high explosive detonations with components of nuclear devices. The conduct of these tests resulted in the dispersion of plutonium, and some americium over areas ranging from several tens to several hundreds of hectares. Of the various locations used for safety tests, the site referred to as ``Plutonium Valley`` was subject to a significant amount of plutonium contamination. Plutonium Valley is located in Area 11 on the eastern boundary of the NTS at an elevation of about 1036 m (3400 ft). Plutonium Valley was the location of four safety tests (A,B,C, and D) conducted during 1956. A major environmental, health, and safety concern is the potential for inhalation of Pu{sup 239,240} by humans as a result of airborne dust containing Pu particles. Thus, the wind transport of Pu{sup 239,240} particles has been the subject of considerable research. This annotated bibliography was created as a reference guide to assist in the better understanding of the environmental characteristics of Plutonium Valley, the safety tests performed there, the processes and variables involved with the wind transport of dust, and as an overview of proposed clean-up procedures.

  1. Remedial actions at the former Vitro Rare Metals plant site, Canonsburg, Washington County, Pennsylvania. Final Environmental Impact Statement. Volume I

    SciTech Connect (OSTI)

    Not Available

    1983-07-01T23:59:59.000Z

    The environmental impacts associated with remedial actions in connection with residual radioactive materials remaining at the inactive uranium processing site located in Canonsburg, Washington County, Pennsylvania are evaluated. The Canonsburg site is an 18.5-acre property that was formerly owned by the Vitro Rare Metals Company. The expanded Canonsburg site would be 30-acre property that would include the Canonsburg site (the former Vitro Rare Metals plant), seven adjacent private houses, and the former Georges Pottery property. During the period 1942 through 1957 the Vitro Manufacturing Company and its successor, the Vitro Corporation of America, processed onsite residues and ores, and government-owned ores, concentrates, and scraps to extract uranium and other rare metals. The Canonsburg site is now the Canon Industrial Park. In addition to storing the residual radioactive materials of this process at the Canonsburg site, about 12,000 tons of radioactively contaminated materials were transferred to a railroad landfill in Burrell Township, Indiana County, Pennsylvania. This Canonsburg FEIS evaluates five alternatives for removing the potential public health hazard associated with the radioactively contaminated materials. In addition to no action, these alternatives involve various combinations of stabilization of the radioactively contaminated materials in place or decontamination of the Canonsburg and Burrell sites by removing the radioactively contaminated materials to another location. In addition to the two sites mentioned, a third site located in Hanover Township, Washington County, Pennsylvania has been considered as a disposal site to which the radioactively contaminated materials presently located at either of the other two sites might be moved.

  2. Environmental proteomics reveals early microbial community responses to biostimulation at a uranium- and nitrate-contaminated site

    SciTech Connect (OSTI)

    Chourey, Karuna [ORNL] [ORNL; Nissen, Silke [ORNL] [ORNL; Vishnivetskaya, T. [University of Tennessee, Knoxville (UTK)] [University of Tennessee, Knoxville (UTK); Shah, Manesh B [ORNL] [ORNL; Pffifner, Susan [University of Tennessee, Knoxville (UTK)] [University of Tennessee, Knoxville (UTK); Hettich, Robert {Bob} L [ORNL; Loeffler, Frank E [ORNL] [ORNL

    2013-01-01T23:59:59.000Z

    High performance mass spectrometry instrumentation coupled with improved protein extraction techniques enable metaproteomics to identify active members of soil and groundwater microbial communities. Metaproteomics workflows were applied to study the initial responses (i.e., 4 days post treatment) of the indigenous aquifer microbiota to biostimulation with emulsified vegetable oil (EVO) at a uranium-contaminated site. Members of the Betaproteobacteria (i.e., Dechloromonas, Ralstonia, Rhodoferax, Polaromonas, Delftia, Chromobacterium) and Firmicutes dominated the biostimulated aquifer community. Proteome characterization revealed distinct differences in protein expression between the microbial biomass collected from groundwater influenced by biostimulation and groundwater collected up-gradient of the EVO injection points. In particular, proteins involved in ammonium assimilation, EVO degradation, and polyhydroxybutyrate (PHB) granule formation were prominent following biostimulation. Interestingly, the atypical NosZ of a Dechloromonas sp. was highly expressed suggesting active nitrous oxide (N2O) respiration. c-type cytochromes were barely detected, as was citrate synthase, a biomarker for hexavalent uranium reduction activity, suggesting that metal reduction has not commenced 4 days post EVO delivery. Environmental metaproteomics identified microbial community responses to biostimulation and elucidated active pathways demonstrating the value of this technique for complementing nucleic acid-based approaches.

  3. Environmental assessment of remedial action at the Lowman Uranium Mill Tailings Site near Lowman, Idaho. Final

    SciTech Connect (OSTI)

    Not Available

    1991-01-01T23:59:59.000Z

    This document assesses the environmental impacts of stabilization on site of the contaminated materials at the Lowman uranium mill tailings site. The Lowman site is 0.5 road mile northeast of the unincorporated village of Lowman, Idaho, and 73 road miles from Boise, Idaho. The Lowman site consists of piles of radioactive sands, an ore storage area, abandoned mill buildings, and windblown/waterborne contaminated areas. A total of 29.5 acres of land are contaminated and most of this land occurs within the 35-acre designated site boundary. The proposed action is to stabilize the tailings and other contaminated materials on the site. A radon barrier would be constructed over the consolidated residual radioactive materials and various erosion control measures would be implemented to ensure the long-term stability of the disposal cell. Radioactive constituents and other hazardous constituents were not detected in the groundwater beneath the Lowman site. The groundwater beneath the disposal cell would not become contaminated during or after remedial action so the maximum concentration limits or background concentrations for the contaminants listed in the draft EPA groundwater protection standards would be met at the point of compliance. No significant impacts were identified as a result of the proposed remedial action at the Lowman site.

  4. Medium-Sized Mammals around a Radioactive Liquid Waste Lagoon at Los Alamos National Laboratory: Uptake of Contaminants and Evaluation of Radio-Frequency Identification Technology

    SciTech Connect (OSTI)

    Leslie A. Hansen; Phil R. Fresquez; Rhonda J. Robinson; John D. Huchton; Teralene S. Foxx

    1999-11-01T23:59:59.000Z

    Use of a radioactive liquid waste lagoon by medium-sized mammals and levels of tritium, other selected radionuclides, and metals in biological tissues of the animals were documented at Technical Area 53 (TA-53) of Los Alamos National Laboratory during 1997 and 1998. Rock squirrel (Spermophilus variegates), raccoon (Procyon lotor), striped skunk (Mephitis mephitis), and bobcat (Lynx rufus) were captured at TA-53 and at a control site on the Santa Fe National Forest. Captured animals were anesthetized and marked with radio-frequency identification (RFD) tags and/or ear tags. We collected urine and hair samples for tritium and metals (aluminum, antimony, arsenic, barium, beryllium, cadmium, chromium, copper, lead, mercury, nickel, selenium, silver, and thallium) analyses, respectively. In addition, muscle and bone samples from two rock squirrels collected from each of TA-53, perimeter, and regional background sites were tested for tritium, {sup 137}Cs, {sup 90}Sr, {sup 238}Pu, {sup 239,240}Pu, {sup 241}Am, and total uranium. Animals at TA-53 were monitored entering and leaving the lagoon area using a RFID monitor to read identification numbers from the RFID tags of marked animals and a separate camera system to photograph all animals passing through the monitor. Cottontail rabbit (Sylvilagus spp.), rock squirrel, and raccoon were the species most frequently photographed going through the RFID monitor. Less than half of all marked animals in the lagoon area were detected using the lagoon. Male and female rock squirrels from the lagoon area had significantly higher tritium concentrations compared to rock squirrels from the control area. Metals tested were not significantly higher in rock squirrels from TA-53, although there was a trend toward increased levels of lead in some individuals at TA-53. Muscle and bone samples from squirrels in the lagoon area appeared to have higher levels of tritium, total uranium, and {sup 137}Cs than samples collected from perimeter and background locations. However, the committed effective dose equivalent estimated from the potential human consumption of the muscle and bone tissue from these rock squirrels did not suggest any human health risk. Indirect routes of tritium uptake, possibly through consumption of vegetation, are important for animals in the lagoon area.

  5. WM'05 Conference, February 27 March 3, 2005, Tucson, AZ WM-5278 IDENTIFYING RADIOACTIVE SOURCES AT THE DEMOLITION SITE

    E-Print Network [OSTI]

    ), in a cooperative partnership with the scrap metal industry, developed a CD ROM based training program to provide's scrap metal supply. In order to prevent this unwanted radioactive material from entering metal will be detected in scrap metal loads. Shielding of the sources by the metal scrap, location of the source within

  6. The siting record: An account of the programs of federal agencies and events that have led to the selection of a potential site for a geologic respository for high-level radioactive waste

    SciTech Connect (OSTI)

    Lomenick, T.F.

    1996-03-01T23:59:59.000Z

    This record of siting a geologic repository for high-level radioactive wastes (HLW) and spent fuel describes the many investigations that culminated on December 22, 1987 in the designation of Yucca Mountain (YM), as the site to undergo detailed geologic characterization. It recounts the important issues and events that have been instrumental in shaping the course of siting over the last three and one half decades. In this long task, which was initiated in 1954, more than 60 regions, areas, or sites involving nine different rock types have been investigated. This effort became sharply focused in 1983 with the identification of nine potentially suitable sites for the first repository. From these nine sites, five were subsequently nominated by the U.S. Department of Energy (DOE) as suitable for characterization and then, in 1986, as required by the Nuclear Waste Policy Act of 1982 (NWPA), three of these five were recommended to the President as candidates for site characterization. President Reagan approved the recommendation on May 28, 1986. DOE was preparing site characterization plans for the three candidate sites, namely Deaf Smith County, Texas; Hanford Site, Washington; and YM. As a consequence of the 1987 Amendment to the NWPA, only the latter was authorized to undergo detailed characterization. A final Site Characterization Plan for Yucca Mountain was published in 1988. Prior to 1954, there was no program for the siting of disposal facilities for high-level waste (HLW). In the 1940s and 1950s, the volume of waste, which was small and which resulted entirely from military weapons and research programs, was stored as a liquid in large steel tanks buried at geographically remote government installations principally in Washington and Tennessee.

  7. Auxiliary analyses in support of performance assessment of a hypothetical low-level waste facility: Two-phase flow and contaminant transport in unsaturated soils with application to low-level radioactive waste disposal. Volume 2

    SciTech Connect (OSTI)

    Binning, P. [Newcastle Univ., NSW (Australia); Celia, M.A.; Johnson, J.C. [Princeton Univ., NJ (United States). Dept. of Civil Engineering and Operations Research

    1995-05-01T23:59:59.000Z

    A numerical model of multiphase air-water flow and contaminant transport in the unsaturated zone is presented. The multiphase flow equations are solved using the two-pressure, mixed form of the equations with a modified Picard linearization of the equations and a finite element spatial approximation. A volatile contaminant is assumed to be transported in either phase, or in both phases simultaneously. The contaminant partitions between phases with an equilibrium distribution given by Henry`s Law or via kinetic mass transfer. The transport equations are solved using a Galerkin finite element method with reduced integration to lump the resultant matrices. The numerical model is applied to published experimental studies to examine the behavior of the air phase and associated contaminant movement under water infiltration. The model is also used to evaluate a hypothetical design for a low-level radioactive waste disposal facility. The model has been developed in both one and two dimensions; documentation and computer codes are available for the one-dimensional flow and transport model.

  8. Non-Destructive Measurements of the Characteristics of Radioactive Contamination of Near Surface Layers of Concrete and Ground with Collimated Spectrometric Detectors

    SciTech Connect (OSTI)

    Potapov, V.N.; Danilovich, A.S.; Ignatov, S.M.; Volkovich, A.G.; Ivanov, O.P.; Stepanov, V.E.; Volkov, V.G. [RRC Kurchatov Institute, 1 Kurchatov Square, Moscow 123182 (Russian Federation)

    2006-07-01T23:59:59.000Z

    The remote radiometric method for estimation of the characteristics of concrete and ground contamination by gamma nuclides was investigated. The studies were carried out for possible realization of a method with two types of spectrometric detectors: 1) scintillator + PMT and 2) scintillator + photo diode. The measurements of Cs-137 contamination were considered, as most widespread gamma-contaminant. The mathematical model of the radiometric device was developed for studying of a method, optimization of device's parameters and search of all dependences necessary for method realization. The collimated radiometer with volume of the detector 20 cm{sup 3} has the limiting sensitivity - MMA = 0.5 {mu}Ci/m{sup 2} (19 kBq/m{sup 2}) at thickness of contaminated concrete layer 5 cm. The method can be realized for measurement of contamination of concrete and ground by other gamma radiating nuclides also. (authors)

  9. Corrective Action Investigation Plan for Corrective Action Unit 168: Areas 25 and 26 Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada (Rev. 0) includes Record of Technical Change No. 1 (dated 8/28/2002), Record of Technical Change No. 2 (dated 9/23/2002), and Record of Technical Change No. 3 (dated 6/2/2004)

    SciTech Connect (OSTI)

    U.S. Department of Energy, National Nuclear Security Administration Nevada

    2001-11-21T23:59:59.000Z

    This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office's approach to collect data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit 168 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 168 consists of a group of twelve relatively diverse Corrective Action Sites (CASs 25-16-01, Construction Waste Pile; 25-16-03, MX Construction Landfill; 25-19-02, Waste Disposal Site; 25-23-02, Radioactive Storage RR Cars; 25-23-18, Radioactive Material Storage; 25-34-01, NRDS Contaminated Bunker; 25-34-02, NRDS Contaminated Bunker; CAS 25-23-13, ETL - Lab Radioactive Contamination; 25-99-16, USW G3; 26-08-01, Waste Dump/Burn Pit; 26-17-01, Pluto Waste Holding Area; 26-19-02, Contaminated Waste Dump No.2). These CASs vary in terms of the sources and nature of potential contamination. The CASs are located and/or associated wit h the following Nevada Test Site (NTS) facilities within three areas. The first eight CASs were in operation between 1958 to 1984 in Area 25 include the Engine Maintenance, Assembly, and Disassembly Facility; the Missile Experiment Salvage Yard; the Reactor Maintenance, Assembly, and Disassembly Facility; the Radioactive Materials Storage Facility; and the Treatment Test Facility Building at Test Cell A. Secondly, the three CASs located in Area 26 include the Project Pluto testing area that operated from 1961 to 1964. Lastly, the Underground Southern Nevada Well (USW) G3 (CAS 25-99-16), a groundwater monitoring well located west of the NTS on the ridgeline of Yucca Mountain, was in operation during the 1980s. Based on site history and existing characterization data obtained to support the data quality objectives process, contaminants of potential concern (COPCs) for CAU 168 are primarily radionuclide; however, the COPCs for several CASs were not defined. To address COPC uncertainty, the analytical program for most CASs will include volatile organic compounds, semivolatile organic compounds, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons, polychlorinated biphenyls, and radionuclides. Upon reviewing historical data and current site conditions, it has been determined that no further characterization is required at USW G3 (CAS 25-99-16) to select the appropriate corrective action. A cesium-137 source was encased in cement within the vadous zone during the drilling of the well (CAS 25-99-16). A corrective action of closure in place with a land-use restriction for drilling near USW G3 is appropriate. This corrective action will be documented in the Corrective Action Decision Document (CADD) for CAU 168. The results of the remaining field investigation will support a defensible evaluation of corrective action alternatives for the other CASs within CAU 168 in this CADD.

  10. Corrective Action Investigation Plan for Corrective Action Unit 166: Storage Yards and Contaminated Materials, Nevada Test Site, Nevada, Rev. No.: 0

    SciTech Connect (OSTI)

    David Strand

    2006-06-01T23:59:59.000Z

    Corrective Action Unit 166 is located in Areas 2, 3, 5, and 18 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit (CAU) 166 is comprised of the seven Corrective Action Sites (CASs) listed below: (1) 02-42-01, Cond. Release Storage Yd - North; (2) 02-42-02, Cond. Release Storage Yd - South; (3) 02-99-10, D-38 Storage Area; (4) 03-42-01, Conditional Release Storage Yard; (5) 05-19-02, Contaminated Soil and Drum; (6) 18-01-01, Aboveground Storage Tank; and (7) 18-99-03, Wax Piles/Oil Stain. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation (CAI) before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on February 28, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 166. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the CAI for CAU 166 includes the following activities: (1) Move surface debris and/or materials, as needed, to facilitate sampling. (2) Conduct radiological surveys. (3) Perform field screening. (4) Collect and submit environmental samples for laboratory analysis to determine if contaminants of concern are present. (5) If contaminants of concern are present, collect additional step-out samples to define the extent of the contamination. (6) Collect samples of investigation-derived waste, as needed, for waste management and minimization purposes. This Corrective Action Investigation Plan has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Under the ''Federal Facility Agreement and Consent Order'', this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection, and field work will commence following approval.

  11. Special Analysis for the Disposal of the Idaho National Laboratory Unirradiated Light Water Breeder Reactor Rods and Pellets Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

    SciTech Connect (OSTI)

    Shott, Gregory [NSTec

    2014-08-31T23:59:59.000Z

    The purpose of this special analysis (SA) is to determine if the Idaho National Laboratory (INL) Unirradiated Light Water Breeder Reactor (LWBR) Rods and Pellets waste stream (INEL103597TR2, Revision 2) is suitable for disposal by shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS). The INL Unirradiated LWBR Rods and Pellets waste stream consists of 24 containers with unirradiated fabricated rods and pellets composed of uranium oxide (UO2) and thorium oxide (ThO2) fuel in zirconium cladding. The INL Unirradiated LWBR Rods and Pellets waste stream requires an SA because the 229Th, 230Th, 232U, 233U, and 234U activity concentrations exceed the Nevada National Security Site (NNSS) Waste Acceptance Criteria (WAC) Action Levels.

  12. Feasibility Study of Biopower in East Helena, Montana. A Study Prepared in Partnership with the Environmental Protection Agency for the RE-Powering America's Land Initiative: Siting Renewable Energy on Potentially Contaminated Land and Mine Sites

    SciTech Connect (OSTI)

    Moriarty, K.

    2013-02-01T23:59:59.000Z

    The U.S. Environmental Protection Agency (EPA) developed the RE-Powering America's Land initiative to reuse contaminated sites for renewable energy generation when aligned with the community's vision for the site. The former American Smelting and Refining Company (Asarco) smelter in East Helena, Montana, was selected for a feasibility study under the initiative. Biomass was chosen as the renewable energy resource based on the wood products industry in the area. Biopower was selected as the technology based on Montana's renewable portfolio standard (RPS) requiring utilities to purchase renewable power.

  13. Feasibility Study of Anaerobic Digestion of Food Waste in St. Bernard, Louisiana. A Study Prepared in Partnership with the Environmental Protection Agency for the RE-Powering America's Land Initiative: Siting Renewable Energy on Potentially Contaminated Land and Mine Sites

    SciTech Connect (OSTI)

    Moriarty, K.

    2013-01-01T23:59:59.000Z

    The U.S. Environmental Protection Agency (EPA) developed the RE-Powering America's Land initiative to re-use contaminated sites for renewable energy generation when aligned with the community's vision for the site. The former Kaiser Aluminum Landfill in St. Bernard Parish, Louisiana, was selected for a feasibility study under the program. Preliminary work focused on selecting a biomass feedstock. Discussions with area experts, universities, and the project team identified food wastes as the feedstock and anaerobic digestion (AD) as the technology.

  14. Active airborne contamination control using electrophoresis

    SciTech Connect (OSTI)

    Veatch, B.D.

    1994-06-01T23:59:59.000Z

    In spite of our best efforts, radioactive airborne contamination continues to be a formidable problem at many of the Department of Energy (DOE) weapons complex sites. For workers that must enter areas with high levels of airborne contamination, personnel protective equipment (PPE) can become highly restrictive, greatly diminishing productivity. Rather than require even more restrictive PPE for personnel in some situations, the Rocky Flats Plant (RFP) is actively researching and developing methods to aggressively combat airborne contamination hazards using electrophoretic technology. With appropriate equipment, airborne particulates can be effectively removed and collected for disposal in one simple process. The equipment needed to implement electrophoresis is relatively inexpensive, highly reliable, and very compact. Once airborne contamination levels are reduced, less PPE is required and a significant cost savings may be realized through decreased waste and maximized productivity. Preliminary ``cold,`` or non-radioactive, testing results at the RFP have shown the technology to be effective on a reasonable scale, with several potential benefits and an abundance of applications.

  15. Survey of Potential Hanford Site Contaminants in the Upper Sediment for the Reservoirs at McNary, John Day, The Dalles, and Bonneville Dams, 2003

    SciTech Connect (OSTI)

    Patton, Gregory W.; Priddy, M; Yokel, Jerel W.; Delistraty, Damon A.; Stoops, Thomas M.

    2005-02-01T23:59:59.000Z

    This report presents the results from a multi-agency cooperative environmental surveillance study. of the study looked at sediment from the pools upstream from dams on the Columbia River that are downstream from Hanford Site operations. The radiological and chemical conditions existing in the upper-level sediment found in the pools upstream from McNary Dam, John Day Dam, The Dalles Lock and Dam, and Bonneville Dam were evaluated. This study also evaluated beach sediment where available. Water samples were collected at McNary Dam to further evaluate potential Hanford contaminants in the lower Columbia River. Samples were analyzed for radionuclides, chemicals, and physical parameters. Results from this study were compared to background values from sediment and water samples collect from the pool upstream of Priest Rapids Dam (upstream of the Hanford Site) by the Hanford Site Surface Environmental Surveillance Project.

  16. Seminar on Radioactive Waste, Modelling and Dose Assessment -Ris National Laboratory 2 -6 December 2002 Assessment of doses and environmental contamination

    E-Print Network [OSTI]

    December 2002 Assessment of doses and environmental contamination from decommissioning of the nuclear on the environment dur- ing the decommissioning of the nuclear facilities at Risø and the assessed consequences facilities at Risø Per Hedemann Jensen Section of Applied Health Physics Risø Department of Decommissioning

  17. Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Slick Rock, Colorado. Remedial action selection report, Appendix B

    SciTech Connect (OSTI)

    Not Available

    1993-07-01T23:59:59.000Z

    The Slick Rock uranium mill tailings sites are located near the small town of Slick Rock, in San Miguel County, Colorado. There are two designated UMTRA sites at Slick Rock, the Union Carbide (UC) site and the North Continent (NC) site. Both sites are adjacent to the Dolores River. The UC site is approximately 1 mile (mi) [2 kilometers (km)] downstream of the NC site. Contaminated materials cover an estimated 55 acres (ac) [22 hectares (ha)] at the UC site and 12 ac (4.9 ha) at the NC site. The sites contain former mill building concrete foundations, tailings piles, demolition debris, and areas contaminated by windblown and waterborne radioactive materials. The total estimated volume of contaminated materials is approximately 620, 000 cubic yards (yd{sup 3}) [470,000 cubic meters (m{sup 3})]. In addition to the contamination at the two processing site areas, four vicinity properties were contaminated. Contamination associated with the UC and NC sites has leached into groundwater.

  18. Restoration of areas disturbed by site studies for a mined commercial radioactive waste repository: The Basalt Waste Isolation Project (BWIP)

    SciTech Connect (OSTI)

    Brandt, C.A.; Rickard, W.H. Jr.; Biehert, R.W.; Newell, R.L.; Page, T.L.

    1989-01-01T23:59:59.000Z

    The Basalt Waste Isolation Project (BWIP) was undertaken to environmentally characterize a portion of the US Department of Energy's Hanford Site in Washington State as a potential host for the nation's first mined commercial nuclear waste repository. Studies were terminated by Congress in 1987. Between 1976 and 1987, 72 areas located across the Hanford Site were disturbed by the BWIP. These areas include borehole pads, a large Exploratory Shaft Facility, and the Near Surface Test Facility. Most boreholes were cleared of vegetation, leveled, and stabilized with a thick layer of compacted pit-run gravel and sand. The Near Surface Test Facility consists of three mined adits, a rock-spoils bench, and numerous support facilities. Restoration began in 1988 with the objective of returning sites to pre-existing conditions using native species. The Hanford Site retains some of the last remnants of the shrub-steppe ecosystem in Washington. The primary constraints to restoring native vegetation at Hanford are low precipitation and the presence of cheatgrass, an extremely capable alien competitor. 5 figs.

  19. Faecal contamination of watercourses from farm waste disposal for three sites in the UK with contrasting soil

    E-Print Network [OSTI]

    Owens, Philip

    potential risk of FIO contamination. Quality of samples was compared with FIO standards for bathing water organic manures were being applied, which were considered to be of high potential risk of causing to seasonal desiccation cracking within the soil, and to intense rainfall events. Watercourse FIO

  20. Salmon Site Remedial Investigation Report, Appendix C

    SciTech Connect (OSTI)

    US DOE /NV

    1999-09-01T23:59:59.000Z

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the installation of a water supply system that will provide potable water to the site and residence in the proximity to the site; (2) continued maintenance of surface institutional controls and subsurface restrictions; and (3) continue to implement the long-term hydrologic monitoring program. The Salmon Site will be relinquished the State of Mississippi as mandated by Public Law 104-201-September 23, 1996, to be used as a demonstration forest/wildlife refuge. Should the land use change in the future and/or monitoring information indicates a change in the site conditions, the DOE will reassess the risk impacts to human health and the environment.

  1. Salmon Site Remediation Investigation Report, Appendix A

    SciTech Connect (OSTI)

    US DOE /Nevada Operations Office

    1999-09-01T23:59:59.000Z

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the installation of a water supply system that will provide potable water to the site and residence in the proximity to the site; (2) continued maintenance of surface institutional controls and subsurface restrictions; and (3) continue to implement the long-term hydrologic monitoring program. The Salmon Site will be relinquished the State of Mississippi as mandated by Public Law 104-201-September 23, 1996, to be used as a demonstration forest/wildlife refuge. Should the land use change in the future and/or monitoring information indicates a change in the site conditions, the DOE will reassess the risk impacts to human health and the environment.

  2. Salmon Site Remedial Investigation Report, Appendix D

    SciTech Connect (OSTI)

    US DOE /NV

    1999-09-01T23:59:59.000Z

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the installation of a water supply system that will provide potable water to the site and residence in the proximity to the site; (2) continued maintenance of surface institutional controls and subsurface restrictions; and (3) continue to implement the long-term hydrologic monitoring program. The Salmon Site will be relinquished the State of Mississippi as mandated by Public Law 104-201-September 23, 1996, to be used as a demonstration forest/wildlife refuge. Should the land use change in the future and/or monitoring information indicates a change in the site conditions, the DOE will reassess the risk impacts to human health and the environment.

  3. Salmon Site Remedial Investigation Report, Exhibit 5

    SciTech Connect (OSTI)

    USDOE /NV

    1999-09-01T23:59:59.000Z

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the installation of a water supply system that will provide potable water to the site and residence in the proximity to the site; (2) continued maintenance of surface institutional controls and subsurface restrictions; and (3) continue to implement the long-term hydrologic monitoring program. The Salmon Site will be relinquished the State of Mississippi as mandated by Public Law 104-201-September 23, 1996, to be used as a demonstration forest/wildlife refuge. Should the land use change in the future and/or monitoring information indicates a change in the site conditions, the DOE will reassess the risk impacts to human health and the environment.

  4. Salmon Site Remedial Investigation Report, Exhibit 4

    SciTech Connect (OSTI)

    USDOE /NV

    1999-09-01T23:59:59.000Z

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the installation of a water supply system that will provide potable water to the site and residence in the proximity to the site; (2) continued maintenance of surface institutional controls and subsurface restrictions; and (3) continue to implement the long-term hydrologic monitoring program. The Salmon Site will be relinquished the State of Mississippi as mandated by Public Law 104-201-September 23, 1996, to be used as a demonstration forest/wildlife refuge. Should the land use change in the future and/or monitoring information indicates a change in the site conditions, the DOE will reassess the risk impacts to human health and the environment.

  5. Salmon Site Remedial Investigation Report, Exhibit 3

    SciTech Connect (OSTI)

    USDOE /NV

    1999-09-01T23:59:59.000Z

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the installation of a water supply system that will provide potable water to the site and residence in the proximity to the site; (2) continued maintenance of surface institutional controls and subsurface restrictions; and (3) continue to implement the long-term hydrologic monitoring program. The Salmon Site will be relinquished the State of Mississippi as mandated by Public Law 104-201-September 23, 1996, to be used as a demonstration forest/wildlife refuge. Should the land use change in the future and/or monitoring information indicates a change in the site conditions, the DOE will reassess the risk impacts to human health and the environment.

  6. Salmon Site Remedial Investigation Report, Exhibit 2

    SciTech Connect (OSTI)

    USDOE NV

    1999-09-01T23:59:59.000Z

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the installation of a water supply system that will provide potable water to the site and residence in the proximity to the site; (2) continued maintenance of surface institutional controls and subsurface restrictions; and (3) continue to implement the long-term hydrologic monitoring program. The Salmon Site will be relinquished the State of Mississippi as mandated by Public Law 104-201-September 23, 1996, to be used as a demonstration forest/wildlife refuge. Should the land use change in the future and/or monitoring information indicates a change in the site conditions, the DOE will reassess the risk impacts to human health and the environment.

  7. Salmon Site Remedial Investigation Report, Exhibit 1

    SciTech Connect (OSTI)

    USDOE /NV

    1999-09-01T23:59:59.000Z

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the installation of a water supply system that will provide potable water to the site and residence in the proximity to the site; (2) continued maintenance of surface institutional controls and subsurface restrictions; and (3) continue to implement the long-term hydrologic monitoring program. The Salmon Site will be relinquished the State of Mississippi as mandated by Public Law 104-201-September 23, 1996, to be used as a demonstration forest/wildlife refuge. Should the land use change in the future and/or monitoring information indicates a change in the site conditions, the DOE will reassess the risk impacts to human health and the environment.

  8. Salmon Site Remedial Investigation Report, Main Body

    SciTech Connect (OSTI)

    US DOE /NV

    1999-09-01T23:59:59.000Z

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the installation of a water supply system that will provide potable water to the site and residence in the proximity to the site; (2) continued maintenance of surface institutional controls and subsurface restrictions; and (3) continue to implement the long-term hydrologic monitoring program. The Salmon Site will be relinquished the State of Mississippi as mandated by Public Law 104-201-September 23, 1996, to be used as a demonstration forest/wildlife refuge. Should the land use change in the future and/or monitoring information indicates a change in the site conditions, the DOE will reassess the risk impacts to human health and the environment.

  9. The performance of blended conventional and novel binders in the in-situ stabilisation/solidification of a contaminated site soil

    E-Print Network [OSTI]

    Wang, Fei; Wang, Hailing; Jin, Fei; Al-Tabbaa, Abir

    2014-11-06T23:59:59.000Z

    RESPONSE: Thank you for your comment. [9, 43] was added in page 3 line 49. [44] was added in page 3 line 54. “[43] D. G. Snelsona, S. Wilda, M. O'Farrellb, Heat of hydration of Portland Cement–Metakaolin–Fly ash (PC–MK–PFA) blends, Cem. Concr. Res. 38... ] . In -situ S/S has three main advantages: 1) it is well established as efficient and cost-effective; 2) it produces no spoil and, hence no landfill waste and 3) there is no risk to site workers of exposure to contamination. Portland cement (PC) and lime...

  10. Public Invited to Comment on Draft Environmental Assessment for Replacement Capability for Disposal of Remote-Handled Low Level Radioactive Waste Generated at the U.S. Department of Energy’s Idaho Site

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy invites the public to read and comment on a draft environmental assessment it has prepared, for a proposal to provide a replacement capability for continued disposal of remote-handled low-level radioactive waste that is generated at the Idaho National Laboratory site.

  11. Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Cleanup Document Date: 10162009 Keywords: recovery, waste site, BC Control, soil, contamination Area: BC Control Area Description: Using Recovery Act funding, contractors are...

  12. Contamination analysis unit

    DOE Patents [OSTI]

    Gregg, Hugh R. (Livermore, CA); Meltzer, Michael P. (Livermore, CA)

    1996-01-01T23:59:59.000Z

    The portable Contamination Analysis Unit (CAU) measures trace quantifies of surface contamination in real time. The detector head of the portable contamination analysis unit has an opening with an O-ring seal, one or more vacuum valves and a small mass spectrometer. With the valve closed, the mass spectrometer is evacuated with one or more pumps. The O-ring seal is placed against a surface to be tested and the vacuum valve is opened. Data is collected from the mass spectrometer and a portable computer provides contamination analysis. The CAU can be used to decontaminate and decommission hazardous and radioactive surface by measuring residual hazardous surface contamination, such as tritium and trace organics It provides surface contamination data for research and development applications as well as real-time process control feedback for industrial cleaning operations and can be used to determine the readiness of a surface to accept bonding or coatings.

  13. Contamination analysis unit

    DOE Patents [OSTI]

    Gregg, H.R.; Meltzer, M.P.

    1996-05-28T23:59:59.000Z

    The portable Contamination Analysis Unit (CAU) measures trace quantities of surface contamination in real time. The detector head of the portable contamination analysis unit has an opening with an O-ring seal, one or more vacuum valves and a small mass spectrometer. With the valve closed, the mass spectrometer is evacuated with one or more pumps. The O-ring seal is placed against a surface to be tested and the vacuum valve is opened. Data is collected from the mass spectrometer and a portable computer provides contamination analysis. The CAU can be used to decontaminate and decommission hazardous and radioactive surfaces by measuring residual hazardous surface contamination, such as tritium and trace organics. It provides surface contamination data for research and development applications as well as real-time process control feedback for industrial cleaning operations and can be used to determine the readiness of a surface to accept bonding or coatings. 1 fig.

  14. Radiation Awareness TrainingRadiation Awareness Training Radioactive Material &Radioactive Material &

    E-Print Network [OSTI]

    Sherrill, David

    · Check all incoming radioactive packages for contamination · Survey all radioactive materials labs) · Sealed sources ­ Nickel-63 (Gas chromatograph) ­ Cesium-137 (Liquid Scintillation Counter) ­ Neutron · CONTAMINATION CONTROL IS THE KEY · Should not leave room until surveyed by ORS #12;Protective Measures ·· Time

  15. alpine site jungfraujoch: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    commercial setting. Contaminants: Contaminants: Vinyl Chloride 166 Clinical Research Site Management Engineering Websites Summary: Clinical Research Site Management Dan...

  16. allosteric site: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    commercial setting. Contaminants: Contaminants: Vinyl Chloride 69 Clinical Research Site Management Engineering Websites Summary: Clinical Research Site Management Dan...

  17. affect redd site: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    commercial setting. Contaminants: Contaminants: Vinyl Chloride 62 Clinical Research Site Management Engineering Websites Summary: Clinical Research Site Management Dan...

  18. agnostic splice site: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    commercial setting. Contaminants: Contaminants: Vinyl Chloride 279 Clinical Research Site Management Engineering Websites Summary: Clinical Research Site Management Dan...

  19. agent dumping site: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    commercial setting. Contaminants: Contaminants: Vinyl Chloride 357 Clinical Research Site Management Engineering Websites Summary: Clinical Research Site Management Dan...

  20. Development of site-specific soil cleanup criteria: New Brunswick Laboratory, New Jersey site

    SciTech Connect (OSTI)

    Veluri, V.R.; Moe, H.J.; Robinet, M.J.; Wynveen, R.A.

    1983-03-01T23:59:59.000Z

    The potential human exposure which results from the residual soil radioactivity at a decommissioned site is a prime concern during D and D projects. To estimate this exposure, a pathway analysis approach is often used to arrive at the residual soil radioactivity criteria. The development of such a criteria for the decommissioning of the New Brunswick Laboratory, New Jersey site is discussed. Contamination on this site was spotty and located in small soil pockets spread throughout the site area. Less than 1% of the relevant site area was contaminated. The major contaminants encountered at the site were /sup 239/Pu, /sup 241/Am, normal and natural uranium, and natural thorium. During the development of the pathway analysis to determine the site cleanup criteria, corrections for the inhomogeneity of the contamination were made. These correction factors and their effect upon the relevant pathway parameters are presented. Major pathways by which radioactive material may reach an individual are identified and patterns of use are specified (scenario). Each pathway is modeled to estimate the transfer parameters along the given pathway, such as soil to air to man, etc. The transfer parameters are then combined with dose rate conversion factors (ICRP 30 methodology) to obtain soil concentration to dose rate conversion factors (pCi/g/mrem/yr). For an appropriate choice of annual dose equivalent rate, one can then arrive at a value for the residual soil concentration. Pathway modeling, transfer parameters, and dose rate factors for the three major pathways; inhalation, ingestion and external exposure, which are important for the NBL site, are discussed.

  1. Addendum to the Corrective Action Decision Document/Closure Report for Corrective Action Unit 529: Area 25 Contaminated Materials, Nevada Test Site, Nevada, Revision 1

    SciTech Connect (OSTI)

    Krauss, Mark J

    2013-10-01T23:59:59.000Z

    This document constitutes an addendum to the Corrective Action Decision Document/Closure Report for Corrective Action Unit 529: Area 25 Contaminated Materials, Nevada Test Site, Nevada as described in the document Recommendations and Justifications To Remove Use Restrictions Established under the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office Federal Facility Agreement and Consent Order dated September 2013. The Use Restriction (UR) Removal document was approved by the Nevada Division of Environmental Protection on October 16, 2013. The approval of the UR Removal document constituted approval of each of the recommended UR removals. In conformance with the UR Removal document, this addendum consists of: This page that refers the reader to the UR Removal document for additional information The cover, title, and signature pages of the UR Removal document The NDEP approval letter The corresponding section of the UR Removal document This addendum provides the documentation justifying the cancellation of the UR for CAS 25-23-17, Contaminated Wash (Parcel H). This UR was established as part of FFACO corrective actions and was based on the presence of total petroleum hydrocarbon diesel-range organics contamination at concentrations greater than the NDEP action level at the time of the initial investigation.

  2. Method for decontamination of radioactive metal surfaces

    DOE Patents [OSTI]

    Bray, L.A.

    1996-08-13T23:59:59.000Z

    Disclosed is a method for removing radioactive contaminants from metal surfaces by applying steam containing an inorganic acid and cerium IV. Cerium IV is applied to contaminated metal surfaces by introducing cerium IV in solution into a steam spray directed at contaminated metal surfaces. Cerium IV solution is converted to an essentially atomized or vapor phase by the steam.

  3. Method for decontamination of radioactive metal surfaces

    DOE Patents [OSTI]

    Bray, Lane A. (Richland, WA)

    1996-01-01T23:59:59.000Z

    Disclosed is a method for removing radioactive contaminants from metal surfaces by applying steam containing an inorganic acid and cerium IV. Cerium IV is applied to contaminated metal surfaces by introducing cerium IV in solution into a steam spray directed at contaminated metal surfaces. Cerium IV solution is converted to an essentially atomized or vapor phase by the steam.

  4. Environmental assessment of remedial action at the Slick Rock uranium mill tailings sites, Slick Rock, Colorado. Revision 1

    SciTech Connect (OSTI)

    Not Available

    1994-09-01T23:59:59.000Z

    The Uranium Mill Tailings Radiation Control Act of 1978 (42 USC {section}7901 et seq.), hereafter referred to as the UMTRCA, authorized the US Department of Energy (DOE) to clean up two uranium mill tailings processing sites near Slick Rock, Colorado, in San Miquel County. Contaminated materials cover an estimated 63 acres of the Union Carbide (UC) processing site and 15 ac of the North Continent (NC) processing site. The sites are within 1 mile of each other and are adjacent to the Dolores River. The sites contain concrete foundations of mill buildings, tailings piles, and areas contaminated by windblown and waterborne radioactive tailings materials. The total estimated volume of contaminated materials is approximately 621,300 cubic yards (yd{sup 3}). In addition to the contamination in the two processing site areas, four VPs were found to contain contamination. As a result of the tailings being exposed to the environment, contamination associated with the UC and NC sites has leached into shallow ground water. Surface water has not been affected. The closest residence is approximately 0.3 air mi from either site. The proposed action is to remediate the UC and NC sites by removing all contaminated materials within the designing site boundaries or otherwise associated with the sites, and relocating them to, and stabilizing them at, a location approximately 5 road mi northeast of the sites on land administered by the Bureau of Land Management (BLM).

  5. Action plan for responses to abnormal conditions in Hanford Site radioactive waste tanks with high organic content. Revision 1

    SciTech Connect (OSTI)

    Fowler, K.D.

    1993-07-01T23:59:59.000Z

    This action plan describes the criteria and the organizational responsibilities required for ensuring that waste storage tanks with high organic contents are maintained in a safe condition at the Hanford Site. In addition, response actions are outlined for (1) prevention or mitigation of excessive temperatures; or (2) a material release from any waste tank with high organic content. Other response actions may be defined by Westinghouse Hanford Company Systems Engineering if a waste tank parameter goes out of specification. Trend analysis indicates the waste tank parameters have seasonal variations, but are otherwise stable.

  6. Volume reduction/solidification of liquid radioactive waste using bitumen at Ontario Hydro`s Bruce Nuclear Generating Station `A`

    SciTech Connect (OSTI)

    Day, J.E.; Baker, R.L.

    1995-05-01T23:59:59.000Z

    Ontario Hydro at the Bruce Nuclear Generating Station `A` has undertaken a program to render the station`s liquid radioactive waste suitable for discharge to Lake Huron by removing sufficient radiological and chemical contaminants to satisfy regulatory requirements for emissions. The system will remove radionuclide and chemical contaminants from five different plant waste streams. The contaminants will be immobilized and stored at on-site radioactive waste storage facilities and the purified streams will be discharged. The discharge targets established by Ontario Hydro are set well below the limits established by the Ontario Ministry of Environment (MOE) and are based on the Best Available Technology Economically Achievable Approach (B.A.T.E.A.). ADTECHS Corporation has been selected by Ontario Hydro to provide volume reduction/solidification technology for one of the five waste streams. The system will dry and immobilize the contaminants from a liquid waste stream in emulsified asphalt using thin film evaporation technology.

  7. Modified Hazard Ranking System/Hazard Ranking System for sites with mixed radioactive and hazardous wastes: Software documentation

    SciTech Connect (OSTI)

    Stenner, R.D.; Peloquin, R.A.; Hawley, K.A.

    1986-11-01T23:59:59.000Z

    The mHRS/HRS software package was developed by the Pacific Northwest Laboratory (PNL) under contract with the Department of Energy (DOE) to provide a uniform method for DOE facilities to use in performing their Conservation Environmental Response Compensation and Liability Act (CERCLA) Phase I Modified Hazard Ranking System or Hazard Ranking System evaluations. The program is designed to remove the tedium and potential for error associated with the performing of hand calculations and the interpreting of information on tables and in reference books when performing an evaluation. The software package is designed to operate on a microcomputer (IBM PC, PC/XT, or PC/AT, or a compatible system) using either a dual floppy disk drive or a hard disk storage system. It is written in the dBASE III language and operates using the dBASE III system. Although the mHRS/HRS software package was developed for use at DOE facilities, it has direct applicability to the performing of CERCLA Phase I evaluations for any facility contaminated by hazardous waste. The software can perform evaluations using either the modified hazard ranking system methodology developed by DOE/PNL, the hazard ranking system methodology developed by EPA/MITRE Corp., or a combination of the two. This document is a companion manual to the mHRS/HRS user manual. It is intended for the programmer who must maintain the software package and for those interested in the computer implementation. This manual documents the system logic, computer programs, and data files that comprise the package. Hardware and software implementation requirements are discussed. In addition, hand calculations of three sample situations (problems) with associated computer runs used for the verification of program calculations are included.

  8. Three-dimensional analysis of future groundwater flow conditions and contaminant plume transport in the Hanford Site unconfined aquifer system: FY 1996 and 1997 status report

    SciTech Connect (OSTI)

    Cole, C.R.; Wurstner, S.K.; Williams, M.D.; Thorne, P.D.; Bergeron, M.P.

    1997-12-01T23:59:59.000Z

    A three-dimensional numerical model of groundwater flow and transport, based on the Coupled Fluid Energy, and Solute Transport (CFEST) code, was developed for the Hanford Site to support the Hanford Groundwater Project (HGWP), managed by Pacific Northwest National Laboratory. The model was developed to increase the understanding and better forecast the migration of several contaminant plumes being monitored by the HGWP, and to support the Hanford Site Composite Analysis for low-level waste disposal in the 200-Area Plateau. Recent modeling efforts have focused on continued refinement of an initial version of the three-dimensional model developed in 1995 and its application to simulate future transport of selected contaminant plumes in the aquifer system. This version of the model was updated using a more current version of the CFEST code called CFEST96. Prior to conducting simulations of contaminant transport with the three-dimensional model, a previous steady-state, two-dimensional model of the unconfined aquifer system was recalibrated to 1979 water-table conditions with a statistical inverse method implemented in the CFEST-INV computer code. The results of the recalibration were used to refine the three-dimensional conceptual model and to calibrate it with a conceptualization that preserves the two-dimensional hydraulic properties and knowledge of the aquifer`s three-dimensional properties for the same 1979 water-table conditions. The transient behavior of the three-dimensional flow model was also calibrated by adjusting model storage properties (specific yield) until transient water-table predictions approximated observed water-table elevations between 1979 and 1996.

  9. Process Knowledge Characterization of Radioactive Waste at the Classified Waste Landfill Remediation Project Sandia National Laboratories, Albuquerque, New Mexico

    SciTech Connect (OSTI)

    DOTSON,PATRICK WELLS; GALLOWAY,ROBERT B.; JOHNSON JR,CARL EDWARD

    1999-11-03T23:59:59.000Z

    This paper discusses the development and application of process knowledge (PK) to the characterization of radioactive wastes generated during the excavation of buried materials at the Sandia National Laboratories/New Mexico (SNL/NM) Classified Waste Landfill (CWLF). The CWLF, located in SNL/NM Technical Area II, is a 1.5-acre site that received nuclear weapon components and related materials from about 1950 through 1987. These materials were used in the development and testing of nuclear weapon designs. The CWLF is being remediated by the SNL/NM Environmental Restoration (ER) Project pursuant to regulations of the New Mexico Environment Department. A goal of the CWLF project is to maximize the amount of excavated materials that can be demilitarized and recycled. However, some of these materials are radioactively contaminated and, if they cannot be decontaminated, are destined to require disposal as radioactive waste. Five major radioactive waste streams have been designated on the CWLF project, including: unclassified soft radioactive waste--consists of soft, compatible trash such as paper, plastic, and plywood; unclassified solid radioactive waste--includes scrap metal, other unclassified hardware items, and soil; unclassified mixed waste--contains the same materials as unclassified soft or solid radioactive waste, but also contains one or more Resource Conservation and Recovery Act (RCRA) constituents; classified radioactive waste--consists of classified artifacts, usually weapons components, that contain only radioactive contaminants; and classified mixed waste--comprises radioactive classified material that also contains RCRA constituents. These waste streams contain a variety of radionuclides that exist both as surface contamination and as sealed sources. To characterize these wastes, the CWLF project's waste management team is relying on data obtained from direct measurement of radionuclide activity content to the maximum extent possible and, in cases where direct measurement is not technically feasible, from accumulated PK of the excavated materials.

  10. 2011 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada National Security Site, Nye County, Nevada: Review of the Performance Assessments and Composite Analyses

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2012-03-20T23:59:59.000Z

    The Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site (National Security Technologies, LLC, 2007a) requires an annual review to assess the adequacy of the Performance Assessments (PAs) and Composite Analyses (CAs), with the results submitted annually to U.S. Department of Energy (DOE) Office of Environmental Management. The Disposal Authorization Statements for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) also require that such reviews be made and that secondary or minor unresolved issues be tracked and addressed as part of the maintenance plan (DOE, 1999a; 2000). The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office performed an annual review of the Area 3 and Area 5 RWMS PAs and CAs for fiscal year (FY) 2011. This annual summary report presents data and conclusions from the FY 2011 review, and determines the adequacy of the PAs and CAs. Operational factors (e.g., waste forms and containers, facility design, and waste receipts), closure plans, monitoring results, and research and development (R and D) activities were reviewed to determine the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada National Security Site (NNSS) (formerly the Nevada Test Site) relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R and D activities were reviewed to determine the adequacy of the CAs. Important developments in FY 2011 include the following: (1) Operation of a new shallow land disposal unit and a new Resource Conservation and Recovery Act (RCRA)-compliant lined disposal unit at the Area 5 RWMS; (2) Development of new closure inventory estimates based on disposals through FY 2011; (3) Evaluation of new or revised waste streams by special analysis; (4) Development of version 2.102 of the Area 3 RWMS GoldSim PA model; and (5) Development of version 4.113 of the Area 5 RWMS GoldSim PA model. Analysis of the latest available data using the Area 5 RWMS v4.113 GoldSim PA model indicates that all performance objectives can be met. The results and conclusions of the Area 5 RWMS PA are judged valid, and there is no need to the revise the PA. The Area 3 RWMS has been in inactive status since July 1, 2006, with the last shipment received in April 2006. In FY 2011, there were no operational changes, monitoring results, or R and D results for the Area 3 RWMS that would impact PA validity. Despite the increase in waste volume and inventory at the Area 3 RWMS since 1996 when the PA was approved, the facility performance evaluated with the Area 3 RWMS PA GoldSim model, version 2.0 (with the final closure inventory), remains well below the performance objectives set forth in U.S. Department of Energy Order DOE O 435.1, 'Radioactive Waste Management' (DOE, 2001). The conclusions of the Area 3 RWMS PA remain valid. A special analysis was prepared to update the PA and CA results for the Area 3 RWMS in FY 2011. Release of the special analysis is planned for FY 2012. The continuing adequacy of the CAs was evaluated with the new models, and no significant changes that would alter CA results or conclusions were found. Inclusion of the Frenchman Flat Underground Test Area (UGTA) results in the Area 5 RWMS CA is scheduled for FY 2016, pending the completion of the closure report for the Frenchman Flat UGTA corrective action unit (CAU) in FY 2015. An industrial site, CAU 547, with corrective action sites near the Area 3 RWMS was found to have a significant plutonium inventory in 2009. CAU 547 will be evaluated for inclusion of future revisions or updates of the Area 3 RWMS CA. The revision of the Area 3 RWMS CA, which will include the UGTA source terms, is expected in FY 2024, following the completion of the Yucca Flat CAU Corrective Action Decision Document, scheduled for FY 2023. Near-term R and D efforts will focus on continuing development of the Are

  11. 2013 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada National Security Site, Nye County, Nevada; Review of the Performance Assessments and Composite Analyses

    SciTech Connect (OSTI)

    Shott, Gregory [NSTec] [NSTec

    2014-03-01T23:59:59.000Z

    The Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site (National Security Technologies, LLC 2007a) requires an annual review to assess the adequacy of the performance assessments (PAs) and composite analyses (CAs), with the results submitted to the U.S. Department of Energy (DOE) Office of Environmental Management. The Disposal Authorization Statements for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) also require that such reviews be made and that secondary or minor unresolved issues be tracked and addressed as part of the maintenance plan (DOE 1999a, 2000). The U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office performed an annual review of the Area 3 and Area 5 RWMS PAs and CAs for fiscal year (FY) 2013. This annual summary report presents data and conclusions from the FY 2013 review, and determines the adequacy of the PAs and CAs. Operational factors (e.g., waste forms and containers, facility design, and waste receipts), closure plans, monitoring results, and research and development (R&D) activities were reviewed to determine the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada National Security Site (NNSS) relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R&D activities were reviewed to determine the adequacy of the CAs. Important developments in FY 2013 include the following: • Development of a new Area 5 RWMS closure inventory estimate based on disposals through FY 2013 • Evaluation of new or revised waste streams by special analysis • Development of version 4.115 of the Area 5 RWMS GoldSim PA/CA model The Area 3 RWMS has been in inactive status since July 1, 2006, with the last shipment received in April 2006. The FY 2013 review of operations, facility design, closure plans, monitoring results, and R&D results for the Area 3 RWMS indicates no changes that would impact PA validity. The conclusion of the annual review is that all performance objectives can be met and the Area 3 RWMS PA remains valid. There is no need to the revise the Area 3 RWMS PA. Review of Area 5 RWMS operations, design, closure plans, monitoring results, and R&D activities indicates that no significant changes have occurred. The FY 2013 PA results, generated with the Area 5 RWMS v4.115 GoldSim PA model, indicate that there continues to be a reasonable expectation of meeting all performance objectives. The results and conclusions of the Area 5 RWMS PA are judged valid, and there is no need to the revise the PA. A review of changes potentially impacting the CAs indicates that no significant changes occurred in FY 2013. The continuing adequacy of the CAs was evaluated with the new models, and no significant changes that would alter the CAs results or conclusions were found. The revision of the Area 3 RWMS CA, which will include the Yucca Flat Underground Test Area (Corrective Action Unit [CAU] 97) source term, is scheduled for FY 2024, following the completion of the Corrective Action Decision Document/Corrective Action Plan in FY 2015. Inclusion of the Frenchman Flat Underground Test Area (CAU 98) results in the Area 5 RWMS CA is scheduled for FY 2016, pending the completion of the CAU 98 Closure Report in FY 2015. Near-term R&D efforts will focus on continuing development of the PA, CA, and inventory models for the Area 3 and Area 5 RWMS.

  12. Year 5 Post-Remediation Biomonitoring of Pesticides and other Contaminants in Marine Waters near the United Heckathorn Superfund Site, Richmond, California

    SciTech Connect (OSTI)

    Kohn, Nancy P.; Kropp, Roy K.

    2002-08-01T23:59:59.000Z

    Marine sediment remediation at the United Heckathorn Superfund Site in Richmond, California, was completed in April 1997. The Record of Decision included a requirement for five years of post-remediation monitoring be conducted in the waterways near the site. The present monitoring year, 2001? 2002, is the fifth and possibly final year of post-remediation monitoring. In March 2002, water and mussel tissues were collected from the four stations in and near Lauritzen Channel that have been routinely monitored since 1997-98. A fifth station in Parr Canal was sampled in Year 5 to document post-remediation water and tissue concentrations there. Dieldrin and dichlorodiphenyl trichloroethane (DDT) were analyzed in water samples and in tissue samples from resident (i.e., naturally occurring) mussels. As in Years 3 and 4, mussels were not transplanted to the study area in Year 5. Year 5 concentrations of dieldrin and total DDT in water and total DDT in tissue were compared with those from Years 1 through 4 of post-remediation monitoring, and with preremediation data from the California State Mussel Watch Program and the Ecological Risk Assessment for the United Heckathorn Superfund Site. Year 5 water samples and mussel tissues were also analyzed for polychlorinated biphenyls (PCB), which were detected in sediment samples during Year 2 monitoring and were added to the water and mussel tissue analyses in 1999. Contaminants of concern in Year 5 water samples were analyzed in both bulk (total) phase and dissolved phase, as were total suspended solids, to evaluate the contribution of particulates to the total contaminant concentration.

  13. Site Management Guide (Blue Book)

    SciTech Connect (OSTI)

    None

    2014-03-01T23:59:59.000Z

    The U.S. Department of Energy (Department) Office of Legacy Management (LM), established in 2003, manages the Department’s postclosure responsibilities and ensures the future protection of human health and the environment. During World War II and the Cold War, the Federal government developed and operated a vast network of industrial facilities for the research, production, and testing of nuclear weapons, as well as other scientific and engineering research. These processes left a legacy of radioactive and chemical waste, environmental contamination, and hazardous facilities and materials at well over 100 sites. Since 1989, the Department has taken an aggressive accelerated cleanup approach to reduce risks and cut costs. At most Departmental sites undergoing cleanup, some residual hazards will remain at the time cleanup is completed due to financial and technical impracticality. However, the Department still has an obligation to protect human health and the environment after cleanup is completed. LM fulfills DOE’s postclosure obligation by providing long-term management of postcleanup sites which do not have continuing missions. LM is also responsible for sites under the Formerly Utilized Sites Remedial Action Program (FUSRAP). Currently, the U.S. Army Corps of Engineers (USACE) is responsible for site surveys and remediation at FUSRAP sites. Once remediation is completed, LM becomes responsible for long-term management. LM also has responsibility for uranium processing sites addressed by Title II of the Uranium Mill Tailings Radiation Control Act (UMTRCA). UMTRCA Title II sites are sites that were commercially owned and are regulated under a U.S. Nuclear Regulatory Commission (NRC) license. For license termination, the owner must conduct an NRC-approved cleanup of any on-site radioactive waste remaining from former uranium ore-processing operations. The site owner must also provide full funding for inspections and, if necessary, ongoing maintenance. Once site cleanup is complete, LM accepts title to these sites on behalf of the United States and assumes long-term management.

  14. Hanford Site physical separations CERCLA treatability test plan

    SciTech Connect (OSTI)

    Not Available

    1992-03-01T23:59:59.000Z

    This test plan describes specifications, responsibilities, and general procedures to be followed to conduct a physical separations soil treatability test in the North Process Pond of the 300-FF-1 Operable Unit at the Hanford Site, Washington. The objective of this test is to evaluate the use of physical separation systems as a means of concentrating chemical and radioactive contaminants into fine soil fractions and thereby minimizing waste volumes. If successful the technology could be applied to clean up millions of cubic meters of contaminated soils in waste sites at Hanford and other sites. It is not the intent of this test to remove contaminated materials from the fine soils. Physical separation is a simple and comparatively low cost technology to potentially achieve a significant reduction in the volume of contaminated soils. Organic contaminants are expected to be insignificant for the 300-FF-I Operable Unit test, and further removal of metals and radioactive contaminants from the fine fraction of soils will require secondary treatment such as chemical extraction, electromagnetic separation, or other technologies. Additional investigations/testing are recommended to assess the economic and technical feasibility of applying secondary treatment technologies, but are not within the scope of this test. This plan provides guidance and specifications for the treatability test to be conducted as a service contract. More detailed instructions and procedures will be provided as part of the vendors (sellers) proposal. The procedures will be approved by Westinghouse Hanford Company (Westinghouse Hanford) and finalized by the seller prior to initiating the test.

  15. Geochemistry and migration of contaminants at the Weldon Spring chemical plant site, St. Charles County, Missouri, 1989--91

    SciTech Connect (OSTI)

    Schumacher, J.G.

    1993-12-31T23:59:59.000Z

    Investigations were conducted by the US Geological Survey in cooperation with the US Department of Energy at the Weldon Spring chemical plant site to determine the geochemistry of the shallow aquifer and geochemical controls on the migration of uranium and other constituents from the raffinate (waste) pits. Water-quality analyses from monitoring wells at the site and vicinity property indicate that water in the shallow aquifer is a calcium magnesium bicarbonate type that is at equilibrium with respect to calcite and slightly supersaturated with respect to dolomite.

  16. Understanding Contamination; Twenty Years of Simulating Radiological Contamination

    SciTech Connect (OSTI)

    Emily Snyder; John Drake; Ryan James

    2012-02-01T23:59:59.000Z

    A wide variety of simulated contamination methods have been developed by researchers to reproducibly test radiological decontamination methods. Some twenty years ago a method of non-radioactive contamination simulation was proposed at the Idaho National Laboratory (INL) that mimicked the character of radioactive cesium and zirconium contamination on stainless steel. It involved baking the contamination into the surface of the stainless steel in order to 'fix' it into a tenacious, tightly bound oxide layer. This type of contamination was particularly applicable to nuclear processing facilities (and nuclear reactors) where oxide growth and exchange of radioactive materials within the oxide layer became the predominant model for material/contaminant interaction. Additional simulation methods and their empirically derived basis (from a nuclear fuel reprocessing facility) are discussed. In the last ten years the INL, working with the Defense Advanced Research Projects Agency (DARPA) and the National Homeland Security Research Center (NHSRC), has continued to develop contamination simulation methodologies. The most notable of these newer methodologies was developed to compare the efficacy of different decontamination technologies against radiological dispersal device (RDD, 'dirty bomb') type of contamination. There are many different scenarios for how RDD contamination may be spread, but the most commonly used one at the INL involves the dispersal of an aqueous solution containing radioactive Cs-137. This method was chosen during the DARPA projects and has continued through the NHSRC series of decontamination trials and also gives a tenacious 'fixed' contamination. Much has been learned about the interaction of cesium contamination with building materials, particularly concrete, throughout these tests. The effects of porosity, cation-exchange capacity of the material and the amount of dirt and debris on the surface are very important factors. The interaction of the contaminant/substrate with the particular decontamination technology is also very important. Results of decontamination testing from hundreds of contaminated coupons have lead to certain conclusions about the contamination and the type of decontamination methods being deployed. A recent addition to the DARPA initiated methodology simulates the deposition of nuclear fallout. This contamination differs from previous tests in that it has been developed and validated purely to simulate a 'loose' type of contamination. This may represent the first time that a radiologically contaminated 'fallout' stimulant has been developed to reproducibly test decontamination methods. While no contaminant/methodology may serve as a complete example of all aspects that could be seen in the field, the study of this family of simulation methods provides insight into the nature of radiological contamination.

  17. Achieving Accelerated Cleanup of Cesium Contaminated Stream at the Savannah River Site; Collaboration between Stakeholders, Regulators, and the Federal Government - 13182

    SciTech Connect (OSTI)

    Bergren, Chris; Flora, Mary; Socha, Ron; Burch, Joseph [Savannah River Nuclear Solutions, LLC, Bldg. 730-4B, Aiken, SC 29808 (United States)] [Savannah River Nuclear Solutions, LLC, Bldg. 730-4B, Aiken, SC 29808 (United States); Freeman, Candice; Hennessey, Brian [United States Department of Energy, Bldg. 730-B, Aiken, SC 29808 (United States)] [United States Department of Energy, Bldg. 730-B, Aiken, SC 29808 (United States)

    2013-07-01T23:59:59.000Z

    The Savannah River Site (SRS) is a 310-square-mile United States Department of Energy (US DOE) nuclear facility located along the Savannah River near Aiken, South Carolina that contains six primary stream/river systems. The Lower Three Runs Stream (LTR) is one of the primary streams within the site that is located in the southeast portion of the Savannah River Site and is a large black water stream system that originates in the northeast portion of SRS and follows a southerly direction before it enters the Savannah River. During reactor operations, secondary reactor cooling water, storm sewer discharges, and miscellaneous wastewater was discharged and contaminated a 36 kilometer stretch of Lower Three Runs Stream that narrows providing a limited buffer of US DOE property along the stream and flood plain. Based on data collected during 2009 and 2010 under Recover Act Funding, the stream was determined to be contaminated with cesium-137 at levels that exceeded acceptable risk based limits. As efficiencies were realized within the SRS Recovery Act Program, funding was made available to design, permit and execute remediation of the LTR. This accelerated Project allowed for the remediation of 36 kilometers of LTR in only nine months from inception to completion, contributing significantly to the Foot Print Reduction of SRS. The scope consisted of excavation and disposal of more than 2064 cubic meters of contaminated soil, and installing 11 kilometers of fence and 2,000 signs at 1000 locations. Confirmatory sampling and analysis, and radiological surveying were performed demonstrating that soil concentrations met the cleanup goals. The project completed with a very good safety record considering the harsh conditions including, excessive rain in the early stages of the project, high summer temperatures, swampy terrain, snakes, wild boar, insects and dense vegetation. The regulatory approval process was compressed by over 75% and required significant efforts from SRS's stakeholders including the regulators, U. S. Environmental Protection Agency (US EPA) and the South Carolina Department of Health and Environmental Control (SCDHEC), and the public including local property owners and the SRS Citizens Advisory Board. Stakeholder buy-in was critical in the up-front planning in order to achieve this challenging cleanup. (authors)

  18. Numerical simulation of groundwater flow and contaminant transport at the K, L, and P areas of the Savannah River Site, Aiken, South Carolina

    SciTech Connect (OSTI)

    Not Available

    1989-11-01T23:59:59.000Z

    The Department of Energy (DOE) is preparing an Environmental Impact Statement (EIS) as part of the process for continuing operation of three reactors at the Savannah River Site (SRS). As required by the National Environmental Policy Act (NEPA), the EIS must address the potential environmental consequences to human health and the environment of this major federal action.'' Some of the possible consequences are related to subsurface transport of radionuclides released to seepage basins during normal reactor operation. To assist in the evaluation of the potential subsurface environmental impacts of these releases, Camp Dresser McKee Inc. (CDM) was contracted in June of 1989 to develop a three-dimensional groundwater flow and contaminant transport model which will simulate the movement of radionuclides at each of the reactor areas after they enter the groundwater system through the seepage basins. This report describes the development, calibration, and simulation results of the groundwater flow and contaminant transport model developed for this task. 10 refs., 63 figs., 11 tabs.

  19. Cross flow filtration of aqueous radioactive tank wastes

    SciTech Connect (OSTI)

    McCabe, D.J. [Westinghouse Savannah River Co., Aiken, SC (United States); Reynolds, B.A. [Battelle Pacific Northwest Lab., Richland, WA (United States); Todd, T.A. [Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United States); Wilson, J.H. [Oak Ridge National Lab., TN (United States)

    1997-02-01T23:59:59.000Z

    The Tank Focus Area (TFA) of the Department of Energy (DOE) Office of Science and Technology addresses remediation of radioactive waste currently stored in underground tanks. Baseline technologies for treatment of tank waste can be categorized into three types of solid liquid separation: (a) removal of radioactive species that have been absorbed or precipitated, (b) pretreatment, and (c) volume reduction of sludge and wash water. Solids formed from precipitation or absorption of radioactive ions require separation from the liquid phase to permit treatment of the liquid as Low Level Waste. This basic process is used for decontamination of tank waste at the Savannah River Site (SRS). Ion exchange of radioactive ions has been proposed for other tank wastes, requiring removal of insoluble solids to prevent bed fouling and downstream contamination. Additionally, volume reduction of washed sludge solids would reduce the tank space required for interim storage of High Level Wastes. The scope of this multi-site task is to evaluate the solid/liquid separations needed to permit treatment of tank wastes to accomplish these goals. Testing has emphasized cross now filtration with metal filters to pretreat tank wastes, due to tolerance of radiation and caustic.

  20. Bioreduction and immobilization of uranium in situ: a case study at a USA Department of Energy radioactive waste site, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    Wu, Weimin [Stanford University; Carley, Jack M [ORNL; Watson, David B [ORNL; Gu, Baohua [ORNL; Brooks, Scott C [ORNL; Kelly, Shelly D [Argonne National Laboratory (ANL); Kemner, Kenneth M [Argonne National Laboratory (ANL); Van Nostrand, Joy [University of Oklahoma, Norman; Wu, Liyou [University of Oklahoma, Norman; Zhou, Jizhong [University of Oklahoma, Norman; Luo, Jian [Georgia Institute of Technology; Cardenas, Erick [Michigan State University, East Lansing; Fields, Matthew Wayne [Miami University, Oxford, OH; Marsh, Terence [Michigan State University, East Lansing; Tiedje, James [Michigan State University, East Lansing; Green, Stefan [Florida State University; Kostka, Joel [Florida State University; Kitanidis, Peter K. [Stanford University; Jardine, Philip [University of Tennessee, Knoxville (UTK); Criddle, Craig [Stanford University

    2011-01-01T23:59:59.000Z

    Bioremediation of uranium contaminated groundwater was tested by delivery of ethanol as an electron donor source to stimulate indigenous microbial bioactivity for reduction and immobilization of uranium in situ, followed by tests of stability of uranium sequestration in the bioreduced area via delivery of dissolved oxygen or nitrate at the US Department of energy's Integrated Field Research Challenge site located at Oak Ridge, Tennessee, USA. After long term treatment that spanned years, uranium in groundwater was reduced from 40-60 mg {center_dot} L{sup -1} to <0.03 mg {center_dot} L{sup -1}, below the USA EPA standard for drinking water. The bioreduced uranium was stable under anaerobic or anoxic conditions, but addition of DO and nitrate to the bioreduced zone caused U remobilization. The change in the microbial community and functional microorganisms related to uranium reduction and oxidation were characterized. The delivery of ethanol as electron donor stimulated the activities of indigenous microorganisms for reduction of U(VI) to U(IV). Results indicated that the immobilized U could be partially remobilized by D0 and nitrate via microbial activity. An anoxic environmental condition without nitrate is essential to maintain the stability of bioreduced uranium.

  1. DOE Media Advisory- DOE extends public comment period on Draft Environmental Assessment for Replacement Capability for Disposal of Remote-Handled Low-Level Radioactive Waste Generated at the U.S. Department of Energy’s Idaho Site

    Broader source: Energy.gov [DOE]

    In response to requests from people interested in National Environmental Policy Act activities occurring at the U.S. Department of Energy’s Idaho Operations Office, the department has extended the public comment period that began September 1 on the Draft Environmental Assessment for Replacement Capability for Disposal of Remote-Handled Low-Level Radioactive Waste Generated at the U.S. Department of Energy’s Idaho Site.

  2. Radioactive mixed waste disposal

    SciTech Connect (OSTI)

    Jasen, W.G.; Erpenbeck, E.G.

    1993-02-01T23:59:59.000Z

    Various types of waste have been generated during the 50-year history of the Hanford Site. Regulatory changes in the last 20 years have provided the emphasis for better management of these wastes. Interpretations of the Atomic Energy Act of 1954 (AEA), the Resource Conservation and Recovery Act of 1976 (RCRA), and the Hazardous and Solid Waste Amendments (HSWA) have led to the definition of radioactive mixed wastes (RMW). The radioactive and hazardous properties of these wastes have resulted in the initiation of special projects for the management of these wastes. Other solid wastes at the Hanford Site include low-level wastes, transuranic (TRU), and nonradioactive hazardous wastes. This paper describes a system for the treatment, storage, and disposal (TSD) of solid radioactive waste.

  3. A brownfield to greenfield success story: Denver Radium Superfund Site

    SciTech Connect (OSTI)

    Baracani, E. [Sverdrup Environmental, Inc., Golden, CO (United States); Bruskin, L.J. [Colorado Dept. of Public Health and the Environment, Denver, CO (United States)

    1996-12-31T23:59:59.000Z

    The Denver Radium Site consists of forty-nine separate sites divided into 11 operable units throughout the city of Denver, Colorado. The sites contained radioactive soils and residues (310,000 tons) from processing of radium in the early 1900s. The majority of the radioactive material was removed, transported by rail, and disposed offsite in Utah. During radiologic cleanup at the former Robinson Brick Company Site (ROBCO), (OU No. 4/5), metal contaminated soils from previous smelting operations were encountered. The Denver Radium Site was placed on the National Priorities List (NPL), and through cooperation of private parties, the state and federal governments, the land was cleaned up and restored to productive use.

  4. ELIPGRID-PC and INRADS{copyright}: Tools for reducing costs and optimizing data collection on sites contaminated with NORM

    SciTech Connect (OSTI)

    Egidi, P.V.

    1996-12-31T23:59:59.000Z

    Oak Ridge National Laboratory (ORNL), Environmental Technology Section (ETS), located in Grand Junction, Colorado has more than ten years experience in radiological surveying and more than twenty years as part of the ongoing Formerly Utilized Sites Remedial Action Project surveys conducted by ORNL Health Sciences Research Division. As part of our mission, ETS researchers develops and applies innovative technologies to share with private industry. The ELIPGRID-PC software and INRADS multidetector radiologic survey instrument are works in progress are discussed. ELIPGRID-PC is a tool that aids in survey design, and the INRADS system automates and increases the amount of data collected.

  5. Long-Term Recovery of PCB-Contaminated Surface Sediments at the Sangamo-Weston / Twelvemile Creek / Lake Hartwell Superfund Site

    SciTech Connect (OSTI)

    Brenner, Richard C.; Magar, Victor S.; Ickes, Jennifer A.; Foote, Eric A.; Abbott, James E.; Bingler, Linda S.; Crecelius, Eric A.

    2004-03-10T23:59:59.000Z

    Natural recovery of contaminated sediments relies on burial of contaminated sediments with increasingly clean sediments over time (i.e., natural capping). Natural capping reduces the risk of resuspension of contaminated surface sediments, and it reduces the potential for contaminant transport into the food chain by limiting bioturbation of contaminated surface or near-surface sediments. This study evaluated the natural recovery of surface sediments contaminated with polychlorinated biphenyls (PCBs) at the Sangamo-Weston/Twelvemile Creek/Lake Hartwell Superfund Site (Lake Hartwell), Pickens County, SC. The primary focus was on sediment recovery resulting from natural capping processes. Total PCB (t-PCB), lead-210 (210Pb), and cesium-137 (137Cs) sediment core profiles were used to establish vertical t-PCB concentration profiles, age date sediments, and determine surface sedimentation and surface sediment recovery rates in 18 cores collected along 10 transects. Four upgradient transects in the headwaters of Lake Hartwell were impacted by historical sediment releases from three upgradient sediment impoundments. These transects were characterized by silt/ clay and sand layering. The highest PCB concentrations were associated with silt/clay layers (1.8-3.5% total organic carbon (TOC)), while sand layers (0.05-0.32% TOC) contained much lower PCB concentrations. The historical sediment releases resulted in substantial burial of PCBcontaminated sediment in the vicinity of these four cores; each core contained less than 1 mg/kg t-PCBs in the surface sand layers. Cores collected from six downgradient Lake Hartwell transects consisted primarily of silt and clay (0.91-5.1% TOC) and were less noticeably impacted by the release of sand from the impoundments. Vertical t-PCB concentration profiles in these cores began with relatively low PCB concentrations at the sediment-water interface and increased in concentration with depth until maximum PCB concentrations were measured at _30-60 cm below the sediment-water interface, ca. 1960-1980. Maximum t-PCB concentrations were followed by progressively decreasing concentrations with depth until the t-PCB concentrations approached the detection limit, where sediments were likely deposited before the onset of PCB use at the Sangamo-Weston plant. The sediments containing the maximum PCB concentrations are associated with the period of maximum PCB release into the watershed. Sedimentation rates averaged 2.1 ( 1.5 g/(cm2 yr) for 12 of 18 cores collected. The 1994 Record of Decision cleanup requirement is 1.0 mg/kg; two more goals (0.4 and 0.05 mg/kg t-PCBs) also were identified. Average surface sedimentation requirements to meet the three goals were 1.4 ( 3.7, 11 ( 4.2, and 33 ( 11 cm, respectively. Using the age dating results, the average recovery dates to meet these goals were 2000.6 ( 2.7, 2007.4 ( 3.5, and 2022.7 ( 11 yr, respectively. (The 95% prediction limits for these values also are provided.) Despite the reduction in surface sediment PCB concentrations, PCB concentrations measured in largemouth bass and hybrid bass filets continue to exceed the 2.0 mg/kg FDA fish tolerance level.

  6. 2012 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada National Security Site, Nye County, Nevada: Review of the Performance Assessments and Composite Analyses

    SciTech Connect (OSTI)

    Shott, G. [National Security Technologies, LLC

    2013-03-18T23:59:59.000Z

    The Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site (National Security Technologies, LLC 2007a) requires an annual review to assess the adequacy of the performance assessments (PAs) and composite analyses (CAs), with the results submitted to the U.S. Department of Energy (DOE) Office of Environmental Management. The Disposal Authorization Statements for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) also require that such reviews be made and that secondary or minor unresolved issues be tracked and addressed as part of the maintenance plan (DOE 1999a, 2000). The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office performed an annual review of the Area 3 and Area 5 RWMS PAs and CAs for fiscal year (FY) 2012. This annual summary report presents data and conclusions from the FY 2012 review, and determines the adequacy of the PAs and CAs. Operational factors (e.g., waste forms and containers, facility design, and waste receipts), closure plans, monitoring results, and research and development (R&D) activities were reviewed to determine the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada National Security Site (NNSS) relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R&D activities were reviewed to determine the adequacy of the CAs. Important developments in FY 2012 include the following: ? Release of a special analysis for the Area 3 RWMS assessing the continuing validity of the PA and CA ? Development of a new Area 5 RWMS closure inventory estimate based on disposals through FY 2012 ? Evaluation of new or revised waste streams by special analysis ? Development of version 4.114 of the Area 5 RWMS GoldSim PA model The Area 3 RWMS has been in inactive status since July 1, 2006, with the last shipment received in April 2006. The FY 2012 review of operations, facility design, closure plans, monitoring results, and R&D results for the Area 3 RWMS indicates no changes that would impact PA validity. A special analysis using the Area 3 RWMS v2.102 GoldSim PA model was prepared to update the PA results for the Area 3 RWMS in FY 2012. The special analysis concludes that all performance objectives can be met and the Area 3 RWMS PA remains valid. There is no need to the revise the Area 3 RWMS PA. Review of Area 5 RWMS operations, design, closure plans, monitoring results, and R&D activities indicates no significant changes other than an increase in the inventory disposed. The FY 2012 PA results, generated with the Area 5 RWMS v4.114 GoldSim PA model, indicate that there continues to be a reasonable expectation of meeting all performance objectives. The results and conclusions of the Area 5 RWMS PA are judged valid, and there is no need to the revise the PA. A review of changes potentially impacting the CAs indicates that no significant changes occurred in FY 2012. The continuing adequacy of the CAs was evaluated with the new models, and no significant changes that would alter CA results or conclusions were found. The revision of the Area 3 RWMS CA, which will include the Underground Test Area source term (Corrective Action Unit [CAU] 97), is scheduled for FY 2024, following the completion of the Yucca Flat CAU 97 Corrective Action Decision Document/Corrective Action Plan in FY 2016. Inclusion of the Frenchman Flat CAU 98 results in the Area 5 RWMS CA is scheduled for FY 2016, pending the completion of the CAU 98 closure report in FY 2015. Near-term R&D efforts will focus on continuing development of the Area 3 and Area 5 RWMS GoldSim PA/CA and inventory models.

  7. Managing Legacy Records for Formerly Utilized Sites. Remedial Action Program Sites

    SciTech Connect (OSTI)

    Clayton, C. [DOE Office of Legacy Management, Washington, DC (United States); Gueretta, J. [Lead DOE Office of Legacy Management, Grand Junction, CO (United States); Tack, J. [Source One Management, Inc., Grand Junction, CO (United States); Widdop, M. [S.M. Stoller Corporation, Grand Junction, CO (United States)

    2008-07-01T23:59:59.000Z

    The Manhattan Engineer District (MED) and U.S. Atomic Energy Commission (AEC) contracted for support work through private and academic parties through the early 1960's. The work often involved radioactive materials. Residual radioactive contamination was left at some of more than 600 potentially contaminated (candidate) sites, and worker health and safety concerns remain from the site operations and subsequent remediation activities. The U.S. Department of Energy (DOE) initiated a program to identify and protect records of MED/AEC activities and of remediation work conducted under the Formerly Utilized Sites Remedial Action Program (FUSRAP) to aid in resolving questions about site conditions, liability, and worker health and safety and to ensure ongoing protectiveness of human health and the environment. This paper discusses DOE activities undertaken to locate records collections, confirm retention schedules and access requirements, and document information about the collections for use by future stewards. In conclusion: DOE-LM recognizes that records and information management is a critical component of effective LTS and M. Records are needed to answer questions about site conditions and demonstrate to the public in the future that the sites are safe. DOE-LM is working to satisfy present needs and anticipate future uses for FUSRAP records, and compile a collection of site and program information from which future stewards can readily locate and retrieve needed information. (authors)

  8. Salmon Site Remedial Investigation Report, Appendix B (Part 1)

    SciTech Connect (OSTI)

    USDOE /NV

    1999-09-01T23:59:59.000Z

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the installation of a water supply system that will provide potable water to the site and residence in the proximity to the site; (2) continued maintenance of surface institutional controls and subsurface restrictions; and (3) continue to implement the long-term hydrologic monitoring program. The Salmon Site will be relinquished the State of Mississippi as mandated by Public Law 104-201-September 23, 1996, to be used as a demonstration forest/wildlife refuge. Should the land use change in the future and/or monitoring information indicates a change in the site conditions, the DOE will reassess the risk impacts to human health and the environment.

  9. Salmon Site Remedial Investigation Report, Appendix B (Part 2)

    SciTech Connect (OSTI)

    USDOE /NV

    1999-09-01T23:59:59.000Z

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the installation of a water supply system that will provide potable water to the site and residence in the proximity to the site; (2) continued maintenance of surface institutional controls and subsurface restrictions; and (3) continue to implement the long-term hydrologic monitoring program. The Salmon Site will be relinquished the State of Mississippi as mandated by Public Law 104-201-September 23, 1996, to be used as a demonstration forest/wildlife refuge. Should the land use change in the future and/or monitoring information indicates a change in the site conditions, the DOE will reassess the risk impacts to human health and the environment.

  10. EIS-0286: Hanford Solid (Radioactive and Hazardous) Waste Program

    Broader source: Energy.gov [DOE]

    The Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement (HSW EIS) analyzes the proposed waste management practices at the Hanford Site.

  11. Environmental assessment of remedial action at the slick rock Uranium Mill Tailings sites Slick Rock, Colorado

    SciTech Connect (OSTI)

    Not Available

    1994-09-01T23:59:59.000Z

    The Uranium Mill Tailings Radiation Control Act of 1978 (42 USC {section} 7901 et seq.), hereafter referred to as the UMTRCA, authorized the U.S. Department of Energy (DOE) to clean up two uranium mill tailings processing sites near Slick Rock, Colorado, in San Miguel County. The purpose of the cleanup is to reduce the potential health effects associated with the radioactive materials remaining on the sites and on vicinity properties (VPs) associated with the sites. Contaminated materials cover an estimated 55 acres of the Union Carbide (UC) processing site and 12 ac of the North Continent (NC) processing site. The total estimated volume of contaminated materials is approximately 61 8,300 cubic yards. In addition to the contamination in the two processing site areas, four VPs were found to contain contamination. As a result of the tailings being exposed to the environment, contamination associated with the UC and NC sites has leached into shallow ground water. Surface water has not been affected. The closest residence is approximately 0.3 air mi from either site. The proposed action is to remediate the UC and NC sites by removing all contaminated materials within the designated site boundaries or otherwise associated with the sites, and relocating them to, and stabilizing them at, a location approximately 5 road mi (8 km) northeast of the sites on land administered by the Bureau of Land Management (BLM). Remediation would be performed by the DOE`s Uranium Mill Tailings Remedial Action (UMTRA) Project. All solid contaminated materials would be buried under 5 feet (ft) of rock and soil materials. The proposed disposal site area is currently used by ranchers for cattle grazing over a 7-month period. The closest residence to the proposed disposal site is 2 air mi. An estimated 44 ac of land would be permanently transferred from the BLM to the DOE and restricted from future use.

  12. Hazardous waste shipment data collection from DOE sites

    SciTech Connect (OSTI)

    Page, L.A.; Kirkpatrick, T.D. (Idaho National Engineering Lab., Idaho Falls, ID (United States)); Stevens, L. (USDOE, Washington, DC (United States))

    1992-01-01T23:59:59.000Z

    Past practices at the US Department of Energy (DOE) sites for offsite release of hazardous waste are being reviewed to determine if radioactively contaminated hazardous wastes were released to commercial treatment, storage, and disposal facilities. Records indicating the presence of radioactivity in waste shipped to and treated at a commercial incineration facility led to a ban on offsite hazardous waste shipments and investigation of past practices for offsite release of hazardous waste from the DOE sites. A House of Representatives Interior and Insular Affairs Committee oversight hearing on potentially contaminated waste shipments to commercial facilities concluded that the main issue was the lack of a uniform national standard to govern disposal of mixed waste.

  13. Hazardous waste shipment data collection from DOE sites

    SciTech Connect (OSTI)

    Page, L.A.; Kirkpatrick, T.D. [Idaho National Engineering Lab., Idaho Falls, ID (United States); Stevens, L. [USDOE, Washington, DC (United States)

    1992-12-31T23:59:59.000Z

    Past practices at the US Department of Energy (DOE) sites for offsite release of hazardous waste are being reviewed to determine if radioactively contaminated hazardous wastes were released to commercial treatment, storage, and disposal facilities. Records indicating the presence of radioactivity in waste shipped to and treated at a commercial incineration facility led to a ban on offsite hazardous waste shipments and investigation of past practices for offsite release of hazardous waste from the DOE sites. A House of Representatives Interior and Insular Affairs Committee oversight hearing on potentially contaminated waste shipments to commercial facilities concluded that the main issue was the lack of a uniform national standard to govern disposal of mixed waste.

  14. Conceptual design report for site drainage control

    SciTech Connect (OSTI)

    Hunter, M.R.

    1996-07-01T23:59:59.000Z

    The Mound Plant (Mound), located in Miamisburg, Ohio, is a Department of Energy (DOE) development and production facility performing support work for DOE`s weapons and energy-related programs. EG&G Mound Applied Technologies, Inc. (EG&G) is the Operating Contractor (OC) for this Government-Owned, Contractor-Operated (GOCO) facility. The work performed at Mound emphasizes nuclear energy and explosives technology. Mound is currently implementing an Environmental, Safety & Health (ES&H) Upgrades Program designed to protect its employees, the public, and the environment from adverse effects caused by facility activities. The first project of this multiphase program is now in the final stages of construction, and the second project is currently under design. Four additional projects, one of which is presented in this report, are in the conceptual design stage. At Mound, 22 soil zones have become contaminated with radioactive material. These zones cover approximately 20 percent of the total area of developed property at the site. During a storm event, the rainwater washes contaminated soil from these zones into the storm sewer system. These radioactive contaminants may then be discharged along with the stormwater into the Great Miami River via the Miami Erie Canal. This conceptual design report (CDR), Site Drainage Control, the fourth project in the ES&H program, describes a project that will provide improvements and much needed repairs to inadequate and deteriorating portions of the storm drainage system on the developed property. The project also will provide a stormwater retention facility capable of storing the stormwater runoff, from the developed property, resulting from a 100-year storm event. These improvements will permit the effective control and monitoring of stormwater to prevent the spread of radioactive contaminants from contaminated soil zones and will provide a means to collect and contain accidental spills of hazardous substances.

  15. Estimation of contamination volume at Seaway Area A, New York.

    SciTech Connect (OSTI)

    Durham, L.; Johnson, R.

    1999-08-04T23:59:59.000Z

    The purpose of this analysis was to estimate the volume of soil with a radioactive contaminant activity level above the cleanup Guideline at Seaway Area A, Tonawanda, New York. A site-specific cleanup guideline of 40 pCi/g thorium-230 was derived for Seaway, as well as for the nearby Ashland 1 and Ashland 2 sites. All three are Formerly Utilized Sites Remedial Action Program (FUSRAP) properties. The level was developed to ensure protection of human health and the environment and compliance with applicable or relevant and appropriate requirements. The available data included historical discrete soil samples taken at the surface and at depth and results of a surficial gamma walkover with a sodium iodide (NaI) 2x2 sensor. The balance of this document provides background information about the site and discusses the available data sets, the methodology used, and the results and conclusions from the analysis.

  16. activity-dependent polyadenylation site: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    commercial setting. Contaminants: Contaminants: Vinyl Chloride 37 Clinical Research Site Management Engineering Websites Summary: Clinical Research Site Management Dan...

  17. allosteric citalopram-binding site: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    commercial setting. Contaminants: Contaminants: Vinyl Chloride 69 Clinical Research Site Management Engineering Websites Summary: Clinical Research Site Management Dan...

  18. atp-binding site lesions: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    commercial setting. Contaminants: Contaminants: Vinyl Chloride 107 Clinical Research Site Management Engineering Websites Summary: Clinical Research Site Management Dan...

  19. adenine dinucleotide-binding site: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    commercial setting. Contaminants: Contaminants: Vinyl Chloride 43 Clinical Research Site Management Engineering Websites Summary: Clinical Research Site Management Dan...

  20. Removal of Historic Low-Level Radioactive Sediment from the Port Hope Harbour - 13314

    SciTech Connect (OSTI)

    Kolberg, Mark [Baird and Associates, 1267 Cornwall Rd., Suite 100, Oakville ON, L6J7T5 (Canada)] [Baird and Associates, 1267 Cornwall Rd., Suite 100, Oakville ON, L6J7T5 (Canada); Case, Glenn [Atomic Energy of Canada Limited, Port Hope, ON (Canada)] [Atomic Energy of Canada Limited, Port Hope, ON (Canada); Ferguson Jones, Andrea [MMM Group Limited, Thornhill, ON (Canada)] [MMM Group Limited, Thornhill, ON (Canada)

    2013-07-01T23:59:59.000Z

    At the Port Hope Harbour, located on the north shore of Lake Ontario, the presence of low-level radioactive sediment, resulting from a former radium and uranium refinery that operated alongside the Harbour, currently limits redevelopment and revitalization opportunities. These waste materials contain radium-226, uranium, arsenic and other contaminants. Several other on-land locations within the community of Port Hope are also affected by the low-level radioactive waste management practices of the past. The Port Hope Project is a community initiated undertaking that will result in the consolidation of an estimated 1.2 million cubic metres of the low-level radioactive waste from the various sites in Port Hope into a new engineered above ground long-term waste management facility. The remediation of the estimated 120,000 m{sup 3} of contaminated sediments from the Port Hope Harbour is one of the more challenging components of the Port Hope Project. Following a thorough review of various options, the proposed method of contaminated sediment removal is by dredging. The sediment from the dredge will then be pumped as a sediment-water slurry mixture into geo-synthetic containment tubes for dewatering. Due to the hard substrate below the contaminated sediment, the challenge has been to set performance standards in terms of low residual surface concentrations that are attainable in an operationally efficient manner. (authors)

  1. Corrective Action Decision Document/Closure Report for Corrective Action Unit 365: Baneberry Contamination Area, Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Patrick Matthews

    2011-09-01T23:59:59.000Z

    Corrective Action Unit 365 comprises one corrective action site (CAS), CAS 08-23-02, U-8d Contamination Area. The purpose of this CADD/CR is to provide justification and documentation supporting the recommendation that no further corrective action is needed for CAU 365 based on the implementation of the corrective action of closure in place with a use restriction (UR). Corrective action investigation (CAI) activities were performed from January 18, 2011, through August 2, 2011, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 365: Baneberry Contamination Area. The purpose of the CAI was to fulfill data needs as defined during the data quality objective (DQO) process. The CAU 365 dataset of investigation results was evaluated based on a data quality assessment. This assessment demonstrated the dataset is complete and acceptable for use in supporting the DQO decisions. Investigation results were evaluated against final action levels (FALs) established in this document. A radiological dose FAL of 25 millirem per year was established based on the Remote Work Area exposure scenario (336 hours of annual exposure). Radiological doses exceeding the FAL were found to be present to the southwest of the Baneberry crater. It was also assumed that radionuclide levels present within the crater and fissure exceed the FAL. Corrective actions were undertaken that consisted of establishing a UR and posting warning signs for the crater, fissure, and the area located to the southwest of the crater where soil concentrations exceeded the FAL. These URs were recorded in the FFACO database; the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Facility Information Management System; and the NNSA/NSO CAU/CAS files. Therefore, NNSA/NSO provides the following recommendations: (1) No further corrective actions beyond what are described in this document are necessary for CAU 365. (2) A Notice of Completion to NNSA/NSO is requested from the Nevada Division of Environmental Protection for closure of CAU 365. (3) Corrective Action Unit 365 should be moved from Appendix III to Appendix IV of the FFACO.

  2. A Prototype Radon Filter for Air A typical, recurring problem in low-background physics is the contamination of sensitive

    E-Print Network [OSTI]

    is the contamination of sensitive surfaces of experimental apparata with the radioactive decay products of 222Rn . What

  3. Nevada Test Site Environmental Report 2009, Attachment A: Site Description

    SciTech Connect (OSTI)

    Cathy Wills, ed.

    2010-09-13T23:59:59.000Z

    This attachment expands on the general description of the Nevada Test Site (NTS) presented in the Introduction to the Nevada Test Site Environmental Report 2009. Included are subsections that summarize the site’s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site’s environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site that afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

  4. Nevada Test Site Environmental Report 2008 Attachment A: Site Description

    SciTech Connect (OSTI)

    Cathy A. Wills

    2009-09-01T23:59:59.000Z

    This attachment expands on the general description of the Nevada Test Site (NTS) presented in the Introduction to the Nevada Test Site Environmental Report 2008 (National Security Technologies, LLC [NSTec], 2009a). Included are subsections that summarize the site’s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site’s environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site that afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

  5. Savannah River Site Environmental Report for 1994

    SciTech Connect (OSTI)

    Arnett, M.W.; Mamatey, A.; Spitzer, D.

    1994-12-16T23:59:59.000Z

    The mission at the Savannah River Site has changed from producing nuclear weapons materials for national defense to managing the waste it has generated, restoring the environment, and enhancing industrial development in and around the site. But no matter what the site`s mission is, it will continue to maintain its comprehensive environmental monitoring and surveillance program. In 1994, effluent monitoring and environmental surveillance were conducted within a 30,000-square-mile area in and around SRS that includes neighboring cities, towns, and counties in Georgia and South Carolina and extends up to 100 miles from the site. Thousands of samples of air, surface water, groundwater, foodstuffs, drinking water, wildlife, rainwater, soil, sediment, and vegetation were collected and analyzed for radioactive and nonradioactive contaminants.

  6. Special Analysis for the Disposal of the Consolidated Edison Uranium Solidification Project Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2013-01-31T23:59:59.000Z

    The purpose of this Special Analysis (SA) is to determine if the Oak Ridge (OR) Consolidated Edison Uranium Solidification Project (CEUSP) uranium-233 (233U) waste stream (DRTK000000050, Revision 0) is acceptable for shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS) on the Nevada National Security Site (NNSS). The CEUSP 233U waste stream requires a special analysis because the concentrations of thorium-229 (229Th), 230Th, 232U, 233U, and 234U exceeded their NNSS Waste Acceptance Criteria action levels. The acceptability of the waste stream is evaluated by determining if performance assessment (PA) modeling provides a reasonable expectation that SLB disposal is protective of human health and the environment. The CEUSP 233U waste stream is a long-lived waste with unique radiological hazards. The SA evaluates the long-term acceptability of the CEUSP 233U waste stream for near-surface disposal as a two tier process. The first tier, which is the usual SA process, uses the approved probabilistic PA model to determine if there is a reasonable expectation that disposal of the CEUSP 233U waste stream can meet the performance objectives of U.S. Department of Energy Manual DOE M 435.1-1, “Radioactive Waste Management,” for a period of 1,000 years (y) after closure. The second tier addresses the acceptability of the OR CEUSP 233U waste stream for near-surface disposal by evaluating long-term site stability and security, by performing extended (i.e., 10,000 and 60,000 y) modeling analyses, and by evaluating the effect of containers and the depth of burial on performance. Tier I results indicate that there is a reasonable expectation of compliance with all performance objectives if the OR CEUSP 233U waste stream is disposed in the Area 5 RWMS SLB disposal units. The maximum mean and 95th percentile PA results are all less than the performance objective for 1,000 y. Monte Carlo uncertainty analysis indicates that there is a high likelihood of compliance with all performance objectives. Tier II results indicate that the long-term performance of the OR CEUSP 233U waste stream is protective of human health and the environment. The Area 5 RWMS is located in one of the least populated and most arid regions of the U.S. Site characterization data indicate that infiltration of precipitation below the plant root zone at 2.5 meters (8.2 feet) ceased 10,000 to 15,000 y ago. The site is not expected to have a groundwater pathway as long as the current arid climate persists. The national security mission of the NNSS and the location of the Area 5 RWMS within the Frenchman Flat Corrective Action Unit require that access controls and land use restrictions be maintained indefinitely. PA modeling results for 10,000 to 60,000 y also indicate that the OR CEUSP 233U waste stream is acceptable for near-surface disposal. The mean resident air pathway annual total effective dose (TED), the resident all-pathways annual TED, and the acute drilling TED are less than their performance objectives for 10,000 y after closure. The mean radon-222 (222Rn) flux density exceeds the performance objective at 4,200 y, but this is due to waste already disposed at the Area 5 RWMS and is only slightly affected by disposal of the CEUSP 233U. The peak resident all-pathways annual TED from CEUSP key radionuclides occurs at 48,000 y and is less than the 0.25 millisievert performance objective. Disposal of the OR CEUSP 233U waste stream in a typical SLB trench slightly increases PA results. Increasing the depth was found to eliminate any impacts of the OR CEUSP 233U waste stream. Containers could not be shown to have any significant impact on performance due to the long half-life of the waste stream and a lack of data for pitting corrosion rates of stainless steel in soil. The results of the SA indicate that all performance objectives can be met with disposal of the OR CEUSP 233U waste stream in the SLB units at the Area 5 RWMS. The long-term performance of the OR CEUSP 233U waste stream disposed in the near surface is protective of human health

  7. Corrective Action Investigation Plan for Corrective Action Unit 137: Waste Disposal Sites, Nevada Test Site, Nevada, Rev. No.:0

    SciTech Connect (OSTI)

    Wickline, Alfred

    2005-12-01T23:59:59.000Z

    This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 137: Waste Disposal Sites. This CAIP has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense. Corrective Action Unit 137 contains sites that are located in Areas 1, 3, 7, 9, and 12 of the Nevada Test Site (NTS), which is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Corrective Action Unit 137 is comprised of the eight corrective action sites (CASs) shown on Figure 1-1 and listed below: (1) CAS 01-08-01, Waste Disposal Site; (2) CAS 03-23-01, Waste Disposal Site; (3) CAS 03-23-07, Radioactive Waste Disposal Site; (4) CAS 03-99-15, Waste Disposal Site; (5) CAS 07-23-02, Radioactive Waste Disposal Site; (6) CAS 09-23-07, Radioactive Waste Disposal Site; (7) CAS 12-08-01, Waste Disposal Site; and (8) CAS 12-23-07, Waste Disposal Site. The Corrective Action Investigation (CAI) will include field inspections, radiological surveys, geophysical surveys, sampling of environmental media, analysis of samples, and assessment of investigation results, where appropriate. Data will be obtained to support corrective action alternative evaluations and waste management decisions. The CASs in CAU 137 are being investigated because hazardous and/or radioactive constituents may be present in concentrations that could potentially pose a threat to human health and the environment. Existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives for the CASs. Additional information will be generated by conducting a CAI before evaluating and selecting corrective action alternatives.

  8. Best Practices for Siting Solar Photovoltaics on Municipal Solid Waste Landfills. A Study Prepared in Partnership with the Environmental Protection Agency for the RE-Powering America's Land Initiative: Siting Renewable Energy on Potentially Contaminated Land and Mine Sites

    SciTech Connect (OSTI)

    Kiatreungwattana, K.; Mosey, G.; Jones-Johnson, S.; Dufficy, C.; Bourg, J.; Conroy, A.; Keenan, M.; Michaud, W.; Brown, K.

    2013-04-01T23:59:59.000Z

    The Environmental Protection Agency and the National Renewable Energy Laboratory developed this best practices document to address common technical challenges for siting solar photovoltaics (PV) on municipal solid waste (MSW) landfills. The purpose of this document is to promote the use of MSW landfills for solar energy systems. Closed landfills and portions of active landfills with closed cells represent thousands of acres of property that may be suitable for siting solar photovoltaics (PV). These closed landfills may be suitable for near-term construction, making these sites strong candidate to take advantage of the 30% Federal Business Energy Investment Tax Credit. It was prepared in response to the increasing interest in siting renewable energy on landfills from solar developers; landfill owners; and federal, state, and local governments. It contains examples of solar PV projects on landfills and technical considerations and best practices that were gathered from examining the implementation of several of these projects.

  9. Nevada Test Site Environmental Report 2005, Attachment A - Site Description

    SciTech Connect (OSTI)

    Cathy A. Wills

    2006-10-01T23:59:59.000Z

    This appendix to the ''Nevada Test Site Environmental Report 2005'', dated October 2006 (DOE/NV/11718--1214; DOE/NV/25946--007) expands on the general description of the Nevada Test Site (NTS) presented in the Introduction. Included are subsections that summarize the site?s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site which afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This appendix complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

  10. 'Supergel' System Cleans Radioactively Contaminated Structures

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of ScienceandMesa del(ANL-IN-03-032) - Energy Innovation Portal Advanced Materials Advanced Materials

  11. ORISE: Radiation and Radioactive Contamination FAQ

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated CodesTransparencyDOENurse TriageInternational Training REAC/TS

  12. Site environmental report for 1996

    SciTech Connect (OSTI)

    Holland, R.C.

    1997-08-01T23:59:59.000Z

    To help verify effective protection of public safety and preservation of the environment, Sandia National Laboratories (SNL)/California maintains an extensive, ongoing environmental monitoring program. This program monitors all significant airborne and liquid effluents and the environment at the SNL/California site perimeter. Lawrence Livermore National Laboratory (LLNL) performs off-site environmental monitoring for both sites. These monitoring efforts ensure that emission controls are effective in preventing contamination of the environment. As part of SNL/California`s Environmental Monitoring Program, an environmental surveillance system measures the possible presence of radioactive and hazardous materials in ambient air, surface water, groundwater, sewage, soil, vegetation, and locally produced food-stuffs. The program also includes an extensive environmental dosimetry program, which measures external radiation levels around the Livermore site and nearby vicinity. Each year, the results of the Environmental Monitoring Program are published in this report, the Site Environmental Report. This executive summary focuses on impacts to the environment and estimated radiation doses to the public from site emissions. Chapter 3, {open_quotes}Compliance Summary,{close_quotes} reviews the site`s various environmental protection activities and compliance status, with applicable environmental regulations. The effluent monitoring and environmental surveillance results for 1996 show that SNL/California operations had no harmful effects on the environment or the public. 37 figs., 12 tabs.

  13. On-Site Oxy-Lance Size Reduction of South Texas Project Reactor Vessel Heads - 12324

    SciTech Connect (OSTI)

    Posivak, Edward [WMG, inc. (United States); Keeney, Gilbert; Wheeler, Dean [Shaw Group (United States)

    2012-07-01T23:59:59.000Z

    On-Site Oxy-Lance size reduction of mildly radioactive large components has been accomplished at other operating plants. On-Site Oxy-Lance size reduction of more radioactive components like Reactor Vessel Heads had previously been limited to decommissioning projects. Building on past decommissioning and site experience, subcontractors for South Texas Project Nuclear Operating Company (STPNOC) developed an innovative integrated system to control smoke, radioactive contamination, worker dose, and worker safety. STP's innovative, easy to use CEDM containment that provided oxy lance access, smoke control, and spatter/contamination control was the key to successful segmentation for cost-effective and ALARA packaging and transport for disposal. Relative to CEDM milling, STP oxy-lance segmentation saved approximately 40 person- REM accrued during 9,000 hours logged into the radiological controlled area (RCA) during more than 3,800 separate entries. Furthermore there were no personnel contamination events or respiratory uptakes of radioactive material during the course of the entire project. (authors)

  14. assessing contaminant attenuation: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Conceptual model for human exposures to contamination in a solar energy facility. Click Kemner, Ken 5 DIAGNOSTIC ASSESSMENT 2 OF CONTAMINATED SITE PROBLEMS...

  15. Geochemical Controls on Contaminant Uranium in Vadose Hanford...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Controls on Contaminant Uranium in Vadose Hanford Formation Sediments at the 200 Area and 300 Area, Hanford Site, Geochemical Controls on Contaminant Uranium in Vadose Hanford...

  16. Remedial Action Plan and Site design for stabilization of the inactive Uranium Mill Tailings sites at Slick Rock, Colorado: Revision 1. Remedial action selection report, Attachment 2, geology report, Attachment 3, ground water hydrology report, Attachment 4, water resources protection strategy. Final

    SciTech Connect (OSTI)

    NONE

    1995-09-01T23:59:59.000Z

    The Slick Rock uranium mill tailings sites are located near the small community of Slick Rock, in San Miguel County, Colorado. There are two designated Uranium Mill Tailings Remedial Action (UMTRA) Project sites at Slick Rock: the Union Carbide site and the North Continent site. Both sites are adjacent to the Dolores River. The sites contain former mill building concrete foundations, tailings piles, demolition debris, and areas contaminated by windblown and waterborne radioactive materials. The total estimated volume of contaminated materials is approximately 621,000 cubic yards (475,000 cubic meters). In addition to the contamination at the two processing site areas, 13 vicinity properties were contaminated. Contamination associated with the UC and NC sites has leached into ground water. Pursuant to the requirements of the Uranium Mill Tailings Radiation Control Act (UMTRCA) (42 USC {section}7901 et seq.), the proposed remedial action plan (RAP) will satisfy the final US Environmental Protection Agency (EPA) standards in 40 CFR Part 192 (60 FR 2854) for cleanup, stabilization, and control of the residual radioactive material (RRM) (tailings and other contaminated materials) at the disposal site at Burro Canyon. The requirements for control of the RRM (Subpart A) will be satisfied by the construction of an engineered disposal cell. The proposed remedial action will consist of relocating the uranium mill tailings, contaminated vicinity property materials, demolition debris, and windblown/weaterborne materials to a permanent repository at the Burro Canyon disposal site. The site is approximately 5 road mi (8 km) northeast of the mill sites on land recently transferred to the DOE by the Bureau of Land Management.

  17. Environmental assessment of remedial action at the Slick Rock uranium mill tailings sites, Slick Rock, Colorado

    SciTech Connect (OSTI)

    NONE

    1995-01-01T23:59:59.000Z

    The Uranium Mill Tailings Radiation Control Act of 1978, hereafter referred to as the UMTRCA, authorized the US Department of Energy (DOE) to clean up two uranium mill tailings processing sites near Slick Rock, Colorado, in San Miguel County. The purpose of the cleanup is to reduce the potential health effects associated with the radioactive materials remaining on the processing sites and on vicinity properties (VPs) associated with the sites. The US Environmental Protection Agency (EPA) promulgated standards for the UMTRCA that contained measures to control the contaminated materials and to protect the ground water from further degradation. The sites contain concrete foundations of mill buildings, tailings piles, and areas contaminated by windblown and waterborne radioactive tailings materials. The proposed action is to remediate the UC and NC sites by removing all contaminated materials within the designated site boundaries or otherwise associated with the sites, and relocating them to, and stabilizing them at, a location approximately 5 road mi (8 km) northeast of the processing sites on land administered by the US Bureau of Land Management (BLM). Remediation would be performed by the DOE`s Uranium Mill Tailings Remedial Action (UMTRA) Project.

  18. Identification of contaminants of concern Columbia River Comprehensive Impact Assessment

    SciTech Connect (OSTI)

    Napier, B.A.; Batishko, N.C.; Heise-Craff, D.A.; Jarvis, M.F.; Snyder, S.F.

    1995-01-01T23:59:59.000Z

    The Columbia River Comprehensive Impact Assessment (CRCIA) Project at the Pacific Northwest Laboratory (PNL) is evaluating the current human and ecological risks from contaminants in the Columbia River. The risks to be studied are those attributable to past and present activities on the Hanford Site. The Hanford Site is located in southcentral Washington State near the town of Richland. Human risk from exposure to radioactive and hazardous materials will be addressed for a range of river use options. Ecological risk will be evaluated relative to the health of the current river ecosystem. The overall purpose of the project is to determine if enough contamination exists in the Columbia River to warrant cleanup actions under applicable environmental regulations. This report documents an initial review, from a risk perspective, of the wealth of historical data concerning current or potential contamination in the Columbia River. Sampling data were examined for over 600 contaminants. A screening analysis was performed to identify those substances present in such quantities that they may pose a significant human or ecological risk. These substances will require a more detailed analysis to assess their impact on humans or the river ecosystem.

  19. Nevada Test Site Environmental Report 2007 Attachment A: Site Description

    SciTech Connect (OSTI)

    Cathy Wills

    2008-09-01T23:59:59.000Z

    This appendix expands on the general description of the Nevada Test Site (NTS) presented in the Introduction to the Nevada Test Site Environmental Report 2007 (U.S. Department of Energy [DOE], 2008). Included are subsections that summarize the site's geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site which afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

  20. Volume reduction/solidification of liquid radioactive waste using bitumen at Ontario hydro`s Bruce nuclear generating station {open_quotes}A{close_quotes}

    SciTech Connect (OSTI)

    Day, J.E.; Baker, R.L. [ADTECHS Corporation, Herndon, VA (United States)

    1994-12-31T23:59:59.000Z

    Ontario Hydro at the Bruce Nuclear Generating Station {open_quotes}A{close_quotes} has undertaken a program to render the station`s liquid radioactive waste suitable for discharge to Lake Huron by removing sufficient radiological and chemical contaminants from five different plant waste streams. The contaminants will be immobilized and stored at on-site radioactive waste storage facilities and the purified streams will be discharged. The discharge targets established by Ontario Hydro are set well below the limits established by the Ontario Ministry of Environment (MOE) and are based on the Best Available Technology Economically Achievable Approach (B.A.T.E.A.). ADTECHS Corporation has been selected by Ontario Hydro to provide volume reduction/solidification technology for one of the five waste streams. The system will dry and immobilize the contaminants from a liquid waste stream in emulsified asphalt using thin film evaporation technology.

  1. GROUND WATER CONTAMINATION

    SciTech Connect (OSTI)

    Unknown

    1999-09-01T23:59:59.000Z

    As required by the terms of the above referenced grant, the following summary serves as the Final Report for that grant. The grant relates to work performed at two separate sites, the Hoe Creek Underground Coal Gasification Site south of Gillette, Wyoming, and the Rock Springs In-Situ Oil Shale Retort Site near Rock Springs, Wyoming. The primary concern to the State of Wyoming at each site is ground water contamination (the primary contaminants of concern are benzene and related compounds), and the purpose of the grant has been to provide tiding for a Geohydrologist at the appropriate State agency, specifically the Land Quality Division (LQD) of the Wyoming Department of Environmental Quality. The LQD Geohydrologist has been responsible for providing technical and regulatory support to DOE for ground water remediation and subsequent surface reclamation. Substantial progress has been made toward remediation of the sites, and continuation of LQD involvement in the remediation and reclamation efforts is addressed.

  2. Corrective Action Decision Document for Corrective Action Unit 168: Areas 25 and 26 Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada: Revision 0, Including Record of Technical Change No. 1

    SciTech Connect (OSTI)

    U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

    2003-08-08T23:59:59.000Z

    This Corrective Action Decision Document identifies and rationalizes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's selection of recommended corrective action alternatives (CAAs) to facilitate the closure of Corrective Action Unit (CAU)168: Areas 25 and 26 Contaminated Materials and Waste Dumps, Nevada Test Site (NTS), Nevada, under the Federal Facility Agreement and Consent Order. Located in Areas 25 and 26 at the NTS in Nevada, CAU 168 is comprised of twelve Corrective Action Sites (CASs). Review of data collected during the corrective action investigation, as well as consideration of current and future operations in Areas 25 and 26 of the NTS, led the way to the development of three CAAs for consideration: Alternative 1 - No Further Action; Alternative 2 - Clean Closure; and Alternative 3 - Close in Place with Administrative Controls. As a result of this evaluation, a combination of all three CAAs is recommended for this CAU. Alternative 1 was the preferred CAA for three CASs, Alternative 2 was the preferred CAA for six CASs (and nearly all of one other CAS), and Alternative 3 was the preferred CAA for two CASs (and a portion of one other CAS) to complete the closure at the CAU 168 sites. These alternatives were judged to meet all requirements for the technical components evaluated as well as all applicable state and federal regulations for closure of the sites and elimination of potential future exposure pathways to the contaminated soils at CAU 168.

  3. Environmental assessment of remedial action at the inactive uraniferous lignite ashing sites at Belfield and Bowman, North Dakota

    SciTech Connect (OSTI)

    Not Available

    1993-09-01T23:59:59.000Z

    The Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978 authorized the US Department of Energy (DOE) to perform remedial actions at Belfield and Bowman inactive lignite ashing sites in southwestern North Dakota to reduce the potential public health impacts from the residual radioactivity remaining at the sites. The US Environmental Protection Agency (EPA) promulgated standards (40 CFR 192) that contain measures to control the residual radioactive materials and other contaminated materials, and proposed standards to protect the groundwater from further degradation. Remedial action at the Belfield and Bowman sites must be performed in accordance with these standards and with the concurrence of the US Nuclear Regulatory Commission (NRC) and the state of North Dakota. The Belfield and Bowman designated sites were used by Union Carbide and Kerr-McGee, respectively, to process uraniferous lignite in the 1960s. Uranium-rich ash from rotary kiln processing of the lignite was loaded into rail cars and transported to uranium mills in Rifle, Colorado, and Ambrosia Lake, New Mexico, respectively. As a result of the ashing process, there is a total of 158,400 cubic yards (yd{sup 3}) [121,100 cubic meters (m{sup 3})] of radioactive ash-contaminated soils at the two sites. Windblown ash-contaminated soil covers an additional 21 acres (8.5 ha) around the site, which includes grazing land, wetlands, and a wooded habitat.

  4. Post-remediation biomonitoring of pesticides and other contaminants in marine waters and sediment near the United Heckathorn Superfund Site, Richmond, California

    SciTech Connect (OSTI)

    LD Antrim; NP Kohn

    2000-05-26T23:59:59.000Z

    Marine sediment remediation at the United Heckathorn Superfund Site was completed in April 1997. Water and mussel tissues were sampled in February 1999 from four stations near Lauritzen Canal in Richmond, California, for Year 2 of post-remediation monitoring of marine areas near the United Heckathorn Site. Dieldrin and dichlorodiphenyl trichloroethane (DDT) were analyzed in water samples, tissue samples from resident mussels, and tissue samples from transplanted mussels deployed for 4 months. Concentrations of dieldrin and total DDT in water and total DDT in tissue were compared with Year 1 of post-remediation monitoring, and with preremediation data from the California State Mussel Watch program (tissues) and the Ecological Risk Assessment for the United Heckathorn Superfund Site (tissues and water). Mussel tissues were also analyzed for polychlorinated biphenyls (PCB), which were detected in sediment samples. Chlorinated pesticide concentrations in water samples were similar to preremediation levels and did not meet remediation goals. Mean dieidrin concentrations in water ranged from 0.62 rig/L to 12.5 ng/L and were higher than the remediation goal (0.14 ng/L) at all stations. Mean total DDT concentrations in water ranged from 14.4 ng/L to 62.3 ng/L and exceeded the remediation goal (0.59 ng/L) at all stations. The highest concentrations of both pesticides were found at the Lauritzen Canal/End station. Despite exceedence of the remediation goals, chlorinated pesticide concentrations in Lauritzen Canal water samples were notably lower in 1999 than in 1998. Tissue samples from biomonitoring organisms (mussels) provide an indication of the longer-term integrated exposure to contaminants in the water column, which overcomes the limitations of grab samples of water. Biomonitoring results indicated that the bioavailability of chlorinated pesticides has been reduced from preremediation levels both in the dredged area and throughout Richmond Harbor. Total DDT and dieldrin concentrations in mussel tissues were dramatically lower than measured levels from preremediation surveys and also lower than Year 1 levels from post-remediation biomonitoring. The lowest levels were found at the Richmond Inner Harbor Channel station (4.1 {micro}g/kg total DDT and 0.59 {micro}g/kg dieldrin, wet weight; mean of resident and transplant mussels). Mean chlorinated pesticide concentrations were highest at Lauritzen Canal/End (82 {micro}g/kg total DDT and 7.1 {micro}g/kg dieldrin, wet weight), followed by Lauritzen Canal/Mouth (22 {micro}/kg total DDT and 1.7 {micro}g/kg dieldrin, wet weight) and Santa Fe Channel/End (7.5 {micro}g/kg total DOT and 0.61 {micro}g/kg dieldrin, wet weight). These levels are 95% to 99% lower than those recorded by the California State Mussel Watch program prior to EPA's response actions. The levels of PCBs in mussel tissue were also reduced by 93% to 97% from preremediation levels. Surface sediment concentrations of dieldrin and DDT in November 1998 were highest in samples from the head or north end of Lauritzen Canal and progressively lower toward the mouth, or south end. Total DDT ranged from 130 ppm (dry weight) at the north end to 3 ppm at the south end. Dieldrin concentrations decreased from 3,270 ppb (dry weight) at the north end to 52 ppb at the south end. These results confirmed elevated pesticide concentrations in sediments collected from Lauritzen Channel by Anderson et al. (1999). The pesticide concentrations were lower than maximum concentrations found in the 1993 Remedial Investigation but comparable to the median levels measured before remediation was completed. Sediment analyses also showed the presence of elevated PCB aroclor 1254, and very high levels of polynuclear aromatic hydrocarbons (PAH) in Lauritzen Channel.

  5. Environmental assessment of remedial action at the Naturita uranium processing site near Naturita, Colorado: Revision 5

    SciTech Connect (OSTI)

    Not Available

    1994-10-01T23:59:59.000Z

    Title 1 of the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, Public Law (PL) 95-604, authorized the US Department of Energy (DOE) to perform remedial action at the inactive Naturita, Colorado, uranium processing site to reduce the potential health effects from the radioactive materials at the site and at vicinity properties associated with the site. Title 2 of the UMTRCA authorized the US Nuclear Regulatory Commission (NRC) or agreement state to regulate the operation and eventual reclamation of active uranium processing sites. The uranium mill tailings at the site were removed and reprocessed from 1977 to 1979. The contaminated areas include the former tailings area, the mill yard, the former ore storage area, and adjacent areas that were contaminated by uranium processing activities and wind and water erosion. The Naturita remedial action would result in the loss of 133 acres (ac) of contaminated soils at the processing site. If supplemental standards are approved by the NRC and the state of Colorado, approximately 112 ac of steeply sloped contaminated soils adjacent to the processing site would not be cleaned up. Cleanup of this contamination would have adverse environmental consequences and would be potentially hazardous to remedial action workers.

  6. Pre-Feasibility Analysis of Pellet Manufacturing on the Former Loring Air Force Base Site. A Study Prepared in Partnership with the Environmental Protection Agency for the RE-Powering America's Land Initiative: Siting Renewable Energy on Potentially Contaminated Land and Mine Sites

    SciTech Connect (OSTI)

    Hunsberger, R.; Mosey, G.

    2014-04-01T23:59:59.000Z

    The U.S. Environmental Protection Agency (EPA) Office of Solid Waste and Emergency Response, in accordance with the RE-Powering America's Lands initiative, engaged the U.S. Department of Energy's (DOE) National Renewable Energy Laboratory (NREL) to conduct feasibility studies to assess the viability of developing renewable energy generating facilities on contaminated sites. This site, in Limestone, Maine -- formerly the location of the Loring Air Force Base but now owned by the Aroostook Band of Micmac -- was selected for the potential to produce heating pellets from woody feedstock. Biomass was chosen as the renewable energy resource to evaluate based on abundant woody-biomass resources available in the area. NREL also evaluates potential savings from converting existing Micmac property from oil-fired heating to pellet heating.

  7. Wide range radioactive gas concentration detector

    DOE Patents [OSTI]

    Anderson, David F. (Los Alamos, NM)

    1984-01-01T23:59:59.000Z

    A wide range radioactive gas concentration detector and monitor which is capable of measuring radioactive gas concentrations over a range of eight orders of magnitude. The device of the present invention is designed to have an ionization chamber which is sufficiently small to give a fast response time for measuring radioactive gases but sufficiently large to provide accurate readings at low concentration levels. Closely spaced parallel plate grids provide a uniform electric field in the active region to improve the accuracy of measurements and reduce ion migration time so as to virtually eliminate errors due to ion recombination. The parallel plate grids are fabricated with a minimal surface area to reduce the effects of contamination resulting from absorption of contaminating materials on the surface of the grids. Additionally, the ionization chamber wall is spaced a sufficient distance from the active region of the ionization chamber to minimize contamination effects.

  8. DEVELOPMENT OF GLASS MATRICES FOR HLW RADIOACTIVE WASTES

    SciTech Connect (OSTI)

    Jantzen, C.

    2010-03-18T23:59:59.000Z

    Vitrification is currently the most widely used technology for the treatment of high level radioactive wastes (HLW) throughout the world. Most of the nations that have generated HLW are immobilizing in either borosilicate glass or phosphate glass. One of the primary reasons that glass has become the most widely used immobilization media is the relative simplicity of the vitrification process, e.g. melt waste plus glass forming frit additives and cast. A second reason that glass has become widely used for HLW is that the short range order (SRO) and medium range order (MRO) found in glass atomistically bonds the radionuclides and governs the melt properties such as viscosity, resistivity, sulphate solubility. The molecular structure of glass controls contaminant/radionuclide release by establishing the distribution of ion exchange sites, hydrolysis sites, and the access of water to those sites. The molecular structure is flexible and hence accounts for the flexibility of glass formulations to waste variability. Nuclear waste glasses melt between 1050-1150 C which minimizes the volatility of radioactive components such as Tc{sup 99}, Cs{sup 137}, and I{sup 129}. Nuclear waste glasses have good long term stability including irradiation resistance. Process control models based on the molecular structure of glass have been mechanistically derived and have been demonstrated to be accurate enough to control the world's largest HLW Joule heated ceramic melter in the US since 1996 at 95% confidence.

  9. DOE Moab Site Cost-Effectively Eliminates 200 Million Gallons...

    Office of Environmental Management (EM)

    Site Cost-Effectively Eliminates 200 Million Gallons of Contaminated Ground Water DOE Moab Site Cost-Effectively Eliminates 200 Million Gallons of Contaminated Ground Water July...

  10. Modeling for Airborne Contamination

    SciTech Connect (OSTI)

    F.R. Faillace; Y. Yuan

    2000-08-31T23:59:59.000Z

    The objective of Modeling for Airborne Contamination (referred to from now on as ''this report'') is to provide a documented methodology, along with supporting information, for estimating the release, transport, and assessment of dose to workers from airborne radioactive contaminants within the Monitored Geologic Repository (MGR) subsurface during the pre-closure period. Specifically, this report provides engineers and scientists with methodologies for estimating how concentrations of contaminants might be distributed in the air and on the drift surfaces if released from waste packages inside the repository. This report also provides dose conversion factors for inhalation, air submersion, and ground exposure pathways used to derive doses to potentially exposed subsurface workers. The scope of this report is limited to radiological contaminants (particulate, volatile and gaseous) resulting from waste package leaks (if any) and surface contamination and their transport processes. Neutron activation of air, dust in the air and the rock walls of the drift during the preclosure time is not considered within the scope of this report. Any neutrons causing such activation are not themselves considered to be ''contaminants'' released from the waste package. This report: (1) Documents mathematical models and model parameters for evaluating airborne contaminant transport within the MGR subsurface; and (2) Provides tables of dose conversion factors for inhalation, air submersion, and ground exposure pathways for important radionuclides. The dose conversion factors for air submersion and ground exposure pathways are further limited to drift diameters of 7.62 m and 5.5 m, corresponding to the main and emplacement drifts, respectively. If the final repository design significantly deviates from these drift dimensions, the results in this report may require revision. The dose conversion factors are further derived by using concrete of sufficient thickness to simulate the drift walls. The gamma-ray scattering properties of concrete are sufficiently similar to those of the host rock and proposed insert material; use of concrete will have no significant impact on the conclusions. The information in this report is presented primarily for use in performing pre-closure radiological safety evaluations of radiological contaminants, but it may also be used to develop strategies for contaminant leak detection and monitoring in the MGR. Included in this report are the methods for determining the source terms and release fractions, and mathematical models and model parameters for contaminant transport and distribution within the repository. Various particle behavior mechanisms that affect the transport of contaminant are included. These particle behavior mechanisms include diffusion, settling, resuspension, agglomeration and other deposition mechanisms.

  11. DOE - Office of Legacy Management -- St Louis Airport Site Vicinity...

    Office of Legacy Management (LM)

    Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: These properties are located in Hazelwood and Berkeley, Missouri,...

  12. Nevada National Security Site Radiological Control Manual

    SciTech Connect (OSTI)

    Radiological Control Managers’ Council

    2012-03-26T23:59:59.000Z

    This document supersedes DOE/NV/25946--801, 'Nevada Test Site Radiological Control Manual,' Revision 1 issued in February 2010. Brief Description of Revision: A complete revision to reflect a recent change in name for the NTS; changes in name for some tenant organizations; and to update references to current DOE policies, orders, and guidance documents. Article 237.2 was deleted. Appendix 3B was updated. Article 411.2 was modified. Article 422 was re-written to reflect the wording of DOE O 458.1. Article 431.6.d was modified. The glossary was updated. This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE) and the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection.' Programs covered by this manual are located at the Nevada National Security Site (NNSS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Livermore, California; and Andrews Air Force Base, Maryland. In addition, fieldwork by NNSA/NSO at other locations is covered by this manual. Current activities at NNSS include operating low-level radioactive and mixed waste disposal facilities for United States defense-generated waste, assembly and execution of subcritical experiments, assembly/disassembly of special experiments, the storage and use of special nuclear materials, performing criticality experiments, emergency responder training, surface cleanup and site characterization of contaminated land areas, environmental activity by the University system, and nonnuclear test operations, such as controlled spills of hazardous materials at the Hazardous Materials Spill Center. Currently, the major potential for occupational radiation exposure is associated with the burial of low-level radioactive waste and the handling of radioactive sources. Remediation of contaminated land areas may also result in radiological exposures.

  13. Radioactive waste material melter apparatus

    DOE Patents [OSTI]

    Newman, Darrell F. (Richland, WA); Ross, Wayne A. (Richland, WA)

    1990-01-01T23:59:59.000Z

    An apparatus for preparing metallic radioactive waste material for storage is disclosed. The radioactive waste material is placed in a radiation shielded enclosure. The waste material is then melted with a plasma torch and cast into a plurality of successive horizontal layers in a mold to form a radioactive ingot in the shape of a spent nuclear fuel rod storage canister. The apparatus comprises a radiation shielded enclosure having an opening adapted for receiving a conventional transfer cask within which radioactive waste material is transferred to the apparatus. A plasma torch is mounted within the enclosure. A mold is also received within the enclosure for receiving the melted waste material and cooling it to form an ingot. The enclosure is preferably constructed in at least two parts to enable easy transport of the apparatus from one nuclear site to another.

  14. Radioactive waste material melter apparatus

    DOE Patents [OSTI]

    Newman, D.F.; Ross, W.A.

    1990-04-24T23:59:59.000Z

    An apparatus for preparing metallic radioactive waste material for storage is disclosed. The radioactive waste material is placed in a radiation shielded enclosure. The waste material is then melted with a plasma torch and cast into a plurality of successive horizontal layers in a mold to form a radioactive ingot in the shape of a spent nuclear fuel rod storage canister. The apparatus comprises a radiation shielded enclosure having an opening adapted for receiving a conventional transfer cask within which radioactive waste material is transferred to the apparatus. A plasma torch is mounted within the enclosure. A mold is also received within the enclosure for receiving the melted waste material and cooling it to form an ingot. The enclosure is preferably constructed in at least two parts to enable easy transport of the apparatus from one nuclear site to another. 8 figs.

  15. Corrective Action Investigation Plan for Corrective Action Unit 366: Area 11 Plutonium Valley Dispersion Sites, Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Patrick Matthews

    2011-09-01T23:59:59.000Z

    Corrective Action Unit 366 comprises the six corrective action sites (CASs) listed below: (1) 11-08-01, Contaminated Waste Dump No.1; (2) 11-08-02, Contaminated Waste Dump No.2; (3) 11-23-01, Radioactively Contaminated Area A; (4) 11-23-02, Radioactively Contaminated Area B; (5) 11-23-03, Radioactively Contaminated Area C; and (6) 11-23-04, Radioactively Contaminated Area D. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed July 6, 2011, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 366. The presence and nature of contamination at CAU 366 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the total effective dose (TED) at sample locations to the dose-based final action level (FAL). The TED will be calculated by summing the estimates of internal and external dose. Results from the analysis of soil samples collected from sample plots will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at each sample location will be used to measure external radiological dose. Based on historical documentation of the releases associated with the nuclear tests, it was determined that CASs 11-23-02, 11-23-03, and 11-23-04 will be investigated as one release site. The three test areas associated with these CASs are in close proximity; the devices tested were all composed of plutonium and enriched uranium; and the ground zeroes are all posted high contamination areas (HCAs). Because the device tested at CAS 11-23-01 was composed primarily of enriched uranium and the ground zero is not a posted HCA, the CAS will be investigated as a separate release. The DQO process also resulted in an assumption that TED within the HCAs and contaminated waste dumps exceeds the FAL and requires corrective action. A field investigation will be performed to define where TED exceeds the FAL and to determine whether other contaminants of concern are present at the site associated with other activities that took place at the site or from spills or waste discovered during the investigation. The presence and nature of contamination from other types of releases (such as migration and any potential releases discovered during the investigation) will be evaluated using soil samples collected from the locations most likely containing contamination, if present. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS.

  16. Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Slick Rock, Colorado: Attachment 4, water resources protection strategy; Preliminary final

    SciTech Connect (OSTI)

    NONE

    1994-03-01T23:59:59.000Z

    This attachment contains a summary of the proposed water resources protection strategy developed to achieve compliance with US EPA ground water protection standards for the remedial action plan at the Slick Rock, CO uranium mill tailings sites. Included are the conceptual design considerations such as climate and infiltration, surface and subsurface drainage, and features for water resources protection such as disposal cell cover components, transient drainage and control of construction water, subsidence and disposal cell longevity. The disposal and control of radioactive materials and nonradioactive contaminants as it relates to ground water protection standards is discussed, and the plan for cleanup and control of existing contamination is outlined.

  17. EA-1331: Remediation of Subsurface and Groundwater Contamination at the Rock Springs in situ Oil Shale Retort Site, Sweetwater County, Wyoming

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts for the proposal for the Rock Springs In-Situ Oil Shale Retort Test Site remediation that would be performed at the Rock Springs site in Sweetwater...

  18. Multimedia assessment of health risks for the Weldon Spring site remedial action project

    SciTech Connect (OSTI)

    Haroun, L.A.; MacDonell, M.M.; Peterson, J.M.; Fingleton, D.J.

    1990-01-01T23:59:59.000Z

    The US Department of Energy (DOE), under its Surplus Facilities Management Program (SFMP), is responsible for cleanup activities at the Weldon Spring site, Weldon Spring, Missouri. The site consists of two noncontiguous areas: the chemical plant area, which includes four raffinate pits, and the quarry. The Weldon Spring site became radioactively and chemically contaminated as a result of processing and disposal activities that took place from the 1940s through the 1960s. The US Department of the Army used the Weldon Spring site to produce dinitrotoluene (DNT) and trinitrotoluene (TNT) explosives from 1941 to 1946. The US Atomic Energy Commission (AEC, predecessor of the DOE) used the site to process uranium and thorium ore concentrates from 1957 to 1966. The quarry was used by the Army and the AEC for waste disposal beginning in the early 1940s; it was last used for disposal in 1969. Wastes placed in the quarry include TNT and DNT residues and radioactively contaminated materials. A summary of disposal activities at the quarry is presented. As part of the environmental compliance process at the Weldon Spring site, a baseline risk evaluation (BRE) was prepared to assess the potential risks associated with contamination present at the quarry. 13 refs., 2 figs., 6 tabs.

  19. RESULTS FOR THE THIRD QUARTER 2007 TANK 50H WAC SLURRY SAMPLE: CHEMICAL AND RADIONUCLIDE CONTAMINANT RESULTS

    SciTech Connect (OSTI)

    Zeigler, K; Ned Bibler, N

    2008-07-11T23:59:59.000Z

    The Saltstone Facility is designed and permitted to immobilize and dispose of low-level radioactive and hazardous liquid waste (salt solution) remaining from the processing of radioactive material at the Savannah River Site. Low activity wastewater streams from the Effluent Treatment Project (ETP), H-Canyon, and the high level waste (HLW) storage tanks, are stored as a mixture in Tank 50H until it can be pumped to the Saltstone Facility for treatment and disposal. Specific waste acceptance criteria (WAC) must be met for the transfer of low-level aqueous waste from Tank 50H to the Saltstone Facility. Low level waste which meets the WAC can be transferred, stored and treated in the Saltstone Production Facility (SPF) for subsequent disposal as saltstone in the Saltstone Disposal Facility (SDF). Waste Solidification Engineering (WSE) has requested through a Technical Task Request (TTR) that the Savannah River National Laboratory (SRNL) measure the concentrations of chemical and radionuclide contaminants listed in the currently approved Saltstone Waste Acceptance Criteria (WAC). A Task Technical and Quality Assurance Plan and Analytical Study Plan has been written for this request. WAC determinations are needed on a quarterly basis for chemical contaminants and every first and third quarter for radioactive contaminants. This memorandum presents the results for the chemical and radionuclide contaminants in the third quarter, from the samples taken from Tank 50 in September, 2007.

  20. Thermal treatment of organic radioactive waste

    SciTech Connect (OSTI)

    Chrubasik, A.; Stich, W. [NUKEM GmbH, Alzenau (Germany)

    1993-12-31T23:59:59.000Z

    The organic radioactive waste which is generated in nuclear and isotope facilities (power plants, research centers and other) must be treated in order to achieve a waste form suitable for long term storage and disposal. Therefore the resulting waste treatment products should be stable under influence of temperature, time, radioactivity, chemical and biological activity. Another reason for the treatment of organic waste is the volume reduction with respect to the storage costs. For different kinds of waste, different treatment technologies have been developed and some are now used in industrial scale. The paper gives process descriptions for the treatment of solid organic radioactive waste of low beta/gamma activity and alpha-contaminated solid organic radioactive waste, and the pyrolysis of organic radioactive waste.

  1. Challenges associated with final status survey implementation at a Formerly Utilized Sites Remedial Action Program (Fusrap) Site's adjacent properties

    SciTech Connect (OSTI)

    Sokody, K.J. [Shaw Environmental and Infrastructure, Tonawanda, NY (United States); Boyle, J.D. [U. S. Army Corps of Engineers - Buffalo District, Buffalo, NY (United States)

    2007-07-01T23:59:59.000Z

    Several properties located adjacent to the Linde Formerly Utilized Sites Remedial Action Program (FUSRAP) site in Tonawanda, New York were radiologically contaminated during Manhattan Engineer District (MED) era activities. These properties exhibited a combination of unique characteristics not previously encountered at the Linde Site. This included the properties being littered with building debris, a combination of metals and cesium-137 (Cs-137) commingled in the soil, thorium-230 (Th-230) being the dominant radioactive MED contaminant, and the radioactive contamination consisting of a five to seventy six centimeter thick black colored lens located at various depths below the ground surface. Because of the unique characteristics, several challenges were encountered with the characterization, implementation of the final status survey process to demonstrate compliance with the Record of Decision (ROD) [1], and subsequent remediation of these properties. Overcoming these challenges required a reevaluation of the previously developed gross gamma screening and soil core screening correlation values that ensured both the primary ROD requirements and expected residual concentrations would be met. Furthermore, modifications to the sampling, field implementation, and documentation process necessitated a revision to the Final Status Survey Plan (FSSP) to accommodate the unique conditions present at the adjacent properties. (authors)

  2. Helium-3/Helium-4 Ratios in Soil Gas as an Indicator of Tritium Contamination Near the 618-11 Burial Ground, Hanford Site, Washington

    SciTech Connect (OSTI)

    Olsen, Khris B.; Dresel, P Evan; Evans, J. C.; Poreda, Robert

    2004-10-09T23:59:59.000Z

    Pacific Northwest National Laboratory sampled and analyzed soil gas for helium-3 and helium-4 concentrations from the vicinity of the 618-11 burial ground. The results of the measurement of helium isotopes in soil gas provided a rapid and cost-effective technique to define the shape and extent of tritium contamination from the 618-11 burial ground.

  3. SUMMARY REPORT FOR ZINC 65 CONTAMINATION CONTROL

    SciTech Connect (OSTI)

    Korinko, P.

    2011-07-14T23:59:59.000Z

    Radioactive zinc, {sup 65}Zn, was detected after extraction of 215 TPBARs in from TVA reactor fuel cycle 6. A team consisting of Tritium Engineering, Tritium Operations, Tritium Radiation Control, and Savannah River National Laboratory personnel evaluated the risk and response and developed short, medium and long term goals for contamination control. One of the goals was incorporated into site Performance Based Incentive CO 3.4, to optimize the filter geometry and operating conditions for the Tritium Extraction Facility. This goal included a scoping study to determine if the contamination could be contained within the high radiation environment of the furnace module as well. In order to optimize the filters studies were conducted to independently evaluate the effect of pore size on pumping efficiency and zinc trapping efficiency (1). A study was also conducted to evaluate the effect of temperature on the trapping efficiency and adhesion (2). In addition, the potential for chemically trapping zinc in the lithium trap was evaluated using a thermodynamic study (3) followed by preliminary experimental testing (4). Based on the work that was completed it is determined that a 20 {mu}m filter heated to between 120 and 200 C will act as an effective physical trap for zinc vapors. It may be possible to chemically react zinc with copper or cobalt to form zinc intermetallic compounds or alloys but additional work under more prototypic conditions are required.

  4. Mechanisms of contaminant migration from grouted waste

    SciTech Connect (OSTI)

    Magnuson, S.O. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Yu, A.D. [Westinghouse Savannah River Co., Aiken, SC (United States)

    1992-12-31T23:59:59.000Z

    Low-level radioactive decontaminated salt solution is generated at the Savannah River Site (SRS) from the In-Tank Precipitation process. The solution is mixed with cement, slag, and fly ash, to form a grout, termed ``Saltstone``, that will be disposed in concrete vaults at the Saltstone Disposal Facility (SDF) [1]. Of the contaminants in the Saltstone, the greatest concern to SRS is the potential release of nitrate to the groundwater because of the high initial nitrate concentration (0.25 g/cm{sup 3}) in the Saltstone and the low Safe Drinking Water Act (SDWA) maximum contaminant level (MCL) of 44 mg/L. The SDF is designed to allow a slow, controlled release over thousands of years. This paper addresses a modeling study of nitrate migration from intact non-degraded concrete vaults in the unsaturated zone for the Radiological Performance Assessment (PA) of the SRS Saltstone Disposal Facility [3]. The PA addresses the performance requirements mandated by DOE Order 5820.2A [4].

  5. Field-deployable, nano-sensing approach for real-time detection of free mercury, speciation and quantification in surface stream waters and groundwater samples at the U.S. Department of Energy contaminated sites

    SciTech Connect (OSTI)

    Campiglia, Andres D. [UCF; Hernandez, Florencio E. [UCF

    2014-08-28T23:59:59.000Z

    The detrimental effects on human health caused by long-term exposure to trace contamination of toxic metals have been documented in numerous epidemiological and toxicological studies. The fact that metals are non-biodegradable and accumulate in the food chain poses a severe threat to the environment and human health. Their monitoring in drinking water, aquatic ecosystems, food and biological fluids samples is then essential for global sustainability. While research efforts employing established methodology continue to advance conceptual/computational models of contaminant behavior, the increasing awareness and public concern with environmental and occupational exposure to toxic metals calls for sensing devices capable to handle on-site elemental analysis in short analysis time. Field analysis with potable methodology prevents unnecessary scrutiny of un-contaminated samples via laboratory-bound methods, reduces analysis cost and expedites turnaround time for decision making and remediation purposes. Of particular toxicological interest are mercury and its species. Mercury is recognized as a major environmental pollution issue. The field-portable sensor developed in this project provides a unique and valuable tool for the on-site, real-time determination of inorganic mercury in surface waters. The ability to perform on-site analysis of mercury should prove useful in remote locations with difficult accessibility. It should facilitate data collection from statistically meaningful population sizes for a better understanding of the dose-effect role and the water-soil-plant-animal-human transfer mechanisms. The acquired knowledge should benefit the development of efficient environmental remediation processes, which is extremely relevant for a globally sustainable environment.

  6. Reducing Contingency through Sampling at the Luckey FUSRAP Site - 13186

    SciTech Connect (OSTI)

    Frothingham, David; Barker, Michelle; Buechi, Steve [U.S. Army Corps of Engineers Buffalo District, 1776 Niagara St., Buffalo, NY 14207 (United States)] [U.S. Army Corps of Engineers Buffalo District, 1776 Niagara St., Buffalo, NY 14207 (United States); Durham, Lisa [Argonne National Laboratory, Environmental Science Division, 9700 S. Cass Ave., Argonne, IL 60439 (United States)] [Argonne National Laboratory, Environmental Science Division, 9700 S. Cass Ave., Argonne, IL 60439 (United States)

    2013-07-01T23:59:59.000Z

    Typically, the greatest risk in developing accurate cost estimates for the remediation of hazardous, toxic, and radioactive waste sites is the uncertainty in the estimated volume of contaminated media requiring remediation. Efforts to address this risk in the remediation cost estimate can result in large cost contingencies that are often considered unacceptable when budgeting for site cleanups. Such was the case for the Luckey Formerly Utilized Sites Remedial Action Program (FUSRAP) site near Luckey, Ohio, which had significant uncertainty surrounding the estimated volume of site soils contaminated with radium, uranium, thorium, beryllium, and lead. Funding provided by the American Recovery and Reinvestment Act (ARRA) allowed the U.S. Army Corps of Engineers (USACE) to conduct additional environmental sampling and analysis at the Luckey Site between November 2009 and April 2010, with the objective to further delineate the horizontal and vertical extent of contaminated soils in order to reduce the uncertainty in the soil volume estimate. Investigative work included radiological, geophysical, and topographic field surveys, subsurface borings, and soil sampling. Results from the investigative sampling were used in conjunction with Argonne National Laboratory's Bayesian Approaches for Adaptive Spatial Sampling (BAASS) software to update the contaminated soil volume estimate for the site. This updated volume estimate was then used to update the project cost-to-complete estimate using the USACE Cost and Schedule Risk Analysis process, which develops cost contingencies based on project risks. An investment of $1.1 M of ARRA funds for additional investigative work resulted in a reduction of 135,000 in-situ cubic meters (177,000 in-situ cubic yards) in the estimated base volume estimate. This refinement of the estimated soil volume resulted in a $64.3 M reduction in the estimated project cost-to-complete, through a reduction in the uncertainty in the contaminated soil volume estimate and the associated contingency costs. (authors)

  7. Combustible radioactive waste treatment by incineration and chemical digestion

    SciTech Connect (OSTI)

    Stretz, L.A.; Crippen, M.D.; Allen, C.R.

    1980-05-28T23:59:59.000Z

    A review is given of present and planned combustible radioactive waste treatment systems in the US. Advantages and disadvantages of various systems are considered. Design waste streams are discussed in relation to waste composition, radioactive contaminants by amount and type, and special operating problems caused by the waste.

  8. Variation in DNA content of blood cells of largemouth bass from contaminated and uncontaminated waters

    SciTech Connect (OSTI)

    Lingenfelser, S.F. [Fish and Wildlife Service, White Marsh, VA (United States); Dallas, C.E. [Univ. of Georgia, Athens, GA (United States). Dept. of Pharmacology and Toxicology; Jagoe, C.H.; Smith, M.H.; Brisbin, I.L. Jr.; Chesser, R.K. [Savannah River Ecology Lab., Aiken, SC (United States)

    1997-10-01T23:59:59.000Z

    Largemouth bass (Micropterus salmoides) were collected from locations with and without documented histories of pollution in Georgia and South Carolina. Whole blood samples were collected from over 3,000 bass and analyzed by flow cytometry to measure changes in cellular DNA content and cell cycle distribution. The coefficient of variation (CV) of the cell cycle phase G{sub 0}G{sub 1} peak was used as a measure of variation in DNA content within an individual. The mean CV varied significantly among locations, and some locations with known chemical or radioactive contaminants had higher CVs. Plotting the frequency distribution of CV values for each site revealed greater skewness and kurtosis in most locations with known contaminants. In each case, a right skewness indicated higher proportions of bass with unusually high CV in these locations. Aneuploid-like patterns were detected in the DNA histograms of five fish, all from locations with histories of contamination. The percentage of cells distributed among phases of the cell cycle (G{sub 0}/G{sub 1}, S, and G{sub 2}M) varied significantly among locations, but there was no apparent relationship to contaminant distribution. Differences in CV and frequency of aneuploids among sites with and without histories of pollution were generally small, but increased variation in DNA content may be associated with contaminant exposure at some locations.

  9. Year 4 Post-Remediation Biomonitoring of Pesticides and Other Contaminants in Marine Waters Near the United Heckathorn Superfund Site, Richmond, California

    SciTech Connect (OSTI)

    Kohn, Nancy P.; Kropp, Roy

    2001-12-20T23:59:59.000Z

    This report is fourth in a series of annual reports describing the results of biomonitoring following remediation of the United Heckathorn Superfund Site.

  10. Cleaning Contaminated Water at Fukushima

    SciTech Connect (OSTI)

    Rende, Dean; Nenoff, Tina

    2013-11-21T23:59:59.000Z

    Crystalline Silico-Titanates (CSTs) are synthetic zeolites designed by Sandia National Laboratories scientists to selectively capture radioactive cesium and other group I metals. They are being used for cleanup of radiation-contaminated water at the Fukushima Daiichi nuclear power plant in Japan. Quick action by Sandia and its corporate partner UOP, A Honeywell Company, led to rapid licensing and deployment of the technology in Japan, where it continues to be used to clean up cesium contaminated water at the Fukushima power plant.

  11. Cleaning Contaminated Water at Fukushima

    ScienceCinema (OSTI)

    Rende, Dean; Nenoff, Tina

    2014-02-26T23:59:59.000Z

    Crystalline Silico-Titanates (CSTs) are synthetic zeolites designed by Sandia National Laboratories scientists to selectively capture radioactive cesium and other group I metals. They are being used for cleanup of radiation-contaminated water at the Fukushima Daiichi nuclear power plant in Japan. Quick action by Sandia and its corporate partner UOP, A Honeywell Company, led to rapid licensing and deployment of the technology in Japan, where it continues to be used to clean up cesium contaminated water at the Fukushima power plant.

  12. Improving Modeling of Iodine-129 Groundwater Contamination Plumes Using the System Assessment Capability

    SciTech Connect (OSTI)

    Dirkes, J.; Nichols, W.E.; Wurstner, S.K.

    2004-01-01T23:59:59.000Z

    Years of production of radioactive materials at the Hanford Site in southeastern Washington State has resulted in contamination of surface, subsurface, and surface water environments. Cleanup of the site has been aided by various tools, including computer software used to predict contaminant migration in the future and estimate subsequent impacts. The System Assessment Capability (SAC) is a total systems tool designed to simulate the movement of contaminants from all waste sites at Hanford through the vadose zone, the unconfined aquifer, and the Columbia River. Except for iodine-129, most of the contaminants modeled by SAC have acceptably matched field measurements. The two most likely reasons for the inconsistency between the measured field data and SAC modeled predictions are an underestimated inventory and an overestimated sorption value (Kd). Field data tend to be point measurements taken from near the surface of the unconfined aquifer. Thus, the depth of the iodine-129 contamination plume on the site is not well characterized. Geostatistical analyses of the measured data were conducted to determine the mass of iodine-129 for four assumed plume depths within the unconfined aquifer. Several simulations for two different Kd’s using the initial SAC inventory were run to determine the effect of an overestimated sorption value on SAC modeled predictions. The initial SAC inventory was then increased for the two different Kd’s to determine the influence of an underestimated inventory on SAC modeled predictions. It was found that evidence for both an underestimated inventory and for an overestimated sorption value for iodine-129 exist. These results suggest that the Kd for iodine-129 should be reevaluated and that a more complete inventory must be generated in order to more accurately model iodine-129 groundwater contamination plumes that match available field data.

  13. Phase I Contaminant Transport Parameters for the Groundwater Flow and Contaminant Transport Model of Corrective Action Unit 97: Yucca Flat/Climax Mine, Nevada Test Site, Nye County, Nevada, Revision 0

    SciTech Connect (OSTI)

    John McCord

    2007-09-01T23:59:59.000Z

    This report documents transport data and data analyses for Yucca Flat/Climax Mine CAU 97. The purpose of the data compilation and related analyses is to provide the primary reference to support parameterization of the Yucca Flat/Climax Mine CAU transport model. Specific task objectives were as follows: • Identify and compile currently available transport parameter data and supporting information that may be relevant to the Yucca Flat/Climax Mine CAU. • Assess the level of quality of the data and associated documentation. • Analyze the data to derive expected values and estimates of the associated uncertainty and variability. The scope of this document includes the compilation and assessment of data and information relevant to transport parameters for the Yucca Flat/Climax Mine CAU subsurface within the context of unclassified source-term contamination. Data types of interest include mineralogy, aqueous chemistry, matrix and effective porosity, dispersivity, matrix diffusion, matrix and fracture sorption, and colloid-facilitated transport parameters.

  14. Acceptance of Soil from Off Site Sources In order to guard against receiving contaminated soils to used as fill material on campus,

    E-Print Network [OSTI]

    de Lijser, Peter

    regulations governing the remediation of site, and hazardous chemical disposal. Local Oversight Program Agency basic information for determining if there has been a release of a hazardous substance that present specifications. Because most sites requiring fill material are located in or near urban areas, the fill materials

  15. Patterns of mercury and methylmercury bioaccumulation in fish species downstream of a long-term mercury-contaminated site in the lower Ebro River

    E-Print Network [OSTI]

    García-Berthou, Emili

    Patterns of mercury and methylmercury bioaccumulation in fish species downstream of a long that the highest biological impact attributable to mercury pollution occurred downstream of the discharge site mercury (THg) and methylmercury (MeHg) at the discharge site and downstream points. Multiple

  16. Environmental assessment of remedial action at the Naturita Uranium Processing Site near Naturita, Colorado. Revision 4

    SciTech Connect (OSTI)

    Not Available

    1994-05-01T23:59:59.000Z

    The Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, Public Law (PL) 95-604, authorized the US Department of Energy (DOE) to perform remedial action at the Naturita, Colorado, uranium processing site to reduce the potential health effects from the radioactive materials at the site and at vicinity properties associated with the site. The US Environmental Protection Agency (EPA) promulgated standards for the UMTRCA that contain measures to control the contaminated materials and to protect groundwater quality. Remedial action at the Naturita site must be performed in accordance with these standards and with the concurrence of the US Nuclear Regulatory Commission (NRC) and the state of Colorado. The proposed remedial action for the Naturita processing site is relocation of the contaminated materials and debris to either the Dry Flats disposal site, 6 road miles (mi) [10 kilometers (km)] to the southeast, or a licensed non-DOE disposal facility capable of handling RRM. At either disposal site, the contaminated materials would be stabilized and covered with layers of earth and rock. The proposed Dry Flats disposal site is on land administered by the Bureau of Land Management (BLM) and used primarily for livestock grazing. The final disposal site would cover approximately 57 ac (23 ha), which would be permanently transferred from the BLM to the DOE and restricted from future uses. The remedial action would be conducted by the DOE`s Uranium Mill Tailings Remedial Action (UMTRA) Project. This report discusses environmental impacts associated with the proposed remedial action.

  17. The Savannah River Site`s Groundwater Monitoring Program. Fourth quarter 1988

    SciTech Connect (OSTI)

    Not Available

    1989-12-31T23:59:59.000Z

    The Environmental Monitoring Group of the Health Protection Department administers the Savannah River Site`s Groundwater Monitoring Program. During fourth quarter 1988 (October--December), routine sampling of monitoring wells and drinking water locations was performed. The drinking water samples were collected from Savannah River Site (SRS) drinking water systems supplied by wells. Two sets of flagging criteria were established in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead they aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. An explanation of flagging criteria for the fourth quarter is presented in the Flagging Criteria section of this document. The drinking water samples were analyzed for radioactive constituents.

  18. Site environmental report for calendar year 1997, Yucca Mountain Site, Nye County, Nevada

    SciTech Connect (OSTI)

    NONE

    1998-10-01T23:59:59.000Z

    This document is the seventh annual Site Environmental Report (SER) submitted by the Yucca Mountain Site Characterization Office (YMSCO) to describe the environmental program implemented by the US Department of Energy (DOE) at Yucca Mountain. As prescribed by the Nuclear Waste Policy Act (NWPA, 1982), this program ensures that site characterization activities are conducted in a manner that minimizes any significant adverse impacts to the environment and complies with all applicable laws and regulations. The most recent guidelines for the preparation of the SER place major emphasis on liquid and gaseous emissions of radionuclides, pollutants or hazardous substances; human exposure to radionuclides; and trends observed by comparing data collected over a period of years. To date, the YMP has not been the source of any radioactive emissions or been responsible for any human exposure to radionuclides. Minuscule amounts of radioactivity detected at the site are derived from natural sources or from dust previously contaminated by nuclear tests conducted in the past at the NTS. Because data for only a few years exist for the site, identification of long-term trends is not yet possible. Despite the lack of the aforementioned categories of information requested for the SER, the YMP has collected considerable material relevant to this report. An extensive environmental monitoring and mitigation program is currently in place and is described herein. Also, as requested by the SER guidelines, an account of YMP compliance with appropriate environmental legislation is provided.

  19. Conceptual Design Report: Nevada Test Site Mixed Waste Disposal Facility Project

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2009-01-31T23:59:59.000Z

    Environmental cleanup of contaminated nuclear weapons manufacturing and test sites generates radioactive waste that must be disposed. Site cleanup activities throughout the U.S. Department of Energy (DOE) complex are projected to continue through 2050. Some of this waste is mixed waste (MW), containing both hazardous and radioactive components. In addition, there is a need for MW disposal from other mission activities. The Waste Management Programmatic Environmental Impact Statement Record of Decision designates the Nevada Test Site (NTS) as a regional MW disposal site. The NTS has a facility that is permitted to dispose of onsite- and offsite-generated MW until November 30, 2010. There is not a DOE waste management facility that is currently permitted to dispose of offsite-generated MW after 2010, jeopardizing the DOE environmental cleanup mission and other MW-generating mission-related activities. A mission needs document (CD-0) has been prepared for a newly permitted MW disposal facility at the NTS that would provide the needed capability to support DOE's environmental cleanup missi