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Sample records for radiological surveys site

  1. radiological. survey

    National Nuclear Security Administration (NNSA)

    7%2A en NNSA to Conduct Aerial Radiological Surveys Over San Francisco, Pacifica, Berkeley, And Oakland, CA Areas http:nnsa.energy.govmediaroompressreleasesamsca

  2. COT"IPREITENS IVE RADIOLOGICAL SURVEY OFF-SITE PROPERTY P NIAGARA...

    Office of Legacy Management (LM)

    COT"IPREITENS IVE RADIOLOGICAL SURVEY OFF-SITE PROPERTY P NIAGARA FALIS STORAGE SITE LEWISTON, NEW YORK Prepared for U.S. DePartment of EnergY as part of the Formerly Utilized ...

  3. Radiological survey report for the Weldon Spring Raffinate Pits site, Weldon Spring, Missouri

    SciTech Connect

    Not Available

    1984-08-01

    The Weldon Spring Site (WSS) is a US Department of Energy (DOE) surplus facility comprising the Raffinate Pits facility, the Quarry, and potentially contaminated vicinity properties. Radiological characterization of the WSS will be conducted in three phases: the Raffinate Pits facility, Quarry, and the vicinity properties. Bechtel National, Inc. (BNI) and its radiological support subcontractor, Eberline Instrument Corporation (EIC), conducted a radiological characterization survey of the Raffinate Pits during 1982 and 1983 in support of on-site construction work and a technical evaluation of site geology. The survey consisted of direct beta-gamma surface readings, near-surface gamma readings, exposure level measurements, and gamma-logs of boreholes. Soil samples were also collected from the surface, shallow boreholes, and trenches on the site. This report describes the radiological characterization of the Raffinate Pits facility, the procedures used to conduct the survey, the survey results, and their significance. 5 references, 9 figures, 8 tables.

  4. Aerial radiological surveys of Steed Pond, Savannah River Site: Dates of surveys, 1984--1989

    SciTech Connect

    Fritzsche, A.E.; Jobst, J.E.

    1993-09-01

    From June 1984 to August 1985, three aerial radiological surveys were conducted over Steed Pond at the Savannah River Site in South Carolina. In addition, Steed Pond was included in larger-area surveys of the Savannah River Site in subsequent years. The surveys were conducted by the Remote Sensing Laboratory of EG&G Energy Measurements, Inc., Las Vegas, Nevada, for the US Department of Energy. Airborne measurements were obtained for both natural and man-made gamma radiation over Steed Pond and surrounding areas. The first survey was conducted when the pond was filled to normal capacity for the time of the year. On September 1, 1984, the Steed Pond dam spillway failed causing the pond to drain. The four subsequent surveys were conducted with the pond drained. The second survey and the third were conducted to study silt deposits exposed by the drop in water level after the spillway`s opening. Steed Pond data from the February 1987 and April 1989 Savannah River Site surveys have been included to bring this study up to date.

  5. 2016 Annual Inspection and Radiological Survey Results for the Piqua, Ohio, Decommissioned Reactor Site

    Office of Legacy Management (LM)

    Radiological Survey Results for the Piqua, Ohio, Decommissioned Reactor Site July 2016 LMS/PIQ/S14427 This page intentionally left blank U.S. Department of Energy 2016 Annual Inspection - Piqua, OH, Decommissioned Reactor Site July 2016 Doc. No. S14427 Page i Contents Abbreviations .................................................................................................................................. ii Summary

  6. Nevada Test Site Area 25, Radiological Survey and Cleanup Project, 1974-1983 (a revised final report). Revision 1

    SciTech Connect

    Miller, M.G.

    1984-12-01

    This report describes the radiological survey, decontamination and decommissioning (D and D) of the Nevada Test Site (NTS) Area 25 facilities and land areas incorporated in the Nuclear Rocket Development Station (NRDS). Buildings, facilities and support systems used after 1959 for nuclear reactor and engine testing were surveyed for the presence of radioactive contamination. The radiological survey portion of the project encompassed portable instrument surveys and removable contamination surveys (swipe) for beta plus gamma and alpha radioactive contamination of facilities, equipment and land areas. Soil sampling was also accomplished. The majority of Area 25 facilities and land areas have been returned to unrestricted use. Remaining radiologically contaminated areas are posted with warning signs and barricades. 9 references, 23 figures.

  7. Formerly utilized MED/AEC sites remedial action program. Radiological survey of the former Watertown arsenal property, Site 34 and Site 41, Watertown, Massachusetts

    SciTech Connect

    Wynveen, R.A.; Smith, W.H.; Sholeen, C.M.; Justus, A.L.; Flynn, K.F.

    1983-10-01

    During the MED/AEC era, work involving radioactive materials was conducted at various sites within the arsenal complex. Building 34 housed a uranium machine shop, and a portion of Building 41 contained a foundry that was used for uranium work. Information provided by site personnel indicated that only depleted uranium was used in these buildings. Results of radiological analyses of contaminated material found at these sites indicated depleted uranium with uranium-236. Both buildings have been razed. The remnants still in place consist of the concrete floor slabs, access drives, and underground utility service trenches. This area is currently under the control of the Watertown Redevelopment Authority of Watertown, Massachusetts. During the period from June 25 through July 1, 1981, the Argonne National Laboratory (ANL), Occupational Health and Safety Division (OHS) Radiological Survey Group (RSG), conducted a radiological survey of Building Sites 34 and 41 at the direction of the US Department of Energy. Significant levels of contamination were found at 33 locations on the pad of Site 34 and in 5 out of 15 soild corings from the perimeter of the pad. No contamination was found on the pad of Site 41; however, two-thirds of this pad was covered with soil up to 4 ft thick. One of the 14 soil corings taken adjacent to the pad of Site 41 had elevated levels of uranium. Levels of contamination in excess of criteria, as identified in ANSI 13.12 and NRC Guidelines, were found at this site. The analyses of the samples from the sewer access points also revealed uranium and radium-226 anomalies. Therefore, according to NRC guidelines dated July 1982, it must be concluded that they are contaminated.

  8. A comparison of four aerial radiological surveys of Par Pond and the surrounding area, Savannah River Site, Aiken, South Carolina. Dates of surveys: 1989--1992

    SciTech Connect

    Feimster, E.L.

    1993-09-01

    A series of gamma radiation surveys was conducted over Par Pond at the Savannah River Site (SRS) in August 1993, October 1991, and August 1992 as part of an effort to monitor the radiological changes around Par Pond as its water level was lowered. The results of an April 1989 survey, which was about one-half the area of those surveys listed above, were used as baseline data for the comparison. Gamma energy spectrum analysis revealed that the only man-made gamma ray emitter detected during the four surveys in the Par Pond area was cesium-137. The comparisons revealed that: (1) significant change in the radiological environment occurred along the Par Pond shoreline as the water levels were lowered, (2) the activity in Lower Three Runs Creek varied slightly as the level/flow rate changed during the pumping process, (3) minor changes occurred in areas adjacent to the Par Pond, and (4) little or no change occurred between surveys in the spatial distribution or kind of sources detected. All changes were directly related to the moisture variations (Par Pond water lowering, rainfall, waterway flow rates) between the survey periods. The distribution, kind, and activity of sources detected beyond the pond bed were consistent between surveys. 60 figs., 14 tabs.

  9. Radiological survey of Latty Avenue in the vicinity of the former Cotter site, Hazelwood/Berkeley, Missouri (LM001)

    SciTech Connect

    Cottrell, W.D.; Carrier, R.F.

    1987-05-01

    A radiological survey was conducted over a proposed construction corridor in the vicinity of the former Cotter site at 9200 Latty Avenue. The survey included gamma exposure rates at the ground surface and at 1 m above the surface throughout the site, sampling of surface soil, sampling of subsurface soil from auger holes, gamma logging of auger holes, and sampling of subsurface water. The results of the survey demonstrated some degree of radioactive contamination in all areas of the construction corridor, extending north and south in some regions onto adjacent private properties. Redistribution of the contamination by flooding, surface runoff, and road and utility line activities was evident. The pattern of contamination ranged from widespread to isolated spots and was found to occur from near the surface to depths of approx.1.8 m. The most highly contaminated region was noted on both sides of Latty Avenue adjacent to the former Cotter site. Concentrations of /sup 230/Th in soil from that region were as high as 16,000 pCi/g.

  10. Formerly utilized MED/AEC sites remedial action program. Radiological survey of the Harshaw Chemical Company, Cleveland, Ohio

    SciTech Connect

    Wynveen, R.A.; Smith, W.H.; Sholeen, C.M.; Justus, A.L.; Flynn, K.F.

    1984-04-01

    During the MED/AEC era, the Harshaw Chemical Company processed large quantities of normal uranium to produce both oxide and fluoride compounds. This work was done under contract to MED and its successor, AEC. Records indicated that at the time the AEC contract was terminated, the facility was decontaminated by Harshaw and released from AEC control in 1960. However, a search of AEC records indicated that documentation was insufficient to determine whether the decontamination work was adequate by current guidelines. Hence, a radiological assessment of the site ws initiated in 1976. The entire grounds and all buildings were surveyed using surface survey instruments to detect surface contamination and radiation detectors to determine general radiation levels. Extensive surface contamination was found throughout the site. While the major contamination was found in Plant C, significant levels of contamination also were found in 16 other buildings and at 32 exterior locations. The contaminating material seemed to be normal uranium exclusively. Air samples were taken at numerous indoor locations throughout the site, but no elevated levels of radon were detected. This was as expected since normal uranium has been separated from radium and hence radon levels are very low. Several soil samples were taken from around the site. Analyses of these samples indicated extensive soil contamination, as well as suspected contamination of the river bed in the vicinity of the plant outfall. Scheduled subsurface investigation of the site, as well as of the river bed and sewer system, have not been conducted. Levels of contamination at this site are significantly above guidelines for release of the site for unrestricted use. 57 figures, 7 tables.

  11. Formerly utilized MED/AEC sites remedial action program. Radiological survey of the Middlesex Municipal Landfill, Middlesex, New Jersey. Final report

    SciTech Connect

    Leggett, R W; Cottrell, W D; Goldsmith, W A; Christian, D J; Haywood, F F; Wagner, E B; Crawford, D J; Doane, R W; Shinpaugh, W H

    1980-04-01

    A radiological survey was conducted at the Middlesex Municipal Landfill in Middlesex, New Jersey. In 1948, dirt contaminated with pitchblende ores was brought to this site from a former ore sampling plant in Middlesex. This survey was conducted in order to characterize the present radiological condition of the site and to determine the extent to which contamination is being transported from the site by natural means such as by drainage. The survey included measurement of (1) radionuclide concentrations in surface and subsurface soil on the site; (2) radionuclide concentrations in surface and subsurface water on the site and in Bound Brook; (3) beta-gamma dose rates and external gamma radiation levels on and near the site; and (4) the rate of /sup 222/Rn emanation from the soil on the site. It was found that most of the contamination on the site is in the top 14 ft of soil; however, there is little contamination of surface soil on the site. Average radon emanation rates, average external gamma radiation levels, and average beta-gamma dose rates on the site do not appear to be significantly higher than background levels. Furthermore, radionuclide concentrations in water taken from Bound Brook near the site were far below guide values stated in federal guidelines.

  12. Formerly utilized MED/AEC sites Remedial Action Program. Radiological survey of the Albany Metallurgical Research Center, United States Bureau of Mines, Albany, Oregon

    SciTech Connect

    Wynveen, R.A.; Smith, W.H.; Sholeen, C.M.; Justus, A.L.; Flynn, K.F.

    1983-06-01

    During the periods 1954 to 1956 and 1960 to 1971, the Albany Metallurgical Research Center (AMRC) was engaged in metallurgical operations that included melting, machining, welding, and alloying of thorium. In addition, research on alloys of uranium and thorium started in 1955 and continued until suspended in 1978. Records indicated that at the time the original AEC contract was terminated, buildings and surrounding areas were decontaminated to the general guidelines provided by the AEC. Those guidelines were not as specific as current guidelines, and detailed records of the final decontamination were not documented. Because of that, radiological assessemnt of this site was initiated in June 1978. During June and July 1978, a radiological survey of the grounds and the buildings was completed. Certain buildings were designated as areas where no survey was necessary; however, it was decided by the ANL survey team to at least perform floor surveys in those buildings. Significant levels of contamination, both loose and fixed, were found in 10 of the 33 buildings surveyed. In addition, about 60 contaminated areas, including 17 with loose contamination, were found outside the buildings. Surveys of the sanitary sewers, the Albany sewage treatment plant and the Ohling Farm showed no significant contamination. Significant levels of contamination were found in the septic system behind Buildings 12 and 17. Air samples taken throughout the site revealed no radon concentrations in excess of the limits proposed by the US Surgeon General (10 CFR 712).

  13. radiological. survey | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    survey NNSA to Conduct Aerial Radiological Surveys Over San Francisco, Pacifica, Berkeley, And Oakland, CA Areas A U.S. Department of Energy National Nuclear Security...

  14. Formerly utilized MED/AEC sites Remedial Action Program. Radiological survey of the former Watertown Arsenal property GSA site Watertown, Massachusetts

    SciTech Connect

    Wynveen, R.A.; Smith, W.H.; Sholeen, C.M.; Justus, A.L.; Flynn, K.F.

    1983-10-01

    The complete radiological survey of all the buildings located on the GSA site revealed no contamination. However, significant contamination was found on the site grounds. A total of approximately 6 m/sup 2/ of surface area exhibited elevated radiation levels. The area of contamination is centered around Section I (the burn area) and spreads out from this point. The contamination includes the subsurface, descending to the water table at the 6-ft level in some places. The contamination is primarily reprocessed depleted uranium. The ambient radiation level in the vicinity of the contamination as measured with a pressurized ionization chamber is significantly above background levels (up to 18 ..mu..R/h). As expected, no significant levels of radon contamination were found in any of the air samples. These levels of contamination of exceed the criteria as defined in ANSI 13.12 and the NRC Guidelines. The ambient radiation levels (up to 18 ..mu..R/h) are not in excess of criteria as defined in Appendix 6.

  15. Formerly utilized MED/AEC sites remedial action program: radiological survey of the Building Site 421, United States, Watertown Arsenel, Watertown, MA. Final report

    SciTech Connect

    1980-02-01

    This report contains the results of surveys of the current radiological condition of the Building Site 421, United States Arsenal Watertown, Watertown, Massachusetts. Findings of this survey indicate there are four spots involving an area of less than 6000 cm/sup 2/ of identifiable low-level residual radioactivity on the concrete pad which is all that remains of Building Site 421. The largest spot is approximately 5000 cm/sup 2/. The other three spots are 100 cm/sup 2/ or less. The beta-gamma readings at these spots are 8.4 x 10/sup 2/ dis/min-100 cm/sup 2/, 2.2 x 10/sup 5/ dis/min-100 cm/sup 2/, 2.2 x 10/sup 5/ dis/min-100 cm/sup 2/ and 8.5 x 10/sup 4/ dis/min-100 cm/sup 2/. No alpha contamination was found at these locations. Gamma spectral analysis of a chip of contaminated concrete from one of the spots indicates that the contaminant is natural uranium. This contamination is fixed in the concrete and does not present an internal or external exposure hazard under present conditions. A hypothetical hazard analysis under a conservative set of assumed conditions indicates minimal internal hazard. The highest End Window contact reading was 0.09 mR/h. None of the other three spots indicated an elevated direct reading with the End Window Detector. Radon daughter concentrations were determined at three locations on the Building 421 pad. These were 0.00013 WL, 0.00011 WL and 0.00009 WL. According to the Surgeon General's Guidelines found in 10 CFR 712, radon daughter concentrations below 0.03 WL do not require remedial action in structures other than private dwellings and schools. Soil samples taken about the site indicate no elevated levels above the natural background levels in the soil. A gamma spectral analysis of a water sample obtained from the storm sewer line near the Building 421 pad indicates no elevated radioactivity in the sample. It was therefore felt that no contamination is present in this sewer.

  16. radiological survey | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    radiological survey San Francisco Bay Area Aerial Radiation Assessment Survey (SAN JOSE and SAN FRANCISCO, California) - A helicopter may be seen flying at low altitudes over portions of the San Francisco Bay Area from January 29 through February 6, 2016. The purpose of the flyovers is to measure naturally occurring background radiation. Officials from the National Nuclear... NNSA to Conduct Aerial Radiological Surveys Over Washington, D.C. and Baltimore, MD Areas WASHINGTON, D.C. AND BALTIMORE,

  17. Formerly utilized MED/AEC sites remedial action program: radiological survey of the former Virginia-Carolina Chemical Corporation Uranium Recovery Pilot Plant, Nichols, Florida. Final report

    SciTech Connect

    Haywood, F F; Doane, R W; Goldsmith, W A; Shinpaugh, W H; Crawford, D J; Fox, W F; Leggett, R W; Stone, D R

    1980-01-01

    The results of a radiological survey conducted at the site of a former uranium recovery pilot plant operated by the Virginia-Carolina Chemical Corporation is presented. All that remains of this operation is a concrete pad situated within the boundary of a phosphate products plant now operated by Conserv, Inc., at the Nichols, Florida site. The survey included measurements designed to characterize the residual radioactivity in the vicinity of this pilot plant and to compare the quantities with federal guidelines for the release of decontaminated property for unrestricted use. The results of this survey indicate that only small quantities of radioactivity exist above normal background levels for that area. Some soil contamination was found in the vicinity of a concrete pad on which the pilot plant stood. Much of this contamination was due to /sup 226/Ra and /sup 238/U. Some beta-gamma dose rates in excess of applicable guidelines were observed in this same area. External gamma-ray exposure rates at 1 m above the ground range from 20 to 100 ..mu..R/hr. None of the direct measurements of alpha contamination were above guideline levels.

  18. Formerly utilized MED/AEC sites remedial action program. Radiological survey of Chemicals Group, Olin Corporation (formerly Blockson Chemical Company) Joliet, Illinois March 27-November 28, 1978

    SciTech Connect

    Wynveen, R.A.; Smith, W.H.; Mayes, C.B.; Justus, A.L.

    1983-05-01

    A comprehensive radiological survey was conducted at Building 55 of the Chemicals Group, Olin Corporation, Joliet, Illinois. The survey included measurements of alpha and beta-gamma contamination, both fixed and removable; beta-gamma exposure readings at contact and at 1 m (3 ft) above the floor or ground level; estimates of radon-daughter concentrations in the air as airborne contaminants; and determinations of concentrations of /sup 137/Cs, the /sup 232/Th decay chain, the /sup 226/Ra decay chain, and uranium in the soil on the site. Thirty-three spots or localized areas and three larger general areas within Building 55 exceeded the allowable limits as given in the Draft ANSI Standard N13.12 for uranium, and the general roof area exceeded the acceptable limits for radium-226. Additionally, two spots or localized areas on the roof substantially exceeded those limits. In 15 instances, the contamination was found to be removable from surfaces and readily available for transfer to other locations. Concentrations of radon daughters in the air of the building, as measured by grab-sampling techniques, were below the limit of 0.01 WL above background as given in the Surgeon General's Guidelines. Analyses of ten soil samples from the site indicated significantly elevated concentrations of uranium and radium at two sampling locations near Building 55. Based on a hypothetical exposure scenario, the maximum potential dose equivalent to an individual for external penetrating radiation resulting from exposure to radioactivity at this site was calculated to be 340 mrem per year. The internal radiation 50-year dose commitments from potential inhalation/ingestion of radioactive material were calculated to be 8300 mrem to the lung, 120 mrem to the bone, 26 mrem to the kidney, and 250 mrem whole body. Few individuals are expected to acquire such doses or dose commitments annually.

  19. Radiological survey of San Diego Bay

    SciTech Connect

    Semler, M.O.; Blanchard, R.L.

    1989-06-01

    A radiological survey of three sites in San Diego Bay provided the basis for the following conclusions: 1. Small quantities of Co-60 (0.02-0.05 pCi/g) are present in the bottom sediments in some areas of the harbor at the Submarine Base. Most, if not all, of the Co-60 contamination present probably originated prior to the earlier 1967 survey that reported Co-60 levels as much as 300 times larger than those observed in this study. The highest Co-60 concentration measured is now less than one percent of the normal background radioactivity in harbor sediment samples. 2. No tritium or gamma-ray emitters, other than trace amounts of those occurring naturally, were detected in surface water from the dock areas or in nearby drinking water supplies. 3. Only radionuclides of natural origin and trace amounts of Cs-137 from fallout of previous nuclear weapons tests were detected in samples of kelp, algae, and fish taken from the harbor at the Submarine Base. 4. Gamma-ray surveys of the harbors near the docking areas and along shorelines and beaches near the shipyards failed to detect any exposure rates above background. 3 refs., 4 figs., 3 tabs.

  20. Formerly utilized MED/AEC sites remedial action program post-remedial-action radiological survey of Kent Chemical Laboratory, the University of Chicago, Chicago, IL

    SciTech Connect

    Wynveen, R.A.; Smith, W.H.; Sholeen, C.M.; Justus, A.L.; Flynn, K.F.

    1983-05-01

    A comprehensive radiological assessment of Kent Laboratory was conducted during September 1977, by the ANL Radiological Survey Group to determine if any radioactive contamination remained. The results of the assessment indicated the need for remedial action. Since 1977, the University has decontaminated this laboratory building, and in May 1983, the Department of Energy requested the ANL Radiological Survey Group to conduct a post-remedial-action survey. All the contaminated areas identified during the 1977 assessment were rechecked. Contamination remained in six of the rooms. Further decontamination of these areas was conducted by university personnel, and as a result, these areas are now free of contamination. However, a contaminated clay pipe in the attic remained. The clay pipe has since been removed and disposed of as solid radioactive waste. During the post-remedial-action survey, six soil samples were collected from excavation trenches dug in Rooms 1 and 2 as part of the University's remedial action efforts. Also, four sludge samples were taken from below the manhole covers in the basement of Kent Chemical Laboratory to assess the radiological condition of the sewer system. A radiological assessment of the sewer system had not been accomplished during the 1977 survey as per program direction. Radiochemical (fluorometric) and gamma-spectral analyses indicated that eight out of ten soil and sludge samples contained levels of radioactivity above expected background concentrations. The soil has since been further excavated. The building is now free of radioactive contamination in excess of background levels; however, the sewers do contain radioactive materials above background levels since contamination was found at appropriate access points. 6 references, 16 figures, 7 tables.

  1. Formerly utilized MED/AEC sites remedial action program. Radiological survey of Eckhart Hall, the University of Chicago, Chicago, Illinois, September 14, 1976-March 22, 1977

    SciTech Connect

    Wynveen, R.A.; Smith, W.H.; Boggs Mayes, C.; Justus, A.L.

    1982-05-01

    A comprehensive radiological survey was conducted at the Eckhart Hall at the University of Chicago, Chicago, Illinois. General radiochemistry and/or physics research was performed at this facility during the MED/AEC era in the 1940s. The building is now used as laboratories, offices, and classrooms. Survey measurements included alpha and beta-gamma contamination determinations, both fixed and removable; beta-gamma exposure readings at contact and at 1 m (3 ft); estimates of radon-daughter concentrations in the air; and determination of concentrations of /sup 137/Cs, the /sup 232/Th decay chain, the /sup 226/Ra decay chain, and uranium in the soil on the site. Thirteen spots of contamination were found to be fixed to or under existing surfaces and not readily available for transfer to other locations. Under current use conditions, the potential for radiation exposure to occupants of this building from these sources of contamination is remote. Concentrations of radon daughters in the air of the building were less than the limit of 0.01 Working Level (WL) above background. No long-lived radionuclides were detected in any air sample. Concentrations of radionuclides in soil samples collected around the facility indicated background levels. The presumed maximum potential internal radiation 50-year dose commitments from inhalation/ingestion of contamination remaining from MED/AEC activities were calculated to be less than 25% of the appropriate annual standards for an individual in an uncontrolled area. Remedial measures such as stabilization of the contamination in place would be applicable as a short-term measure. In order to reduce the risk in the event that building modifications take place in the future, health physics procedures and coverage are recommended. The long-term solution would involve decontamination by removal of the radioactive residues.

  2. Nevada National Security Site Radiological Control Manual

    SciTech Connect

    Radiological Control Managers’ Council

    2012-03-26

    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

  3. Radiological Scoping Survey of the Scotia Depot, Scotia, NY

    SciTech Connect

    Bailey, E. N.

    2008-02-25

    The objectives of the radiological scoping survey were to collect adequate field data for use in evaluating the radiological condition of Scotia Depot land areas, warehouses, and support buildings.

  4. Formerly utilized MED/AEC sites remedial-action program. Radiological survey of Kent Chemical Laboratory, The University of Chicago, Chicago, Illinois, September 7-13, 1977

    SciTech Connect

    Wynveen, R.A.; Smith, W.H.; Mayes, C.B.; Justus, A.L.

    1982-05-01

    A comprehensive radiological survey was conducted at the Kent Chemical Laboratory at the University of Chicago, Chicago, Illinois. General radiochemistry and/or physics research was performed at this facility during the MED/AEC era in the 1940s. The building is now used as laboratories, offices, and classrooms. The survey was undertaken to determine the location and quantities of any radioactive materials remaining from the MED/AEC operations. Nineteen spots of contamination possibly resulting from MED/AEC occupancy in 12 rooms exceeded the allowable limits for /sup 226/Ra and /sup 239/Pu as given in the ANSI Standard N13.12. Under current use conditions, the potential for radiation exposure to occupants of this building from these sources of contamination is remote. Concentrations of radon daughters in the air of the building were below the limit of 0.01 Working Level above background as given in the Surgeon General's Guidelines. Concentrations of radionuclides in soil samples from near the laboratory were essentially at background levels. The maximum potential dose for external penetrating radiation resulting from exposure to the radioactivity remaining from MED/AEC operations was calculated to be 500 mrem a year, which is equal to the 500 mrem standard for an individual in an uncontrolled area. In order to reduce the potential for radiation exposure, remedial measures such as stabilization of the contamination in place would be applicable as a short-term measure. In order to reduce the risk in the event that building modifications take place in the future, health physics procedures and coverage are recommended. The long-term solution would involve decontamination by removal of the radioactive residues from the 12 rooms or areas where contamination possibly resulting from MED/AEC activities was detected.

  5. Formerly utilized MED/AEC sites remedial-action program. Radiological survey of Ryerson Physical Laboratory, The University of Chicago, Chicago, Illinois, September 11-25, 1976

    SciTech Connect

    Wynveen, R.A.; Smith, W.H.; Mayes, C.B.; Justus, A.L.

    1982-05-01

    A comprehensive radiological survey was conducted at the Ryerson Physical Laboratory at the University of Chicago, Chicago, Illinois. General radiochemistry and/or physics research was performed at this facility during the MED/AEC era in the 1940s. The building is now used as laboratories, offices, and classrooms. The survey was undertaken to determine the location and quantities of any radioactive materials remaining from the MED/AEC activities. Forty spots of contamination in 26 rooms possibly resulting from MED/AEC occupancy exceeded the allowable limits as given in ANSI Standard N13.12 for Group 1 nuclides. The potential for radiation exposure to occupants of this building from these sources of contamination is remote under current use conditions. Concentrations of radon daughters in the air of the building were less than the limit of 0.01 WL above background as given in the Surgeon General's Guidelines. Concentrations of radionuclides in soil samples collected around the facility indicated background levels. The presumed maximum potential dose for external penetrating radiation resulting from exposure to the radioactivity remaining from MED/AEC operations was calculated to be 140 mrem a year, which is 30% of the 500-mrem standard for an individual in an uncontrolled area. In order to reduce the potential for radiation exposure, remedial measures such as stabilization of the contamination in place would be applicable as a short-term measure. In order to reduce the risk in the event that building modifications take place in the future, health physics procedures and coverage are recommended. The long-term solution would involve decontamination by removal of the radioactive residues from the 26 rooms or areas where contamination possibly resulting from MED/AEC activities was detected.

  6. Autonomous mobile robot for radiologic surveys

    DOEpatents

    Dudar, Aed M.; Wagner, David G.; Teese, Gregory D.

    1994-01-01

    An apparatus for conducting radiologic surveys. The apparatus comprises in the main a robot capable of following a preprogrammed path through an area, a radiation monitor adapted to receive input from a radiation detector assembly, ultrasonic transducers for navigation and collision avoidance, and an on-board computer system including an integrator for interfacing the radiation monitor and the robot. Front and rear bumpers are attached to the robot by bumper mounts. The robot may be equipped with memory boards for the collection and storage of radiation survey information. The on-board computer system is connected to a remote host computer via a UHF radio link. The apparatus is powered by a rechargeable 24-volt DC battery, and is stored at a docking station when not in use and/or for recharging. A remote host computer contains a stored database defining paths between points in the area where the robot is to operate, including but not limited to the locations of walls, doors, stationary furniture and equipment, and sonic markers if used. When a program consisting of a series of paths is downloaded to the on-board computer system, the robot conducts a floor survey autonomously at any preselected rate. When the radiation monitor detects contamination, the robot resurveys the area at reduced speed and resumes its preprogrammed path if the contamination is not confirmed. If the contamination is confirmed, the robot stops and sounds an alarm.

  7. Autonomous mobile robot for radiologic surveys

    DOEpatents

    Dudar, A.M.; Wagner, D.G.; Teese, G.D.

    1994-06-28

    An apparatus is described for conducting radiologic surveys. The apparatus comprises in the main a robot capable of following a preprogrammed path through an area, a radiation monitor adapted to receive input from a radiation detector assembly, ultrasonic transducers for navigation and collision avoidance, and an on-board computer system including an integrator for interfacing the radiation monitor and the robot. Front and rear bumpers are attached to the robot by bumper mounts. The robot may be equipped with memory boards for the collection and storage of radiation survey information. The on-board computer system is connected to a remote host computer via a UHF radio link. The apparatus is powered by a rechargeable 24-volt DC battery, and is stored at a docking station when not in use and/or for recharging. A remote host computer contains a stored database defining paths between points in the area where the robot is to operate, including but not limited to the locations of walls, doors, stationary furniture and equipment, and sonic markers if used. When a program consisting of a series of paths is downloaded to the on-board computer system, the robot conducts a floor survey autonomously at any preselected rate. When the radiation monitor detects contamination, the robot resurveys the area at reduced speed and resumes its preprogrammed path if the contamination is not confirmed. If the contamination is confirmed, the robot stops and sounds an alarm. 5 figures.

  8. Solar Site Survey Toolkit

    Energy.gov [DOE]

    After a couple outings, a principal technologist at Sandia National Laboratories saw a need for a travel kit that would have the necessary tools to make the task of site surveys more manageable and safer. They have had great success using the kit in the field already.

  9. Radiological re-survey results at 130 West Central Avenue, Maywood, New Jersey (MJ029)

    SciTech Connect

    Murray, M.E.; Johnson, C.A.

    1994-01-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from 1916 to 1959. During the early years of operation, MCW stored wastes and residues in low-lying areas west of the processing facilities and consequently some of the residuals containing radioactive materials migrated offsite to the surrounding area. Subsequently, the U.S. Department of Energy (DOE), designated for remedial action the old MCW property and several vicinity properties. Additionally, in 1984, the property at 130 West Central Ave., Maywood, New Jersey and properties in its vicinity were included as a decontamination research and development project under the DOE Formerly Utilized Sites Remedial Action Program. In 1987 and 1988, at the request of DOE, ORNL conducted a radiological survey on this property. A second radiological survey by ORNL was conducted on this property in May, 1993 at the request of DOE after an ad hoc radiological survey, requested by a new property owner and conducted by Bechtel National, Inc. (BNI), identified some contamination not previously found by ORNL. The purpose of the survey was to determine if residuals from the old MCW were present on the property, and if so, if any radiological elements present were above guidelines. A certified civil survey was requisitioned by ORNL to determine actual property boundaries before beginning the radiological survey. The radiological re-survey included a surface gamma scan and the collection of a large number of soil samples for radionuclide analyses.

  10. Nevada Test Site Radiological Control Manual

    SciTech Connect

    Radiological Control Managers' Council - Nevada Test Site

    2009-10-01

    This document supersedes DOE/NV/11718--079, “NV/YMP Radiological Control Manual,” Revision 5 issued in November 2004. Brief Description of Revision: A complete revision to reflect the recent changes in compliance requirements with 10 CFR 835, and for use as a reference document for Tenant Organization Radiological Protection Programs.

  11. Formerly utilized MED/AEC sites remedial action program. Radiological survey of Universal Cyclopes, Inc. , Titusville, Plant (formerly Vulcan Crucible Steel Company, Aliquippa, Pennsylvania, May 2-8, 1978

    SciTech Connect

    Wynveen, R.A.; Smith, W.H.; Mundis, R.L.; Mayes, C.B.

    1982-05-01

    A radiological survey was conducted at the Universal Cyclops, Inc. Titusville Plant (formerly Vulcan Crucible Steel Company), in Aliquippa, Pennsylvania, to determine the location and quantities of any radioactive materials remaining on the site as a result of MED/AEC activities in the late 1940s. This facility was used for rolling uranium billets during the MED/AEC era. The survey included measurements of alpha and beta-gamma contamination, both fixed and removable; beta-gamma exposure readings at contact and at 1 m (3 ft) above the floor or ground level; and measurements of the concentrations of radon daughters in air and concentrations of /sup 137/Cs, the /sup 232/Th decay chain, the /sup 226/Ra decay chain, and uranium in the soil on the site. Fourteen spots of contamination exceeded the allowable limits for natural uranium. Under current use conditions, the potential for radiation exposure of occupants of the building from these sources of contamination is remote. Concentrations of radon daughters were below the 0.01 WL limit. Calculated radon concentrations based on the radon-daughter determinations ranged from 0.11 to 0.27 pCi/l. The concentration guide for /sup 222/Rn in uncontrolled areas is 3 pCi/l. Analysis of soil samples from the site indicated elevated concentrations of uranium (15.1 +- 0.7 to 109.0 +- 5.5 pCi/g) at one sampling location near the building. There currently are no regulatory limits for uranium concentration in soil, but, a proposed guide value is pCi/g. After evaluation of results of the survey, it was concluded that although some areas of the Universal Cyclops facility are contaminated, these areas do not pose a significant risk to the present occupants of the building. Nonetheless, in a few cases the contamination does exceed accepted guidelines. Remedial measures are indicated to bring the contaminated areas within the guidelines.

  12. Radiological survey results at 1 Shady Lane, Lodi, New Jersey (LJ095)

    SciTech Connect

    Foley, R.D.; Johnson, C.A.

    1995-07-01

    The US Department of Energy (DOE) conducted remedial action at the Stepan property in Maywood, New Jersey and several vicinity properties in Lodi, New Jersey as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are in the vicinity of the DOE-owned Maywood Interim Storage Site (MISS), adjacent to the former Maywood Chemical Works facility. The property at One Shady Lane, Lodi, New Jersey was not one of these vicinity properties but was surveyed by DOE at the request of the owner. At the request of DOE, a team from Oak Ridge National Laboratory conducted a radiological survey at this property. The purpose of the survey, conducted in November 1994, was to confirm whether remedial actions were to be performed on the property in order to be in compliance with the identified Guidelines. The radiological survey included surface gamma scans and gamma readings at 1 meter, and the collection of soil samples for radionuclide analysis. Results of the survey demonstrated that all radiological measurements on the property at One Shady Lane, Lodi, New Jersey, were comparable to background levels in the area, and well within the limits prescribed by DOE radiological guidelines. Based on the results of the radiological survey data, this property does not meet guidelines for inclusion under FUSRAP.

  13. Nevada Test Site Radiological Control Manual. Revision 1

    SciTech Connect

    None, None

    2010-02-09

    This document supersedes DOE/NV/25946--801, “Nevada Test Site Radiological Control Manual,” Revision 0 issued in October 2009. Brief Description of Revision: A minor revision to correct oversights made during revision to incorporate the 10 CFR 835 Update; and for use as a reference document for Tenant Organization Radiological Protection Programs.

  14. Radiological survey results at 14 Cliff Street, Beverly, Massachusetts (VB011)

    SciTech Connect

    Foley, R.D.; Carrier, R.F.

    1992-08-01

    At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 14 Cliff Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium dust from work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan and the collection of soil samples for radionuclide analyses. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines.

  15. Formerly utilized MED/AEC sites remedial action program. Radiological survey of the West Stands, New Chemistry Lab and Annex, and Ricketts Laboratory, the University of Chicago, Chicago, Illinois, August 31-September 2, 1977

    SciTech Connect

    Wynveen, R.A.; Smith, W.H.; Mayes, C.B.; Justus, A.L.

    1982-05-01

    A radiological survey was conducted at the former locations of the West Stands, the New Chemistry Lab and Annex, and Ricketts Laboratory at the University of Chicago, Chicago, Illinois. General radiochemistry and/or physics research for the MED/AEC program was performed at these sites during the 1940s. The buildings have since been razed. The survey was undertaken to determine the presence of any radionuclides remaining from the MED/AEC operations that could have been spilled or released from the former structures. Environmental soil samples (corings) were collected from the areas where the West Stands, New Chemistry Lab and Annex, and Ricketts Laboratory once stood. The soil corings were taken at what appeared to be undisturbed locations near the sites of the three former facilities. Analyses of the soil corings included determination of the concentrations of /sup 137/Cs, the /sup 232/Th decay chain, the /sup 226/Ra decay chain, and uranium in the soil. The levels of uranium and the /sup 226/Ra decay chain found in the samples indicated that no concentrations above natural background levels were present. Slightly elevated levels of /sup 60/Co were found in soil taken from the top 5 cm of the ground at two sampling sites, but this activity was presumed to have been traceable to induced activity from contaminated stainless steel that had been stored in the area during operations not related to MED/AEC activities. No increased radiation dose attributable to exposure to residual radioactivity from MED/AEC activities is expected.

  16. Formerly utilized MED/AEC sites remedial action progam. Radiological survey of the Albany Metallurgical Research Center, United States Bureau of Mines, Biomass Facility and the Back Forty Area, Albany, Oregon

    SciTech Connect

    Wynveen, R.A.; Smith, W.H.; Sholeen, C.M.; Justus, A.L.; Flynn, K.F.

    1983-06-01

    This report contains survey results identifying the current radiological condition of two areas located at the site of the United States Bureau of Mines' Albany Metallurgical Research Center in Albany, Oregon. These areas are designed as the BioMass Facility and the Back Forty. The BioMass Facility was a pilot plant for the production of oil from wood waste; it consists of five structures on a two-acre site. The Back Forty is a vacant area of about 14 acres south of the BioMass Facility. Both areas were reportedly used as dump sites for the Bureau of Mines operations. No contamination was found to be associated with the structures, equipment, or material in the BioMass Facility; however, four relatively small areas of contamination were found in the exterior grounds. The maximum radiation level measured was 0.7 mR/h at 1 cm. A relatively large area (approx. 0.8 acre) in the Back Forty area exhibited anomalous radiation levels. Radiation levels as high as 100 ..mu..R/h were measured at 3 ft above ground. This area was reportedly used as a dump site for Bureau of Mines activities. The structures, equipment, and material associated with the BioMass Facility can be released for unrestricted use. However, because of the subsurface contamination found in both the BioMass and the Back Forty areas, some restrictions should be incorporated into any planned useage for this site. Some discussion regarding these hazards are included in the text of this report.

  17. Results of the independent radiological verification survey at 112 Avenue E, Lodi, New Jersey (LJ082V)

    SciTech Connect

    Rodriguez, R.E.; Johnson, C.A.

    1996-09-01

    Thorium ores were processed by the Maywood Chemical Works until the property was sold to Stepan Chemical Company in 1959. Wastes were stored at what is now called the Maywood Interim Storage Site (MISS), owned by the U.S. Department of Energy (DOE). Because of the migration of residuals off site into the surrounding areas, the Stepan property and several vicinity properties were designated for remedial action under the 1984 Energy and Water Development Appropriations Act. The DOE conducted radiological surveys of these sites to evaluate current radiological conditions as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). In 1988, radiological surveys of some private residential properties on Avenue E in Lodi, New Jersey were conducted by members of an ORNL radiological survey team. Results of this survey indicated radiological contamination in excess of the DOE criteria for surface contamination at this vicinity property (112 Avenue E), and it was recommended for remediation. In the fall of 1995, a verification survey of this vicinity property was conducted by ORNL, the independent verification contractor for this effort, in conjunction with decontamination operations conducted under the supervision of Bechtel National Incorporated. The verification survey included complete surface gamma scans of the grounds and the collection of soil samples for radionuclide analysis. This report describes the radiological verification survey of this residential property. Based on the remedial action and verification survey data reported in this document, all radiological measurements fall below the limits prescribed by DOE radiological guidelines established for this site, and the property at 112 Avenue E, Lodi, New Jersey successfully meets the DOE radiological guidelines for unrestricted use.

  18. Results of the independent radiological verification survey at 113 Avenue E, Lodi, New Jersey (LJ081V)

    SciTech Connect

    Rodriguez, R.E.; Johnson, C.A.

    1996-09-01

    Thorium ores were processed by the Maywood Chemical Works until the property was sold to Stepan Chemical Company in 1959. Wastes were stored at what is now called the Maywood Interim Storage Site (MISS), owned by the U. S. Department of Energy (DOE). Because of the migration of residuals off site into the surrounding areas, the Stepan property and several vicinity properties were designated for remedial action under the 1984 Energy and Water Development Appropriations Act. The DOE conducted radiological surveys of these sites to evaluate current radiological conditions as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). In 1988, radiological surveys of some private residential properties on Avenue E in Lodi, New Jersey were conducted by members of an ORNL radiological survey team. Results of this survey indicated radiological contamination in excess of the DOE criteria for surface contamination at this vicinity property (113 Avenue E), and it was recommended for remediation. In the fall of 1995, a verification survey of this vicinity property was conducted by ORNL, the independent verification contractor for this effort, in conjunction with decontamination operations conducted under the supervision of Bechtel National Incorporated. The verification survey included complete surface gamma scans of the grounds and the collection of soil samples for radionuclide analysis. This report describes the radiological verification survey of this residential property.

  19. Results of the independent radiological verification survey at 108 Avenue E, Lodi, New Jersey (LJ084V)

    SciTech Connect

    Rodriguez, R.E.; Johnson, C.A.

    1996-09-01

    Thorium ores were processed by the Maywood Chemical Works until the property was sold to Stepan Chemical Company in 1959. Wastes were stored at what is now called the Maywood Interim Storage Site (MISS), owned by the US Department of Energy (DOE). Because of the migration of residuals off site into the surrounding areas, the Stepan property and several vicinity properties were designated for remedial action under the 1984 Energy and Water Development Appropriations Act. The DOE conducted radiological surveys of these sites to evaluate current radiological conditions as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). In 1988, radiological surveys of some private residential properties on Avenue E in Lodi, New Jersey were conducted by members of an ORNL radiological survey team. Results of this survey indicated radiological contamination in excess of the DOE criteria for surface contamination at this vicinity property (108 Avenue E), and it was recommended for remediation. In the fall of 1995, a verification survey of this vicinity property was conducted by ORNL, the independent verification contractor for this effort, in conjunction with decontamination operations conducted under the supervision of Bechtel National Incorporated. The verification survey included complete surface gamma scans of the grounds and the collection of soil samples for radionuclide analysis. This report describes the radiological verification survey of this residential property.

  20. RADIOLOGICAL SURVEY OF A PORTION OF PROPERTY OWNED BY MODERN...

    Office of Legacy Management (LM)

    for the DEPARTMENT OF ENERGY as part of the Formerly ... Figure Page 1 Plan view of Former AEC Storage Site Showing ... Survey Techniques A survey grid system (100-ft spacing) was ...

  1. Radiological re-survey results at 146 West Central Avenue, Maywood, New Jersey (MJ034)

    SciTech Connect

    Murray, M.E.; Johnson, C.A.

    1994-05-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from 1916 to 1959. During the early years of operation, MCW stored wastes and residues in low-lying areas west of the processing facilities and consequently some of the residuals containing radioactive materials migrated offsite to the surrounding area. Subsequently, the U.S. Department of Energy (DOE) designated for remedial action the old MCW property and several vicinity properties. Additionally, in 1984, the property at 146 West Central Ave., Maywood, New Jersey and properties in its vicinity were included as a decontamination research and development project under the DOE Formerly Utilized Sites Remedial Action Program. In 1987 and 1988, at the request of DOE, Oak Ridge National Laboratory (ORNL) conducted a radiological survey on this property. A report describing this survey was published in 1989. A second radiological survey by ORNL was conducted on this property in May 1993 at the request of DOE after an ad hoc radiological survey, requested by the property owner and conducted by Bechtel National, Inc. (BNI), identified some contamination not previously found by ORNL. The purpose of the second ORNL survey was to determine whether radioactive materials from the old MCW were present on the property, and if so, if radioactive materials present were above guidelines. A certified civil survey was requisitioned by ORNL to determine actual property boundaries before beginning the radiological re-survey. The re-survey included a surface gamma scan and the collection of a large number of soil samples for radionuclide analyses. Results of this survey demonstrated that although elevated residual thorium-232 contamination was present in a few isolated spots on the southern end of the backyard, it did not exceed DOE guidelines.

  2. NNSA to Conduct Aerial Radiological Surveys Over San Francisco, Pacifica,

    National Nuclear Security Administration (NNSA)

    Berkeley, And Oakland, CA Areas | National Nuclear Security Administration | (NNSA) Conduct Aerial Radiological Surveys Over San Francisco, Pacifica, Berkeley, And Oakland, CA Areas August 27, 2015 A U.S. Department of Energy National Nuclear Security Administration (NNSA) helicopter may be seen flying at low altitudes around the California Bay Area from September 1 - 6, 2015. The purpose of the flyovers is to measure naturally occurring background radiation. A twin-engine Bell 412

  3. Results of the radiological survey of the Excelsior Steel Ball Company, Tonawanda, New York (TNY005)

    SciTech Connect

    McKenzie, S.P.; Brown, K.S.

    1998-07-01

    At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted two radiological surveys of property belonging to the Excelsior Steel Ball Company, which is surrounded on three sides by the former site of the Linde Uranium Refinery, Tonawanda, New York. The surveys were performed in September 1997 and February 1998. The purpose of the first survey was to determine if radioactive residuals were present from previous activities at the former Linde site. The Linde Air Products Division of Union Carbide Corporation, Tonawanda, New York, had used radioactive materials at that location for work performed under government contract from 1942 through 1948. The purpose of the second survey was to collect additional biased samples from an area of the site where biased sample results showed slightly elevated levels of thorium-232.

  4. Radiological characterization of the Kellex site. Publication No. 45020. [Metal fabrication; pilot plant to demonstrate units for gaseous diffusion

    SciTech Connect

    Hutchinson, S.W.

    1981-03-01

    A radiological characterization has been conducted at the former Kellex Corporation site in Jersey City, New Jersey. Although several prior surveys and a remedial action were conducted, there was still a need for more information about the radiological condition of the site. A grid was established on the site and the surface was surveyed by a mobile in situ detection system. Trenches were systematically dug in an attempt to find subsurface areas of contamination. Material from the trenches was surveyed by the in situ measurement system and trench sidewalls were soil sampled and surveyed using portable dose rate and count rate instrumentation. Results of the survey indicated that radioactivity levels on the site were at or near background. Small amounts of contaminated material were found but not enough to exceed the guideline specified.

  5. Results of the radiological survey at 205 Main Street, Lodi, New Jersey (LJ075)

    SciTech Connect

    Foley, R.D.; Carrier, R.F.; Floyd, L.M.; Crutcher, J.W.

    1989-08-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 205 Main Street, Lodi, New Jersey (LJ075), was conducted during 1987 and 1988. Results of the survey indicated radioactivity in the range of normal background for the northern New Jersey area. Radiological assessments of soil samples from the site demonstrate no radionuclide concentrations in excess of DOE Formerly Utilized Sites Remedial Action Program criteria. 5 refs., 21 figs., 3 tabs.

  6. Results of the radiological survey at State Route 17 Becker Avenue, Maywood, New Jersey (MJ033)

    SciTech Connect

    Foley, R.D.; Carrier, R.F.

    1990-03-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. 5 refs., 2 figs., 3 tabs.

  7. Northern Marshall Islands radiological survey: sampling and analysis summary

    SciTech Connect

    Robison, W.L.; Conrado, C.L.; Eagle, R.J.; Stuart, M.L.

    1981-07-23

    A radiological survey was conducted in the Northern Marshall Islands to document reamining external gamma exposures from nuclear tests conducted at Enewetak and Bikini Atolls. An additional program was later included to obtain terrestrial and marine samples for radiological dose assessment for current or potential atoll inhabitants. This report is the first of a series summarizing the results from the terrestrial and marine surveys. The sample collection and processing procedures and the general survey methodology are discussed; a summary of the collected samples and radionuclide analyses is presented. Over 5400 samples were collected from the 12 atolls and 2 islands and prepared for analysis including 3093 soil, 961 vegetation, 153 animal, 965 fish composite samples (average of 30 fish per sample), 101 clam, 50 lagoon water, 15 cistern water, 17 groundwater, and 85 lagoon sediment samples. A complete breakdown by sample type, atoll, and island is given here. The total number of analyses by radionuclide are 8840 for /sup 241/Am, 6569 for /sup 137/Cs, 4535 for /sup 239 +240/Pu, 4431 for /sup 90/Sr, 1146 for /sup 238/Pu, 269 for /sup 241/Pu, and 114 each for /sup 239/Pu and /sup 240/Pu. A complete breakdown by sample category, atoll or island, and radionuclide is also included.

  8. Results of the radiological survey at Two Mile Creek, Tonawanda, New York (TNY002)

    SciTech Connect

    Murray, M.E.; Rodriguez, R.E.; Uziel, M.S.

    1997-08-01

    At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at Two Mile Creek, Tonawanda, New York. The survey was performed in November 1991 and May 1996. The purpose of the survey was to determine if radioactive materials from work performed under government contract at the Linde Air Products Division of Union Carbide Corporation, Tonawanda, New York, had been transported into the creek. The survey included a surface gamma scan in accessible areas near the creek and the collection of soil, sediment, and core samples for radionuclide analyses. Survey results indicate that no significant material originating at the Linde plant is presently in the creek. Three of the 1991 soil sample locations on the creek bank and one near the lake contained slightly elevated concentrations of {sup 238}U with radionuclide distributions similar to that found in materials resulting from former processing activities at the Linde site.

  9. Formerly utilized MED/AEC sites remedial action program. Geohydrological and radiological survey of the Albany Research Center, United States Bureau of Mines, Albany, Oregon, July 1983. Supplement 1

    SciTech Connect

    Wynveen, R.A.; Smith, W.H.; Sholeen, C.M.; Justus, A.L.; Flynn, K.F.; Tsai, S.Y.

    1984-06-01

    The purpose of this report is to present details of follow-up investigations of certain conditions revealed by the results of the initial survey - specifically the potential for contamination of groundwater and for lateral subsurface migration of radioactive waste from contaminated areas on the Albany Research Center site. 9 references, 12 figures, 7 tables.

  10. Radiological survey of the inactive uranium-mill tailings at Rifle, Colorado

    SciTech Connect

    Haywood, F.F.; Jacobs, D.J.; Ellis, B.S.; Hubbard, H.M. Jr.; Shinpaugh, W.H.

    1980-06-01

    Results of radiological surveys of two inactive uranium-mill sites near Rifle, Colorado, in May 1976 are presented. These sites are referred to as Old Rifle and New Rifle. The calculated /sup 226/Ra inventory of the latter site is much higher than at the older mill location. Data on above-ground measurements of gamma exposure rates, surface and near-surface concentration of /sup 226/Ra in soil and sediment samples, concentration of /sup 226/Ra in water, calculated subsurface distribution of /sup 226/Ra, and particulate radionuclide concentrations in air samples are given. The data serve to define the extent of contamination in the vicinity of the mill sites and their immediate surrounding areas with tailings particles. Results of these measurements were utilized as technical input for an engineering assessment of these two sites.

  11. Site survey method and apparatus

    DOEpatents

    Oldham, James G.; Spencer, Charles R.; Begley, Carl L.; Meyer, H. Robert

    1991-06-18

    The disclosure of the invention is directed to a site survey ground vehicle based apparatus and method for automatically detecting source materials, such as radioactivity, marking the location of the source materials, such as with paint, and mapping the location of the source materials on a site. The apparatus of the invention is also useful for collecting and analyzing samples. The apparatus includes a ground vehicle, detectors mounted at the front of the ground vehicle, and individual detector supports which follow somewhat irregular terrain to allow consistent and accurate detection, and autolocation equipment.

  12. Site survey method and apparatus

    DOEpatents

    Oldham, J.G.; Spencer, C.R.; Begley, C.L.; Meyer, H.R.

    1991-06-18

    The disclosure of the invention is directed to a site survey ground vehicle based apparatus and method for automatically detecting source materials, such as radioactivity, marking the location of the source materials, such as with paint, and mapping the location of the source materials on a site. The apparatus of the invention is also useful for collecting and analyzing samples. The apparatus includes a ground vehicle, detectors mounted at the front of the ground vehicle, and individual detector supports which follow somewhat irregular terrain to allow consistent and accurate detection, and autolocation equipment. 19 figures.

  13. Radiological Survey Results for the Niagara Mohawk Right-of-Way, Tonawanda, New York (TNY004)

    SciTech Connect

    McKenzie, S.P.; Uziel, M.S.

    1998-11-01

    At the request of the U.S. Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey of a small portion of the Niagara Mohawk Power Corporation right-of-way in Tonawanda, New York. The purpose of the survey was to determine if radioactive residuals had migrated from or been redistributed onto the Niagara Mohawk right-of-way from the former Linde property to the west. The Linde Air Products Division of Union Carbide Corporation, Tonawanda New York, had used radioactive materials at that location for work performed under government contract from 1942 through 1948. The survey was performed in May 1996 in response to Formerly Utilized Sites Remedial Action Program (FUSRAP) requirements. These requirements dictate that the radiological status of certain vicinity properties shall be assessed and documented according to prescribed procedures prior to certification of the property for release for unrestricted use. Such release can only be granted if the property is found to be within current applicable authorized limits. The survey included a gamma scan of accessible areas and the collection and radionuclide analysis of soil samples from the portion of right-of-way located east of the former Linde plant site and north of the railway spur entrance gate. Results of the survey indicate that radioactive material probably originating from the Linde plant is located on the Niagara Mohawk right-of-way in the area surveyed. Surface gamma exposure rates were elevated above typical background levels. Four scattered surface soil samples exceeded DOE guideline values for {sup 238}U, and 8 of 13 surface soil samples exceeded DOE guideline values for {sup 226}Ra. The radionuclide distribution in these samples was similar to that found in materials resulting from former processing activities at the Linde site. It is recommended that the property be designated for remedial action by DOE.

  14. Results of the independent radiological verification survey at the former Bridgeport Brass Company Facility, Seymour, Connecticut (SSC001)

    SciTech Connect

    Foley, R.D.; Rice, D.E.; Allred, J.F.; Brown, K.S.

    1995-03-01

    At the request of the USDOE, a team from ORNL conducted an independent radiological verification survey at the former Bridgeport Brass Company Facility, Seymour, Connecticut, from September 1992 to March 1993. Purpose of the survey was to determine whether residual levels of radioactivity inside the Ruffert Building and selected adjacent areas were rmediated to levels below DOE guidelines for FUSRAP sites. The property was contaminated with radioactive residues of {sup 238}U from uranium processing experiments conducted by Reactive Metals, Inc., from 1962 to 1964 for the Atomic Energy Commission. A previous radiological survey did not characterize the entire floor space because equipment which could not be moved at the time made it inaccessible for radiological surveys. During the remediation process, additional areas of elevated radioactivity were discovered under stationary equipment, which required additional remediation and further verification. Results of the independent radiological verification survey confirm that, with the exception of the drain system inside the building, residual uranium contamination has been remediated to levels below DOE guidelines for unrestricted release of property at FUSRAP sites inside and outside the Ruffert Building. However, certain sections of the drain system retain uranium contamination above DOE surface guideline levels. These sections of pipe are addressed in separate, referenced documentation.

  15. Results of the radiological survey at 5 Hancock Street, Lodi, New Jersey (LJ029)

    SciTech Connect

    Cottrell, W.D.; Floyd, L.M.; Francis, M.W.; Mynatt, J.O.

    1989-09-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 5 Hancock Street, Lodi, New Jersey (LJ029), was conducted during 1985 and 1986. Results of the survey demonstrated concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of the material originating from the MCW site. 5 refs., 6 figs., 3 tabs.

  16. Results of the radiological survey at 112 Avenue E, Lodi, New Jersey (LJ082)

    SciTech Connect

    Foley, R.D.; Floyd, L.M.

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residue, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 112 Avenue E, Lodi, New Jersey (LJ082), was conducted during 1988. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 2 figs., 3 tabs.

  17. Results of the radiological survey at 113 Avenue E, Lodi, New Jersey (LJ081)

    SciTech Connect

    Foley, R.D.; Floyd, L.M.

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 113 Avenue E, Lodi, New Jersey (LJ081), was conducted during 1988. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 5 refs, 2 figs., 3 tabs.

  18. Results of the radiological survey at 62 Trudy Drive, Lodi, New Jersey (LJ080)

    SciTech Connect

    Foley, R.D.; Floyd, L.M.

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 62 Trudy Drive, Lodi, New Jersey (LJ080), was conducted during 1988. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 5 refs., 5 figs., 3 tabs.

  19. Results of the radiological survey at 108 Avenue E, Lodi, New Jersey (LJ084)

    SciTech Connect

    Foley, R.D.; Floyd, L.M.

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 108 Avenue E, Lodi, New Jersey (LJ084), was conducted during 1988. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 5 refs., 2 figs., 2 tabs.

  20. Results of the radiological survey at 79 Avenue B, Lodi, New Jersey (LJ091)

    SciTech Connect

    Foley, R.D.; Floyd, L.M.

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 79 Avenue B, Lodi, New Jersey (LJ091), was conducted during 1988. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 5 refs., 2 figs., 2 tabs.

  1. Results of the radiological survey at 7 Hancock Street, Lodi, New Jersey (LJ027)

    SciTech Connect

    Cottrell, W.D.; Floyd, L.M.; Francis, M.W.; Mynatt, J.O.

    1989-09-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. AT the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 7 Hancock Street, Lodi, New Jersey (LJ027), was conducted during 1985 and 1986. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 5 refs., 5 figs., 3 tabs.

  2. Formerly utilized MED/AEC sites remedial action program. Radiological survey of The George Herbert Jones Chemical Laboratory, The University of Chicago, Chicago, Illinois, June 13-17, 1977

    SciTech Connect

    Wynveen, R.A.; Smith, W.H.; Mayes, C.B.; Justus, A.L.

    1982-05-01

    A comprehensive radiological survey was conducted at George Herbert Jones Chemical Laboratory at the University of Chicago, Chicago, Illinois. Radiochemistry for the MED/AEC project was performed in this building in the 1940s. The building is now used as laboratories, offices, and classrooms. The survey was undertaken to determine the location and quantities of any radioactive materials remaining from the MED/AEC operations. Forty-three spots of contamination possibly resulting from MED/AEC occupancy in 17 rooms exceeded the allowable limits as given in the ANSI Standard N13.12. Under current use conditions, the potential for radiation exposure to occupants of this building from these sources of contamination is remote. Concentrations of radon daughters in the air of the building, as measured with grab-sampling techniques, were below the limit of 0.01 WL above background as given in the Surgeon General's Guidelines. No long-lived radionuclides were detected in any air sample. Concentrations of radionuclides in soil samples from near the laboratory generally indicated background levels. In order to reduce the potential for radiation exposure, remedial measures such as stabilization of the contamination in place would be applicable as a short-term measure. In order to reduce the risk in the event that building modifications take place in the future, health physics procedures and coverage are recommended. The long-term solution would involve decontamination by removal of the radioactive residues from the 17 rooms or areas where contamination possibly resulting from MED/AEC activities was detected.

  3. Radiological Conditions at the Semipalatinsk Test Site, Kazakhstan: Preliminary Assessment and Recommendations for Further Study

    SciTech Connect

    Napier, Bruce A. )

    1999-01-01

    This is a review of the book ''Radiological Conditions at the Semipalatinsk Test Site, Kazakhstan: Preliminary Assessment and Recommendations for Further Study.''

  4. Results of the radiological survey at 80 Industrial Road, Lodi, New Jersey (LJ061)

    SciTech Connect

    Foley, R.D.; Carrier, R.F.; Floyd, L.M.; Crutcher, J.W.

    1989-07-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 80 Industrial Road, Lodi, New Jersey (LJ061), was conducted during 1985 and 1986. Results of the survey demonstrated radionuclide concentrations in excess of DOE remedial action criteria, primarily from the /sup 232/Th decay chain, with some contamination from /sup 226/Ra. The radionuclide distributions are typical of the type of material originating from the MCW site. 5 refs., 11 figs., 3 tabs.

  5. Results of the radiological survey at 48 Schlosser Drive, Rochelle Park, New Jersey (RJ005)

    SciTech Connect

    Foley, R.D.; Brown, K.S.

    1992-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956.MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from thisthorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy(DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally [sup 232]Tb, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 48 Schlosser Drive, Rochelle Park, New Jersey (RJO05), was conducted on July 14, 1991. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

  6. Results of the radiological survey at 37 Schlosser Drive, Rochelle Park, New Jersey (RJ002)

    SciTech Connect

    Foley, R.D.; Brown, K.S.

    1992-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 37 Schlosser Drive, Rochelle Park, New Jersey (RJ002), was conducted on July 14, 1991. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

  7. Results of the radiological survey at 28 Long Valley Road, Lodi, New Jersey (LJ047)

    SciTech Connect

    Cottrell, W.D.; Floyd, L.M.; Francis, M.W.; Mynatt, J.O.

    1989-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 28 Long Valley Road, Lodi, New Jersey (LJ047), was conducted during 1985, 1986, 1987. Some radionuclide measurements were greater than typical background levels in the northern New Jersey area. However, results of the Survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. 5 refs., 8 figs., 3 tabs.

  8. Results of the radiological survey at 27 Schlosser Drive, Rochelle Park, New Jersey (RJ004)

    SciTech Connect

    Foley, R.D.; Brown, K.S.

    1992-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally [sup 232]Tb, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 27 Schlosser Drive, Rochelle Park, New Jersey (RJ004), was conducted on July 14, 1991. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

  9. Results of the radiological survey at 30 Long Valley Road, Lodi, New Jersey (LJ045)

    SciTech Connect

    Cottrell, W.D.; Floyd, L.M.; Francis, M.W.; Mynatt, J.O.

    1989-11-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 30 Long Valley Road, Lodi, New Jersey (LJ045), was conducted during 1985, 1986, and 1987. Some radionuclide measurements were greater than typical background levels in the northern New Jersey area. However, results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. 5 refs., 10 figs., 3 tabs.

  10. Results of the radiological survey at 31 Schlosser Drive, Rochelle Park, New Jersey (RJ003)

    SciTech Connect

    Foley, R.D.; Brown, K.S.

    1992-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally [sup 232]Tb, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 31 Schlosser Drive, Rochelle Park, New Jersey (RJ003), was conducted on July 14, 1991. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

  11. Results of the radiological survey at 27 Schlosser Drive, Rochelle Park, New Jersey (RJ004)

    SciTech Connect

    Foley, R.D.; Brown, K.S.

    1992-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Tb, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 27 Schlosser Drive, Rochelle Park, New Jersey (RJ004), was conducted on July 14, 1991. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

  12. Results of the radiological survey at 90 C Avenue, Lodi, New Jersey (LJ079)

    SciTech Connect

    Foley, R.D.; Floyd, L.M.

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducted an investigative radiological survey during 1988 at 90 C Avenue, Lodi, New Jersey (LJ079), one of the properties in the vicinity of the MCW site. The survey included a gamma radiation scan of the surface and at one meter above the surface, as well as radionuclide sampling of surface and subsurface soil. The survey objective was to determine whether this site was contaminated with radioactive residues derived from MCW, principally /sup 232/Th. Results of the survey demonstrated radionuclide concentrations in excess of DOE remedial action criteria, primarily from the /sup 232/Th decay chain, with some contamination from /sup 226/Ra. The radionuclide distributions are typical of the type of material originating from the MCW site. 5 refs., 3 figs., 3 tabs.

  13. Results of the radiological survey at 77 Sinninger Street, Maywood, New Jersey (MJ052)

    SciTech Connect

    Foley, R.D.; Brown, K.S.

    1993-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 77 Sinninger Street, Maywood, New Jersey (MJ052), was conducted on December 17, 1992. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

  14. Results of the radiological survey at 48 Schlosser Drive, Rochelle Park, New Jersey (RJ005)

    SciTech Connect

    Foley, R.D.; Brown, K.S.

    1992-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956.MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from thisthorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy(DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Tb, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 48 Schlosser Drive, Rochelle Park, New Jersey (RJO05), was conducted on July 14, 1991. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

  15. Results of the radiological survey at 37 Schlosser Drive, Rochelle Park, New Jersey (RJ002)

    SciTech Connect

    Foley, R.D.; Brown, K.S.

    1992-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally [sup 232]Th derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 37 Schlosser Drive, Rochelle Park, New Jersey (RJ002), was conducted on July 14, 1991. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

  16. Results of the radiological survey at 31 Schlosser Drive, Rochelle Park, New Jersey (RJ003)

    SciTech Connect

    Foley, R.D.; Brown, K.S.

    1992-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Tb, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 31 Schlosser Drive, Rochelle Park, New Jersey (RJ003), was conducted on July 14, 1991. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

  17. Results of the radiological survey at 9 Hancock Street, Lodi, New Jersey (LJ028)

    SciTech Connect

    Cottrell, W.D.; Floyd, L.M.; Francis, M.W.; Mynatt, J.O.

    1989-09-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 9 Hancock Street, Lodi, New Jersey (LJ028), was conducted during 1985 and 1986. Some radionuclide measurements were greater than typical background levels in the northern New Jersey area. However, results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. 5 refs., 6 figs., 3 tabs.

  18. Results of the radiological survey at 7 Redstone Lane, Lodi, New Jersey (LJ044)

    SciTech Connect

    Cottrell, W.D.; Floyd, L.M.; Francis, M.W.; Mynatt, J.O.

    1989-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclides analyses. The survey of this site, 7 Redstone Lane, Lodi, New Jersey (LJ044), was conducted during 1985 and 1986. Some radionuclide measurements were greater than typical background levels in the northern New Jersey area. However, results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. 5 refs., 4 figs., 3 tabs.

  19. Results of the radiological survey at 32 Long Valley Road, Lodi, New Jersey (LJ046)

    SciTech Connect

    Cottrell, W.D.; Floyd, L.M.; Francis, M.W.; Mynatt, J.O.

    1989-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 32 Long Valley Road, Lodi, New Jersey (LJ046), was conducted during 1985, 1986, and 1987. Some radionuclide measurements were greater than typical background levels in the northern New Jersey area. However, results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. 5 refs., 6 figs., 3 tabs.

  20. Results of the radiological verification survey of the partial remediation at 90 Avenue C, Lodi, New Jersey (LJ079V)

    SciTech Connect

    Foley, R.D.; Johnson, C.A.

    1994-02-01

    The property at 90 Avenue C, Lodi, New Jersey is one of the vicinity properties of the former Maywood Chemical Works, Maywood, New Jersey designated for remedial action by the US Department of Energy (DOE). In July 1991, Bechtel National, Inc. performed a partial remedial action on this property. At the request of DOE, a team from Oak Ridge National Laboratory conducted an independent radiological verification survey in July, 1991 at this site. The purpose of the verification survey was to ensure the effectiveness of remedial actions performed within FUSRAP and to confirm the site`s compliance with DOE guidelines. The radiological survey included surface gamma scans indoors and outdoors, ground-level beta-gamma measurements, and systematic and biased soil and material sampling. Results of the verification survey demonstrated that all radiological measurements on the portions of the property that had been remediated were within DOE guidelines. However, there still remains a portion of the property to be remediated that is not covered by this verification survey.

  1. Formerly utilized MED/AEC sites remedial action program. Radiological survey of the National Guard Armory at Washington Park, 52nd Street and Cottage Grove Avenue, Chicago, Illinois, September 19, 1977-October 11, 1978

    SciTech Connect

    Wynveen, R.A.; Smith, W.H.; Mayes, C.B.; Justus, A.L.

    1983-01-01

    A comprehensive radiological survey was conducted at the Illinois National Guard Armory at Washington Park in Chicago. This facility, used for uranium processing during the MED/AEC era, is now used as offices, classrooms, and storage and garage areas. Forty-two spots of contaminaton in nine rooms or areas exceeded the allowable limits for uranium as given in the ANSI Standard N13.12. In most instances, the contamination was found to be removable and available for transfer to other locations. However, under current use conditions, the potential for radiation exposure to occupants of this building from these sources of contamination is small. Concentrations of radon daughters in the air in the building, as measured by grab-sampling techniques, were less than the limit of 0.01 WL above background as given in the Surgeon General's Guidelines in 10 CFR 712. No long-lived radionuclides were detected in any air sample. Concentrations of radionuclides in soil samples collected around the facility indicated essentially background levels. The presumed maximum 50-year dose commitments from potential inhalation/ingestion of residual contamination were calculated to be 2.5 mrem to the lung, 0.51 mrem to the bone, 0.12 mrem to the kidney, and 0.031 mrem wholebody; each of these is less than 0.5% of the appropriate standards for an individual in an uncontrolled area. In order to rduce the potential for radiation exposure, remedial measures such as stabilization of the contamination in place would be applicable as a short-term measure. In order to reduce the risk in the event that building modifications take place in the future, health physics procedures and coverage are recommended. The long-term solution would involve dcontamination by removal of the radioactive residues from the 11 rooms or areas in the facility.

  2. Off-site consequences of radiological accidents: methods, costs and schedules for decontamination

    SciTech Connect

    Tawil, J.J.; Bold, F.C.; Harrer, B.J.; Currie, J.W.

    1985-08-01

    This report documents a data base and a computer program for conducting a decontamination analysis of a large, radiologically contaminated area. The data base, which was compiled largely through interviews with knowledgeable persons both in the public and private sectors, consists of the costs, physical inputs, rates and contaminant removal efficiencies of a large number of decontamination procedures. The computer program utilizes this data base along with information specific to the contaminated site to provide detailed information that includes the least costly method for effectively decontaminating each surface at the site, various types of property losses associated with the contamination, the time at which each subarea within the site should be decontaminated to minimize these property losses, the quantity of various types of labor and equipment necessary to complete the decontamination, dose to radiation workers, the costs for surveying and monitoring activities, and the disposal costs associated with radiological waste generated during cleanup. The program and data base are demonstrated with a decontamination analysis of a hypothetical site. 39 refs., 24 figs., 155 tabs.

  3. Radiological Survey Results for the R.P. Adams Company Property, Tonawanda, New York (TNY003)

    SciTech Connect

    Carrier, R.F.; McKenzie, S.P.; Uziel, M.S.

    1998-11-01

    At the request of the U.S. Department of Energy (DOE), a team horn Oak Ridge National Laboratory conducted a radiological survey of property belonging to the R P. Adarns Company, Inc., Tonawanda, New York. The survqy was performed in November 1995 and May and July 1996. The P-e of tie SUIWY was to determine if radioactive residuals had migrated, or been re&stribu@ from the former Linde property to the south onto the R P. Adams property. The Linde Air Products Division of Union Carbide Corporation, Toni~w~da, New York, had used radioactive materials at that location for work performed under government contract born 1942 through 1948. The survey was performed in response to Formerly Utilized Sites Remedial Action Program (FUSRAP) requirements. These requirements dictate that the radiological status of certain vicinity properties shall be assessed and docw.nented according to prescribed procedures prior to certification of the property for release for unrestricted use. Such release can only be granted if the property is found to be within current applicable authorized limits. The survey included a gamma scan of accessible areas in both the developed and the undeveloped portions of the property and the collection and radionuclide analysis of soil samples. A comparison of these data to the current DOE guidelines shows that all radionuclide concentrations and radioactivity levels found on the property are below the current guidelines. Therefore, this property should not be included in the FUSRAP program for remediation. xi

  4. Results of the radiological survey at the Granite City Steel facility, Granite City, Illinois

    SciTech Connect

    Swaja, R.E.; Cottrell, W.D.

    1990-07-01

    In the late 1950s and early 1960s, uranium ingots were x-rayed for the Atomic Energy Commission at the South Plant facility of the Granite City Steel Company, Granite City, Illinois. The x-ray equipment is still housed in a building on the southern end of the property. At the time of the survey, neither the equipment nor the building had been used for some time. It is the policy of the US Department of Energy (DOE) to verify that such sites are in compliance with current federal guidelines. Because documentation establishing the current radiological condition of the property is unavailable, a radiological survey was conducted by members of the Measurement Applications and Development Group of the Oak Ridge National Laboratory in March 1989. The survey included: measurement of gamma exposure rates both indoors and outdoors; collection and radionuclide analysis of soil and debris samples; and measurements to determine alpha and beta-gamma surface contamination. 3 refs., 12 figs., 3 tabs.

  5. Results of the radiological survey at 133 Maywood Avenue, Maywood, New Jersey (MJ025)

    SciTech Connect

    Foley, R.D.; Carrier, R.F.; Floyd, L.M.; Crutcher, J.W. )

    1989-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 133 Maywood Avenue, Maywood, New Jersey (MJ025), was conducted during 1987. The survey results demonstrate that all radionuclide concentrations and measurements conform to DOE remedial action criteria. All values are at or below typical background values found in northern New Jersey. 5 refs., 2 figs., 3 tabs.

  6. Results of the radiological survey at 14 Long Valley Road, Lodi, New Jersey (LJ070)

    SciTech Connect

    Foley, R.D.; Carrier, R.F.

    1989-12-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 14 Long Valley Road, Lodi New Jersey (LJ070), was conducted during 1987. Survey measurements indicate that the property contained radioactive contamination primarily from the {sup 232}Th decay chain. The radionuclide distributions are typical of the type of material originating from processing operations at the MCW. 5 refs., 5 figs., 3 tabs.

  7. Results of the radiological survey at 83 Belle Avenue, Maywood, New Jersey (MJ047)

    SciTech Connect

    Foley, R.D.; Floyd, L.M.

    1989-11-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 83 Belle Avenue, Maywood, New Jersey (MJ047), was conducted during 1988. 5 refs., 2 figs., 3 tabs.

  8. Results of the radiological survey at 15 John Street, Lodi, New Jersey (LJ087)

    SciTech Connect

    Foley, R.D.; Floyd, L.M.

    1989-12-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 15 John Street, Lodi, New Jersey (LJ087), was conducted during 1988. 5 refs., 3 figs., 3 tabs.

  9. Results of the radiological survey at 48 Long Valley Road, Lodi, New Jersey (LJ085)

    SciTech Connect

    Foley, R.D.; Floyd, L.M.

    1989-11-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 48 Long Valley Road, Lodi, New Jersey (LJ085), was conducted during 1988. 5 refs., 6 figs., 3 tabs.

  10. Results of the radiological survey at 104 Avenue E, Lodi, New Jersey (LJ086)

    SciTech Connect

    Foley, R.D.; Floyd, L.M.

    1989-12-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 104 Avenue E, Lodi, New Jersey (LJ086), was conducted during 1988. 5 refs., 2 figs., 3 tabs.

  11. Results of the radiological survey at 137 Maywood Avenue, Maywood, New Jersey (MJ026)

    SciTech Connect

    Foley, R.D.; Carrier, R.F.

    1989-12-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 137 Maywood Avenue, Maywood, New Jersey (MJ026), was conducted during 1987. 6 refs., 2 figs., 3 tabs.

  12. Results of the radiological survey at 17 John Street, Lodi, New Jersey

    SciTech Connect

    Foley, R.D.; Floyd, L.M.

    1989-12-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 17 John Street, Lodi, New Jersey (LJ088), was conducted during 1988. 5 refs., 2 figs., 3 tabs.

  13. Results of the radiological survey at 21 West Central Avenue, Maywood, New Jersey (MJ046)

    SciTech Connect

    Foley, R.D.; Floyd, L.M.

    1989-11-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 21 West Central Avenue, Maywood, New Jersey (MJ046), was conducted during 1988. 5 refs., 2 figs., 3 tabs.

  14. An aerial radiological survey of the West Valley Demonstration Project and surrounding area, West Valley, New York

    SciTech Connect

    Berry, H.A.

    1991-09-01

    An aerial radiological survey of the West Valley Demonstration Project and the surrounding area was conducted from mid-August through early September 1984 by EG G Energy Measurements, Inc. for the United States Department of Energy. The radiological survey was part of the United States Department of Energy Comprehensive Integrated Remote Sensing (CIRS) program, which provides state-of-the-art remote sensing to support the needs of the various DOE facilities. The survey consisted of airborne measurements of both natural and man-made gamma radiation emanating from the terrestrial surface. These measurements allowed an estimate of the distribution of isotopic concentrations in the area surrounding the project site. Results are reported as isopleths superimposed on aerial photographs of the area. Gamma ray energy spectra are also presented for the net man-made radionuclides. 8 refs., 16 figs., 9 tabs.

  15. Radiological survey results at the former Bridgeport Brass Company facility, Seymour, Connecticut

    SciTech Connect

    Foley, R.D.; Carrier, R.F.

    1993-06-01

    At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey of the former Bridgeport Brass Company facility, Seymour, Connecticut. The survey was performed in May 1992. The purpose of the survey was to determine if the facility had become contaminated with residuals containing radioactive materials during the work performed in the Ruffert building under government contract in the 1960s. The survey included a gamma scanning over a circumscribed area around the building, and gamma and beta-gamma scanning over all indoor surfaces as well as the collection of soil and other samples for radionuclide analyses. Results of the survey demonstrated radionuclide concentrations in indoor and outdoor samples, and radiation measurements over floor and wall surfaces, in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines. Elevated uranium concentrations outdoors were limited to several small, isolated spots. Radiation measurements exceeded guidelines indoors over numerous spots and areas inside the building, mainly in Rooms 1--6 that had been used in the early government work.

  16. OFF-SITE SURVEILLANCE ACTIVITIES OF TFE SOUTHWESTERN RADIOLOG1 CAL BEALTH LABORATORY

    Office of Legacy Management (LM)

    SURVEILLANCE ACTIVITIES OF TFE SOUTHWESTERN RADIOLOG1 CAL BEALTH LABORATORY from July through December 1969 - by Environmental Surveillance Southwestern Radiological Health Laboratory ENVIROhMENTAL PROTECTION AGEXCI' February 1971 This surveillance performed under a Xenorandum of Understanding (No. SF 54 373) for the U. S . ATOMIC %I.;Ei?GY COMXESSION OFF-SITE SURVEILLANCE ACTIVITIES OF TRE SQUTmJESTERN RADIOLOGICAL HEALTH LABORATORY from July through December 1969 by Environmental Surveillance

  17. Final report of the radiological release survey of Building 11 at the Grand Junction Office Facility

    SciTech Connect

    Johnson, R.K.; Corle, S.G.

    1997-09-01

    The U.S. Department of Energy (DOE) Grand Junction Office (GJO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore concentrates and mill tailings during vanadium refining activities of the Manhattan Engineer District, and during sampling, assaying, pilot milling, storage, and brokerage activities conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJO Remedial Action Project (GJORAP) to clean up and restore the facility lands, improvements, and underlying aquifer. WASTREN-Grand Junction is the site contractor for the facility and the remedial action contractor for GJORAP. Building 11 and the underlying soil were found not to be radiologically contaminated; therefore, the building can be released for unrestricted use. Placards have been placed at the building entrances indicating the completion of the radiological release survey and prohibiting the introduction of any radioactive materials within the building without written approvals from the GJO Facilities Operations Manager. This document was prepared in response to a DOE-GJO request for an individual final release report for each GJO building.

  18. Final report of the radiological release survey of Building 19 at the Grand Junction Office Facility

    SciTech Connect

    Johnson, R.K.; Corle, S.G.

    1997-09-01

    The U.S. Department of Energy (DOE) Grand Junction Office (GJO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore concentrates and mill tailings during vanadium refining activities of the Manhattan Engineer District, and during sampling, assaying, pilot milling, storage, and brokerage activities conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJO Remedial Action Project (GJORAP) to clean up and restore the facility lands, improvements, and underlying aquifer. WASTREN-Grand Junction is the site contractor for the facility and the remedial action contractor for GJORAP. Building 19 and the underlying soil were found not to be radiologically contaminated; therefore, the building can be released for unrestricted use. Placards have been placed at the building entrances indicating the completion of the radiological release survey and prohibiting the introduction of any radioactive materials within the building without written approvals from the GJO Facilities Operations Manager. This document was prepared in response to a DOE-GJO request for an individual final release report for each GJO building.

  19. Final report of the radiological release survey of Building 54 at the Grand Junction Office Facility

    SciTech Connect

    Johnson, R.K.; Corle, S.G.

    1997-09-01

    The U.S. Department of Energy (DOE) Grand Junction Office (GJO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore concentrates and mill tailings during vanadium refining activities of the Manhattan Engineer District, and during sampling, assaying, pilot milling, storage, and brokerage activities conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJO Remedial Action Project (GJORAP) to clean up and restore the facility lands, improvements, and underlying aquifer. WASTREN-Grand Junction is the site contractor for the facility and the remedial action contractor for GJORAP. Building 54 and the underlying soil were found not to be radiologically contaminated, and can be released for unrestricted use. Placards have been placed at the building entrances indicating the completion of the radiological release survey and prohibiting the introduction of any radioactive materials within the building without written approvals from the GJO Facilities Operations Manager. This document was prepared in response to a DOE-GJO request for an individual release report for each GJO building.

  20. Final report of the radiological release survey of Building 29 at the Grand Junction Office Facility

    SciTech Connect

    Johnson, R.K.; Corle, S.G.

    1997-09-01

    The U.S. Department of Energy (DOE) Grand Junction Office (GJO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore concentrates and mill tailing during vanadium refining activities of the Manhattan Engineer District, and during sampling, assaying, pilot milling, storage, and brokerage activities conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJO Remedial Action Project (GJORAP) to clean up and restore the facility lands, improvements, and underlying aquifer. WASTREN-Grand Junction is the site contractor for the facility and the remedial action contractor for GJORAP. Building 29 and the underlying soil were found not to be radiologically contaminated; therefore, the building can be released for unrestricted use. Placards have been placed at the building entrances indicating the completion of the radiological release survey and prohibiting the introduction of any radioactive materials within the building without written approvals from the GJO Facilities Operations Manager. This document was prepared in response to a DOE-GJO request for an individual final release report for each GJO building.

  1. Results of the radiological survey at 110 E Hunter Avenue, Maywood, New Jersey (MJ022)

    SciTech Connect

    Foley, R.D.; Carrier, R.F.; Floyd, L.M.; Crutcher, J.W. )

    1989-09-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 110 E. Hunter Avenue, Maywood, New Jersey (MJ022), was conducted during 1987. Following the removal of a small chunk of material showing elevated gamma exposure rates, all radionuclide concentrations and measurements conformed to DOE remedial action criteria. The slightly elevated radionuclide concentrations found in other soil samples were the result of naturally enhances radioactivity characteristic of some environmental materials such as coal ash and were unrelated to operations at the MCW site. The survey data demonstrate that the property requires no further action on the part of DOE. 4 refs., 2 figs., 3 tabs.

  2. Radiological survey of Johnston Atoll. Dates of survey: April-August 1980. Revision 1

    SciTech Connect

    Jaffe, R.J.; Tipton, W.J.

    1982-04-01

    A radiological survey was conducted over all land areas of Johnston Atoll between April and August 1980. The survey was performed to locate and quantify residual surface transuranic (i.e., plutonium and americium) contamination resulting from three THOR missile aborts which occurred during that portion of the 1962 atmospheric nuclear testing series conducted by the United States from Johnston Island. A high purity germanium planar detector was utilized to enhance the detection sensitivity for the 59.5 keV gamma ray from /sup 241/Am. Results are reported as equivalent surface concentration in units of nCi/m/sup 2/. Conversion factors are also included for several other assumed source distributions. Soil samples were obtained to determine plutonium-to-americium ratios. 7 references, 14 figures, 1 table.

  3. Radiological Survey Results for Areas A1 North, A5A, A6, and B2 at the Molycorp Washington Remediation Project, Washington, Pennsylvania

    SciTech Connect

    W.C. Adams

    2007-03-13

    Perform radiological surveys of the Molycorp Washington Remediation Project (MWRP) facility in Washington, Pennsylvania

  4. Radiological survey report for the former Middlesex Sampling Plant, Middlesex, New Jersey

    SciTech Connect

    Not Available

    1985-03-01

    The former Middlesex Sampling Plant (MSP), Middlesex, New Jersey is currently owned by the United States Department of Energy (DOE). It was used from 1943 to 1967 as a sampling and storage facility for uranium and thorium concentrates. During the course of operations, the buildings and grounds at the site became contaminated. In 1980, DOE initiated a multiphase remedial action project to clean up the site and several vicinity properties onto which contamination from the plant had migrated. Material from these properties was consolidated in a storage pile at the MSP during Phases I and II of the project. A decision by DOE regarding the final disposition of the site will be made once the results of an engineering evaluation of disposition alternatives and of other studies required by the National Environmental Policy Act are available. This report describes the current radiological status of the MSP site as determined by a characterization survey performed to obtain information necessary for the development of the Phase III engineering design. The grounds and the four buildings on-site were surveyed; uranium-238 and radium-226 concentrations exceeded DOE remedial action guidelines. Approximately 69,000 m/sup 3/ (91,000 yd/sup 3/) of material must be removed for the site to comply with guidelines. This total comprises the following approximate volumes: 13,000 m/sup 3/ (17,000 yd/sup 3/) of asphalt/gravel and soil from the grounds, 3650 m/sup 3/ (4775 yd/sup 3/) from demolition of the Boiler House and Process Building, and 52,000 m/sup 3/ (69,000 yd/sup 3/) of contaminated material that is or will be stored on-site. In addition, parts of the Garage and Administration Building must be decontaminated. 14 refs., 11 figs., 6 tabs.

  5. An aerial radiological survey of the Fernald Environmental Management Project and surrounding area, Fernald, Ohio

    SciTech Connect

    Phoenix, K.A.

    1997-04-01

    An aerial radiological survey was conducted from May 17--22, 1994, over a 36 square mile (93 square kilometer) area centered on the Fernald Environmental Management Project located in Fernald, Ohio. The purpose of the survey was to detect anomalous gamma radiation in the environment surrounding the plant. The survey was conducted at a nominal altitude of 150 feet (46 meters) with a line spacing of 250 feet (76 meters). A contour map of the terrestrial gamma exposure rate extrapolated to 1 meter (3.3 feet) above ground was prepared and overlaid on an aerial photograph of the area. Analysis of the data for man made sources showed five sites within the boundaries of the Fernald Environmental Management Project having elevated readings. The exposure rates outside the plant boundary were typical of naturally occurring background radiation. Soil samples and pressurized ion chamber measurements were obtained at four locations within the survey boundaries to supplement the aerial data. It was concluded that although the radionuclides identified in the high-exposure-rate areas are naturally occurring, the levels encountered are greatly enhanced due to industrial activities at the plant.

  6. Review of radiological surveys of the General Services Administration's Raritan Depot in Edison, New Jersey

    SciTech Connect

    Herzenberg, C.L.; Winter, R.C.

    1986-10-01

    This report reviews two recent radiological surveys of the General Services Administration (GSA) Raritan Depot in Edison, New Jersey, that were conducted after somewhat elevated levels of radiation were detected within a depot building. The first survey indicated gamma radiation levels were higher than natural background levels in some buildings and identified the probable source of the radiation as gypsum-like building tiles that contained natural uranium-chain radionuclides at a level 20 times higher than other materials. Elevated levels of radon and radon decay products also were detected in some buildings. A follow-on survey was conducted to confirm the January measurements and to measure radiation levels at other locations: additional buildings at the depot, buildings on the Middlesex County College campus, and a possible outdoor disposal site. EPA measurements established that ceiling material is the primary source of the radiation. Radioisotope analysis of the ceiling tile material from buildings with elevated radiation levels showed the presence of radium-226 at levels of approximately 25 picocuries per gram (pCi/g); this material would thus have to be treated as hazardous waste, should it be removed. This report critiques the methodology and results of the two surveys and recommends further action.

  7. Results of the independent radiological verification survey of the lower Sheffield Brook floodplain, Wayne, New Jersey

    SciTech Connect

    Yalcintas, M.G.; Carrier, R.F.

    1989-05-01

    Prior to 1971, the W.R. Grace Company processed and stored radioactive materials at Wayne, New Jersey, under license to the Atomic Energy Commission. Decontamination of structures and storage of waste materials on the property at the Wayne Interim Storage Site (WISS) took place in 1974. Surveys by the State of New Jersey Department of Environmental Protection and by Oak Ridge Associated Universities for the NRC in 1982 indicated that properties adjacent to the WISS contained surface contamination by radioactive residuals in amounts exceeding those acceptable under US Department of Energy (DOE) remedial action guidelines. At the request of DOE, remedial actions have been conducted by Bechtel National, Inc., to remove radioactive residuals from properties adjacent to the site. It is the policy of DOE to assign an independent verification contractor to ensure the effectiveness of remedial actions performed within the Formerly Utilized Sites Remedial Action Program. This report describes the methods and results of those studies that were conducted by the Measurement Applications and Development Group of the Oak Ridge National Laboratory for the lower Sheffield Brook floodplain west of the WISS. Based upon post-remedial action and verification survey data, it was concluded that residual soil concentrations and gamma levels following excavation and backfilling of the area are within the limits prescribed by DOE radiological guidelines. 12 refs., 6 figs., 8 tabs.

  8. Radiological survey of the inactive uranium-mill tailings at Durango, Colorado

    SciTech Connect

    Haywood, F.F.; Perdue, P.T.; Shinpaugh, W.H.; Ellis, B.S.; Chou, K.D.

    1980-03-01

    Results of a radiological survey of the inactive uranium-mill site at Durango, Colorado, conducted in April 1976, in cooperation with a team from Ford, Bacon and Davis Utah Inc., are presented together with descriptions of the instruments and techniques used to obtain the data. Direct above-ground gamma measurements and analysis of surface soil and sediment samples indicate movement of tailings from the piles toward Lightner Creek on the north and the Animas River on the east side of the piles. The concentration of /sup 226/Ra in the former raffinate pond area is only slightly above the background level. Two structures in Durango were found to contain high concentrations of airborne radon daughters, where tailings are known to have been utilized in construction. Near-background concentrations of radon daughters were found in a well-ventilated building close to the tailings.

  9. Limitations Influencing Interventional Radiology in Canada: Results of a National Survey by the Canadian Interventional Radiology Association (CIRA)

    SciTech Connect

    O'Brien, Jeremy; Baerlocher, Mark Otto Asch, Murray R.; Hayeems, Eran; Kachura, John R.; Collingwood, Peter

    2007-09-15

    Purpose. To describe the current state and limitations to interventional radiology (IR) in Canada through a large, national survey of Canadian interventional radiologists. Methods. An anonymous online survey was offered to members of the Canadian Interventional Radiology Association (CIRA). Only staff radiologists were invited to participate. Results. Seventy-five (75) responses were received from a total of 247, giving a response rate of 30%. Respondents were split approximately equally between academic centers (47%) and community practice (53%), and the majority of interventional radiologists worked in hospitals with either 200-500 (49%) or 500-1,000 (39%) beds. Procedures listed by respondents as most commonly performed in their practice included PICC line insertion (83%), angiography and stenting (65%), and percutaneous biopsy (37%). Procedures listed as not currently performed but which interventional radiologists believed would benefit their patient population included radiofrequency ablation (36%), carotid stenting (34%), and aortic stenting (21%); the majority of respondents noted that a lack of support from referring services was the main reason for not performing these procedures (56%). Impediments to increasing scope and volume of practice in Canadian IR were most commonly related to room or equipment shortage (35%), radiologist shortage (33%), and a lack of funding or administrative support (28%). Conclusion. Interventional radiology in Canada is limited by a number of factors including funding, manpower, and referral support. A concerted effort should be undertaken by individual interventional radiologists and IR organizations to increase training capacity, funding, remuneration, and public exposure to IR in order to help advance the subspecialty.

  10. Improving Site-Specific Radiological Performance Assessments - 13431

    SciTech Connect

    Tauxe, John; Black, Paul; Catlett, Kate; Lee, Robert; Perona, Ralph; Stockton, Tom; Sully, Mike

    2013-07-01

    An improved approach is presented for conducting complete and defensible radiological site-specific performance assessments (PAs) to support radioactive waste disposal decisions. The basic tenets of PA were initiated some thirty years ago, focusing on geologic disposals and evaluating compliance with regulations. Some of these regulations were inherently probabilistic (i.e., addressing uncertainty in a quantitative fashion), such as the containment requirements of the U.S. Environmental Protection Agency's (EPA's) 40 CFR 191, Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes, Chap. 191.13 [1]. Methods of analysis were developed to meet those requirements, but at their core early PAs used 'conservative' parameter values and modeling approaches. This limited the utility of such PAs to compliance evaluation, and did little to inform decisions about optimizing disposal, closure and long-term monitoring and maintenance, or, in general, maintaining doses 'as low as reasonably achievable' (ALARA). This basic approach to PA development in the United States was employed essentially unchanged through the end of the 20. century, principally by the U.S. Department of Energy (DOE). Performance assessments developed in support of private radioactive waste disposal operations, regulated by the U.S. Nuclear Regulatory Commission (NRC) and its agreement states, were typically not as sophisticated. Discussion of new approaches to PA is timely, since at the time of this writing, the DOE is in the midst of revising its Order 435.1, Radioactive Waste Management [2], and the NRC is revising 10 CFR 61, Licensing Requirements for Land Disposal of Radioactive Waste [3]. Over the previous decade, theoretical developments and improved computational technology have provided the foundation for integrating decision analysis (DA) concepts and objective-focused thinking, plus a Bayesian approach to

  11. ORNL/luSA-85/6 Health and Safety Research Division PRELIMINARY RADIOLOGICAL SURVEY OF TEE FORMER HAVENS PLANT

    Office of Legacy Management (LM)

    luSA-85/6 Health and Safety Research Division PRELIMINARY RADIOLOGICAL SURVEY OF TEE FORMER HAVENS PLANT OF TEE BRIDGEPORT BRASS COMPANY, BRIDGEPORT, CONNECTICUT May 1985 Work performed as part of the RADIOLOGICAL SURVEY ACCIVITIES PROGRAM OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37831 operated by MARTIN MARIETTA ENERGY SYSTEMS, INC. for the U. S. DEPARTMENT OF ENERGY under Contract No. DE-AC05-840R21400 \ .-l__--.-- -- PRELIMINARY RADIOLOGICAL SURVEY OF THE FORMER HAVENS PLAEJT OF THE

  12. RADIOLOGICAL SURVEY STATION DEVELOPMENT FOR THE PIT DISASSEMBLY AND CONVERSION PROJECT

    SciTech Connect

    Dalmaso, M.; Gibbs, K.; Gregory, D.

    2011-05-22

    The Savannah River National Laboratory (SRNL) has developed prototype equipment to demonstrate remote surveying of Inner and Outer DOE Standard 3013 containers for fixed and transferable contamination in accordance with DOE Standard 3013 and 10 CFR 835 Appendix B. When fully developed the equipment will be part of a larger suite of equipment used to package material in accordance with DOE Standard 3013 at the Pit Disassembly and Conversion Project slated for installation at the Savannah River Site. The prototype system consists of a small six-axis industrial robot with an end effector consisting of a force sensor, vacuum gripper and a three fingered pneumatic gripper. The work cell also contains two alpha survey instruments, swipes, swipe dispenser, and other ancillary equipment. An external controller interfaces with the robot controller, survey instruments and other ancillary equipment to control the overall process. SRNL is developing automated equipment for the Pit Disassembly and Conversion (PDC) Project that is slated for the Savannah River Site (SRS). The equipment being developed is automated packaging equipment for packaging plutonium bearing materials in accordance with DOE-STD-3013-2004. The subject of this paper is the development of a prototype Radiological Survey Station (RSS). Other automated equipment being developed for the PDC includes the Bagless transfer System, Outer Can Welder, Gantry Robot System (GRS) and Leak Test Station. The purpose of the RSS is to perform a frisk and swipe of the DOE Standard 3013 Container (either inner can or outer can) to check for fixed and transferable contamination. This is required to verify that the contamination levels are within the limits specified in DOE-STD-3013-2004 and 10 CFR 835, Appendix D. The surface contamination limit for the 3013 Outer Can (OC) is 500 dpm/100 cm2 (total) and 20 dpm/100 cm2 (transferable). This paper will concentrate on the RSS developments for the 3013 OC but the system for the

  13. Results of the radiological survey at 146 W. Central Avenue, Maywood, New Jersey (MJ034)

    SciTech Connect

    Foley, R.D.; Carrier, R.F.

    1989-11-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and reining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from OaK Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. These surveys typically include direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, a private property at 146 West Central Avenue, Maywood, New Jersey (MJ034), was conducted during 1987 and 1988. While some measurements at this property were greater than background levels typically encountered in the New jersey area, no radiation levels nor radionuclide concentrations exceeded the guidelines established by the DOE for the Maywood, New Jersey, area remedial action plan. However, because of the proximity of the railroad property, which will be remediated, and the DOE's ALARA (As Low As Reasonably Achievable) policy, concurrent removal of the slightly elevated soil layers at 146 W. Central Avenue may be justified. 6 refs., 6 figs., 3 tabs.

  14. Radiological Survey Tool Set for ArcGIS 8.3 and ArcPad 6.0

    SciTech Connect

    ROGER, COTTRELL

    2004-11-30

    The Radiological Control Operations (RCO) group at the Savannah River Site (SRS) is tasked with conducting routine surveys for the detection of radiological contaminants in the environment. The Radiological Survey Tool Set (RSTS) was developed by the Environmental & Geographic Information Systems (EGIS) group of SRS to assist RCO personnel in this survey process. The tool set consists of two major components. The first component is a custom extension for ArcGIS 8.3 that allows the user to interactively create a sampling plan prior to entering the field. Additionally, the extension allows the user to upload field-collected data to the GIS with post-processing functionality. The second component is a custom ArcPad 6.0 applet. This applet provides the user with navigational capabilities to a selected origin point with the help of Global Positioning Systems (GPS) technology, and the recording of the sample data results into a hand-held field computer via ArcPad 6.0 software.

  15. Surface radiological investigations at the proposed SWSA 7 Site, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    McKenzie, S.P.; Murray, M.E.; Uziel, M.S.

    1995-08-01

    A surface radiological investigation was conducted intermittently from June 1994 to June 1995 at the proposed site for Solid Waste Storage Area (SWSA) 7. The stimulus for this survey was the observation in June 1992 of a man`s trousers became contaminated with {sup 9O}Sr while he was reviewing work on top of the High Flux Isotope Reactor (HFIR) cooling tower. Radiation surveys identified {sup 9O}Sr on the roofs of older buildings at the HFIR site. Since no {sup 9O}Sr was found on buildings built between 1988 and 1990, the {sup 9O}Sr was thought to have been deposited prior to 1988. Later in 1992, beta particles were identified on a bulldozer that had been used in a wooded area southwest of the Health Physics Research Reactor (HPRR) Access Road. More recently in April 1995, {sup 9O}Sr particles were identified on the top side of ceiling tiles in the overhead area of a building in the HFIR Complex. Considering that the proposed SWSA 7 site was located between the HFIR complex and the HPRR Access Road, it was deemed prudent to investigate the possibility that beta particles might also be present at the SWSA 7 site. A possible explanation for the presence of these particles has been provided by long-time ORNL employees and retirees. Strontium-90 as the titanate was developed in the early 1960s as part of the Systems for Nuclear Auxiliary Power (SNAP) Program. Strontium titanate ({sup 90}SrTiO{sub 3}) was produced at the Fission Product Development Laboratory (Building 3517) in the ORNL main plant area. Waste from the process was loaded into a 1-in. lead-lined dumpster, which was transferred to SWSA 5 where it was dumped into a trench. Dumping allowed some articles to become airborne.

  16. Site-specific analysis of radiological and physical parameters for cobbly soils at the Gunnison, Colorado, processing site

    SciTech Connect

    Not Available

    1993-10-01

    The remedial action at the Gunnison, Colorado, processing site is being performed under the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978 [Public Law (PL) 95-6041]. Under UMTRCA, the US Environmental Protection Agency (EPA) is charged with the responsibility of developing appropriate and applicable standards for the cleanup of radiologically contaminated land and buildings at 24 designated sites, including the Gunnison, Colorado, inactive processing site. The remedial action at the processing site will be conducted to remove the tailings and contaminated materials to meet the EPA bulk soil cleanup standards for surface and subsurface soils. The site areas disturbed by remedial action excavation will be either contoured or backfilled with radiologically uncontaminated soil and contoured to restore the site. The final contours will produce a final surface grade that will create positive drainage from the site.

  17. Results of the radiological survey at the National Community Bank, 113 Essex Street, Maywood, New Jersey (MJ021)

    SciTech Connect

    Foley, R.D.; Cottrell, W.D.; Floyd, L.M.

    1989-09-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, the National Community Bank, 113 Essex Street, Maywood, New Jersey (MJ021), was conducted during 1986. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 5 refs., 2 figs., 3 tabs.

  18. Results of the radiological survey at Interstate 80, North Right of Way at Lodi Brook, Lodi, New Jersey (LJ077)

    SciTech Connect

    Foley, R.D.; Floyd, L.M.

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and oil sampling for radionuclide analyses. The survey of this site, on the North Right of Way of Interstate 80 at Lodi Brook, Lodi, New Jersey (LJ077), was conducted during 1988. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 5 refs., 3 figs., 3 tabs.

  19. Radiological Final Status Survey of the Hammond Depot, Hammond, Indiana

    SciTech Connect

    T.J. Vitkus

    2008-04-07

    ORISE conducted extensive scoping, characterization, and final status surveys of land areas and structures at the DNSC’s Hammond Depot located in Hammond, Indiana in multiple phases during 2005, 2006 and 2007.

  20. OFF-SITE SURVEILLANCE ACTIVITIES 0" THE SOUTHWESTERN RADIOLOGICAL...

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    ... between the U.S. Atomic Energy Commission (AEC) and the Public Health Service (PHS), the ... Test Site (NTS), Nuclear Rocket Development Station, and the Nellis Air Force Range. ...

  1. Data Quality Objectives Supporting Radiological Air Emissions Monitoring for the PNNL Site

    SciTech Connect

    Barnett, J. Matthew; Meier, Kirsten M.; Snyder, Sandra F.; Fritz, Brad G.; Poston, Ted M.; Rhoads, Kathleen

    2010-05-25

    This document of Data Quality Objectives (DQOs) was prepared based on the U.S. Environmental Protection Agency (EPA) Guidance on Systematic Planning Using the Data Quality Objectives Process, EPA, QA/G4, 2/2006 (EPA 2006) as well as several other published DQOs. Pacific Northwest National Laboratory (PNNL) is in the process of developing a radiological air monitoring program for the PNNL Site that is distinct from that of the nearby Hanford Site. Radiological emissions at the PNNL Site result from Physical Sciences Facility (PSF) major emissions units. A team was established to determine how the PNNL Site would meet federal regulations and address guidelines developed to monitor and estimate offsite air emissions of radioactive materials. The result is a program that monitors the impact to the public from the PNNL Site.

  2. Results of the Independent Radiological Verification Survey of the B Ditch at DuPont Chambers Works, Deepwater, New Jersey (DNJ001V)

    SciTech Connect

    Johnson, C.A.; Murray, M.E.

    1998-12-01

    This report documents the results of a radiological verification survey conducted at the Chambers Works of the E. I. DuPont Company in Deepwater, New Jersey by a team from the Oak Ridge National Laboratory (ORNL) in response to the Department of Energy's (DOE) Environmental Restoration Program requirements. The survey was to confirm that radioactive residuals previously identified in a portion of a central drainage ditch (the B Ditch) had been remediated to bring that portion of the property into compliance with current U.S. Department of Energy guidelines. The survey was conducted in the spring of 1997 in conjunction with DuPont's remediation and stabilization of the B Ditch to remove elevated levels of 2,4-dinitrotoluene and organic lead compounds. Portions of this ditch were located in an area where former Manhattan Engineering District of the Atomic Energy Commission work was conducted, and an independent verification survey was taken to ensure that this area had been remediated to radionuclide concentrations and activity levels below the applicable guideline limits. The survey included directly measured radiation levels and soil analysis to determine concentrations of uranium, and to compare these data to applicable guidelines. The results of the independent verification survey on this property demonstrate that the remediated and surveyed section of the B Ditch at the DuPont Chambers Works, Deepwater, New Jersey, successfully meets remedial action objectives, and radiological measurements in that portion of the property fall below the limits prescribed by radiological guidelines established for this site.

  3. DOE - Office of Legacy Management -- WNI Split Rock Site - 043

    Office of Legacy Management (LM)

    Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The Western Nuclear, Inc. (WNI) Split Rock site is a Uranium Mill ...

  4. Confirmatory Survey for the Partial Site Release at the ABB Inc. CE Winsor Site, Windsor, CT

    SciTech Connect

    W.C. Adams

    2008-06-27

    The objectives of the confirmatory surveys were to confirm that remedial actions had been effective in meeting established release criteria and that documentation accurately and adequately describes the final radiological conditions of the PSR Impacted Areas.

  5. Results of the radiological survey at the former Chapman Valve Manufacturing Company, Indian Orchard, Massachusetts (CIO001)

    SciTech Connect

    Foley, R.D.; Uziel, M.S.

    1992-07-01

    Radiological survey was conducted at Building 23 (Department No. 40) at the former Chapman Valve Manufacturing Company, Indian Orchard, Massachusetts. The survey was performed in August 1991. The purpose of the survey was to determine whether the property was contaminated with radioactive residues, principally {sup 238}U, as a result of work done for the Atomic Energy Commission (AEC) during the 1940s. The survey included a gamma scan, a beta-gamma scan, and measurement of alpha activity; measurement of direct and removable alpha and beta-gamma levels; and the collection of soil, dust, debris, and smear samples for radionuclide analyses. Survey emphasis was on interior floors, walls, and overhead beams. Radionuclide analysis of soil, dust, and debris, and analysis of smear samples indicate that residual {sup 238}U attributable to former AEC-supported operations is present at this site. Elevated levels of radioactivity were particularly evident on the floors and walls in the western part of the central area of the building (grid blocks Al through A6). Concentrations of {sup 238}U in dust samples collected from overhead beams exceeded DOE guidelines in grid blocks Al through A14 and remained elevated in grid blocks A15 through A19. Dust on a movable overhead crane in grid block A23 was well above the guideline, probably because the crane had at some time been located further west. Some contamination was evident in grid blocks B1 through B5, but clutter and debris in this area prevented a thorough survey.

  6. Radiological Assessment Survey of the Vance road Facility Source Vault Building Materials, Oak Ridge Institute for Science and Education, Oak Ridge, Tennessee

    SciTech Connect

    J. R. Morton

    2000-09-01

    From the 1950s, the Vance Road laboratory was the site of extensive nuclear medical research and involved the used of numerous radionuclides. These nuclides were stored in a source vault stored on the first floor of the facility. Nuclear medical research is no longer conducted in this facility, and the source vault was remediated in preparation for converting the area to office space and general use. The Environmental Survey and Site Assessment Program (ESSAP) of ORISE performed a radiological assessment survey of the source vault and its associated miscellaneous building materials and laboratory equipment in preparation for the conversion to general use space.

  7. Results of the radiological survey at Sumitomo Machinery Corporation of America, 7 Malcolm Avenue, Teterboro, New Jersey (TJ001)

    SciTech Connect

    Foley, R.D.; Floyd, L.M.

    1989-02-01

    A radiological survey of the commercial property at 7 Malcolm Avenue, Teterboro, New Jersey, was conducted on November 12--20, 1986. Samples of the soil surface were taken for further analyses during this time. Conversations with property owners revealed that originally this site was part of a single property of approximately 107 acres owned entirely by the Bendix Aerospace Corporation. During this period of total property ownership, Bendix was licensed by the Nuclear Regulatory Commission to use thorium in on-site Navy/Bendix process. Around 1976, the property was subdivided into three parcels, and one parcel of about 7 acres was purchased by Sumitomo Corporation. 5 refs., 3 figs., 5 tabs.

  8. Results of the radiological survey at Greg's Auto Emporium, 60 State Highway 46, Lodi, New Jersey (LJ089)

    SciTech Connect

    Foley, R.D.; Floyd, L.M.

    1989-11-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, Greg's Auto Emporium, 60 State Highway 46, Lodi, New Jersey (LJ089), was conducted during 1988. 5 refs., 3 figs., 3 tabs.

  9. An aerial radiological survey of the Tonopah Test Range including Clean Slate 1,2,3, Roller Coaster, decontamination area, Cactus Springs Ranch target areas. Central Nevada

    SciTech Connect

    Proctor, A.E.; Hendricks, T.J.

    1995-08-01

    An aerial radiological survey was conducted of major sections of the Tonopah Test Range (TTR) in central Nevada from August through October 1993. The survey consisted of aerial measurements of both natural and man-made gamma radiation emanating from the terrestrial surface. The initial purpose of the survey was to locate depleted uranium (detecting {sup 238}U) from projectiles which had impacted on the TTR. The examination of areas near Cactus Springs Ranch (located near the western boundary of the TTR) and an animal burial area near the Double Track site were secondary objectives. When more widespread than expected {sup 241}Am contamination was found around the Clean Slates sites, the survey was expanded to cover the area surrounding the Clean Slates and also the Double Track site. Results are reported as radiation isopleths superimposed on aerial photographs of the area.

  10. An Aerial Radiological Survey of the Portsmouth Gaseous Diffusion Plant and Surrounding Area, Portsmouth, Ohio

    SciTech Connect

    Namdoo Moon

    2007-12-01

    An aerial radiological survey was conducted over the 16 square-mile (~41 square-kilometer) area surrounding the Portsmouth Gaseous Diffusion Plant. The survey was performed in August 2007 utilizing a large array of helicopter mounted sodium iodide detectors. The purpose of the survey was to update the previous radiological survey levels of the environment and surrounding areas of the plant. A search for a missing radium-226 source was also performed. Implied exposure rates, man-made activity, and excess bismuth-214 activity, as calculated from the aerial data are presented in the form of isopleth maps superimposed on imagery of the surveyed area. Ground level and implied aerial exposure rates for nine specific locations are compared. Detected radioisotopes and their associated gamma ray exposure rates were consistent with those expected from normal background emitters. At specific plant locations described in the report, man-made activity was consistent with the operational histories of the location. There was no spectral activity that would indicate the presence of the lost source.

  11. Final report of the radiological release survey of Building 30B at the Grand Junction Office Facility

    SciTech Connect

    Krauland, P.A.; Corle, S.G.

    1997-09-01

    The U.S. Department of Energy (DOE) Grand Junction Office (GJO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore concentrates and mill tailings during vanadium refining activities of the Manhattan Engineer District, and during sampling, assaying, pilot milling, storage, and brokerage activities conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJO Remedial Action Project (GJORAP) to clean up and restore the facility lands, improvements, and underlying aquifer. WASTREN-Grand Junction is the site contractor for the facility and the remedial action contractor for GJORAP. Building 30B and the underlying soil were found not to be radiologically contaminated; therefore, the building can be released for unrestricted use. Placards have been placed at the building entrances indicating the completion of the radiological release survey and prohibiting the introduction of any radioactive materials within the building without written approvals from the GJO Facilities Operations Manager. This document was prepared in response to a DOE-GJO request for an individual final release report for each GJO building.

  12. Results of the Radiological Survey of the Iowa Army Ammunition Plant, Middletown, Iowa

    SciTech Connect

    Murray, M.E.

    2001-07-17

    At the request of the U.S. Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted an indoor radiological survey of property at the Iowa Army Ammunition Plant (IAAAP), Middletown, Iowa in June 2000. The purpose of the survey was to determine if radioactive residuals resulting from previous Atomic Energy Commission (AEC) activities were present inside selected Line 1 buildings at the IAAAP and conduct sampling in those areas of previous AEC operations that utilized radioactive components at some point during the manufacturing process, in order to evaluate any possible immediate health hazards and to collect sufficient information to determine the next type of survey. The AEC occupied portions of IAAAP from 1947 to 1975 to assemble nuclear weapons. The surveyed areas were identified through interviews with current and former IAAAP employees who had worked at the plant during AEC's tenure, and from AEC records.

  13. ORISE: Characterization surveys

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    objective characterization surveys to define the extent of radiological contamination at sites scheduled for decontamination and decommissioning (D&D). A fundamental...

  14. DRAFT - Design of Radiological Survey and Sampling to Support Title Transfer or Lease of Property on the Department of Energy Oak Ridge Reservation

    SciTech Connect

    Cusick L.T.

    2002-09-25

    The U.S. Department of Energy (DOE) owns, operates, and manages the buildings and land areas on the Oak Ridge Reservation (ORR) in Oak Ridge, Tennessee. As land and buildings are declared excess or underutilized, it is the intent of DOE to either transfer the title of or lease suitable property to the Community Reuse Organization of East Tennessee (CROET) or other entities for public use. It is DOE's responsibility, in coordination with the U.S. Environmental Protection Agency (EPA), Region 4, and the Tennessee Department of Environment and Conservation (TDEC), to ensure that the land, facilities, and personal property that are to have the title transferred or are to be leased are suitable for public use. Release of personal property must also meet site requirements and be approved by the DOE contractor responsible for site radiological control. The terms title transfer and lease in this document have unique meanings. Title transfer will result in release of ownership without any restriction or further control by DOE. Under lease conditions, the government retains ownership of the property along with the responsibility to oversee property utilization. This includes involvement in the lessee's health, safety, and radiological control plans and conduct of site inspections. It may also entail lease restrictions, such as limiting access to certain areas or prohibiting digging, drilling, or disturbing material under surface coatings. Survey and sampling requirements are generally more rigorous for title transfer than for lease. Because of the accelerated clean up process, there is an increasing emphasis on title transfers of facilities and land. The purpose of this document is to describe the radiological survey and sampling protocols that are being used for assessing the radiological conditions and characteristics of building and land areas on the Oak Ridge Reservation that contain space potentially available for title transfer or lease. After necessary surveys and

  15. Surface Radiation Survey at the Shepley’s Hill Remediation Site, Devens, Massachusettes

    SciTech Connect

    J. R. Giles; C. P. Oertel; L. G. Roybal

    2009-09-01

    The Idaho National Laboratory (INL) provided technical support for ongoing environmental remediation activities at the Shepley’s Hill remediation site, near Devens, MA. The technical support included the completion of a radiation survey of naturally occurring radioactive materials (NORM) at Shepley’s Hill, Shepley’s Hill landfill cover, and Red Cove areas. The objective of the radiation survey was to assess the ability of the INL backpack sodium iodide spectroscopy (BaSIS) system to detect elevated levels of NORM that may be associated with radon-222 emanation from near surface and subsurface fractures in the area. It is postulated that these fracture zones provide subsurface conduits for the transport of environmental contaminants. As such, location of these fracture sets will proved EPA Region 1 with the means for completing the development of an accurate site conceptual model. The results of the radiological survey show that some of the radiological anomalies correlate with currently mapped rock outcrops; however, not all of the rock outcrops in the surveyed area have been mapped. As such, it is not conclusive that all of the radiological anomalies correspond with surface rock outcrops. EPA Region 1 intends to perform a more comprehensive correlation of the radiation data collected with the BaSIS system with additional data sets such as detailed bedrock structural mapping, 2-dimensional resistivity profiling, and high-resolution topographic mapping. The results of this effort will be used in consideration of designing a potential follow-on effort for mapping of radon.

  16. radiological survey

    National Nuclear Security Administration (NNSA)

    application of nuclear science. NNSA maintains and enhances the safety, security, reliability and performance of the U.S. nuclear weapons stockpile without nuclear testing;...

  17. A survey of films for use as dosimeters in interventional radiology

    SciTech Connect

    Fajardo, L.C.; Geise, R.A.; Ritenour, E.R.

    1995-04-01

    Analysis of radiation doses in interventional radiological procedures that can lead to deterministic radiation effects such as erythema and epilation would assist physicians in planning patient care after exposure and in reducing doses. Photographic films used to measure skin exposure in the past are too sensitive for the high doses involved in interventional procedures. Seventeen different types of films, many of which are generally available in hospitals, were surveyed to see if any would meet the demands of interventional radiology. Sensitometric curves obtained demonstrate that most films are inappropriate for high dose procedures. Using Kodak Fine Grain Positive and Deupont duplicating films and automatic processing, doses as high as 2.8 Gy could be measured with reasonable accuracy. Similar results can be obtained by manually processing Kodak XV-2 verification film at room temperature.

  18. An Aerial Radiological survey of the Alvin W. Vogtle Nuclear Plant and surrounding area, Waynesboro, Georgia: Date of survey: August--September 1988

    SciTech Connect

    Not Available

    1990-09-01

    An Aerial Radiological Survey was conducted during the period of August 24 to September 14, 1988 over an area of approximately 310 square kilometers (120 square miles) surrounding the Alvin W. Vogtle Nuclear Plant. The Vogtle Nuclear Plant is located near Augusta, Georgia, along the Savannah River and adjacent to the Savannah River Site (SRS). Several anomalous areas were identified in the portion of the survey extending into the SRS perimeter. The dominant isotopes found in these areas were cesium-137 and cobalt-60. All of these man-made anomalies identified by the aerial measurements were attributed to SRS processing. For the remainder of the survey area, the inferred radiation exposure rates generally varied from 6 to 10 microroentgens per hour ({mu}R/h), which was found to be due to naturally occurring uranium, thorium, and radioactive potassium gamma emitters. The reported exposure rate values included an estimated cosmic ray contribution of 3.6 {mu}R/h. Soils samples and pressurized ion chamber measurements were obtained at three locations within the survey boundaries to support the aerial data. The exposure rate values obtained from these groundbased measurements were in agreement with the corresponding inferred aerial values. 6 refs., 13 figs., 4 tabs.

  19. Results of the radiological survey at Route 17(S) and Becker Avenue, Rochelle Park, New Jersey (RJ001)

    SciTech Connect

    Foley, R.D.; Carrier, R.F.

    1989-11-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The surveys typically include direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this commercial property at Route 17(S) and Becker Avenue, Rochelle Park, New Jersey (RJ001), was conducted in 1986. Measurements taken at the commercial property located at Route 17(S) and Becker Avenue indicate slightly elevated gamma exposure rates in three areas of the parking lot. Although results of analysis of the asphalt disclosed radionuclide concentrations in excess of the applicable criterion, their presence is due to naturally radioactive substances in asphalt patching materials and is not associated with material from the MCW site. Therefore, it is recommended that this site be eliminated from consideration for inclusion in the DOE remedial action program. 5 refs., 2 figs., 3 tabs.

  20. An aerial radiological survey of the EG G Mound Applied Technologies and surrounding area, Miamisburg, Ohio

    SciTech Connect

    Not Available

    1992-11-01

    An aerial radiological survey was conducted over EG G Mound Applied Technologies, Miamisburg, Ohio, during the period of June 9--24, 1989. The purpose of the 41-square-kilometer (16-square-mile) survey was to document the terrestrial gamma environment of the plant and surrounding area. In addition, ground-based exposure rate measurements and soil samples were obtained to support the aerial data. An exposure rate contour map at 1 meter above ground level was.constructed from the gamma data and overlaid on an aerial photograph and map of the area. Exposure rates measured in the area typically ranged from 9 to 11 microroentgens per hour ([mu]R/h).

  1. Radiological surveys of properties in the Middlesex, New Jersey area. Final report

    SciTech Connect

    Leggett, R W; Haywood, F.F. Cottrell, W.D.

    1981-03-01

    Results of the radiological surveys conducted at three properties in the Middlesex, New Jersey area as well as one additional location downstream from the Middlesex Sampling Plant (Willow Lake), are presented. The survey revealed that the yard around the church rectory on Harris Avenue is contaminated with a /sup 226/Ra-bearing material, probably pitchblende ore from the former Middlesex Sampling Plant. The elevated /sup 226/Ra concentrations around and, to a lesser extent, underneath the rectory are leading to elevated /sup 222/Rn concentrations in air in the rectory and elevated alpha contamination levels (from radon daughters) on surfaces inside the rectory. External gamma radiation levels in the rectory yard are well above background levels, and beta-gamma dose rates at many points in the yard are above federal guidelines for the release of property for unrestricted use. The radiological survey of a parking lot at the Union Carbide plant in Bound Brook, New Jersey revealed that a nearly circular region of 50-ft diam in the lot showed above-background external gamma radiation levels. Two isolated spots within this region showed concentrations of uranium in soil above the licensable level stated in 10 CFR 40. Soil samples taken in the area of elevated gamma radiation levels generally showed nearly equal activities of /sup 226/Ra and /sup 238/U. The survey at the residences on William Street in Piscataway, revealed that the front yeard is generally contaminated from near the surface to a depth of 1.5 to 2.5 ft with /sup 226/Ra-bearing material, possibly pitchblende ore. The remainder of the yard shows scattered contaminaion. External gamma radiation levels inside the house are above the background level near some outside walls.

  2. Legacy Site Decontamination Experience as Applied to the Urban Radiological Dispersal Device

    SciTech Connect

    Drake, J.L.; MacKinney, J.A.

    2007-07-01

    Pursuant to the National Response Plan, Nuclear/Radiological Incident Annex [1], the Environmental Protection Agency (EPA) is assigned lead agency responsibility for decontamination and clean-up efforts following a domestic terrorist event involving a radiological dispersal device (RDD). An RDD incident in a modern city environment poses many of the same issues and problems traditionally faced at 'legacy' clean up projects being performed across our country. However there are also many aspects associated with an urban RDD clean-up that have never been faced in legacy site remediation. For example, the demolition and destructive technologies widely used in legacy remediation would be unacceptable in the case of historically or architecturally significant properties or those with prohibitively high replacement cost; contaminated properties will likely belong to numerous small private entities whose business interests are at stake; reducing the time required to decontaminate and return a city to normal use cannot be overemphasized due to its tremendous economic and political impact. The mission of the EPA's National Homeland Security Research Center (NHSRC) includes developing the best technology and tools needed for field personnel to achieve their goals should that event occur. To that end, NHSRC has been exploring how the vast experience within the legacy site remediation community could be tapped to help meet this need, and to identify gaps in decontamination technology. This paper articulates much of what has been learned over the past year as a result of efforts to identify these technology and procedural needs to address the urban RDD. This includes comparing and contrasting remediation techniques and methodologies currently used in nuclear facility and site cleanup with those that would be needed following an urban RDD event. Finally, this presentation includes an appeal to the radiological decontamination community to come forward with ideas and technologies

  3. Data Quality Objectives Supporting Radiological Air Emissions Monitoring for the PNNL Site

    SciTech Connect

    Barnett, J. Matthew; Meier, Kirsten M.; Snyder, Sandra F.; Fritz, Brad G.; Poston, Theodore M.; Antonio, Ernest J.

    2012-11-12

    Pacific Northwest National Laboratory (PNNL) is in the process of developing a radiological air monitoring program for the PNNL Site that is distinct from that of the nearby Hanford Site. The original DQO (PNNL-19427) considered radiological emissions at the PNNL Site from Physical Sciences Facility (PSF) major emissions units. This first revision considers PNNL Site changes subsequent to the implementation of the original DQO. A team was established to determine how the PNNL Site changes would continue to meet federal regulations and address guidelines developed to monitor air emissions and estimate offsite impacts of radioactive material operations. The result is an updated program to monitor the impact to the public from the PNNL Site. The team used the emission unit operation parameters and local meteorological data as well as information from the PSF Potential-to-Emit documentation and Notices of Construction submitted to the Washington State Department of Health (WDOH). The locations where environmental monitoring stations would most successfully characterize the maximum offsite impacts of PNNL Site emissions from the three PSF buildings with major emission units were determined from these data. Three monitoring station locations were determined during the original revision of this document. This first revision considers expanded Department of Energy operations south of the PNNL Site and relocation of the two offsite, northern monitoring stations to sites near the PNNL Site fenceline. Inclusion of the southern facilities resulted in the proposal for a fourth monitoring station in the southern region. The southern expansion added two minor emission unit facilities and one diffuse emission unit facility. Relocation of the two northern stations was possible due to the use of solar power, rather than the previous limitation of the need for access to AC power, at these more remote locations. Addendum A contains all the changes brought about by the revision 1

  4. "Speak Up" Survey Results - Hanford Site

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    in the survey. The goal is to use the results to continuously improve Hanford's safety culture and work environment. Results for the "Speak Up" Survey An Organizational Climate and...

  5. Radiological survey of the inactive uranium-mill tailings at Maybell, Colorado

    SciTech Connect

    Haywood, F.F.; Perdue, P.T.; Ellis, B.S.

    1980-03-01

    Results of a radiological survey of the inactive uranium-mill tailings near Maybell, Colorado are presented. Measurements of external gamma exposure rate at 1 m above the tailings ranged 16 to 340 ..mu..R/hr with an average value of 65 ..mu..R/hr. Radionuclide analysis of offsite soil and sediment samples, as well as above-ground gamma exposure rate measurements defined the spread of contamination around the tailings pile. This spread is greatest toward the east, in the direction of surface water runoff. Calculated concentrations of /sup 226/Ra in all of the holes drilled in the tailngs, based on gamma monitoring data, showed maximum concentrations in the range 100 to 800 pCi/g.

  6. A Radiological Survey Approach to Use Prior to Decommissioning: Results from a Technology Scanning and Assessment Project Focused on the Chornobyl NPP

    SciTech Connect

    Milchikov, A.; Hund, G.; Davidko, M.

    1999-10-20

    The primary objectives of this project are to learn how to plan and execute the Technology Scanning and Assessment (TSA) approach by conducting a project and to be able to provide the approach as a capability to the Chernobyl Nuclear Power Plant (ChNPP) and potentially elsewhere. A secondary objective is to learn specifics about decommissioning and in particular about radiological surveying to be performed prior to decommissioning to help ChNPP decision makers. TSA is a multi-faceted capability that monitors and analyzes scientific, technical, regulatory, and business factors and trends for decision makers and company leaders. It is a management tool where information is systematically gathered, analyzed, and used in business planning and decision making. It helps managers by organizing the flow of critical information and provides managers with information they can act upon. The focus of this TSA project is on radiological surveying with the target being ChNPP's Unit 1. This reactor was stopped on November 30, 1996. At this time, Ukraine failed to have a regulatory basis to provide guidelines for nuclear site decommissioning. This situation has not changed as of today. A number of documents have been prepared to become a basis for a combined study of the ChNPP Unit 1 from the engineering and radiological perspectives. The results of such a study are expected to be used when a detailed decommissioning plan is created.

  7. Environmental Survey preliminary report, Hanford Site, Richland, Washington

    SciTech Connect

    Not Available

    1987-08-01

    This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Hanford Site, conducted August 18 through September 5, 1986. The Survey is being conducted by an interdisciplinary team of environmental specialists, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Individual team components are being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the Hanford Site. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. This phase of the Survey involves the review of existing site environmental data, observations of the operations carried on at the Hanford Site, and interviews with site personnel. The Survey team developed a Sampling and Analysis Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The Sampling and Analysis Plan will be executed by a DOE National Laboratory or a support contractor. When completed, the results will be incorporated into the Environmental Survey Interim Report for the Hanford Site. The Interim Report will reflect the final determinations of the Hanford Site Survey. 44 refs., 88 figs., 74 tabs.

  8. The Role of Gamma-ray Imaging in Performing Radiological Characterisation at the Magnox Storage Ponds at the Bradwell Decommissioning Site - 13628

    SciTech Connect

    Hughes, Karl; Shaw, Tracey

    2013-07-01

    A gamma-ray imaging device has been used to perform radiological characterisation work at the spent fuel ponds complex at the site of the Bradwell Magnox Power Station, which is currently undergoing accelerated decommissioning. The objective of using a gamma-ray imaging system was to independently verify previous radiological survey work and to evaluate the adequacy of the random distribution of the destructive core sampling which had been performed. In performing this work the gamma-ray imager clearly identified the exact locations of the sources of radiation that gave rise to the elevated gamma dose rates measured by conventional health physics surveys of the area. In addition, the gamma-ray imager was able to characterise each hotspot as being either dominated by Cs-137 or by Co-60. The gamma imaging survey was undertaken with a RadScan gamma imaging system deployed on the walkways which run along the lengths of the ponds; this enabled the whole imaging survey to be performed with minimal dose uptake, demonstrating the ALARP principle within decommissioning. (authors)

  9. Final Status Survey Report for Corrective Action Unit 117 - Pluto Disassembly Facility, Building 2201, Nevada National Security Site, Nevada

    SciTech Connect

    Jeremy Gwin and Douglas Frenette

    2010-09-30

    This document contains the process knowledge, radiological data and subsequent statistical methodology and analysis to support approval for the radiological release of Corrective Action Unit (CAU) 117 – Pluto Disassembly Facility, Building 2201 located in Area 26 of the Nevada National Security Site (NNSS). Preparations for release of the building began in 2009 and followed the methodology described in the Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM). MARSSIM is the DOE approved process for release of Real Property (buildings and landmasses) to a set of established criteria or authorized limits. The pre-approved authorized limits for surface contamination values and corresponding assumptions were established by DOE O 5400.5. The release criteria coincide with the acceptance criteria of the U10C landfill permit. The U10C landfill is the proposed location to dispose of the radiologically non-impacted, or “clean,” building rubble following demolition. However, other disposition options that include the building and/or waste remaining at the NNSS may be considered providing that the same release limits apply. The Final Status Survey was designed following MARSSIM guidance by reviewing historical documentation and radiological survey data. Following this review a formal radiological characterization survey was performed in two phases. The characterization revealed multiple areas of residual radioactivity above the release criteria. These locations were remediated (decontaminated) and then the surface activity was verified to be less than the release criteria. Once remediation efforts had been successfully completed, a Final Status Survey Plan (10-015, “Final Status Survey Plan for Corrective Action Unit 117 – Pluto Disassembly Facility, Building 2201”) was developed and implemented to complete the final step in the MARSSIM process, the Final Status Survey. The Final Status Survey Plan consisted of categorizing each individual room

  10. Radiological protection guidelines for the Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program

    SciTech Connect

    Gilbert, T.L.

    1984-01-01

    The need for a definitive basis for radiological guidelines and criteria for FUSRAP became apparent by 1981 and led ORO to sponsor a joint ANL/BNI/LANL/ORO effort under the chairmanship of Wayne Hansen (LANL) that resulted in a final FUSRAP radiological guidelines document in March 1983. A separate effort to develop guidelines for remedial action criteria for SFMP was in progress at PNL. The need to coordinate both efforts with impending revisions of DOE Radiological Protection Standards and impending new developments in EPA and NRC Radiological Protection Standards led to convening of the first DOE Workshop on Remedial Action Criteria in Gaithersburg, Maryland, in February 1984, followed by a second workshop in June 1984 at ANL. The major decisions were to base the criteria on dosimetry models and basic limits currently recommended by the International Commission on Radiological Protection, to emphasize the development and use of site-specific rather than generic guidelines and criteria for residual radionuclide concentrations in the ground, and to prepare a manual to accompany the guidelines that would present procedures and tables for deriving site-specific soil guidelines and criteria for the remedial action programs. A joint ANL/LANL/ORNL/PNL effort to prepare a definitive set of guidelines and a manual has been initiated. The scope, status, and current plans for this effort, and some of the key issues, are presented. 10 references, 1 table.

  11. EA-1900: Radiological Work and Storage Building at the Knolls Atomic Power Laboratory Kesselring Site, West Milton, New York

    Energy.gov [DOE]

    The Naval Nuclear Propulsion Program (NNPP) intent to prepare an Environmental Assessment for a radiological work and storage building at the Knolls Atomic Power Laboratory (Kesselring Site in West Milton, New York. A new facility is needed to streamline radioactive material handling and storage operations, permit demolition of aging facilities, and accommodate efficient maintenance of existing nuclear reactors.

  12. Environmental Survey preliminary report, Nevada Test Site, Mercury, Nevada

    SciTech Connect

    Not Available

    1988-04-01

    This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Nevada Test Site (NTS), conducted June 22 through July 10, 1987. The Survey is being conducted by a multidisciplinary team of environmental specialists led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Individual team members are outside experts being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the NTS. The Survey covers all environment media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. This phase of the Survey involves the review of existing site environmental data, observations of the operations and activities performed at the NTS, and interviews with site personnel. The Survey team developed a Sampling and Analysis Plan to assist in further assessing certain environmental problems identified during its on-site activities. The Sampling and Analysis Plan is being executed by the Battelle Columbus Division under contract with DOE. When completed, the results will be incorporated into the NTS Environmental Survey Interim Report. The Interim Report will reflect the final determinations of the NTS Survey. 165 refs., 42 figs., 52 tabs.

  13. Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites | Department of Energy Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites Pre-MARSSIM Surveys in a

  14. Project RU LlSON COPY ON-SITE RADIOLOGICAL PROGRAMS DURING REENTRY DISILLING THROUGH PRODUCTION TESTING

    Office of Legacy Management (LM)

    RU LlSON COPY ON-SITE RADIOLOGICAL PROGRAMS DURING REENTRY DISILLING THROUGH PRODUCTION TESTING FINAL REPOAT EBERLlNE INSTRUMENT CORPORATION Santa Fe, New Mexico Date Published - December 1973 PREPARED FOR THE U. S. ATOMIC ENERGY COMMISSION N E V A D A OPERATIONS OFFICE UNDER CONTRACT NO. AT(26-11-294 DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best available original document. Project RULISON ON-S1l'E RADIOLOGICAL PROGRAMS D U

  15. Challenges associated with final status survey implementation at a Formerly Utilized Sites Remedial Action Program (Fusrap) Site's adjacent properties

    SciTech Connect

    Sokody, K.J.; Boyle, J.D.

    2007-07-01

    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)

  16. Results of the radiological survey at the ALCOA Research Laboratory, 600 Freeport Road, New Kensington, Pennsylvania (ANK001)

    SciTech Connect

    Foley, R.D.; Brown, K.S.

    1992-10-01

    At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the ALCOA Research Laboratory, 600 Freeport Road, New Kensington, Pennsylvania. The survey was performed on November 12, 1991. The purpose of the survey was to determine whether the property was contaminated with radioactive residues, principally [sup 238]U, as a result of work done for the Manhattan Engineer District in 1944. The survey included measurement of direct alpha and beta-gamma levels in the northeast comer of the basement of Building 29, and the collection of a debris sample from a floor drain for radionuclide analysis. The survey area was used for experimental canning of uranium slugs prior to production activities at the former New Kensington Works nearby.

  17. Results of the Independent Radiological Verification Survey of Remediation at Building 31, Former Linde Uranium Refinery, Tonawanda, New York (LI001V)

    SciTech Connect

    McKenzie, S.P.; Uziel, M.S.

    1998-11-01

    As part of the Formerly Utilized Sites Remedial Action Progmq a team from Oak Ridge National Laboratory (ORNL) conducted a radiological veriihtion survey of Building 31 at the former Linde Uranium Refinery, Tonawau& New York. The purpose of the survey was to ver@ that remedial action completed by the project management contractor had reduced contamination levels to within authorized limits. Prior to remediatioq tied radioactive material was prevalent throughout the building and in some of the ductwork Decontaminadon consisted of removing surfhce contamination from floors, baseboards, and overhead areas; removing some air ducts; and vacuuming dust. Building 31 at the former Linde site in TonawandA New Yorlq was thoroughly investigated inside and outside for radionuclide residues. The verification team discovered previously undetected contaminadon beneath the concrete pad on the first floor and underneath floor tiles on the second floor. All suspect floor tiles were removed and any contamination beneath them cleaned to below guideline levels. The verification team also discovered elevated radiation levels associated with overhead air lines that led to the eventual removal of the entire air lige and a complete investigation of the history of all process piping in the building. Final verification surveys showed that residual surface beta-gamma activity levels were slightly elevated in some places but below U.S. Department of Energy applicable guidelines for protection against radiation (Table 1). Similarly, removable radioactive contamination was also below applicable guidelines. Exposure rates within the building were at typical background levels, and no consistently elevated indoor radon concentrations were measured. However, radionuclide analysis of subsurface soil from beneath the concrete floor on the ground level showed concentrations of `*U and'% that exceeded applicable guidelines. At the time of this survey, there was no measured exposure pathway for this

  18. 2010 Ecological Survey of the Pacific Northwest National Laboratory Site

    SciTech Connect

    Chamness, Michele A.; Perry, Christopher; Downs, Janelle L.; Powell, Sylvia D.

    2011-02-16

    The U.S. Department of Energy (DOE) Pacific Northwest Site Office (PNSO) oversees and manages the DOE contract for the Pacific Northwest National Laboratory (PNNL), a DOE Office of Science multi-program laboratory located in Richland, Washington. PNSO is responsible for ensuring that all activities conducted on the PNNL Site comply with applicable laws, policies, and DOE orders. The DOE Pacific Northwest Site Office Cultural and Biological Resources Management Plan (DOE/PNSO 2008) addresses the requirement for annual surveys and monitoring for species of concern and to identify and map invasive species. In addition to the requirement for an annual survey, proposed project activities must be reviewed to assess any potential environmental consequences of conducting the project. The assessment process requires a thorough understanding of the resources present, the potential impacts of a proposed action to those resources, and the ultimate consequences of those actions. The PNNL Site is situated on the southeastern corner of the DOE Hanford Site, located at the north end of the city of Richland in south-central Washington. The site is bordered on the east by the Columbia River, on the west by Stevens Drive, and on the north by the Hanford Site 300 Area (Figure 1). The environmental setting of the PNNL Site is described in Larson and Downs (2009). There are currently two facilities on the PNNL Site: the William R. Wiley Environmental Molecular Sciences Laboratory (EMSL), and the recently completed Physical Sciences Facility (PSF). This report describes the results of the annual survey of the biological resources found on the undeveloped portions of the PNNL Site in 2010. A brief description of the methods PNNL ecologists used to conduct the surveys and the results of the surveys are presented. Actions taken to fully delineate noxious weed populations discovered in 2009 and efforts in 2010 to control those weeds also are described. Appendix A provides a list of plant and

  19. Results of the post remedial action survey of areas 4 through 10 at the former Kellex site in Jersey City, New Jersey

    SciTech Connect

    Clark, C.; Berven, B.A.; Cottrell, W.D.; Goldsmith, W.A.

    1982-01-01

    A post remedial action survey was conducted at the former Kellex Corporation Research Facility in Jersey City, New Jersey. The Kellex facility was involved in the Manhattan Project, particularly in the area of engineering research in gaseous diffusion for uranium enrichment. As a result of those operations, this site was included by the US Department of Energy (DOE) in their Formerly Utilized Sites Remedial Action Program (FUSRAP). During comprehensive radiological surveys conducted by Oak Ridge National Laboratory in the summer of 1979, ten areas were located with levels of radionuclides in soil in excess of DOE criteria. This report describes the results of radiological surveys conducted in seven of these locations (Areas 4 to 10) following remedial action. Results of these surveys indicate that remedial action was successful in reducing radioactive contamination in these areas to criteria values established by DOE. 7 references, 19 figures, 31 tables.

  20. 2011 Annual Ecological Survey: Pacific Northwest National Laboratory Site

    SciTech Connect

    Becker, James M.; Chamness, Michele A.

    2012-02-27

    The U.S. Department of Energy (DOE) Pacific Northwest Site Office (PNSO) oversees and manages the DOE contract for the Pacific Northwest National Laboratory (PNNL), a DOE Office of Science multi-program laboratory located in Richland, Washington. PNSO is responsible for ensuring that all activities conducted on the PNNL site comply with applicable laws, policies, and DOE Orders. The DOE Pacific Northwest Site Office Cultural and Biological Resources Management Plan (DOE/PNSO 2008) addresses the requirement for annual surveys and monitoring for species of concern and to identify and map invasive species. In addition to the requirement for an annual survey, proposed project activities must be reviewed to assess any potential environmental consequences of conducting the project. The assessment process requires a thorough understanding of the resources present, the potential impacts of a proposed action to those resources, and the ultimate consequences of those actions. The PNNL site is situated on the southeastern corner of the DOE Hanford Site, located at the north end of the city of Richland in south-central Washington. The site is bordered on the east by the Columbia River, on the west by Stevens Drive, and on the north by the Hanford Site 300 Area (Figure 1). The environmental setting of the PNNL site is described in Larson and Downs (2009). There are currently two facilities on the PNNL site: the William R. Wiley Environmental Molecular Sciences Laboratory and the Physical Sciences Facility. This report describes the annual survey of biological resources found on the undeveloped upland portions of the PNNL site. The annual survey is comprised of a series of individual field surveys conducted on various days in late May and throughout June 2011. A brief description of the methods PNNL ecologists used to conduct the baseline surveys and a summary of the results of the surveys are presented. Appendix A provides a list of plant and animal species identified in the

  1. Radiological Assessment for the Removal of Legacy BPA Power Lines that Cross the Hanford Site

    SciTech Connect

    Millsap, William J.; Brush, Daniel J.

    2013-11-13

    This paper discusses some radiological field monitoring and assessment methods used to assess the components of an old electrical power transmission line that ran across the Hanford Site between the production reactors area (100 Area) and the chemical processing area (200 Area). This task was complicated by the presence of radon daughters -- both beta and alpha emitters -- residing on the surfaces, particularly on the surfaces of weathered metals and metals that had been electrically-charged. In many cases, these activities were high compared to the DOE Surface Contamination Guidelines, which were used as guides for the assessment. These methods included the use of the Toulmin model of argument, represented using Toulmin diagrams, to represent the combined force of several strands of evidences, rather than a single measurement of activity, to demonstrate beyond a reasonable doubt that no or very little Hanford activity was present and mixed with the natural activity. A number of forms of evidence were used: the overall chance of Hanford contamination; measurements of removable activity, beta and alpha; 1-minute scaler counts of total surface activity, beta and alpha, using "background makers"; the beta activity to alpha activity ratios; measured contamination on nearby components; NaI gamma spectral measurements to compare uncontaminated and potentially-contaminated spectra, as well as measurements for the sentinel radionuclides, Am- 241 and Cs-137 on conducting wire; comparative statistical analyses; and in-situ measurements of alpha spectra on conducting wire showing that the alpha activity was natural Po-210, as well as to compare uncontaminated and potentially-contaminated spectra.

  2. The Mound site survey project for the characterization of radioactive materials in site soils

    SciTech Connect

    Stought, R.L.; Edling, D.A.; Draper, D.G.

    1988-05-16

    This report summarizes the results of a site survey project conducted at Monsanto Research Corporation's Mound Facility during 1982--1985. The objectives of the site survey were: To characterize the nineteen sites previously identified as having known levels of contamination; to identify and characterize by quantity and type of radionuclide(s) any additional major sites having levels of contamination exceeding 10 pCi/g (for Pu-238) of soil; to estimate the volume of contaminated soil; and to estimate the cost of stabilizing or removing the contaminated soil. This report provides information on objectives 1 and 2 above. A separate report will address objectives 3 and 4.

  3. The Mound site survey project for the characterization of radioactive materials in site soils

    SciTech Connect

    Stought, R.L.; Edling, D.A.; Draper, D.G.

    1988-05-16

    This report summarizes the results of a site survey project conducted at Monsanto Research Corporation`s Mound Facility during 1982--1985. The objectives of the site survey were: To characterize the nineteen sites previously identified as having known levels of contamination; to identify and characterize by quantity and type of radionuclide(s) any additional major sites having levels of contamination exceeding 10 pCi/g (for Pu-238) of soil; to estimate the volume of contaminated soil; and to estimate the cost of stabilizing or removing the contaminated soil. This report provides information on objectives 1 and 2 above. A separate report will address objectives 3 and 4.

  4. Nearest Neighbor Averaging and its Effect on the Critical Level and Minimum Detectable Concentration for Scanning Radiological Survey Instruments that Perform Facility Release Surveys.

    SciTech Connect

    Fournier, Sean Donovan; Beall, Patrick S; Miller, Mark L.

    2014-08-01

    Through the SNL New Mexico Small Business Assistance (NMSBA) program, several Sandia engineers worked with the Environmental Restoration Group (ERG) Inc. to verify and validate a novel algorithm used to determine the scanning Critical Level (L c ) and Minimum Detectable Concentration (MDC) (or Minimum Detectable Areal Activity) for the 102F scanning system. Through the use of Monte Carlo statistical simulations the algorithm mathematically demonstrates accuracy in determining the L c and MDC when a nearest-neighbor averaging (NNA) technique was used. To empirically validate this approach, SNL prepared several spiked sources and ran a test with the ERG 102F instrument on a bare concrete floor known to have no radiological contamination other than background naturally occurring radioactive material (NORM). The tests conclude that the NNA technique increases the sensitivity (decreases the L c and MDC) for high-density data maps that are obtained by scanning radiological survey instruments.

  5. Radiological Control Manual

    SciTech Connect

    Not Available

    1993-04-01

    This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records.

  6. Potential Offsite Radiological Doses Estimated for the Proposed Divine Strake Experiment, Nevada Test Site

    SciTech Connect

    Ron Warren

    2006-12-01

    An assessment of the potential radiation dose that residents offsite of the Nevada Test Site (NTS) might receive from the proposed Divine Strake experiment was made to determine compliance with Subpart H of Part 61 of Title 40 of the Code of Federal Regulations, National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities. The Divine Strake experiment, proposed by the Defense Threat Reduction Agency, consists of a detonation of 700 tons of heavy ammonium nitrate fuel oil-emulsion above the U16b Tunnel complex in Area 16 of the NTS. Both natural radionuclides suspended, and historic fallout radionuclides resuspended from the detonation, have potential to be transported outside the NTS boundary by wind. They may, therefore, contribute radiological dose to the public. Subpart H states ''Emissions of radionuclides to the ambient air from Department of Energy facilities shall not exceed those amounts that would cause any member of the public to receive in any year an effective dose equivalent of 10 mrem/yr'' (Title 40 of the Code of Federal Regulations [CFR] 61.92) where mrem/yr is millirem per year. Furthermore, application for U.S. Environmental Protection Agency (EPA) approval of construction of a new source or modification of an existing source is required if the effective dose equivalent, caused by all emissions from the new construction or modification, is greater than or equal to 0.1 mrem/yr (40 CFR 61.96). In accordance with Section 61.93, a dose assessment was conducted with the computer model CAP88-PC, Version 3.0. In addition to this model, a dose assessment was also conducted by the National Atmospheric Release Advisory Center (NARAC) at the Lawrence Livermore National Laboratory. This modeling was conducted to obtain dose estimates from a model designed for acute releases and which addresses terrain effects and uses meteorology from multiple locations. Potential radiation dose to a hypothetical maximally

  7. Microsoft Word - Berger Radiological Conditions.doc

    Office of Legacy Management (LM)

    Dec. 2, 2009 1 Summary of Information Regarding Radiological Conditions of NFSS Vicinity Properties J. D. Berger, CHP DeNuke Contracting Services, Inc. Oak Ridge, TN The following is a summary of the information obtained from reviews of radiological survey reports, prepared by ORAU in support of the DOE Formerly Utilized Sites Remedial Action Program. These reports were obtained for review from the IVEA Program at ORAU/ORISE. A list of the reports, reviewed for this summary, is included at the

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

    SciTech Connect

    Lambert, K.A.; Mitchell, M.M.; Jean, D.; Byrd, C.S.

    1997-09-01

    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.

  9. Waste Isolation Pilot Plant (WIPP) site gravity survey and interpretation

    SciTech Connect

    Barrows, L.J.; Fett, J.D.

    1983-04-01

    A portion of the WIPP site has been extensively surveyed with high-precision gravity. The main survey (in T22S, R31E) covered a rectangular area 2 by 4-1/3 mi encompassing all of WIPP site Zone II and part of the disturbed zone to the north of the site. Stations were at 293-ft intervals along 13 north-south lines 880 ft apart. The data are considered accurate to within a few hundredths of a milligal. Long-wavelength gravity anomalies correlate well with seismic time structures on horizons below the Castile Formation. Both the gravity anomalies and the seismic time structures are interpreted as resulting from related density and velocity variations within the Ochoan Series. Shorter wavelength negative gravity anomalies are interpreted as resulting from bulk density alteration in the vicinity of karst conduits. The WIPP gravity survey was unable to resolve low-amplitude, long-wavelength anomalies that should result from the geologic structures within the disturbed zone. It did indicate the degree and character of karst development within the surveyed area.

  10. In-Situ Radiological Surveys to Address Nuclear Criticality Safety Requirements During Remediation Activities at the Shallow Land Disposal Area, Armstrong County, Pennsylvania - 12268

    SciTech Connect

    Norris, Phillip; Mihalo, Mark; Eberlin, John; Lambert, Mike; Matthews, Brian

    2012-07-01

    Cabrera Services Inc. (CABRERA) is the remedial contractor for the Shallow Land Disposal Area (SLDA) Site in Armstrong County Pennsylvania, a United States (US) Army Corps of Engineers - Buffalo District (USACE) contract. The remediation is being completed under the USACE's Formerly Utilized Sites Remedial Action Program (FUSRAP) which was established to identify, investigate, and clean up or control sites previously used by the Atomic Energy Commission (AEC) and its predecessor, the Manhattan Engineer District (MED). As part of the management of the FUSRAP, the USACE is overseeing investigation and remediation of radiological contamination at the SLDA Site in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), 42 US Code (USC), Section 9601 et. seq, as amended and, the National Oil and Hazardous Substance Pollution Contingency Plan (NCP), Title 40 of the Code of Federal Regulations (CFR) Section 300.430(f) (2). The objective of this project is to clean up radioactive waste at SLDA. The radioactive waste contains special nuclear material (SNM), primarily U-235, in 10 burial trenches, Cabrera duties include processing, packaging and transporting the waste to an offsite disposal facility in accordance with the selected remedial alternative as defined in the Final Record of Decision (USACE, 2007). Of particular importance during the remediation is the need to address nuclear criticality safety (NCS) controls for the safe exhumation and management of waste containing fissile materials. The partnership between Cabrera Services, Inc. and Measutronics Corporation led to the development of a valuable survey tool and operating procedure that are essential components of the SLDA Criticality Safety and Material Control and Accountability programs. Using proven existing technologies in the design and manufacture of the Mobile Survey Cart, the continued deployment of the Cart will allow for an efficient and reliable methodology to

  11. Informed Consent for Interventional Radiology Procedures: A Survey Detailing Current European Practice

    SciTech Connect

    O'Dwyer, H.M.; Lyon, S.M.; Fotheringham, T.; Lee, M.J.

    2003-09-15

    Purpose: Official recommendations for obtaining informed consent for interventional radiology procedures are that the patient gives their consent to the operator more than 24 hr prior to the procedure. This has significant implications for interventional radiology practice. The purpose of this study was to identify the proportion of European interventional radiologists who conform to these guidelines. Methods: A questionnaire was designed consisting of 12 questions on current working practice and opinions regarding informed consent. These questions related to where, when and by whom consent was obtained from the patient. Questions also related to the use of formal consent forms and written patient information leaflets. Respondents were asked whether they felt patients received adequate explanation regarding indications for intervention,the procedure, alternative treatment options and complications. The questionnaire was distributed to 786 European interventional radiologists who were members of interventional societies. The anonymous replies were then entered into a database and analyzed. Results: Two hundred and fifty-four (32.3%) questionnaires were returned. Institutions were classified as academic (56.7%),non-academic (40.5%) or private (2.8%). Depending on the procedure,in a significant proportion of patients consent was obtained in the outpatient department (22%), on the ward (65%) and in the radiology day case ward (25%), but in over half (56%) of patients consent or re-consent was obtained in the interventional suite. Fifty percent of respondents indicated that they obtain consent more than 24 hr before some procedures, in 42.9% consent is obtained on the morning of the procedure and 48.8% indicated that in some patients consent is obtained immediately before the procedure. We found that junior medical staff obtained consent in 58% of cases. Eighty-two percent of respondents do not use specific consent forms and 61% have patient information leaflets. The

  12. Preclosure radiological safety evaluation: Exploratory Studies Facility; Yucca Mountain Site Characterization Project

    SciTech Connect

    Schelling, F.J.; Smith, J.D.

    1993-07-01

    A radiological safety evaluation is performed to determine the impacts of Exploratory Studies Facility (ESF) design changes on the preclosure public radiological safety for a potential nuclear waste repository at Yucca Mountain, Nevada. Although the ESF design has undergone significant modification, incorporation of the modified design requires only modest changes to the conceptual repository configuration. To the extent feasible, the results of earlier safety evaluations presented in SAND84-2641, SAND88-7061, and SAND89-7024, which were based on the original ESF configuration, are compared with the results for the modified configuration. This comparison provides an estimate of the range of analysis uncertainty. This preliminary analysis indicates that there are no Q-scenarios, which are defined as those scenarios with a net occurrence probability of greater than 10{sup {minus}6}/yr and produce a radiological dose at the 5-km controlled area boundary of greater than 0.5 rem. The analysis yielded estimates for an underground accident of a probability of 3.8 {times} 10{sup {minus}15}/yr and a dose of 1.5 rem. For a surface-initiated accident, a probability of 1.5 {times} 10{sup {minus}12}/yr and a dose of 0.6 rem was estimated.

  13. Surface radiation survey and soil sampling of the 300-FF-1 operable unit, Hanford Site, southeastern Washington: A case study

    SciTech Connect

    Teel, S.S.; Olsen, K.B.

    1990-10-01

    The methods used for conducting a radiological characterization of the soil surface for the Phase I Remedial Investigation of a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) site is presented via a case study. The study site is an operable unit (300-FF-1) located in and adjacent to the 300 Area of the US Department of Energy's Hanford Site in southeastern Washington State. The operable unit contains liquid and solid waste disposal facilities associated with nuclear fuels fabrication. Continuous surface radiation surveying and soil sampling of selected locations were conducted. Contamination was found in several locations within the operable unit including areas near the liquid and solid waste disposal facilities. Instruments used during surveying included portable beta/gamma (P-11) detectors, and the Ultrasonic Ranging and Data System using an NaI (Tl) detector. Laboratory analyses results indicate that above-background radiation levels were primarily due to the presence of uranium. Both types of field instruments used in the study were effective in detecting surface contamination from radionuclides; however, each had specific advantages. Guidelines are presented for the optimum use of these instruments when performing a radiological characterization of the soil surface. 4 refs., 3 figs., 3 tabs.

  14. OFF-SITE RADIOLOGICAL SAFETY PROGRAM FOR PROJECT RULISON FLARING, PHASE I11

    Office of Legacy Management (LM)

    RADIOLOGICAL SAFETY PROGRAM FOR PROJECT RULISON FLARING, PHASE I11 F i.EMSL-LV-539-8 c by Monitoring Operations D i v i s i o n Environmental M o n i t o r i n g and Support Laboratory U. S. ENVIRONMENTAL PROTECTION AGENCY Las Vegas, Nevada Published November 1976 T h i s s u r v e i 1 lance performed under a Memorandum o f Understanding No. AT( 26-1 )-539 f o r t h e U. S. ENERGY RESEARCH AND DEVELOPMENT ADMINISTRATION , I 1 DISCLAIMER T h i s report was prepared a s a n account of work

  15. Preliminary site survey report for the Uniroyal Chemical Company, formerly the Diamond Magnesium Company, 720 Fairport-Nursery Road, Painesville, Ohio (DMP001)

    SciTech Connect

    Foley, R.D.; Floyd, L.M.

    1990-03-01

    At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducted a preliminary radiological survey at the Uniroyal Chemical Company, formerly the Diamond Magnesium Company, 720 Fairport-Nursery Road, Painesville, Ohio (DMP001), in 1988. The purpose of the survey was to determine whether the property was contaminated with radioactive residues from the former Manhattan Engineer District (MED) project. The scope of this preliminary survey primarily covered the area west of the buildings around the railroad car spill containment basin. The survey included direct measurement of gamma radiation levels at the surface and soil sampling for radionuclide analyses. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria for both {sup 238}U and {sup 226}Ra in soil. Based on the results of this radiological assessment, it is recommended that a follow-up, detailed radiological survey of both surface and subsurface environs be performed to more precisely define the extent of the contamination. 5 refs., 10 figs., 3 tabs.

  16. Radiological survey of the Mare Island Naval Shipyard, Alameda Naval Air Station, and Hunters Point Shipyard

    SciTech Connect

    Semler, M.O.; Blanchard, R.L. . Eastern Environmental Radiation Facility)

    1989-06-01

    Since 1963, the Eastern Environmental Radiation Facility (EERF), US Environmental Protection Agency (USEPA), in cooperation with the US Naval Sea Systems Command (NAVSEA) has surveyed facilities serving nuclear-powered warships on the Atlantic and Pacific coasts and the Gulf of Mexico. These surveys assess whether the operation of nuclear-powered warships, during construction, maintenance, overhaul, or refueling, have created elevated levels of radioactivity. The surveys emphasize sampling those areas and pathways that could expose the public. In 1984, NAVSEA requested that EPA survey all active facilities serving nuclear-powered warships over the next three years. This report contains the results of surveys conducted at Naval facilities located at Mare Island, Alameda, and Hunters Point in the San Francisco region. The locations of these facilities are shown. 3 refs., 4 figs., 3 tabs.

  17. ANL-14/01 Surveillance of Site A and Plot M

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    ... N. W. and Sedlet, J., Formerly Utilized MEDAEC Sites Remedial Action Program - Radiological Survey of ... Report DOEEV-00057 (April 1978). 2. Golchert, N. W., Sedlet, ...

  18. Acquisition Information Management system telecommunication site survey results

    SciTech Connect

    Hake, K.A.; Key, B.G.

    1993-09-01

    The Army acquisition community currently uses a dedicated, point-to-point secure computer network for the Army Material Plan Modernization (AMPMOD). It must transition to the DOD supplied Defense Secure Network 1 (DSNET1). This is one of the first networks of this size to begin the transition. The type and amount of computing resources available at individual sites may or may not meet the new network requirements. This task surveys these existing telecommunications resources available in the Army acquisition community. It documents existing communication equipment, computer hardware, associated software, and recommends appropriate changes.

  19. Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program -12184

    SciTech Connect

    Clayton, Christopher; Kothari, Vijendra; Starr, Ken; Widdop, Michael; Gillespie, Joey

    2012-02-26

    The U. S. Department of Energy (DOE) methods and protocols allow evaluation of remediation and final site conditions to determine if remediated sites remain protective. Two case studies are presented that involve the Niagara Falls Storage Site (NFSS) and associated vicinity properties (VPs), which are being remediated under the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are a part of the former Lake Ontario Ordnance Works (LOOW). In response to stakeholders concerns about whether certain remediated NFSS VPs were putting them at risk, DOE met with stakeholders and agreed to evaluate protectiveness. Documentation in the DOE records collection adequately described assessed and final radiological conditions at the completed VPs. All FUSRAP wastes at the completed sites were cleaned up to meet DOE guidelines for unrestricted use. DOE compiled the results of the investigation in a report that was released for public comment. In conducting the review of site conditions, DOE found that stakeholders were also concerned about waste from the Separations Process Research Unit (SPRU) at the Knolls Atomic Power Laboratory (KAPL) that was handled at LOOW. DOE agreed to determine if SPRU waste remained at that needed to be remediated. DOE reviewed records of waste characterization, historical handling locations and methods, and assessment and remediation data. DOE concluded that the SPRU waste was remediated on the LOOW to levels that pose no unacceptable risk and allow unrestricted use and unlimited exposure. This work confirms the following points as tenets of an effective long-term surveillance and maintenance (LTS&M) program:  Stakeholder interaction must be open and transparent, and DOE must respond promptly to stakeholder concerns.  DOE, as the long-term custodian, must collect and preserve site records in order to demonstrate that remediated sites pose no unacceptable risk.  DOE must continue to maintain constructive relationships

  20. Data Quality Objectives Summary Report Supporting Radiological Air Surveillance Monitoring for the INL Site

    SciTech Connect

    Haney, Thomas Jay

    2015-05-01

    This report documents the Data Quality Objectives (DQOs) developed for the Idaho National Laboratory (INL) Site ambient air surveillance program. The development of the DQOs was based on the seven-step process recommended “for systematic planning to generate performance and acceptance criteria for collecting environmental data” (EPA 2006). The process helped to determine the type, quantity, and quality of data needed to meet current regulatory requirements and to follow U.S. Department of Energy guidance for environmental surveillance air monitoring design. It also considered the current air monitoring program that has existed at INL Site since the 1950s. The development of the DQOs involved the application of the atmospheric dispersion model CALPUFF to identify likely contamination dispersion patterns at and around the INL Site using site-specific meteorological data. Model simulations were used to quantitatively assess the probable frequency of detection of airborne radionuclides released by INL Site facilities using existing and proposed air monitors.

  1. Data Quality Objectives Supporting Radiological Air Emissions Monitoring for the Marine Sciences Laboratory, Sequim Site

    SciTech Connect

    Barnett, J. Matthew; Meier, Kirsten M.; Snyder, Sandra F.; Antonio, Ernest J.; Fritz, Brad G.; Poston, Theodore M.

    2012-12-27

    This document of Data Quality Objectives (DQOs) was prepared based on the U.S. Environmental Protection Agency (EPA) Guidance on Systematic Planning Using the Data Quality Objectives Process, EPA, QA/G4, 2/2006 (EPA 2006), as well as several other published DQOs. The intent of this report is to determine the necessary steps required to ensure that radioactive emissions to the air from the Marine Sciences Laboratory (MSL) headquartered at the Pacific Northwest National Laboratory’s Sequim Marine Research Operations (Sequim Site) on Washington State’s Olympic Peninsula are managed in accordance with regulatory requirements and best practices. The Sequim Site was transitioned in October 2012 from private operation under Battelle Memorial Institute to an exclusive use contract with the U.S. Department of Energy, Office of Science, Pacific Northwest Site Office.

  2. BCLDP site environmental report for calendar year 1997 on radiological and nonradiological parameters

    SciTech Connect

    Fry, J.

    1998-09-30

    Battelle Memorial Institute currently maintains its retired nuclear research facilities in a surveillance and maintenance (S and M) mode and continues decontamination and decommissioning (D and D) activities. The activities are referred to as the Battelle Columbus Laboratories Decommissioning Project (BCLDP). Operations reference in this report are performed in support of S and M and D and D activities. The majority of this report is devoted to discussion of the West Jefferson facility, because the source term at this facility is larger than the source term at Battelle`s King Avenue site. The contamination found at the King Avenue site consists of small amounts of residual radioactive material in solid form, which has become embedded or captured in nearby surfaces such as walls, floors, ceilings, drains, laboratory equipment, and soils. By the end of calendar year (CY) 1997, most remediation activities were completed at the King Avenue site. The contamination found at the West Jefferson site is the result of research and development activities with irradiated materials. During CY 1997, multiple tests at the West Jefferson Nuclear Sciences Area found no isotopes present above the minimum detectable activity (MDA) for air releases or for liquid discharges to Big Darby Creek. Data obtained from downstream sampling locations were statistically indistinguishable from background levels.

  3. Results of the radiological survey at the ALCOA Research Laboratory, 600 Freeport Road, New Kensington, Pennsylvania (ANK001). Environmental Restoration and Waste Management Non-Defense Programs

    SciTech Connect

    Foley, R.D.; Brown, K.S.

    1992-10-01

    At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the ALCOA Research Laboratory, 600 Freeport Road, New Kensington, Pennsylvania. The survey was performed on November 12, 1991. The purpose of the survey was to determine whether the property was contaminated with radioactive residues, principally {sup 238}U, as a result of work done for the Manhattan Engineer District in 1944. The survey included measurement of direct alpha and beta-gamma levels in the northeast comer of the basement of Building 29, and the collection of a debris sample from a floor drain for radionuclide analysis. The survey area was used for experimental canning of uranium slugs prior to production activities at the former New Kensington Works nearby.

  4. Environmental radiological monitoring of air, rain, and snow on and near the Hanford Site, 1945-1957

    SciTech Connect

    Hanf, R.W.; Thiede, M.E.

    1994-03-01

    This report is a result of the Hanford Environmental Dose Reconstruction (HEDR) Project. The goal of the HEDR Project is to estimate the radiation dose that individuals could have received from emissions since 1944 at the Hanford Site near Richland, Washington. Members of the HEDR Project`s Environmental Monitoring Data Task have developed databases of historical environmental measurements of such emissions. Hanford documents were searched for information on the radiological monitoring of air, rain, and snow at and near the Hanford Site in Richland, Washington. The monitoring information was reviewed and summarized. The end product is a yearly overview of air, rain, and snow samples as well as ambient radiation levels in the air that were measured from 1945 through 1957. The following information is provided in each annual summary: the media sampled, the constituents (radionuclides) measured/reported, the sampling locations, the sampling frequencies, the sampling methods, and the document references. For some years a notes category is included that contains additional useful information. For the years 1948 through 1957, tables summarizing the sampling locations for the various sample media are also included in the appendix. A large number of documents were reviewed to obtain the information in this report. A reference list is attached to the end of each annual summary. All of the information summarized here was obtained from reports originating at Hanford. These reports are all publicly available and can be found in the Richland Operations Office (RL) public reading room. The information in this report has been compiled without analysis and should only be used as a guide to the original documents.

  5. DOE - Office of Legacy Management -- U S Naval Radiological Defense...

    Office of Legacy Management (LM)

    Naval Radiological Defense Laboratory - CA 0-06 FUSRAP Considered Sites Site: U. S. NAVAL RADIOLOGICAL DEFENSE LABORATORY (CA.0-06) Eliminated from consideration under FUSRAP - ...

  6. Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program - 12184

    SciTech Connect

    Clayton, Christopher; Kothari, Vijendra; Starr, Ken; Widdop, Michael; Gillespie, Joey

    2012-07-01

    The U.S. Department of Energy (DOE) methods and protocols allow evaluation of remediation and final site conditions to determine if remediated sites remain protective. Two case studies are presented that involve the Niagara Falls Storage Site (NFSS) and associated vicinity properties (VPs), which are being remediated under the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are a part of the former Lake Ontario Ordnance Works (LOOW). In response to stakeholders concerns about whether certain remediated NFSS VPs were putting them at risk, DOE met with stakeholders and agreed to evaluate protectiveness. Documentation in the DOE records collection adequately described assessed and final radiological conditions at the completed VPs. All FUSRAP wastes at the completed sites were cleaned up to meet DOE guidelines for unrestricted use. DOE compiled the results of the investigation in a report that was released for public comment. In conducting the review of site conditions, DOE found that stakeholders were also concerned about waste from the Separations Process Research Unit (SPRU) at the Knolls Atomic Power Laboratory (KAPL) that was handled at LOOW. DOE agreed to determine if SPRU waste remained at that needed to be remediated. DOE reviewed records of waste characterization, historical handling locations and methods, and assessment and remediation data. DOE concluded that the SPRU waste was remediated on the LOOW to levels that pose no unacceptable risk and allow unrestricted use and unlimited exposure. This work confirms the following points as tenets of an effective long-term surveillance and maintenance (LTS and M) program: - Stakeholder interaction must be open and transparent, and DOE must respond promptly to stakeholder concerns. - DOE, as the long-term custodian, must collect and preserve site records in order to demonstrate that remediated sites pose no unacceptable risk. - DOE must continue to maintain constructive relationships with

  7. ORNL-5680 Radiological Surveys

    Office of Legacy Management (LM)

    ... This conclusion is based on measurements of 226Ra in ... water sediment samples represents only that percentage of the activity (normally between 50 and 100%) available by hot ...

  8. Radiological and Environmental Monitoring at the Clean Slate I and III Sites, Tonopah Test Range, Nevada, With Emphasis on the Implications for Off-site Transport

    SciTech Connect

    Mizell, Steve A; Etyemezian, Vic; McCurdy, Greg; Nikolich, George; Shadel, Craig; Miller, Julianne J

    2014-09-01

    In 1963, the U.S. Department of Energy (DOE) (formerly the Atomic Energy Commission [AEC]) implemented Operation Roller Coaster on the Tonopah Test Range (TTR) and an adjacent area of the Nevada Test and Training Range (NTTR) (formerly the Nellis Air Force Range [NAFR]). Operation Roller Coaster consisted of four tests in which chemical explosions were detonated in the presence of nuclear devices to assess the dispersal of radionuclides and evaluate the effectiveness of storage structures to contain the ejected radionuclides. These tests resulted in the dispersal of plutonium over the ground surface downwind of the test ground zero (GZ). Three tests—Clean Slate I, II, and III—were conducted on the TTR in Cactus Flat. The fourth, Double Tracks, was conducted in Stonewall Flat on the NTTR. The Desert Research Institute (DRI) installed two monitoring stations in 2008, Station 400 at the Sandia National Laboratories (SNL) Range Operations Center (ROC) and Station 401 at Clean Slate III. Station 402 was installed at Clean Slate I in 2011 to measure radiological, meteorological, and dust conditions. The monitoring activity was implemented to determine if radionuclide contamination in the soil at the Clean Slate sites was being transported beyond the contamination area boundaries. Some of the data collected also permits comparison of radiological exposure at the TTR monitoring stations to conditions observed at Community Environmental Monitoring Program (CEMP) stations around the NTTR. Annual average gross alpha values from the TTR monitoring stations are higher than values from the surrounding CEMP stations. Annual average gross beta values from the TTR monitoring stations are generally lower than values observed for the surrounding CEMP stations. This may be due to use of sample filters with larger pore space because when glass-fiber filters began to be used at TTR Station 400, gross beta values increased. Gamma spectroscopy typically identified only naturally

  9. Designation Survey - Palmerton, Pa. Ore Storage Site William...

    Office of Legacy Management (LM)

    Deccmmissionlng Projects U. S. Department of Energy Germantorn. Maryland 20545 Dear Mr. ... Ore S&uage Site i 1 We have reviewed Aerospace's report, the Palmerton. PA Ore Storage ...

  10. Supplemental Radiological Survey Plan for the Lease of the Rooms Associated with C107 of Building K-1006 at the East Tennessee Technology Park, Oak Ridge, Tennessee

    SciTech Connect

    Blevins M.F.

    2010-09-01

    In 1998, a portion of Bldg. K-1006 was leased to the Community Reuse Organization of East Tennessee (CROET) as part of the reindustrialization efforts at the East Tennessee Technology Park (ETTP). The facility was subleased and is being used as an analytical laboratory. The 1998 lease did not include rooms C107, C107-A, C107-B, C107-C, and C107-D. The lease of these rooms is now desired. These rooms comprise the area to be surveyed. The building was constructed as a laboratory facility to support the gaseous diffusion uranium enrichment process. It also contains offices and administrative spaces for laboratory personnel. After the gaseous diffusion process was shut down in the mid-1980s, the building was used to provide research and development support to ETTP environmental, safety, and health programs; the Toxic Substances Control Act Incinerator; the Central Neutralization Facility; and other multi-site waste treatment activities. It also served as the chemistry laboratory for the Environmental Technology Technical Services Organization. The activities currently conducted in Bldg. K-1006 utilize a variety of analytical techniques. Some of the major techniques being employed are X-ray analysis, electron microanalysis, and spectrochemical analysis. In 1998, a portion of Bldg. K-1006 was leased to CROET as part of the reindustrialization efforts at ETTP. The facility was subleased and is being used as an analytical laboratory. The 1998 lease did not include Rooms C107, C107-A, C107-B, C107-C, and C107-D. Some demolition of furniture and decontamination activities has taken place for Rooms C 107 and C 107-B since the last radiological survey of those rooms. In March 2009, a final remedial action (RA) was performed for the Bldg. K-1006 north basement sump. The Bldg. K-1006 north basement sump is a nominal 30-in.-diameter, 36-in.-deep concrete structure in the north corner of room C107B. The building receives groundwater in-leakage that is periodically pumped to the

  11. Nuclear and Radiological Field Training Center | Y-12 National...

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    ... Nuclear and Radiological Field Training Center A site used for nuclear research in Oak ... and Radiological Field Training Center - the only facility of its kind in the world. ...

  12. Multi-agency radiation survey and site investigation manual (MARSIM). Final report

    SciTech Connect

    1997-12-01

    The MARSSIM provides information on planning, conducting, evaluating, and documenting building surface and surface soil final status radiological surveys for demonstrating compliance with dose or risk-based regulations or standards. The MARSSIM is a multi-agency consensus document that was developed collaboratively by four Federal agencies having authority and control over radioactive materials: Department of Defense (DOD), Department of Energy (DOE), Environmental Protection Agency (EPA), and Nuclear Regulatory Commission (NRC). The MARSSIM`s objective is to describe a consistent approach for planning, performing, and assessing building surface and surface soil final status surveys to meet established dose or risk-based release criteria, while at the same time encouraging an effective use of resources.

  13. "CONFIRMATORY SURVEY RESULTS FOR THE ABB COMBUSTION ENGINEERING SITE WINDSOR, CONNECTICUT DCN 5158-SR-02-2

    SciTech Connect

    ADAMS, WADE C

    2013-03-25

    The objectives of the confirmatory activities were to provide independent contractor field data reviews and to generate independent radiological data for use by the NRC in evaluating the adequacy and accuracy of the contractor's procedures and FSS results. ORAU reviewed ABB CE's decommissioning plan, final status survey plan, and the applicable soil DCGLs, which were developed based on an NRC-approved radiation dose assessment. The surveys include gamma surface scans, gamma direct measurements, and soil sampling.

  14. Multiagency radiation survey and site investigation manual (MARSSIM): Overview/Update

    SciTech Connect

    Petullo, C.F.; Meck, R.

    1996-06-01

    The Environmental Protection Agency (EPA), the Nuclear Regulatory Commission (NRC), the Department of Energy (DOE), and the Department of Defense (DOD-Army, Navy and Air Force) are jointly developing a single federal guidance document for investigating and characterizing sites that have been contaminated with radioactive materials. The multi-agency radiation survey and site investigation manual (MARSSIM) is being written to support implementation of Federal rules, currently under development, for the cleanup of sites contaminated with radioactive materials. The MARSSIM will provide guidance for planning, conducting, evaluating, and documenting environmental and structural radiation and sampling surveys in support of remediation of radioactive contamination. The philosophy, Standardized techniques and methodologies that form the basis for this manual are consistent with Federal limits, guidelines, and procedures. The sampling and radiation surveys that will be depicted in the manual will only entail the use of commercially available instrumentation and equipment. Survey designs and evaluation of results will only incorporate standard statistical approaches.

  15. Radiological Control Manual. Revision 0, January 1993

    SciTech Connect

    Not Available

    1993-04-01

    This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records.

  16. Radiological Control

    Directives, Delegations, and Other Requirements [Office of Management (MA)]

    2009-06-16

    The Department of Energy (DOE) has developed this Standard to assist line managers in meeting their responsibilities for implementing occupational radiological control programs.

  17. Radiological Control

    Energy.gov [DOE] (indexed site)

    ... of Radiological Conditions ......of this Standard to the extent appropriate to facility ... the underlying reasons or causes for the success or failure ...

  18. Magnetic field survey at PG&E photovoltaic sites

    SciTech Connect

    Chang, G.J.; Jennings, C.

    1994-08-01

    Public awareness has aroused concerns over the possible effects of magnetic fields on human health. While research continues to determine if magnetic fields do, in fact, affect human health, concerned individuals are requesting data on magnetic field sources in their environments to base personal decisions about limiting their exposure to these sources. Timely acceptance and implementation of photovoltaics (PV), particularly for distributed applications such as PV rooftops, windows, and vehicles, may be hampered by the lack of PV magnetic field data. To address this situation, magnetic flux density was measured around equipment at two PVUSA (Photovoltaics for Utility Scale Applications) project sites in Kerman and Davis, California. This report documents the data and compares the PV magnetic fields with published data on more prevalent magnetic field sources. Although not comprehensive, electric and magnetic field (EMF) data taken at PVUSA indicate that 60-Hz magnetic fields (the EMF type of greatest public concern) are significantly less for PV arrays than for household applications. Therefore, given the present EMF research knowledge, PV array EMF may not merit considerable concern. The PV system components exhibiting significant AC magnetic fields are the transformers and power conditioning units (PCUs). However, the AC magnetic fields associated with these components are localized and are not detected at PV system perimeters. Concern about transformer and PCU EMF would apply to several generation and storage technologies.

  19. Dungeness crab survey for the Southwest Ocean Disposal Site off Grays Harbor, Washington, June 1990

    SciTech Connect

    Higgins, B.J.; Pearson, W.H. )

    1991-09-01

    As part of the Grays Harbor Navigation Improvement Project, the Seattle District of the US Army Corps of Engineers has begun active use of the Southwest Ocean Disposal Site off Grays Harbor, Washington. This survey was to verify that the location of the area of high crab density observed during site selection surveys has not shifted into the Southeast Ocean Disposal Site. In June 1990, mean densities of juvenile Dungeness crab were 146 crab/ha within the disposal site and 609 crab/ha outside ad north of the disposal site. At nearshore locations outside the disposal site, juvenile crab density was 3275 crab/ha. Despite the low overall abundance, the spatial distribution of crab was such that the high crab densities in 1990 have remained outside the Southwest Ocean Disposal Site. The survey data have confirmed the appropriateness of the initial selection of the disposal site boundaries and indicated no need to move to the second monitoring tier. 8 refs., 9 figs., 2 tabs.

  20. Independent Verification Survey Report for the Operable Unit-1 Miamisburg Closure Project, Miamisburg, OH

    SciTech Connect

    Weaver, P.

    2008-03-17

    The objectives of the independent verification survey were to confirm that remedial actions have been effective in meeting established release criteria and that documentation accurately and adequately describes the current radiological and chemical conditions of the MCP site.

  1. Uranium-Bearing Evaporite Mineralization Influencing Plume Persistence: Literature review and DOE-LM Site Surveys

    Office of Scientific and Technical Information (OSTI)

    LMS/S13437 ESL-RPT-2015-05 WlKsEIBantillO Sciences Laboratory Uranium-Bearing Evaporite Mineralization Influencing Plume Persistence: Literature Review and DOE-LM Site Surveys May 2016 U.S. DEPARTMENT OF ENERGY Legacy Management This page intentionally left blank Contents 1.0 Introduction............................................................................................................................1 2.0 Evaporite Literature

  2. Principles on Radiological Characterization of the Unit 1 at Ignalina NPP for Decommissioning Purposes

    SciTech Connect

    Poskas, P.; Zujus, R.; Drumstas, G.; Poskas, R.; Simonis, V.

    2008-07-01

    There is only one nuclear power plant in Lithuania - Ignalina NPP (INPP). The INPP operated two similar units with installed capacity of 1500 MW(each). They were commissioned in 12/1983 and 08/1987, and the original design lifetime was projected out to 2010 and 2015 respectively. But the first Unit of Ignalina NPP was shutdown December 31, 2004, and second Unit will be closed down before 2010 taking into consideration substantial long-term financial assistance from the EU, G7 and other states as well as international institutions. Implementation of dismantling activities requires detailed knowledge of the radiological situation at the Unit 1. General Programme of Radiological Survey for Ignalina NPP Unit 1 based on NUREG-1575 was prepared in 2005- 2006 by Consortium led by Lithuanian Energy Institute and approved by Regulatory Bodies. It includes such main steps as historical site assessment, scoping, characterization, remedial actions/decontamination support surveys and final status surveys. General Programme of Radiological Survey defines content and principles of the surveys, and preliminary survey considerations, including identification of the contaminants, establishment of the free release levels, principles on areas classification depending on contamination potential, identification of the final survey units, criteria for selection survey instrumentation, techniques and methods etc. So, in the paper information on these principles and the content of the different stages in General Programme of Radiological Survey is presented. (authors)

  3. Radiological Control

    National Nuclear Security Administration (NNSA)

    RADIOLOGICAL CONTROL U.S. Department of Energy SAFT Washington, D.C. 20585 DISTRIBUTION ... DOE-STD-1098-2008 ii This document is available on the Department of Energy Technical ...

  4. Survey of subsurface treatment technologies for environmental restoration sites at Sandia National Laboratories, New Mexico.

    SciTech Connect

    McGrath, Lucas K.; Ho, Clifford Kuofei; Wright, Jerome L.

    2003-08-01

    This report provides a survey of remediation and treatment technologies for contaminants of concern at environmental restoration (ER) sites at Sandia National Laboratories, New Mexico. The sites that were evaluated include the Tijeras Arroyo Groundwater, Technical Area V, and Canyons sites. The primary contaminants of concern at these sites include trichloroethylene (TCE), tetrachloroethylene (PCE), and nitrate in groundwater. Due to the low contaminant concentrations (close to regulatory limits) and significant depths to groundwater ({approx}500 feet) at these sites, few in-situ remediation technologies are applicable. The most applicable treatment technologies include monitored natural attenuation and enhanced bioremediation/denitrification to reduce the concentrations of TCE, PCE, and nitrate in the groundwater. Stripping technologies to remove chlorinated solvents and other volatile organic compounds from the vadose zone can also be implemented, if needed.

  5. 2010 Dry and 2009 - 2010 Wet Season Branchiopod Survey Report, Site 300

    SciTech Connect

    Dexter, W

    2011-03-14

    Lawrence Livermore National Laboratory (LLNL) requested that Condor Country Consulting, Inc. (CCCI) perform wet season surveys and manage the dry season sampling for listed branchiopods in two ponded locations within the Site 300 Experimental Test Site. Site 300 is located in Alameda and San Joaquin Counties, located between the Cities of Livermore and Tracy. The two pool locations have been identified for possible amphibian enhancement activities in support of the Compensation Plan for impacts tied to the Building 850 soil clean-up project. The Building 850 project design resulted in formal consultation with the U.S. Fish and Wildlife Service (USFWS) as an amendment (File 81420-2009-F-0235) to the site-wide Biological Opinion (BO) (File 1-1-02-F-0062) in the spring of 2009 and requires mitigation for the California tiger salamander (AMCA, Ambystoma californiense) and California red-legged frog (CRLF, Rana draytonii) habitat loss. Both pools contain breeding AMCA, but do not produce metamorphs due to limited hydroperiod. The pool to the southeast (Pool BC-FS-2) is the preferred site for amphibian enhancement activities, and the wetland to northwest (Pool OA-FS-1) is the alternate location for enhancement. However, prior to enhancement, LLNL has been directed by USFWS (BO Conservation Measure 17 iii) to 'conduct USFWS protocol-level branchiopod surveys to determine whether listed brachiopod species are present within the compensation area.' CCCI conducted surveys for listed branchiopods in the 2009-2010 wet season to determine the presence of federally-listed branchiopods at the two pools (previous surveys with negative findings were performed by CCCI in 2001-2002 and 2002-2003 onsite). Surveys were conducted to partially satisfy the survey requirements of the USFWS 'Interim Survey Guidelines to Permittees for Recovery Permits under Section 10(a)(1)(A) of the Endangered Species Act for the Listed Vernal Pool Branchiopods' ('Guidelines, USFWS 1996 and BO Conservation

  6. DOE/EV-0005/15 Formerly Utilized MED/AEC Sites Remedial Action Program

    Office of Legacy Management (LM)

    15 Formerly Utilized MED/AEC Sites Remedial Action Program Radiological Survey of the Bayo Canyon, Los Alamos, New Mexico June 1979 Final Report Prepared for U.S. Department of Energy Assistant Secretary for Environment Division of Environmental Control Technology DOE/EV-0005/15 UC-71 Formerly Utilized MED/AEC Sites Remedial Action Program Radiological Survey of the Bayo Canyon, Los Alamos, New Mexico June 1979 Final Report Prepared for U.S. Department of Energy Assistant Secretary for

  7. Wetland survey of selected areas in the K-24 Site Area of responsibility

    SciTech Connect

    Rosensteel, B.A.; Awl, D.J.

    1995-07-01

    In accordance with DOE Regulations for Compliance with Floodplain/Wetlands Environmental Review Requirements, wetland surveys were conducted in selected areas within the K-25 Area of Responsibility during the summer of 1994. These areas are Mitchell Branch, Poplar Creek, the K-770 OU, Duct Island Peninsula, the Powerhouse area, and the K-25 South Corner. Previously surveyed areas included in this report are the main plant area of the K-25 Site, the K-901 OU, the AVLIS site, and the K-25 South Site. Wetland determinations were based on the USACE methodology. Forty-four separate wetland areas, ranging in size from 0.13 to 4.23 ha, were identified. Wetlands were identified in all of the areas surveyed with the exception of the interior of the Duct Island Peninsula and the main plant area of the K-25 Site. Wetlands perform functions such as floodflow alteration, sediment stabilization, sediment and toxicant retention, nutrient transformation, production export, and support of aquatic species and wildlife diversity and abundance. The forested, scrub-shrub, and emergent wetlands identified in the K-25 area perform some or all of these functions to varying degrees.

  8. Gnome site decontamination and decommissioning project

    SciTech Connect

    Orcutt, J.A.; Sorom, E.R.

    1982-08-01

    In July 1977, DOE/Headquarters directed DOE/NV to design a decontamination and decommissioning plan for the Gnome site, 48 kilometers southeast of Carlsbad, New Mexico. The plan incorporated three distinct phases. During Phase I, both aerial and ground radiological surveys were conducted on the site. Radiological decontamination criteria were established, and a decontamination plan was developed based on the radiological survey results. During Phase II, site preparatory and rehabilitation work was completed. The actual land area decontamination was accomplished during Phase III with conventional earthmoving equipment. A gravity water injection system deposited 36,700 metric tons of contaminated soil and salt in the Gnome cavity. After completion of the decontamination and decommissioning operations, the Gnome site was returned to the Bureau of Land Management for unrestricted surface use.

  9. Challenges with Final Status Surveys at a Large Decommissioning Site - 13417

    SciTech Connect

    Downey, Heath; Collopy, Peter; Shephard, Eugene; Walter, Nelson; Conant, John

    2013-07-01

    As part of decommissioning a former nuclear fuel manufacturing site, one of the crucial final steps is to conduct Final Status Surveys (FSS) in order to demonstrate compliance with the release criteria. At this decommissioning site, the area for FSS was about 100 hectares (248 acres) and included varying terrain, wooded areas, ponds, excavations, buildings and a brook. The challenges in performing the FSS included determining location, identifying FSS units, logging gamma walkover survey data, determining sample locations, managing water in excavations, and diverting water in the brook. The approaches taken to overcome these challenges will be presented in the paper. The paper will present and discuss lessons learned that will aid others in the FSS process. (authors)

  10. NIAGARA FALLS STORAGE SITE

    Office of Legacy Management (LM)

    :i" _,, ' _~" ORISE 95/C-70 :E : i:; :' l,J : i.: RADIOLOGICAL SURVEY Op BUILDINGS 401, ' 403, AND ' m HITTMAN BUILDING $ <,' 2:. NIAGARA FALLS STORAGE SITE I .~~ ; " LEWISTON, ' NEW YORK : f? j:,:i I ,.J- ;b f" /: Li _e.*. ~,, I ,,~, ,:,,;:, Prepared by T. .I. Vitkus i,c Environmental Survey and Site Assessment Program Energy/Environment Systems Division ;>::; Oak Ridge Institute for Science and Education .,:, "Oak Ridge, Temressee 37831-0117 .F P ., ? :_ &,d

  11. BASELINE PARAMETER UPDATE FOR HUMAN HEALTH INPUT AND TRANSFER FACTORS FOR RADIOLOGICAL PERFORMANCE ASSESSMENTS AT THE SAVANNAH RIVER SITE

    SciTech Connect

    Coffield, T; Patricia Lee, P

    2007-01-31

    The purpose of this report is to update parameters utilized in Human Health Exposure calculations and Bioaccumulation Transfer Factors utilized at SRS for Performance Assessment modeling. The reason for the update is to utilize more recent information issued, validate information currently used and correct minor inconsistencies between modeling efforts performed in SRS contiguous areas of the heavy industrialized central site usage areas called the General Separations Area (GSA). SRS parameters utilized were compared to a number of other DOE facilities and generic national/global references to establish relevance of the parameters selected and/or verify the regional differences of the southeast USA. The parameters selected were specifically chosen to be expected values along with identifying a range for these values versus the overly conservative specification of parameters for estimating an annual dose to the maximum exposed individual (MEI). The end uses are to establish a standardized source for these parameters that is up to date with existing data and maintain it via review of any future issued national references to evaluate the need for changes as new information is released. These reviews are to be added to this document by revision.

  12. A Survey of Vegetation and Wildland Fire Hazards on the Nevada Test Site, September 2004

    SciTech Connect

    Bechtel Nevada

    2004-09-01

    In the spring of 2004 a survey was conducted by Bechtel Nevada Ecological Services on the Nevada Test Site to characterize vegetation resources and climatic components of the environment that contribute to wildland fires. The field surveyed assessed 211 sites along major Nevada Test Site corridors for the abundance of native perennial and annual species and invasive weeds. The abundance of fine-textured (grasses and herbs) and coarse-textured (woody) biomass was visually estimated on numerical scales ranging from one to five. Wildland fires are costly to control and to mitigate once they occur. Revegetation of burned areas is very slow without reseeding or transplanting with native species and other rehabilitation efforts. Untreated areas become much more vulnerable to future fires once invasive species, rather than native species, colonize a burned area.The annual assessment of wildland fire hazards on the Nevada Test Site is scheduled to be implemented each spring in the near future with results being reported directly to the U.S. Department of Energy and the Bechtel Nevada Fire Marshal.

  13. Mesocarnivore Surveys on Lawrence Livermore National Laboratory Site 300, Alameda and San Joaquin Counties, California

    SciTech Connect

    Clark, H O; Smith, D A; Cypher, B L; Kelly, P A; Woollett, J S

    2004-11-16

    Lawrence Livermore National Laboratory (LLNL), operated under cooperative agreement between the University of California and the U. S. Department of Energy, administers and operates an approximately 11 mi{sup 2} (28 km{sup 2}) test site in the remote hills at the northern end of the South Coast Ranges of Central California (Figure 1). Known as Site 300, this expanse of rolling hills and canyons supports a diverse array of grassland communities typical of lowland central California. The facility serves a variety of functions related to testing non-nuclear explosives, lasers, and weapons subsystems. The primary purpose of this project was to determine the presence of any mesocarnivores on Site 300 that use the property for foraging, denning, and other related activities. The surveys occurred from mid-September to mid-October, 2002.

  14. Radiological dose assessment for the decontaminated concrete removed from 183-H solar evaporation basins at the Hanford site, Richland, Washington

    SciTech Connect

    Kamboj, S.; Faillace, E.; Yu, C.

    1997-01-01

    Potential maximum radiation dose rates over a 1,000-year time horizon were calculated for exposure to the decontaminated concrete removed from the 183-H Solar Evaporation Basins at the Hanford Site, Richland, Washington. The RESRAD computer code, Version 5.62, which implements the methodology described in the US Department of Energy`s manual for developing residual radioactive material guidelines, was used in this evaluation. Currently, the concrete is not being used. Four potential exposure scenarios were developed for the land area where the decontaminated concrete will be stored. In Scenario A industrial use of the land is assumed; in Scenario B recreational use of the land is assumed; in Scenario C residential use of the land is assumed; and in Scenario D (a plausible but unlikely land-use scenario), the presence of a subsistence farmer in the immediate vicinity of the land is assumed. For Scenarios A and B, water used for drinking is assumed to be surface water from the Columbia River; for Scenarios C and D, groundwater drawn from a well located at the downgradient edge of the storage area is the only source of water for drinking, irrigation, and raising livestock. Conservative parameters values were used to estimate the radiation doses. The results of the evaluation indicate that the US Department of Energy`s dose limit of 100 mrem/yr would not be exceeded for any of the scenarios analyzed. The potential maximum dose rates for Scenarios A, B, C, and D are 0.75, 0.022, 29, 29 mrem/yr, respectively. An uncertainty analysis was performed to determine which parameters have the greatest impact on the estimated doses. The doses in Scenarios C and D were found to be very sensitive to the magnitude of the irrigation rate.

  15. Savannah River Site environmental data for 1992

    SciTech Connect

    Arnett, M.W.

    1993-09-01

    The figures and tables in this report represent a capsule view of the routine environmental monitoring and surveillance programs at the Savannah River Site. An attempt has been made to include all available data from environmental research programs. The first section of the book is a collection of maps of radiological and nonradiological sampling locations. Also included are general radiological and nonradiological sampling and analysis schedules; a list of the media sampled, along with sample sizes and representative aliquots; a list of the lower limits of detection for radiological detection instruments; the minimum detectable concentrations for gamma analysis of water and air samples; and the minimum detectable concentrations for gamma analysis of soil, food, fish and wildlife, and vegetation samples. Following the first section are data tables containing radiological and nonradiological effluent monitoring results, radiological and nonradiological environmental surveillance results, dose estimates, quality assurance activities, and results of nonroutine occurrences and special surveys.

  16. General Employee Radiological Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    _______ Change Notice 1 June 2009 DOE HANDBOOK GENERAL EMPLOYEE RADIOLOGICAL TRAINING U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Not Measurement Sensitive This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 1 DOE-HDBK-1131-2007 Original Change Part 2 page 5 The average annual radiation dose to a

  17. General Employee Radiological Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    DOE HANDBOOK GENERAL EMPLOYEE RADIOLOGICAL TRAINING U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Not Measurement Sensitive This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-HDBK-1131-2007 iii Foreword This Handbook describes an implementation process for core training as recommended in chapter 14,

  18. General Employee Radiological Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Not Measurement Sensitive DOE-HDBK-1131-2007 December 2007_______ Change Notice 1 Reaffirmed 2013 DOE HANDBOOK GENERAL EMPLOYEE RADIOLOGICAL TRAINING U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 1 DOE-HDBK-1131-2007 Original Change Part 2 page 5 The

  19. I COMPREHENSIVE RADIOLOGICAL SURVEY I

    Office of Legacy Management (LM)

    ... Atomic Power Laboratory (KAPL) in Schenectady, New York. Receipt of additional wastes was ... surface soil, and micrometeorological conditions (e.g. surface wind speed and direction). ...

  20. Siting Study Framework and Survey Methodology for Marine and Hydrokinetic Energy Project in Offshore Southeast Florida

    SciTech Connect

    Vinick, Charles; Riccobono, Antonino, MS; Messing, Charles G., Ph.D.; Walker, Brian K., Ph.D.; Reed, John K., Ph.D.

    2012-02-28

    Dehlsen Associates, LLC was awarded a grant by the United States Department of Energy (DOE) Golden Field Office for a project titled 'Siting Study Framework and Survey Methodology for Marine and Hydrokinetic Energy Project in Offshore Southeast Florida,' corresponding to DOE Grant Award Number DE-EE0002655 resulting from DOE funding Opportunity Announcement Number DE-FOA-0000069 for Topic Area 2, and it is referred to herein as 'the project.' The purpose of the project was to enhance the certainty of the survey requirements and regulatory review processes for the purpose of reducing the time, efforts, and costs associated with initial siting efforts of marine and hydrokinetic energy conversion facilities that may be proposed in the Atlantic Ocean offshore Southeast Florida. To secure early input from agencies, protocols were developed for collecting baseline geophysical information and benthic habitat data that can be used by project developers and regulators to make decisions early in the process of determining project location (i.e., the siting process) that avoid or minimize adverse impacts to sensitive marine benthic habitat. It is presumed that such an approach will help facilitate the licensing process for hydrokinetic and other ocean renewable energy projects within the study area and will assist in clarifying the baseline environmental data requirements described in the U.S. Department of the Interior Bureau of Ocean Energy Management, Regulation and Enforcement (formerly Minerals Management Service) final regulations on offshore renewable energy (30 Code of Federal Regulations 285, published April 29, 2009). Because projects generally seek to avoid or minimize impacts to sensitive marine habitats, it was not the intent of this project to investigate areas that did not appear suitable for the siting of ocean renewable energy projects. Rather, a two-tiered approach was designed with the first step consisting of gaining overall insight about seabed conditions

  1. Interim Letter Report - Verification Survey of 19 Grids in the Lester Flat Area, David Witherspoon Inc. 1630 Site Knoxville, Tennessee

    SciTech Connect

    P.C. Weaver

    2008-10-17

    Perform verification surveys of 19 available grids located in the Lester Flat Area at the Davod Witherspoon Site. The survey grids included E11, E12, E13, F11, F12, F13, F14, F15, G15, G16, G17, H16, H17, H18, X16, X17, X18, K16, and J16.

  2. For S Radiological

    Office of Legacy Management (LM)

    ? . -. .- * -* (\/If.r.-5- .* , d- For S Radiological ' mer Bridgepo pecial Metals Adrian, Survey of the Irt Brass Company Extrusion Plant, Michigan / /f?t' . ( F. F. Haywood H. W. Dickson W. D. Cottrell W. H. Shinpaugh _ : I., _-. .I ( ._ rc/ DOE/EV-0005128 ORNL-57 13 / J. E. Burden 0. R. Stone R. W. Doane W. A. Goldsmith 4 , Printed in the United States of America. Available from National Technical Information Service U.S. Department of Commerce 5285 Port Royal Road, Springfield, Virginia

  3. Radiological Triage | National Nuclear Security Administration | (NNSA)

    National Nuclear Security Administration (NNSA)

    Radiological Triage Triage Logo NNSA's Triage is a non-deployable, secure, on-line capability that provides remote support to emergency responders in the event of a nuclear or radiological emergency. Triage has on-call scientists available 24 hours a day to analyze site-specific data and confirm radioisotope identification in the event of a radiological incident. The data is transmitted through the Triage website or provided over the telephone. Triage is an integrated system that is comprised of

  4. Radiological Control Technician Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ... of candidates for Radiological Control Technician (RCT) and for RCT Supervisor. ... OEBs as indicated in DOE's Radiological Control Standard (RCS) and the RCT Training ...

  5. Description of the Formerly Utilized Sites Remedial Action Program

    SciTech Connect

    Not Available

    1980-09-01

    The background and the results to date of the Department of Energy program to identify and evaluate the radiological conditions at sites formerly utilized by the Corps of Engineers' Manhattan Engineer District (MED) and the US Atomic Energy Commission (AEC) are summarized. The sites of concern were federally, privately, and institutionally owned and were used primarily for research, processing, and storage of uranium and thorium ores, concentrates, or residues. Some sites were subsequently released for other purposes without radiological restriction. Surveys have been conducted since 1974 to document radiological conditions at such sites. Based on radiological surveys, sites are identified in this document that require, or are projected to require, remedial action to remove potential restrictions on the use of the property due to the presence of residual low-level radioactive contamination. Specific recommendations for each site will result from more detailed environmental and engineering surveys to be conducted at those sites and, if necessary, an environmental impact assessment or environmental impact statement will be prepared. Section 3.0 describes the current standards and guidelines now being used to conduct remedial actions. Current authority of the US Department of Energy (DOE) to proceed with remedial actions and the new authority required are summarized. A plan to implement the Formerly Utilized Sites Remedial Action Program (FUSRAP) in accordance with the new authority is presented, including the objectives, scope, general approach, and a summary schedule. Key issues affecting schedule and cost are discussed.

  6. Verification Survey of the Building 4059 Site (Phase B); Post Historical Site Assessment Sites, Block 1; and Radioactive Materials Handling Facility HOldup Pond (Site 4614), Santa Susana Field Laboratory, The Boeing Company, Ventura County, California

    SciTech Connect

    T.J. Vitkus

    2008-06-06

    Confirm that the final radiological conditions were accurately and adequately described in the FSS documentation, relative to the established release criteria.

  7. Estimating radiological background using imaging spectroscopy

    SciTech Connect

    Bernacki, Bruce E.; Schweppe, John E.; Stave, Sean C.; Jordan, David V.; Kulisek, Jonathan A.; Stewart, Trevor N.; Seifert, Carolyn E.

    2014-06-13

    Optical imaging spectroscopy is investigated as a method to estimate radiological background by spectral identification of soils, sediments, rocks, minerals and building materials derived from natural materials and assigning tabulated radiological emission values to these materials. Radiological airborne surveys are undertaken by local, state and federal agencies to identify the presence of radiological materials out of regulatory compliance. Detection performance in such surveys is determined by (among other factors) the uncertainty in the radiation background; increased knowledge of the expected radiation background will improve the ability to detect low-activity radiological materials. Radiological background due to naturally occurring radiological materials (NORM) can be estimated by reference to previous survey results, use of global 40K, 238U, and 232Th (KUT) values, reference to existing USGS radiation background maps, or by a moving average of the data as it is acquired. Each of these methods has its drawbacks: previous survey results may not include recent changes, the global average provides only a zero-order estimate, the USGS background radiation map resolutions are coarse and are accurate only to 1 km – 25 km sampling intervals depending on locale, and a moving average may essentially low pass filter the data to obscure small changes in radiation counts. Imaging spectroscopy from airborne or spaceborne platforms can offer higher resolution identification of materials and background, as well as provide imaging context information. AVIRIS hyperspectral image data is analyzed using commercial exploitation software to determine the usefulness of imaging spectroscopy to identify qualitative radiological background emissions when compared to airborne radiological survey data.

  8. RADIOLOGICAL ASSESSMENT

    Office of Legacy Management (LM)

    ASSESSMENT and STABILIZATION' SCENARIOS PARRERSBURG,'W. VA. SITE FEBRUARY 1980 M. CARSON J. COFFMAN N. MANDELTORT, Division of Nuclear Service Operations Chem-Nuclear Systems, ...

  9. Radiological Assessment for the Vance Road Facility Source Vault, Oak Ridge Institute for Science and Education, Oak Ridge, Tennessee

    SciTech Connect

    J. R. Morton

    2000-09-01

    From the 1950s, the Vance Road laboratories had been used for a broad range of nuclear medicine research involving numerous radionuclides. These radionuclides were stored in the a source vault located on the first floor of the facility. The Environmental Survey and Site Assessment Program (ESSAP) of ORISE performed a radiological assessment survey of the source vault after it had been remediated and in preparation for converting the area to office space.

  10. DOE - Office of Legacy Management -- Berkeley CA Site - CA 03

    Office of Legacy Management (LM)

    Berkeley CA Site - CA 03 FUSRAP Considered Sites Berkeley, CA Alternate Name(s): University of California Gilman Hall, University of California CA.03-1 Location: Gilman Hall, University of California, Berkeley, California CA.03-1 Historical Operations: Performed research and development on the synthesis and production of plutonium, resulting in uranium, plutonium, cesium and americium contamination. CA.03-3 CA.03-5 Eligibility Determination: Eligible CA.03-1 CA.03-2 Radiological Survey(s):

  11. Final report: survey and removal of radioactive surface contamination at environmental restoration sites, Sandia National Laboratories/New Mexico. Volume 2

    SciTech Connect

    Lambert, K.A.; Mitchell, M.M.; Jean, D.; Byrd, C.S.

    1997-09-01

    This report contains the Appendices A-L including Voluntary Corrective Measure Plans, Waste Management Plans, Task-Specific Health and Safety Plan, Analytical Laboratory Procedures, Soil Sample Results, In-Situ Gamma Spectroscopy Results, Radionuclide Activity Summary, TCLP Soil Sample Results, Waste Characterization Memoranda, Waste Drum Inventory Data, Radiological Risk Assessment, and Summary of Site-Specific Recommendations.

  12. Gamma radiological surveys of the Oak Ridge Reservation, Paducah Gaseous Diffusion Plant, and Portsmouth Gaseous Diffusion Plant, 1990-1993, and overview of data processing and analysis by the Environmental Restoration Remote Sensing Program, Fiscal Year 1995

    SciTech Connect

    Smyre, J.L.; Moll, B.W.; King, A.L.

    1996-06-01

    Three gamma radiological surveys have been conducted under auspices of the ER Remote Sensing Program: (1) Oak Ridge Reservation (ORR) (1992), (2) Clinch River (1992), and (3) Portsmouth Gaseous Diffusion Plant (PORTS) (1993). In addition, the Remote Sensing Program has acquired the results of earlier surveys at Paducah Gaseous Diffusion Plant (PGDP) (1990) and PORTS (1990). These radiological surveys provide data for characterization and long-term monitoring of U.S. Department of Energy (DOE) contamination areas since many of the radioactive materials processed or handled on the ORR, PGDP, and PORTS are direct gamma radiation emitters or have gamma emitting daughter radionuclides. High resolution airborne gamma radiation surveys require a helicopter outfitted with one or two detector pods, a computer-based data acquisition system, and an accurate navigational positioning system for relating collected data to ground location. Sensors measure the ground-level gamma energy spectrum in the 38 to 3,026 KeV range. Analysis can provide gamma emission strength in counts per second for either gross or total man-made gamma emissions. Gross count gamma radiation includes natural background radiation from terrestrial sources (radionuclides present in small amounts in the earth`s soil and bedrock), from radon gas, and from cosmic rays from outer space as well as radiation from man-made radionuclides. Man-made count gamma data include only the portion of the gross count that can be directly attributed to gamma rays from man-made radionuclides. Interpretation of the gamma energy spectra can make possible the determination of which specific radioisotopes contribute to the observed man-made gamma radiation, either as direct or as indirect (i.e., daughter) gamma energy from specific radionuclides (e.g., cesium-137, cobalt-60, uranium-238).

  13. Federal Radiological Monitoring and Assessment Center Overview of FRMAC Operations

    SciTech Connect

    1998-03-01

    In the event of a major radiological emergency, 17 federal agencies with various statutory responsibilities have agreed to coordinate their efforts at the emergency scene under the umbrella of the Federal Radiological Emergency Response Plan. This cooperative effort will ensure that all federal radiological assistance fully supports their efforts to protect the public. the mandated federal cooperation ensures that each agency can obtain the data critical to its specific responsibilities. This Overview of Federal Radiological Monitoring and Assessment Center (FRMAC) describes the FRMAC response activities to a major radiological emergency. It also describes the federal assets and subsequent operational activities which provide federal radiological monitoring and assessment of the off-site areas.

  14. Insight from Public Surveys Related to Siting of Nuclear Waste Facilities: An Overview of Findings from a 2015 Nationwide Survey of US Residents

    SciTech Connect

    Jenkins-Smith, Hank C.; Gupta, Kuhika; Silva, Carol L.; Bonano, Evaristo J.; Rechard, Robert P.

    2015-09-01

    The results described in this report are an analysis of nationwide surveys, administered between 2006 and 2015, which measure preferences of US residents concerning the environment and energy sources. The Energy & Environment (EE) survey series is conducted annually by the Center for Energy, Security & Society (CES&S), a joint research collaboration of the University of Oklahoma and Sandia National Laboratories. The annual EE survey series is designed to track evolving public views on nuclear materials management in the US. The 2015 wave of the Energy and Environment survey (EE15) was implemented using a web-based questionnaire, and was completed by 2,021 respondents using an Internet sample that matches the characteristics of the adult US population as estimated in the US Census. A special focus of the EE15 survey is how survey respondents understand and evaluate “consent” in the context of the storage and transportation of spent nuclear fuel (SNF). This report presents an overview of key results from analyses of questions related to consent-based siting and other elements of the nuclear energy fuel cycle.

  15. Standardized radiological dose evaluations

    SciTech Connect

    Peterson, V.L.; Stahlnecker, E.

    1996-05-01

    Following the end of the Cold War, the mission of Rocky Flats Environmental Technology Site changed from production of nuclear weapons to cleanup. Authorization baseis documents for the facilities, primarily the Final Safety Analysis Reports, are being replaced with new ones in which accident scenarios are sorted into coarse bins of consequence and frequency, similar to the approach of DOE-STD-3011-94. Because this binning does not require high precision, a standardized approach for radiological dose evaluations is taken for all the facilities at the site. This is done through a standard calculation ``template`` for use by all safety analysts preparing the new documents. This report describes this template and its use.

  16. 2013 Environmental/Radiological Assistance Directory (ERAD) Presentati...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Radiological Assistance Directory (ERAD) meetings PDF icon Nov 2013 Derived Intervention and Response Levels for Tritium Oxide at the Savannah River Site; Tim Janik,...

  17. DOE-HDBK-1131-98; General Employee Radiological Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ... DOE-HDBK-1131-98 iii Course Developers Christine Liner Savannah River Site (Development ... Radiological Controls, Monitoring (Dosimetry), Emergency Procedures, ALARA Program, ...

  18. Hospital Triage in First Hours After Nuclear or Radiological...

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Hospital Triage in the First 24 Hours after a Nuclear or Radiological Disaster Medical professionals with the Radiation Emergency Assistance CenterTraining Site (REACTS) at the...

  19. Radiological control manual. Revision 1

    SciTech Connect

    Kloepping, R.

    1996-05-01

    This Lawrence Berkeley National Laboratory Radiological Control Manual (LBNL RCM) has been prepared to provide guidance for site-specific additions, supplements and interpretation of the DOE Radiological Control Manual. The guidance provided in this manual is one methodology to implement the requirements given in Title 10 Code of Federal Regulations Part 835 (10 CFR 835) and the DOE Radiological Control Manual. Information given in this manual is also intended to provide demonstration of compliance to specific requirements in 10 CFR 835. The LBNL RCM (Publication 3113) and LBNL Health and Safety Manual Publication-3000 form the technical basis for the LBNL RPP and will be revised as necessary to ensure that current requirements from Rules and Orders are represented. The LBNL RCM will form the standard for excellence in the implementation of the LBNL RPP.

  20. Effectiveness of Shallow Temperatures Surveys to Target a Geothermal Reservoir at Previously Explored Sites at McGee Mountain, Nevada

    Energy.gov [DOE]

    DOE Geothermal Peer Review 2010 - Presentation. Project Objectives: To evaluate the cost-effectiveness of two innovative technologies in early-stage geothermal exploration:a) shallow (2m) survey; b) hydroprobe; and Identify a geothermal resource at the project site.

  1. Savannah River Site RCRA Facility Investigation plan: Road A Chemical Basin

    SciTech Connect

    Not Available

    1989-06-01

    The nature of wastes disposed of at the Road A Chemical Basin (RACB) is such that some degree of soil contamination is probable. Lead has also been detected in site monitoring wells at concentrations above SRS background levels. A RCRA Facility Investigation (RFI) is proposed for the RACB and will include a ground penetrating radar (GPR) survey, collection and chemical and radiological analyses of soil cores, installation of groundwater monitoring wells, collection and chemical and radiological analyses of groundwater samples, and collection of chemical and radiological analyses of surface water and sediment samples. Upon completion of the proposed RFI field work and chemical and radiological analyses, and RFI report should be prepared to present conclusions on the nature and extent of contamination at the site, and to make recommendations for site remediation. If contamination is detected at concentrations above SRS background levels, a receptor analysis should be done to evaluate potential impacts of site contamination on nearby populations.

  2. Digital Surveying Directional Surveying Specialists | Open Energy...

    OpenEI (Open Energy Information) [EERE & EIA]

    Surveying Specialists Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: Digital Surveying Directional Surveying Specialists Author Directional Surveying...

  3. Electrical Resistivity and Seismic Surveys at the Nevada Test Site, Nevada, April 2007

    SciTech Connect

    Seth S. Haines; Bethany L. Burton; Donald S. Sweetkind; Theodore H. Asch

    2009-03-30

    In April 2007, the USGS collected direct-current (DC) electrical resistivity data and shear- (S) and compressional- (P) wave seismic data to provide new detail of previously mapped, overlapping fault splays at two administrative areas in the Nevada Test Site (NTS). In NTS Area 7, we collected two-dimensional DC resistivity data along a transect crossing the Yucca Fault parallel to, and between, two transects along which resistivity data were collected in a previous study in 2006. In addition, we collected three-dimensional DC resistivity data in a grid that overlies part of the 2007 transect. The DC resistivity data show that the fault has a footwall that is more conductive than the hanging wall and an along-strike progression of the fault in a location where overlapping splays are present. Co-located with the northernmost of the two 2006 DC resistivity transects, we acquired S- and P-wave seismic data for both reflection and refraction processing. The S-wave data are corrupted by large amounts of converted (P-wave) energy likely due to the abundance of fractured caliche in the shallow subsurface. The P-wave data show minimal reflected energy, but they show clear refracted first arrivals. We have inverted these first arrival times to determine P-wave seismic velocity models. The seismic model for the transect in Area 7 shows low velocities extending to the base of the model at the location of the Yucca Fault, as well as low velocities at the eastern end of the transect, in the vicinity of the adjacent crater. These new surveys provide further detail about the geometry of the Yucca Fault in this location where it shows two overlapping splays. We collected P- and S-wave seismic data along a transect in the southern part of NTS Area 2, corresponding with the location of a 2006 DC resistivity transect that targeted a set of small faults identified with field mapping. Again, the S-wave data are difficult to interpret. The P-wave data show clear first arrivals that we

  4. Radiological/Nuclear Applications

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Radiological/Nuclear Applications Radiological/Nuclear Applications Radiological sensors in action, solutions for you. Radiological and Nuclear Capabilities-for Collaboration View our capability sheets: get details of what we do. Boron 10 Neutron Detector New Neutron Detector Materials How we deploy innovation radiiological-nuclear bubble In the mid-1990s, Los Alamos scientists were developing proton radiography techniques for a variety of applications and decided to try using muons instead of

  5. Radiological Technician Training

    Energy.gov [DOE] (indexed site)

    Part 2 of 9 Radiological Control Technician Training Technician Qualification Standard ... . . . . . . . . 1 Phase I: RCT Academics Training . . . . . . . . . . . . . . . . . . . . ...

  6. Radiological Control Technician Training

    Energy Saver

    Part 8 of 9 Radiological Control Technician Training Oral Examination Boards Phase III ... Training of Oral Board Members ......

  7. Radiological Characterization Technical Report on Californium-252 Sealed Source Transuranic Debris Waste for the Off-Site Source Recovery Project at Los Alamos National Laboratory

    SciTech Connect

    Feldman, Alexander

    2014-04-24

    This document describes the development and approach for the radiological characterization of Cf-252 sealed sources for shipment to the Waste Isolation Pilot Plant. The report combines information on the nuclear material content of each individual source (mass or activity and date of manufacture) with information and data on the radionuclide distributions within the originating nuclear material. This approach allows for complete and accurate characterization of the waste container without the need to take additional measurements. The radionuclide uncertainties, developed from acceptable knowledge (AK) information regarding the source material, are applied to the summed activities in the drum. The AK information used in the characterization of Cf-252 sealed sources has been qualified by the peer review process, which has been reviewed and accepted by the Environmental Protection Agency.

  8. Surveys

    Energy.gov [DOE]

    Surveys can be a useful way to gauge the opinions of your readers and learn more about your website's audiences, but you'll often need approval from the Office of Management and Budget (OMB) to run...

  9. Confirmatory Survey of the Fuel Oil Tank Area - Humboldt Bay Power Plant, Eureka, California

    SciTech Connect

    ADAMS, WADE C

    2012-04-09

    During the period of February 14 to 15, 2012, ORISE performed radiological confirmatory survey activities for the former Fuel Oil Tank Area (FOTA) and additional radiological surveys of portions of the Humboldt Bay Power Plant site in Eureka, California. The radiological survey results demonstrate that residual surface soil contamination was not present significantly above background levels within the FOTA. Therefore, it is ORISE’s opinion that the radiological conditions for the FOTA surveyed by ORISE are commensurate with the site release criteria for final status surveys as specified in PG&E’s Characterization Survey Planning Worksheet. In addition, the confirmatory results indicated that the ORISE FOTA survey unit Cs-137 mean concentrations results compared favorably with the PG&E FOTA Cs-137 mean concentration results, as determined by ORISE from the PG&E characterization data. The interlaboratory comparison analyses of the three soil samples analyzed by PG&E’s onsite laboratory and the ORISE laboratory indicated good agreement for the sample results and provided confidence in the PG&E analytical procedures and final status survey soil sample data reporting.

  10. Intensive archaeological survey of the proposed Central Sanitary Wastewater Treatment Facility, Savannah River Site, Aiken and Barnwell Counties, South Carolina

    SciTech Connect

    Stephenson, D.K.; Sassaman, K.E.

    1993-11-01

    The project area for the proposed Central Sanitary Wastewater Treatment Facility on the Savannah River Site includes a six-acre tract along Fourmile Branch and 18 mi of trunk line corridors. Archaeological investigations of the six-acre parcel resulted in the discovery of one small prehistoric site designated 38AK465. This cultural resource does not have the potential to add significantly to archaeological knowledge of human occupation in the region. The Savannah River Archaeological Research Program (SRARP) therefore recommends that 38AK465 is not eligible for nomination to the National Register of Historic Places (NRHP) and further recommends a determination of no effect. Archaeological survey along the trunk line corridors implicated previously recorded sites 38AK92, 38AK145, 38AK415, 38AK417, 38AK419, and 38AK436. Past disturbance from construction had severely disturbed 38AK92 and no archaeological evidence of 38AK145, 38AK419, and 38AK436 was recovered during survey. Lacking further evidence for the existence of these sites, the SRARP recommends that 38AK92, 38AK145, 38AK419, and 38AK436 are not eligible for nomination to the NRHP and thus warrant a determination of no effect. Two of these sites, 38Ak415 and 38AK417, required further investigation to evaluate their archaeological significance. Both of the sites have the potential to yield significant data on the prehistoric period occupation of the Aiken Plateau and the SRARP recommends that they are eligible for nomination to the NRHP. The Savannah River Archaeological Research Program recommends that adverse effects to sites 38AK415 and 38AK417 from proposed construction can be mitigated through avoidance.

  11. Designation of Sites for Remedial Action - Metal Hydrides, Beverly,

    Office of Legacy Management (LM)

    T: Designation of Sites for Remedial Action - Metal Hydrides, Beverly, MA; Bridgeport Brass, Adrian, MI and Seymour, Chicago, IL CT; National Guard Armory, 0: Joe LaGrone, Manager Oak Ridge Operations Office Based on the attached radiological survey data (Attachments 1 through 3) and an appropriate authority review, the following properties are being authorized for remedial action. It should be noted that the attached survey data are for designation purposes only and that Bechtel National, Inc.

  12. Routine Radiological Environmental Monitoring Plan. Volume 1

    SciTech Connect

    Bechtel Nevada

    1999-12-31

    The U.S. Department of Energy manages the Nevada Test Site in a manner that meets evolving DOE Missions and responds to the concerns of affected and interested individuals and agencies. This Routine Radiological Monitoring Plan addressess complicance with DOE Orders 5400.1 and 5400.5 and other drivers requiring routine effluent monitoring and environmental surveillance on the Nevada Test Site. This monitoring plan, prepared in 1998, addresses the activities conducted onsite NTS under the Final Environmental Impact Statement and Record of Decision. This radiological monitoring plan, prepared on behalf of the Nevada Test Site Landlord, brings together sitewide environmental surveillance; site-specific effluent monitoring; and operational monitoring conducted by various missions, programs, and projects on the NTS. The plan provides an approach to identifying and conducting routine radiological monitoring at the NTS, based on integrated technical, scientific, and regulatory complicance data needs.

  13. Evaluation of critical pathways, radionuclides, and remedial measures for reducing the radiological dose to returning populations at a former nuclear test site

    SciTech Connect

    Robison, W. L., LLNL

    1997-11-01

    Bikini Island, the major residence island at Bikini Atoll, was contaminated with radioactive fallout as a result of the BRAVO test conducted on March 1, 1954. We have identified the critical radionuclides and supplied radiological data needed to develop dose estimates for all possible exposure pathways. These estimates show that the major dose to returning populations would result from ingestion of cesium-137 (137 Cs) in locally grown terrestrial foods where the predicted population average effective dose exceeds current federal guidelines. Consequently, we designed several long-term field experiments to develop and evaluate methods to reduce the 137 Cs content in locally grown foods.This paper gives a general outline of the remediation experiments with a more detailed description of a preferred combined option. Our comparative evaluation on various remedial methods show that the combined option--potassium treatment of the entire islands with limited excavation of soil in village an d housing areas--will be effective in reducing the dose to about 10% of pretreatment levels, and offers very significant benefits with respect to adverse environmental impacts as well as savings in overall costs, time, and required expert resources.

  14. Guidance on the Use of Hand-Held Survey Meters for radiological Triage: Time-Dependent Detector Count Rates Corresponding to 50, 250, and 500 mSv Effective Dose for Adult Males and Adult Females

    SciTech Connect

    Bolch, W.E.; Hurtado, J.L.; Lee, C.; Manger, Ryan P; Hertel, Nolan; Burgett, E.; Dickerson, W.

    2012-01-01

    In June 2006, the Radiation Studies Branch of the Centers for Disease Control and Prevention held a workshop to explore rapid methods of facilitating radiological triage of large numbers of potentially contaminated individuals following detonation of a radiological dispersal device. Two options were discussed. The first was the use of traditional gamma cameras in nuclear medicine departments operated as makeshift wholebody counters. Guidance on this approach is currently available from the CDC. This approach would be feasible if a manageable number of individuals were involved, transportation to the relevant hospitals was quickly provided, and the medical staff at each facility had been previously trained in this non-traditional use of their radiopharmaceutical imaging devices. If, however, substantially larger numbers of individuals (100 s to 1,000 s) needed radiological screening, other options must be given to first responders, first receivers, and health physicists providing medical management. In this study, the second option of the workshop was investigated by the use of commercially available portable survey meters (either NaI or GM based) for assessing potential ranges of effective dose (G50, 50Y250, 250Y500, and 9500 mSv). Two hybrid computational phantoms were used to model an adult male and an adult female subject internally contaminated with 241Am, 60Cs, 137Cs, 131I, or 192Ir following an acute inhalation or ingestion intake. As a function of time following the exposure, the net count rates corresponding to committed effective doses of 50, 250, and 500 mSv were estimated via Monte Carlo radiation transport simulation for each of four different detector types, positions, and screening distances. Measured net count rates can be compared to these values, and an assignment of one of four possible effective dose ranges could be made. The method implicitly assumes that all external contamination has been removed prior to screening and that the measurements be

  15. Survey of ecological resources at selected US Department of Energy sites

    SciTech Connect

    McAllister, C.; Beckert, H.; Abrams, C.

    1996-09-01

    The U.S. Department of Energy (DOE) owns and manages a wide range of ecological resources. During the next 30 years, DOE Headquarters and Field Offices will make land-use planning decisions and conduct environmental remediation and restoration activities in response to federal and state statutes. This document fulfills, in part, DOE`s need to know what types of ecological resources it currently owns and manages by synthesizing information on the types and locations of ecological resources at 10 DOE sites: Hanford Site, Idaho National Engineering Laboratory, Lawrence Livermore National Laboratory, Sandia National Laboratory, Rocky Flats Plant, Los Alamos National Laboratory, savannah River Site, Oak Ridge National Laboratory, Argonne National Laboratory, and Fernald Environmental Management Project. This report summarizes information on ecosystems, habitats, and federally listed threatened, endangered, and candidate species that could be stressed by contaminants or physical activity during the restoration process, or by the natural or anthropogenic transport of contaminants from presently contaminated areas into presently uncontaminated areas. This report also provides summary information on the ecosystems, habitats, and threatened and endangered species that exist on each of the 10 sites. Each site chapter contains a general description of the site, including information on size, location, history, geology, hydrology, and climate. Descriptions of the major vegetation and animal communities and of aquatic resources are also provided, with discussions of the treatened or endangered plant or animal species present. Site-specific ecological issues are also discussed in each site chapter. 106 refs., 11 figs., 1 tab.

  16. DOE - Office of Legacy Management -- Oxford OH Site - OH 22

    Office of Legacy Management (LM)

    Oxford OH Site - OH 22 FUSRAP Considered Sites Oxford, OH Alternate Name(s): Alba Craft Shop Alba Craft Laboratory Albaugh dba Alba Craft Shop OH.22-3 OH.22-4 Location: 10-14 West Rose Avenue, Oxford, Ohio OH.22-7 Historical Operations: Performed metal fabrication under subcontract with AEC prime contract to National Lead Company of Ohio on uranium metal. Includes VPs. OH.22-5 OH.22-6 OH.22-8 Eligibility Determination: Eligible OH.22-1 OH.22-2 Radiological Survey(s): Assessment Survey,

  17. Radiological Assistance Program

    Directives, Delegations, and Other Requirements [Office of Management (MA)]

    1992-04-10

    To establish Department of Energy (DOE) policy, procedures, authorities, and responsibilities for its Radiological Assistance Program. Canceled by DOE O 153.1.

  18. Office of Radiological Security

    National Nuclear Security Administration (NNSA)

    of physical security of radiological materials;

  19. Provision of mobile and man-portable radiation detection equipment;
  20. Regional cooperation on safeguards...

  21. Radiological Control Technician Training

    Energy.gov [DOE] (indexed site)

    ... addresses the training requirements of 10 CFR 835.103 for Radiological Control Technicians, it must be supplemented with facility specific information to achieve full compliance. ...

  22. Radiological Control Technician Training

    Energy.gov [DOE] (indexed site)

    7of 9 Radiological Control Technician Training Practical Training Phase II Coordinated and Conducted for the Office of Health, Safety and Security U.S. Department of Energy ...

  1. Radiological Control Technician Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    HANDBOOK RADIOLOGICAL CONTROL TECHNICIAN TRAINING U.S. Department of Energy AREA TRNG ... an implementation process for core training as recommended in chapter 14 to ...

  2. Radiological Control Technician Training

    Energy.gov [DOE] (indexed site)

    Radiological Control Technician Training Facility Practical Training Attachment Phase IV Coordinated and Conducted for the Office of Health, Safety and Security U.S. Department of ...

  3. Nuclear and Radiological Field Training Center | Y-12 National Security

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Complex ... Nuclear and Radiological Field Training Center A site used for nuclear research in Oak Ridge, Tennessee during the Manhattan Project is now the Y-12 National Security Complex's Nuclear and Radiological Field Training Center - the only facility of its kind in the world. The Center provides world-class nuclear and radiological training in a safe, secure, realistic environment using expert instruction and personnel to serve as observers/evaluators for customer training. For military

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

    SciTech Connect

    Danilovich, Alexey; Ivanov, Oleg; Lemus, Alexey; Smirnov, Sergey; Stepanov, Vyacheslav; Volkovich, Anatoly

    2012-07-01

    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

  5. Final Report - Independent Verification Survey Activities at the Seperations Process Research Unit Sites, Niskayuna, New York

    SciTech Connect

    Evan Harpenau

    2011-03-15

    The Separations Process Research Unit (SPRU) complex located on the Knolls Atomic Power Laboratory (KAPL) site in Niskayuna, New York, was constructed in the late 1940s to research the chemical separation of plutonium and uranium (Figure A-1). SPRU operated as a laboratory scale research facility between February 1950 and October 1953. The research activities ceased following the successful development of the reduction oxidation and plutonium/uranium extraction processes. The oxidation and extraction processes were subsequently developed for large scale use by the Hanford and Savannah River sites (aRc 2008a). Decommissioning of the SPRU facilities began in October 1953 and continued through the 1990s.

  6. Improving Water Management: Applying ModelBuilder to site water impoundments using AEM survey data

    SciTech Connect

    Sams, J.I.; Lipinski, B.A.; Harbert, W.P.; Ackman, T.E.

    2007-01-01

    ArcGIS ModelBuilder was used to create a GIS-based decision support model that incorporated digital elevation data and electromagnetic geophysical results gathered by helicopter to screen potential sites for water disposal impoundments produced from coal bed natural gas.

  7. Siting Study Framework and Survey Methodology for Marine and Hydrokinetic Energy Projects in Offshore Southeast Florida

    SciTech Connect

    Vinick, Charles

    2011-09-26

    Presentation from the 2011 Water Peer Review in which principal investigator discusses project progess to Investigate areas offshore southeast Florida that appeared most suitable for siting of marine and hydrokinetic energy conversion facilities that may be proposed in the Atlantic Ocean offshore of southeast Florida.

  8. U.S. Department of Energy 2012 Annual Inspection - Piqua, OH, Decommissioned Reactor Site

    Office of Legacy Management (LM)

    Piqua, OH, Decommissioned Reactor Site May 2012 Page 1 2012 Annual Inspection and Radiological Survey Results for the Piqua, Ohio, Decommissioned Reactor Site Summary The former Piqua Nuclear Power Facility (PNPF), a decommissioned nuclear power demonstration facility, was inspected on April 10, 2012. The site, located on the east bank of the Great Miami River in Piqua, Ohio, is in good physical condition. There is no requirement for a follow-up inspection. The former PNPF consists of a reactor

  9. Surface radiation survey for the Phase 1 remedial investigation of the 300-FF-1 operable unit on the Hanford Site

    SciTech Connect

    Teel, S.S.; Olsen, K.B.

    1990-10-01

    This report summarizes Task 3a-1 of the Phase I Remedial Investigation for the 300-FF-1 Operable Unit on the Hanford Site, near Richland, Washington. The purpose of the Remedial Investigation is to determine the nature and extent of the risk presented by releases of hazardous substances from the operable unit. The purpose of Task 3a-1 was to locate any areas of contaminated soil outside of operable unit waste facility boundaries. Surface radiation survey and sampling activities in the 300-FF-1 Operable Unit were conducted from September 1989 to December 1989 and April 1990 to June 1990. Surveys were conducted primarily using portable Geiger-Muller beta/gamma detectors. As a result, 77 locations were found where radiation occurred above a statistically calculated background estimate. The Ultra Sonic Ranging and Data System (USRADS) was also used to survey a limited area. Analysis of the USRADS data revealed several elevated measurements that were not detected at the same locations with the Geiger-Muller detector. 6 refs., 14 figs., 4 tabs.

  10. Siting landfills and incinerators in areas of historic unpopularity: Surveying the views of the next generation

    SciTech Connect

    De Feo, Giovanni; Williams, Ian D.

    2013-12-15

    Highlights: • Opinions and knowledge of young people in Italy about waste were studied. • Historic opposition to construction of waste facilities is difficult to overcome. • Awareness of waste management develops with knowledge of environmental issues. • Many stakeholders’ views are needed when siting a new waste management facility. • Respondents’ opinions were influenced by their level of environmental knowledge. - Abstract: The Campania Region in Southern Italy has suffered many problems with municipal solid waste management since the mid-1990s, leading to significant public disturbances and subsequent media coverage. This paper reports on the current views and knowledge of young people (university students) in this region about waste management operations and facilities, specifically the siting of landfills and incinerators. By means of a structured questionnaire, opinion and knowledge were systematically examined by degree type and course year. The study took place in 2011 at the University of Salerno campus. A sample of 900 students, comprising 100 students for each of the nine considered faculties, and 20 students for every academic course year, was randomly selected. Only about a quarter of respondents were not opposed to the siting of a landfill or an incinerator in their city. This clearly highlights that historic opposition to the construction of waste facilities is difficult to overcome and that distrust for previous poor management or indiscretions is long-lived and transcends generations. Students from technical faculties expressed the most reasonable opinion; opinion and knowledge were statistically related (Chi-square test, p < 0.05) to the attended faculty, and the knowledge grew linearly with progression through the university. This suggests that awareness of waste management practices develops with experience and understanding of environmental issues. There is general acceptance that many stakeholders – technicians, politicians

  11. ORISE: Radiological program assessment services

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    ORISE focuses its radiological audit and assessment services in these key areas: Nondestructive assay (NDA) Radiological control programs Environmental monitoring programs ...

  12. Radiological Training for Tritium Facilities

    Energy Saver

    Change Notice No. 2 May 2007 DOE HANDBOOK RADIOLOGICAL TRAINING FOR TRITIUM FACILITIES ... Change Notice 2. Radiological Safety Training for Tritium Facilities ...

  13. 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

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

    2005-02-01

    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.

  14. Final Report-Confirmatory Survey Results for the ABB Combustion Engineering Site, Windsor, Connecticut; Revision 1 (DCN 5158-SR-02-1) (Docket No. 030-03754; RFTA No. 12-003)

    SciTech Connect

    ADAMS, WADE C

    2013-01-28

    The objectives of the confirmatory activities were to provide independent contractor field data reviews and to generate independent radiological data for use by the NRC in evaluating the adequacy and accuracy of the contractor's procedures and FSS results. ORAU reviewed ABB CE's decommissioning plan, final status survey plan, and the applicable soil DCGLs, which were developed based on an NRC-approved radiation dose assessment. The surveys included gamma surface scans, gamma direct measurements, and soil sampling.

  15. Survey of Potential Geothermal Exploration Sites at Newberry Volcano Deschutes County, Oregon.

    SciTech Connect

    Priest, George R.; Vogt, Beverly F.; Black, Gerald L.

    1983-01-01

    The study summarizes the current data, generates some new data, and recommends further steps which should be taken to investigate the electrical power production potential of Newberry volcano. The objective was to concentrate on data from the developable flanks of the volcano. All previous data on the geology, hydrology, and geophysics were summarized. A soil-mercury survey focused on the flanks of the volcano was conducted. Samples from 1000 km/sup 2/ of the volcano were analyzed for mercury content. All this information was utilized to evaluate (1) the likelihood of future discovery of electrical-quality geothermal fluids on the flanks, and (2) the most cost-effective means of improving the quality of available power generation estimates for the volcano. 37 figures.

  16. PPPL Site Environmental Report

    SciTech Connect

    Virginia Finley, Robeert Sheneman and Jerry Levine

    2012-12-21

    Contained in the following report are data for radioactivity in the environment collected and analyzed by Princeton Plasma Physics Laboratorys Princeton Environmental, Analytical, and Radiological Laboratory (PEARL). The PEARL is located on?site and is certified for analyzing radiological and non?radiological parameters through the New Jersey Department of Environmental Protections Laboratory Certification Program, Certification Number 12471. Non?radiological surface and ground water samples are analyzed by NJDEP certified subcontractor laboratories QC, Inc. and Accutest Laboratory. To the best of our knowledge, these data, as contained in the Annual Site Environmental Report for 2011, are documented and certified to be correct.

  17. Hydroelectric power in Hawaii. A report on the statewide survey of potential hydroelectric sites

    SciTech Connect

    Beck, C. A.

    1981-02-01

    An assessment was made of the hydropower potential in Hawaii. The major conclusion of this study is that hydropower resources in the State of Hawaii are substantial, and they offer the potential for major increases in hydropower generating capacity. Hydropower resources on all islands total about 50 MW of potential generating capacity. Combined with the 18 MW of existing hydropower capacity, hydropower resources potentially could generate about 307 million kWh of electric energy annually. This represents about 28% of the present combined electricity needs of the Neighbor Islands, Kauai, Molokai, Maui, and the Big Island. Hydropower resources on Kauai equal 72% of that island's electricity needs; on Molokai, 40%, on the Big Island, 20%; and on Maui, 18%. The island of Oahu, however, has only small hydropower resources, and could only generate a negligible portion of its electricity needs from this energy source. A summary of existing and future (potential) hydropower capacities and estimated annual outputs for each island is presented. How much of the potential capacity is being actively considered for development and how much is only tentatively proposed at the time is indicated. The economics of hydropower at specific sites were analyzed. The major conclusion of this analysis is that hydropower development costs vary widely among the different sites, but that generally the cost of hydroelectric power is either less than or comparable to the cost of oil-fired power.

  18. Confirmatory Survey Report for the Quehanna Decommissioning Project, Karthaus, PA

    SciTech Connect

    W. C. Adams

    2007-10-30

    The survey activities consisted of visual inspections and radiological surveys including beta and gamma surface scans and surface beta activity measurements.

  19. Ground penetrating radar surveys over an alluvial DNAPL site, Paducah Gaseous Diffusion Plant, Kentucky

    SciTech Connect

    Carpenter, P.J. |; Doll, W.E.; Phillips, B.E.

    1994-09-01

    Ground penetrating radar (GPR) surveys were used to map shallow sands and gravels which are DNAPL migration pathways at the Paducah Gaseous Diffusion Plant in western Kentucky. The sands and gravels occur as paleochannel deposits, at depths of 17-25 ft, embedded in Pleistocene lacustrine clays. More than 30 GPR profiles were completed over the Drop Test Area (DTA) to map the top and base of the paleochannel deposits, and to assess their lateral continuity. A bistatic radar system was used with antenna frequencies of 25 and 50 MHz. An average velocity of 0.25 ft/ns for silty and clayey materials above the paleochannel deposits was established from radar walkaway tests, profiles over culverts of known depth, and comparison of radar sections with borings. In the south portion of the DTA, strong reflections corresponded to the water table at approximately 9-10 ft, the top of the paleochannel deposits at approximately 18 ft, and to gravel horizons within these deposits. The base of these deposits was not visible on the radar sections. Depth estimates for the top of the paleochannel deposits (from 50 records) were accurate to within 2 ft across the southern portion of the DTA. Continuity of these sands and gravels could not be assessed due to interference from air-wave reflections and lateral changes in signal penetration depth. However, the sands and gravels appear to extend across the entire southern portion of the DTA, at depths as shallow as 17 ft. Ringing, air-wave reflections and diffractions from powerlines, vehicles, well casings, and metal equipment severly degraded GPR profiles in the northern portion of the DTA; depths computed from reflection times (where visible) were accurate to within 4 ft in this area. The paleochannel deposits are deeper to the north and northeast where DNAPL has apparently pooled (DNAPL was not directly imaged by the GPR, however). Existing hydrogeological models of the DTA will be revised.

  20. DOE - Office of Legacy Management -- Fairfield OH Site - OH 23

    Office of Legacy Management (LM)

    Fairfield OH Site - OH 23 FUSRAP Considered Sites Fairfield, OH Alternate Name(s): Associate Aircraft Tool & Manufacturing, Inc. Associated Aircraft Tool and Manufacturing Company Force Control Industries Former Dixie Machinery OH.23-1 OH.23-2 Location: 3660 Dixie Highway, Fairfield, Ohio OH.23-2 Historical Operations: Produced natural uranium hollow slugs, resulting in uranium metal contamination. OH.23-4 OH.23-5 Eligibility Determination: Eligible OH.23-1 OH.23-2 Radiological Survey(s):

  1. DOE standard: Radiological control

    SciTech Connect

    Not Available

    1999-07-01

    The Department of Energy (DOE) has developed this Standard to assist line managers in meeting their responsibilities for implementing occupational radiological control programs. DOE has established regulatory requirements for occupational radiation protection in Title 10 of the Code of Federal Regulations, Part 835 (10 CFR 835), ``Occupational Radiation Protection``. Failure to comply with these requirements may lead to appropriate enforcement actions as authorized under the Price Anderson Act Amendments (PAAA). While this Standard does not establish requirements, it does restate, paraphrase, or cite many (but not all) of the requirements of 10 CFR 835 and related documents (e.g., occupational safety and health, hazardous materials transportation, and environmental protection standards). Because of the wide range of activities undertaken by DOE and the varying requirements affecting these activities, DOE does not believe that it would be practical or useful to identify and reproduce the entire range of health and safety requirements in this Standard and therefore has not done so. In all cases, DOE cautions the user to review any underlying regulatory and contractual requirements and the primary guidance documents in their original context to ensure that the site program is adequate to ensure continuing compliance with the applicable requirements. To assist its operating entities in achieving and maintaining compliance with the requirements of 10 CFR 835, DOE has established its primary regulatory guidance in the DOE G 441.1 series of Guides. This Standard supplements the DOE G 441.1 series of Guides and serves as a secondary source of guidance for achieving compliance with 10 CFR 835.

  2. Automatic Estimation of the Radiological Inventory for the Dismantling of Nuclear Facilities

    SciTech Connect

    Garcia-Bermejo, R.; Felipe, A.; Gutierrez, S.; Salas, E.; Martin, N.

    2008-01-15

    The estimation of the radiological inventory of Nuclear Facilities to be dismantled is a process that included information related with the physical inventory of all the plant and radiological survey. Estimation of the radiological inventory for all the components and civil structure of the plant could be obtained with mathematical models with statistical approach. A computer application has been developed in order to obtain the radiological inventory in an automatic way. Results: A computer application that is able to estimate the radiological inventory from the radiological measurements or the characterization program has been developed. In this computer applications has been included the statistical functions needed for the estimation of the central tendency and variability, e.g. mean, median, variance, confidence intervals, variance coefficients, etc. This computer application is a necessary tool in order to be able to estimate the radiological inventory of a nuclear facility and it is a powerful tool for decision taken in future sampling surveys.

  3. Evaluation of Final Radiological Conditions at Areas of the Niagara Falls

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program | Department of Energy Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program (March 2012) Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program (March 2012) (320.28 KB

  4. Results of radiological measurements taken in the Niagara Falls, New York, area (NF002)

    SciTech Connect

    Williams, J.K.; Berven, B.A.

    1986-11-01

    The results of a radiological survey of 100 elevated gamma radiation anomalies in the Niagara Falls, New York, area are presented. These radiation anomalies were identified by a mobile gamma scanning survey during the period October 3-16, 1984, and were recommended for an onsite survey to determine if the elevated levels of radiation may be related to the transportation of radioactive waste material to the Lake Ontario Ordnance Works for storage. In this survey, radiological measurements included outdoor gamma exposure rates at 1 m above the surface; outdoor gamma exposure rates at the surface, range of gamma exposure rates during scan; and uranium, radium, and thorium concentrations in biased surface soil samples. The results show 38 anomalies (35 located along Pletcher Road and 3 associated with other unreleated locations) were found to exceed Formerly Utilized Sites Remedial Action Program (FUSRAP) remedial action guidelines and were recommended for formal characterization surveys. (Since the time of this survey, remedial actions have been conducted on the 38 anomalies identified as exceeding FUSRAP guidelines, and the radioactive material above guidelines has been removed.) The remaining 62 anomalies are associated with asphalt driveways and parking lots, which used a phosphate slag material (previously identified as cyclowollastonite, synthetic CaSiO/sub 3/). This rocky-slag waste material was used for bedding under asphalt surfaces and in general gravel applications. Most of the contaminated soil and rock samples collected at the latter anomalies had approximately equal concentrations of /sup 226/Ra and /sup 238/U and, therefore, are not related to materials connected with the Niagara Falls Storage Site (NFSS), including material that was transported to the NFSS. 13 refs., 7 figs., 14 tabs.

  5. NEVADA TEST SITE RADIOLOGICAL CONTROL MANUAL

    Office of Scientific and Technical Information (OSTI)

    ... Disintegrations per Minute (dpm): The rate of emission by ... DOE: The United States Department of Energy. DOE Activity: An ... in extreme cases coma and death; a significant ...

  6. WIPP Radiological Release Report Phase 1

    Office of Environmental Management (EM)

    Phase 1 Radiological Release Event at the Waste Isolation Pilot Plant on February 14, 2014 April 2014 Radiological Release Event at the Waste Isolation Pilot Plant Radiological ...

  7. WIPP Radiological Relase Report Phase 2

    Office of Environmental Management (EM)

    Phase 2 Radiological Release Event at the Waste Isolation Pilot Plant, February 14, 2014 April 2015 Radiological Release Event at the Waste Isolation Pilot Plant Radiological Release ...

  8. Radiological worker training

    SciTech Connect

    1998-10-01

    This Handbook describes an implementation process for core training as recommended in Implementation Guide G441.12, Radiation Safety Training, and as outlined in the DOE Radiological Control Standard (RCS). The Handbook is meant to assist those individuals within the Department of Energy, Managing and Operating contractors, and Managing and Integrating contractors identified as having responsibility for implementing core training recommended by the RCS. This training is intended for radiological workers to assist in meeting their job-specific training requirements of 10 CFR 835. While this Handbook addresses many requirements of 10 CFR 835 Subpart J, it must be supplemented with facility-specific information to achieve full compliance.

  9. Residual radioactivity in the vicinity of formerly utilized MED/AEC sites

    SciTech Connect

    Haywood, F. F.; Goldsmith, W. A.

    1980-01-01

    As demand for uranium and thorium was accelerated during the 1940's, services of chemical and metallurgical firms and major research facilities were contracted as needed by the Manhattan Engineer District (MED). A lack of documentation of the radiological status at the time contracts were terminated at these facilities led the Department of Energy (DOE), and its predecessor the Energy Research and Development Administration (ERDA), to develop a major radiological resurvey program to fill this information void. A combination of aerial and ground-level radiological monitoring teams were utilized to identify and assess off-site radioactivity. Results from comprehensive aerial surveys provide the approximate areal extent of elevated radiation levels on the ground. These aerial survey results led to two types of ground-level surveys: (1) gamma-ray scanning on foot or from a motorized vehicle (mobile lab based system) to pinpoint the location of residual radioactivity; and (2) compehensive radiological surveys to determine the amount and type of materials present on specific parcels of private and public property identified during the scanning. This type of investigation was initiated in 1978 and has been successful in identifying and assessing the potential radiation hazard from property on which materials bearing natural radioactivity have been found. This paper contains a description of the techniques used to find and evaluate radioactive material displaced outside the boundaries of a formerly utilized site.

  10. Monument Survey

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Photographs from the WIPP Permanent Marker Monument Survey John Hart & Associates, 2000 Photograph of the Gnome Marker located about 10 miles SW of the WIPP site For more...

  11. 324 Building Baseline Radiological Characterization

    SciTech Connect

    R.J. Reeder, J.C. Cooper

    2010-06-24

    This report documents the analysis of radiological data collected as part of the characterization study performed in 1998. The study was performed to create a baseline of the radiological conditions in the 324 Building.

  12. Interim Letter Report - Verification Survey of Partial Grid E9, David Witherspoon, Inc. 1630 Site Knoxville, Tennessee

    SciTech Connect

    P.C. Weaver

    2008-06-12

    Conduct verification surveys of available grids at the DWI 1630 in Knoxville, Tennessee. A representative with the Independent Environmental Assessment and Verification (IEAV) team from ORISE conducted a verification survey of a partial area within Grid E9.

  13. Radiological Control Technician Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    9 of 9 Radiological Control Technician Training Facility Practical Training Attachment Phase IV Coordinated and Conducted for the Office of Health, Safety and Security U.S. Department of Energy DOE-HDBK-1122-2009 This page intentionally left blank ii DOE-HDBK-1122-2009 Table of Contents Page Introduction................................................................................................................................1 Facility Job Performance Measures

  14. Radiological Technician Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    DOE-HDBK-1122-2009 Part 2 of 9 Radiological Control Technician Training Technician Qualification Standard Coordinated and Conducted for the Office of Health, Safety and Security U.S. Department of Energy DOE-HDBK-1122-2009 This page intentionally left blank. ii DOE-HDBK-1122-2009 Table of Contents Page Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .1 Purpose of Qualification Standard . . . . . . . . . . . . . . . . .

  15. NNSA Conducts International Radiological Response Training in...

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    NNSA Conducts International Radiological Response Training in Vienna August 01, 2013 ... Radiological Assistance Program Training for Emergency Response Advanced ...

  16. NV/YMP RADIOLOGICAL CONTROL MANUAL

    SciTech Connect

    U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION NEVADA SITE OFFICE; BECHTEL NEVADA

    2004-11-01

    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), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) and the Yucca Mountain Office of Repository Development (YMORD). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations Part 835 (10 CFR 835), Occupational Radiation Protection. Programs covered by this manual are located at the Nevada Test Site (NTS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Pleasanton, California; and at Andrews Air Force Base, Maryland. In addition, field work by NNSA/NSO at other locations is also covered by this manual.

  17. Background report for the formerly utilized Manhattan Engineer District/Atomic Energy Commission sites program

    SciTech Connect

    1980-09-01

    The Department of Energy is conducting a program to determine radiological conditions at sites formerly used by the Army Corps of Engineers' Manhattan Engineer District and the Atomic Energy Commission in the early years of nuclear energy development. Also included in the program are sites used in the Los Alamos plutonium development program and the Trinity atomic bomb test site. Materials, equipment, buildings, and land became contaminated, primarily with naturally occurring radioactive nuclides. They were later decontaminated in accordance with the standards and survey methods in use at that time. Since then, however, radiological criteria, and proposed guidelines for release of such sites for unrestricted use have become more stringent as research on the effects of low-level radiation has progressed. In addition, records documenting some of these decontamination efforts cannot be found, and the final radiological conditions of the sites could not be adequately determined from the records. As a result, the Formerly Utilized Sites Program was initiated in 1974 to identify these formerly used sites and to reevaluate their radiological status. This report covers efforts through June 1980 to determine the radiological status of sites for which the existing conditions could not be clearly defined. Principal contractor facilities and associated properties have already been identified and activities are continuing to identify additional sites. Any new sites located will probably be subcontractor facilities and areas used for disposal of contractor waste or equipment; however, only limited information regarding this equipment and material has been collected to date. As additional information becomes available, supplemental reports will be published.

  18. Radiological Control Technical Position, Regarding Use of Social Security

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Numbers in Dose Reports | Department of Energy Radiological Control Technical Position, Regarding Use of Social Security Numbers in Dose Reports Radiological Control Technical Position, Regarding Use of Social Security Numbers in Dose Reports August 12,2009 When Federal privacy laws were enacted, social security numbers were classified as PII (personally identifiable information). Since most sites used the social security number for identifying workers, it was necessary to give guidance to

  19. Radiological Source Registry and Tracking (RSRT) | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Radiological Source Registry and Tracking (RSRT) Radiological Source Registry and Tracking (RSRT) Department of Energy (DOE) Notice N 234.1 Reporting of Radioactive Sealed Sources has been superseded by DOE Order O 231.1B Environment, Safety and Health Reporting. O 231.1B identifies the requirements for centralized inventory and transaction reporting for radioactive sealed sources. Each DOE site/facility operator that owns, possesses, uses or maintains in custody those accountable radioactive

  20. Real Time Quantitative Radiological Monitoring Equipment for Environmental Assessment

    SciTech Connect

    John R. Giles; Lyle G. Roybal; Michael V. Carpenter

    2006-03-01

    The Idaho National Laboratory (INL) has developed a suite of systems that rapidly scan, analyze, and characterize radiological contamination in soil. These systems have been successfully deployed at several Department of Energy (DOE) laboratories and Cold War Legacy closure sites. Traditionally, these systems have been used during the characterization and remediation of radiologically contaminated soils and surfaces; however, subsequent to the terrorist attacks of September 11, 2001, the applications of these systems have expanded to include homeland security operations for first response, continuing assessment and verification of cleanup activities in the event of the detonation of a radiological dispersal device. The core system components are a detector, a spectral analyzer, and a global positioning system (GPS). The system is computer controlled by menu-driven, user-friendly custom software designed for a technician-level operator. A wide variety of detectors have been used including several configurations of sodium iodide (NaI) and high-purity germanium (HPGe) detectors, and a large area proportional counter designed for the detection of x-rays from actinides such as Am-241 and Pu-238. Systems have been deployed from several platforms including a small all-terrain vehicle (ATV), hand-pushed carts, a backpack mounted unit, and an excavator mounted unit used where personnel safety considerations are paramount. The INL has advanced this concept, and expanded the system functionality to create an integrated, field-deployed analytical system through the use of tailored analysis and operations software. Customized, site specific software is assembled from a supporting toolbox of algorithms that streamline the data acquisition, analysis and reporting process. These algorithms include region specific spectral stripping, automated energy calibration, background subtraction, activity calculations based on measured detector efficiencies, and on-line data quality checks

  1. Final Report Independent Verification Survey of the High Flux Beam Reactor, Building 802 Fan House Brookhaven National Laboratory Upton, New York

    SciTech Connect

    Harpeneau, Evan M.

    2011-06-24

    On May 9, 2011, ORISE conducted verification survey activities including scans, sampling, and the collection of smears of the remaining soils and off-gas pipe associated with the 802 Fan House within the HFBR (High Flux Beam Reactor) Complex at BNL. ORISE is of the opinion, based on independent scan and sample results obtained during verification activities at the HFBR 802 Fan House, that the FSS (final status survey) unit meets the applicable site cleanup objectives established for as left radiological conditions.

  2. CLOSURE REPORT FOR CORRECTIVE ACTION UNIT 115: AREA 25 TEST CELL A FACILITY, NEVADA TEST SITE, NEVADA

    SciTech Connect

    NA

    2006-03-01

    This Closure Report (CR) describes the activities performed to close CAU 115, Area 25 Test Cell A Facility, as presented in the NDEP-approved SAFER Plan (NNSA/NSO, 2004). The SAFER Plan includes a summary of the site history, process knowledge, and closure standards. This CR provides a summary of the completed closure activities, documentation of waste disposal, and analytical and radiological data to confirm that the remediation goals were met and to document final site conditions. The approved closure alternative as presented in the SAFER Plan for CAU 115 (NNSA/NSO, 2004) was clean closure; however, closure in place was implemented under a Record of Technical Change (ROTC) to the SAFER Plan when radiological surveys indicated that the concrete reactor pad was radiologically activated and could not be decontaminated to meet free release levels. The ROTC is included as Appendix G of this report. The objectives of closure were to remove any trapped residual liquids and gases, dispose regulated and hazardous waste, decontaminate removable radiological contamination, demolish and dispose aboveground structures, remove the dewar as a best management practice (BMP), and characterize and restrict access to all remaining radiological contamination. Radiological contaminants of concern (COCs) included cobalt-60, cesium-137, strontium-90, uranium-234/235/236/238, and plutonium-239/240. Additional COCs included Resource Conservation and Recovery Act (RCRA) metals, polychlorinated biphenyls (PCBs), and asbestos.

  3. Accident Investigation Report- Radiological Release

    Office of Energy Efficiency and Renewable Energy (EERE)

    On February 14, 2014, an airborne radiological release occurred at the Department of Energy Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. Because access to the underground was restricted following the event, the investigation was broken into two phases. The Phase 1 report focused on how the radiological material was released into the atmosphere and Phase 2, performed once limited access to the underground was re‐established, focused on the source of the released radiological material.

  4. Federal Radiological Monitoring and Assessment Center (FRMAC) overview of FRMAC operations

    SciTech Connect

    1996-02-01

    In the event of a major radiological emergency, 17 federal agencies with various statutory responsibilities have agreed to coordinate their efforts at the emergency scene under the umbrella of the Federal Radiological Emergency Response plan (FRERP). This cooperative effort will assure the designated Lead Federal Agency (LFA) and the state(s) that all federal radiological assistance fully supports their efforts to protect the public. The mandated federal cooperation ensures that each agency can obtain the data critical to its specific responsibilities. This Overview of the Federal Radiological Monitoring and Assessment Center (FRMAC) Operations describes the FRMAC response activities to a major radiological emergency. It also describes the federal assets and subsequent operational activities which provide federal radiological monitoring and assessment of the off-site areas. These off-site areas may include one or more affected states.

  5. Smart Radiological Dosimeter

    DOEpatents

    Kosslow, William J.; Bandzuch, Gregory S.

    2004-07-20

    A radiation dosimeter providing an indication of the dose of radiation to which the radiation sensor has been exposed. The dosimeter contains features enabling the monitoring and evaluating of radiological risks so that a user can concentrate on the task at hand. The dosimeter provides an audible alarm indication that a predetermined time period has elapsed, an audible alarm indication reminding the user to check the dosimeter indication periodically, an audible alarm indicating that a predetermined accumulated dose has been prematurely reached, and an audible alarm indication prior or to reaching the 3/4 scale point.

  6. CONFIRMATORY SURVEY RESULTS FOR PORTIONS OF THE ABB COMBUSTION ENGINEERING SITE IN WINDSOR, CONNECTICUT DURING THE FALL OF 2011

    SciTech Connect

    Wade C. Adams

    2011-12-09

    From the mid-1950s until mid-2000, the Combustion Engineering, Inc. (CE) site in Windsor, Connecticut (Figure A-1) was involved in the research, development, engineering, production, and servicing of nuclear fuels, systems, and services. The site is currently undergoing decommissioning that will lead to license termination and unrestricted release in accordance with the requirements of the License Termination Rule in 10 CFR Part 20, Subpart E. Asea Brown Boveri Incorporated (ABB) has been decommissioning the CE site since 2001.

  7. Radiological Security Partnership | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) Programs / Nonproliferation / Global Material Security / Radiological Security Radiological Security Partnership Radiological Security Partnership Secure Your Business, Your Community, and Your Country. Sign Up Today for Services Provided by the Radiological Security Partnership. RSP Logo Initiative of the Global Material Security Program Formerly the Global Threat Reduction Initiative RSP Registration RSP More Info Learn More Radiological Security Partnership

  8. HEALTH AND SAFETY RESEARCH DIVISION REPORT OF INCLUSION SURVEY...

    Office of Legacy Management (LM)

    An inclusion radiological survey of location CA00401 was conducted on Sep- tember 27, 1985 by Oak Ridge National Laboratory. This property, located at Mayer Street, is classified ...

  9. Preliminary Notice of Violation, Rocky Flats Environmental Technology Site- EA-96-05

    Energy.gov [DOE]

    Preliminary Notice of Violation issued to Safe Sites of Colorado related to Radiological and Work Control Deficiencies associated with Two Radiological Release Events at the Rocky Flats Environmental Technology Site, (EA-96-05)

  10. Radiological Worker Computer Based Training

    Energy Science and Technology Software Center

    2003-02-06

    Argonne National Laboratory has developed an interactive computer based training (CBT) version of the standardized DOE Radiological Worker training program. This CD-ROM based program utilizes graphics, animation, photographs, sound and video to train users in ten topical areas: radiological fundamentals, biological effects, dose limits, ALARA, personnel monitoring, controls and postings, emergency response, contamination controls, high radiation areas, and lessons learned.

  11. FORMERLY UTILIZED SITES REUEDIAL ACTION PROGRAM ELIMINATION REPORT

    Office of Legacy Management (LM)

    Office of Environmental Restoration and Waste Management Office of Environmental ... U.S. Department of Energy, "Radiological Survey of the M iddlesex Municipal Landfill, M ...

  12. Handling and Packaging a Potentially Radiologically Contaminated...

    Office of Environmental Management (EM)

    Handling and Packaging a Potentially Radiologically Contaminated Patient Handling and Packaging a Potentially Radiologically Contaminated Patient The purpose of this procedure is...

  13. Nuclear Radiological Threat Task Force Established | National...

    National Nuclear Security Administration (NNSA)

    Nuclear Radiological Threat Task Force Established Washington, DC NNSA's Administrator Linton Brooks announces the establishment of the Nuclear Radiological Threat Reduction Task ...

  14. ORISE Resources: Radiological and Nuclear Terrorism: Medical...

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    to mass casualties that may involve radiological injuries. The interactive, two-hour training, titled Radiological and Nuclear Terrorism: Medical Response to Mass Casualties...

  15. PIA - Radiological Work Permit | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    PIA - Radiological Work Permit PDF icon PIA - Radiological Work Permit More Documents & Publications PIA - Bonneville Power Adminstration Ethics Helpline Occupational Medical ...

  16. radiological consquence management | National Nuclear Security...

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Apply for Our Jobs Our Jobs Working at NNSA Blog Home radiological consquence management radiological consquence management Fukushima: Five Years Later After the March 11, 2011, ...

  17. radiological response | National Nuclear Security Administration

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Apply for Our Jobs Our Jobs Working at NNSA Blog Home radiological response radiological response Fukushima: Five Years Later After the March 11, 2011, Japan earthquake, tsunami, ...

  18. 2011 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect

    Mike Lewis

    2012-02-01

    This report summarizes radiological monitoring performed of the Idaho National Laboratory Site's Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  19. Radiological Dose Calculations for Fusion Facilities

    SciTech Connect

    Michael L. Abbott; Lee C. Cadwallader; David A. Petti

    2003-04-01

    This report summarizes the results and rationale for radiological dose calculations for the maximally exposed individual during fusion accident conditions. Early doses per unit activity (Sieverts per TeraBecquerel) are given for 535 magnetic fusion isotopes of interest for several release scenarios. These data can be used for accident assessment calculations to determine if the accident consequences exceed Nuclear Regulatory Commission and Department of Energy evaluation guides. A generalized yearly dose estimate for routine releases, based on 1 Terabecquerel unit releases per radionuclide, has also been performed using averaged site parameters and assumed populations. These routine release data are useful for assessing designs against US Environmental Protection Agency yearly release limits.

  20. Remedial action at the Acid/Pueblo Canyon site, Los Alamos, New Mexico. Final report

    SciTech Connect

    1984-10-01

    The Acid/Pueblo Canyon site (TA-45) was designated in 1976 for remedial action under the Formerly Utilized Sites Remedial Action Program (FUSRAP). During the period 1943 to 1964 untreated and treated liquid wastes generated by nuclear weapons research activities at the Los Alamos Scientific Laboratory (LASL) were discharged into the two canyons. A survey of the site conducted by LASL in 1976 to 1977 identified two areas where radiological contamination exceeded criteria levels. The selected remedial action was based on extensive radiological characterization and comprehensive engineering assessments and comprised the excavation and disposal of 390 yd/sup 3/ of contaminated soil and rock. This document describes the background to the remedial action, the parties involved in administering and executing it, the chronology of the work, verification of the adequacy of the remedial action, and the cost incurred. 14 references, 5 figures, 5 tables.

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

    SciTech Connect

    NSTec Environmental Restoration

    2012-07-17

    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

  2. RADRELAY RADIOLOGICAL DATA LINK DEVICE

    SciTech Connect

    Harpring, L; Frank Heckendorn, F

    2007-11-06

    The RadRelay effort developed small, field appropriate, portable prototype devices that allow radiological spectra to be downloaded from field radiological detectors, like the identiFINDER-U, and transmitted to land based experts. This communications capability was designed for the U. S. Coast Guard (USCG) but is also applicable to the Customs and Border Protection (CBP) personnel working in remote locations. USCG Level II personnel currently use the identiFINDER-U Hand-Held Radioisotope ID Devices (HHRIID) to detect radiological materials during specific boarding operations. These devices will detect not only radiological emissions but will also evaluate those emissions against a table of known radiological spectra. The RadRelay has been developed to significantly improve the functionality of HHRIID, by providing the capability to download radiological spectra and then transmit them using satellite or cell phone technology. This remote wireless data transfer reduces the current lengthy delay often encountered between the shipboard detection of unknown radiological material and the evaluation of that data by technical and command personnel. That delay is reduced from hours to minutes and allows the field located personnel to remain on station during the inspection and evaluation process.

  3. INDEPENDENT CONFIRMATORY SURVEY OF THE NUCLEAR RESEARCH LABORATORY AT THE UNIVERSITY OF ILLINOIS URBANA-CHAMPAIGN, ILLINOIS

    SciTech Connect

    EVAN M. HARPENAU

    2012-06-28

    ORAU conducted confirmatory survey activities within the NRL at the University during the week of May 7, 2012. The survey activities included visual inspections/ assessments, surface activity measurements, and volumetric concrete sampling activities. During the course of the confirmatory activities, ORAU noted several issues with the survey-for-release activities performed at the University. Issues included inconsistencies with: survey unit classifications were not designated according to Multi-Agency Radiation Survey and Site Investigation Manual guidance; survey instrument calibrations were not representative of the radionuclides of concern; calculations for instrumentation detection capabilities did not align with the release criteria discussed in the licensee’s survey guidance documents; total surface activity measurements were in excess of the release criteria; and Co-60 and Eu-152 concentrations in the confirmatory concrete samples were above their respective guidelines. Based on the significant programmatic issues identified, ORAU cannot independently conclude that the NRL satisfied the requirements and limits for release of materials without radiological restrictions.

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

    SciTech Connect

    Smedes, H.W.

    1983-04-01

    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.

  5. Operation Cornerstone onsite radiological safety report for announced nuclear tests, October 1988--September 1989

    SciTech Connect

    Not Available

    1990-08-01

    Cornerstone was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site (NTS) from October 1, 1988, through September 30, 1989. This report includes those experiments publicly announced. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Radiation Protection Technicians (RPT) with portable radiation detection instruments surveyed reentry routes into ground zeros (GZ) before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage were provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined.

  6. Estimate Radiological Dose for Animals

    Energy Science and Technology Software Center

    1997-12-18

    Estimate Radiological dose for animals in ecological environment using open literature values for parameters such as body weight, plant and soil ingestion rate, rad. halflife, absorbed energy, biological halflife, gamma energy per decay, soil-to-plant transfer factor, ...etc

  7. Radiological Training for Tritium Facilities

    Energy Saver

    ... by Title 10 Code of Federal Regulations Occupational Radiation Protection, (10 CFR 835) Subpart J and as outlined in the DOE standard DOE-STD-1098-99, Radiological Control (RCS). ...

  8. Radiological cleanup of Enewetak Atoll

    SciTech Connect

    Not Available

    1981-01-01

    For 8 years, from 1972 until 1980, the United States planned and carried out the radiological cleanup, rehabilitation, and resettlement of Enewetak Atoll in the Marshall Islands. This documentary records, from the perspective of DOD, the background, decisions, actions, and results of this major national and international effort. The documentary is designed: First, to provide a historical document which records with accuracy this major event in the history of Enewetak Atoll, the Marshall Islands, the Trust Territory of the Pacific Islands, Micronesia, the Pacific Basin, and the United States. Second, to provide a definitive record of the radiological contamination of the Atoll. Third, to provide a detailed record of the radiological exposure of the cleanup forces themselves. Fourth, to provide a useful guide for subsequent radiological cleanup efforts elsewhere.

  9. Radiological Monitoring Continues at WIPP

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Radiological Monitoring Continues at WIPP CARLSBAD, N.M., February 19, 2014 - Radiological control personnel continue to collect surface and underground monitoring samples at the U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) after an underground air monitor detected airborne radiation around 11:30 p.m. (MT) on February 14. Recent laboratory analyses by Carlsbad Environmental Monitoring and Research Center (CEMRC) found some trace amounts of americium and plutonium from a

  10. Radiological training for tritium facilities

    SciTech Connect

    1996-12-01

    This program management guide describes a recommended implementation standard for core training as outlined in the DOE Radiological Control Manual (RCM). The standard is to assist those individuals, both within DOE and Managing and Operating contractors, identified as having responsibility for implementing the core training recommended by the RCM. This training may also be given to radiological workers using tritium to assist in meeting their job specific training requirements of 10 CFR 835.

  11. ORISE: Radiological program assessment services

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Radiological program assessment services Minimizing the risk of human exposure to hazardous levels of radioactive materials requires designing a comprehensive safety program that ensures appropriate measures are taken to protect workers and the public. As a U.S. Department of Energy (DOE) institute, the Oak Ridge Institute for Science and Education (ORISE) understands the importance of having an effective safety program in place to assure stakeholders and regulators that your radiological

  12. Radiological Protection for DOE Activities

    Directives, Delegations, and Other Requirements [Office of Management (MA)]

    1995-09-29

    Establishes radiological protection program requirements that, combined with 10 CFR 835 and its associated implementation guidance, form the basis for a comprehensive program for protection of individuals from the hazards of ionizing radiation in controlled areas. Extended by DOE N 441.3. Cancels DOE 5480.11, DOE 5480.15, DOE N 5400.13, DOE N 5480.11; please note: the DOE radiological control manual (DOE/EH-0256T)

  13. Supplementary radiological and beryllium characterization of the facility at 425 Peek Street, Schenectady, New York

    SciTech Connect

    Foley, R.D.; Allred, J.F.; Carrier, R.F.

    1994-10-01

    At the request of the Office of Naval Reactors through the Office of Remedial Action and Waste Technology, a radiological survey of the Peek Street industrial facility, the adjacent state-owned bike path, and two nearby residential properties was conducted by Oak Ridge National Laboratory (ORNL) in November 1989. The results indicated small isolated areas that exceeded DOE guidelines. These areas totaled approximately 0.2 m{sup 2} of floor area and approximately 3 m{sup 2} of wall area inside the building, and two small areas totaling approximately 5 m{sup 2} outside the building. A small section of one of these areas extended beyond the fence on the east side of the industrial property onto the state-owned property. No residual radioactive material or elevated radiation levels were detected on any portion of the paved section of the bike path or the residential properties adjacent to the site. Because the elevated radiation levels were localized and limited in extent, any credible use scenario, including current use conditions, indicated that no significant radiation exposures would accrue to individuals frequenting the area. Samples were also analyzed for elemental beryllium since that material had formerly been used at the site. In conjunction with the planned remediation at the facility, a supplementary characterization survey was performed to further define the areas containing beryllium in excess of the identified guidelines. Additional radiological characterization of Ra-226, Th-232, and U-238 was also performed in areas that were largely inaccessible prior to the remediation efforts.

  14. DOEIEV-0005/33 ANL-OHS/HP-82-104 FORMERLY UTILIZED MED/AEC SITES

    Office of Legacy Management (LM)

    DOEIEV-0005/33 ANL-OHS/HP-82-104 FORMERLY UTILIZED MED/AEC SITES REMEDIAL ACTION PROGRAM RADIOLOGICAL SURVEY OF UNIVERSAL CYCLOPS, INC. TITUSVILLE PLANT (Formerly Vulcan Crucible Steel Company) ALIQUIPPA, PENNSYLVANIA May 2-8, 1978 OCCUPATIONAL HEALTH AND SAFETY DIVISION Health Physics Section ARGONNE NATIONAL LABORATORY, ARGONNE, ILLINOIS Prepared for the U. S. DEPARTMENT OF ENERGY under Contract W-31 -109.Eng-38 The facilities of Argonne National Laboratory are owned by the United States

  15. Radiological assessments for the National Ignition Facility

    SciTech Connect

    Hong, Kou-John; Lazaro, M.A.

    1996-08-01

    The potential radiological impacts of the National Ignition Facility (NIF), a proposed facility for fusion ignition and high energy density experiments, were assessed for five candidate sites to assist in site selection. The GENII computer program was used to model releases of radionuclides during normal NIF operations and a postulated accident and to calculate radiation doses to the public. Health risks were estimated by converting the estimated doses into health effects using a standard cancer fatality risk factor. The greatest calculated radiation dose was less than one thousandth of a percent of the dose received from natural background radiation; no cancer fatalities would be expected to occur in the public as the result of normal operations. The highest dose conservatively estimated to result from a postulated accident could lead to one in one million risk of cancer.

  16. LITERATURE SURVEY FOR GROUNDWATER TREATMENT OPTIONS FOR NITRATE IODINE-129 AND URANIUM 200-ZP-1 OPERABLE UNIT HANFORD SITE

    SciTech Connect

    BYRNES ME

    2008-06-05

    This literature review presents treatment options for nitrate, iodine-129, and uranium, which are present in groundwater at the 200-ZP-I Groundwater Operable Unit (OU) within the 200 West Area of the Hanford Site. The objective of this review is to determine available methods to treat or sequester these contaminants in place (i.e., in situ) or to pump-and-treat the groundwater aboveground (i.e., ex situ). This review has been conducted with emphasis on commercially available or field-tested technologies, but theoretical studies have, in some cases, been considered when no published field data exist. The initial scope of this literature review included only nitrate and iodine-I 29, but it was later expanded to include uranium. The focus of the literature review was weighted toward researching methods for treatment of nitrate and iodine-129 over uranium because of the relatively greater impact of those compounds identified at the 200-ZP-I OU.

  17. MONTHLY RADIATION SURVEY TECHNICAL BASIS

    SciTech Connect

    BROWN, R.L.

    2003-06-13

    This document details the technical basis, analysis, and justification for rescheduling radiation surveys in occupied radiation areas within Tank Farm Facilities from a weekly to a monthly frequency. The purpose of this document is to provide the technical basis, analysis, and justification for seeking a technical equivalency determination (TED) to TFRCM Article 552.1.b. The scope of this document limited to radiation surveys in occupied areas, no equivalency is being sought for high radiation area boundary surveys, radiological buffer area surveys, active ventilations surveys, or work coverage surveys.

  18. Radiological assessment. A textbook on environmental dose analysis

    SciTech Connect

    Till, J.E.; Meyer, H.R.

    1983-09-01

    Radiological assessment is the quantitative process of estimating the consequences to humans resulting from the release of radionuclides to the biosphere. It is a multidisciplinary subject requiring the expertise of a number of individuals in order to predict source terms, describe environmental transport, calculate internal and external dose, and extrapolate dose to health effects. Up to this time there has been available no comprehensive book describing, on a uniform and comprehensive level, the techniques and models used in radiological assessment. Radiological Assessment is based on material presented at the 1980 Health Physics Society Summer School held in Seattle, Washington. The material has been expanded and edited to make it comprehensive in scope and useful as a text. Topics covered include (1) source terms for nuclear facilities and Medical and Industrial sites; (2) transport of radionuclides in the atmosphere; (3) transport of radionuclides in surface waters; (4) transport of radionuclides in groundwater; (5) terrestrial and aquatic food chain pathways; (6) reference man; a system for internal dose calculations; (7) internal dosimetry; (8) external dosimetry; (9) models for special-case radionuclides; (10) calculation of health effects in irradiated populations; (11) evaluation of uncertainties in environmental radiological assessment models; (12) regulatory standards for environmental releases of radionuclides; (13) development of computer codes for radiological assessment; and (14) assessment of accidental releases of radionuclides.

  19. Federal Radiological Monitoring and Assessment Center Analytical Response

    SciTech Connect

    E.C. Nielsen

    2003-04-01

    The Federal Radiological Monitoring and Assessment Center (FRMAC) is authorized by the Federal Radiological Emergency Response Plan to coordinate all off-site radiological response assistance to state and local government s, in the event of a major radiological emergency in the United States. The FRMAC is established by the U.S. Department of Energy, National Nuclear Security Administration, to coordinate all Federal assets involved in conducting a comprehensive program of radiological environmental monitoring, sampling, radioanalysis, quality assurance, and dose assessment. During an emergency response, the initial analytical data is provided by portable field instrumentation. As incident responders scale up their response based on the seriousness of the incident, local analytical assets and mobile laboratories add additional capability and capacity. During the intermediate phase of the response, data quality objectives and measurement quality objectives are more rigorous. These higher objectives will require the use of larger laboratories, with greater capacity and enhanced capabilities. These labs may be geographically distant from the incident, which will increase sample management challenges. This paper addresses emergency radioanalytical capability and capacity and its utilization during FRMAC operations.

  20. A survey of cavity-nesting bees and wasps in loblolly pine stands of the Savannah River Site, Aiken County, South Carolina.

    SciTech Connect

    Horn, S.; Hanula, J., L.

    2004-03-10

    Horn, Scott, and James L. Hanula. 2004. A survey of cavity-nesting bees and wasps in loblolly pine stands of the Savannah River Site, Aiken County, South Carolina. 39(3): 464-469. Abstract: In recent years concern over widespread losses in biodiversity has grown to include a possible decline of many native pollinators, primarily bees. Factors such as habitat fragmentation, agricultural practices, use of pesticides, the introduction of invasive species, or changes in land use may negatively impact these vital organisims. Most reported studies show that human impacts on pollinators are overwhelmingly negative. Reductions in pollinator populations may profoundly impact plant population dynamics and ecosystem function. Little baseline data exists on the diversity and relative abundance of bees and wasps in southern forests. The objective of this study was to develop a simple, effective method of surveying cavity-nesting bees and wasps and to determine species diversity in mature forests of loblolly pine, the most widely planted tree species in the southern United States.

  1. How to deal with radiologically contaminated vegetation

    SciTech Connect

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

    1996-12-31

    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.

  2. WIPP Radiological Relase Report Phase 2

    Office of Environmental Management (EM)

    Department of Energy Office of Environmental Management Accident Investigation Report Phase 2 Radiological Release Event at the Waste Isolation Pilot Plant, February 14, 2014 April 2015 Radiological Release Event at the Waste Isolation Pilot Plant Radiological Release Event at the Waste Isolation Pilot Plant Disclaimer On February 14, 2014, an airborne radiological release occurred at the Department of Energy Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. On March 4, 2014, an

  3. Operational Guidelines/Radiological Emergency Response

    Energy.gov [DOE]

    Operational Guidelines/Radiological Emergency Response. Provides information and resources concerning the development of Operational Guidelines as part of planning guidance for protection and recovery following Radiological Dispersal Device (RDD) and/or Improvised Nuclear Device (IND) incidents. Operational Guidelines Technical (OGT) Manual, 2009 RESRAD-RDD Complementing Software to OGT Manual EPA Protective Action Guidelines (2013), Interim Final Federal Radiological Monitoring and Assessment Center (FRMAC) Federal Radiological Preparedness Coordinating Committee (FRPCC)

  4. Radiological Assistance Program | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    | (NNSA) Radiological Assistance Program RAP Logo NNSA's Radiological Assistance Program (RAP) is the nation's premier first-response resource in assessing an emergency situation and advising decision-makers on further steps to take to evaluate and minimize the hazards of a radiological incident. RAP provides resources (trained personnel and equipment) to evaluate, assess, advise, isotopically identify, search for, and assist in the mitigation of actual or perceived nuclear or radiological

  5. Nuclear & Radiological Material Removal | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    & Radiological Material Removal | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation...

  6. International Data on Radiological Sources

    SciTech Connect

    Martha Finck; Margaret Goldberg

    2010-07-01

    ABSTRACT The mission of radiological dispersal device (RDD) nuclear forensics is to identify the provenance of nuclear and radiological materials used in RDDs and to aid law enforcement in tracking nuclear materials and routes. The application of databases to radiological forensics is to match RDD source material to a source model in the database, provide guidance regarding a possible second device, and aid the FBI by providing a short list of manufacturers and distributors, and ultimately to the last legal owner of the source. The Argonne/Idaho National Laboratory RDD attribution database is a powerful technical tool in radiological forensics. The database (1267 unique vendors) includes all sealed sources and a device registered in the U.S., is complemented by data from the IAEA Catalogue, and is supported by rigorous in-lab characterization of selected sealed sources regarding physical form, radiochemical composition, and age-dating profiles. Close working relationships with global partners in the commercial sealed sources industry provide invaluable technical information and expertise in the development of signature profiles. These profiles are critical to the down-selection of potential candidates in either pre- or post- event RDD attribution. The down-selection process includes a match between an interdicted (or detonated) source and a model in the database linked to one or more manufacturers and distributors.

  7. Departmental Radiological Emergency Response Assets

    Directives, Delegations, and Other Requirements [Office of Management (MA)]

    2007-06-27

    The order establishes requirements and responsibilities for the DOE/NNSA national radiological emergency response assets and capabilities and Nuclear Emergency Support Team assets. Supersedes DOE O 5530.1A, DOE O 5530.2, DOE O 5530.3, DOE O 5530.4, and DOE O 5530.5.

  8. radiological | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    radiological NNSA program strengthens national security from afar The Nuclear Smuggling Detection and Deterrence (NSDD) program is a key component of NNSA's core mission to reduce nuclear threats. The program, part of NNSA's Office of Defense Nuclear Nonproliferation, provides partners tools and training to deter, detect, and investigate smuggling of

  9. Radiological Security Partnership Information | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) About / Our Programs / Nonproliferation / Global Material Security / Radiological Security / Radiological Security Partnership Radiological Security Partnership Information Radioactive sources play an important role in a number of commercial, medical, and research facilities. The benefits of these sources must be balanced with proper security. The Department of Energy's (DOE) National Nuclear Security Administration (NNSA) is working with the Nuclear Regulatory

  10. TEPP Training - Modular Emergency Response Radiological Transportation

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Training (MERRTT) | Department of Energy Training - Modular Emergency Response Radiological Transportation Training (MERRTT) TEPP Training - Modular Emergency Response Radiological Transportation Training (MERRTT) Once the jurisdiction has completed an evaluation of their plans and procedures, they will need to address any gaps in training. To assist, TEPP has developed the Modular Emergency Response Radiological Transportation Training (MERRTT) program. MERRTT provides fundamental knowledge

  11. Model Recovery Procedure for Response to a Radiological Transportation...

    Office of Environmental Management (EM)

    for Response to a Radiological Transportation Incident Model Recovery Procedure for Response to a Radiological Transportation Incident This Transportation Emergency...

  12. Corrective Action Investigation Plan for Corrective Action Unit 137: Waste Disposal Sites, Nevada Test Site, Nevada, Rev. No.:0

    SciTech Connect

    Wickline, Alfred

    2005-12-01

    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

  13. Mobile autonomous robotic apparatus for radiologic characterization

    DOEpatents

    Dudar, Aed M.; Ward, Clyde R.; Jones, Joel D.; Mallet, William R.; Harpring, Larry J.; Collins, Montenius X.; Anderson, Erin K.

    1999-01-01

    A mobile robotic system that conducts radiological surveys to map alpha, beta, and gamma radiation on surfaces in relatively level open areas or areas containing obstacles such as stored containers or hallways, equipment, walls and support columns. The invention incorporates improved radiation monitoring methods using multiple scintillation detectors, the use of laser scanners for maneuvering in open areas, ultrasound pulse generators and receptors for collision avoidance in limited space areas or hallways, methods to trigger visible alarms when radiation is detected, and methods to transmit location data for real-time reporting and mapping of radiation locations on computer monitors at a host station. A multitude of high performance scintillation detectors detect radiation while the on-board system controls the direction and speed of the robot due to pre-programmed paths. The operators may revise the preselected movements of the robotic system by ethernet communications to remonitor areas of radiation or to avoid walls, columns, equipment, or containers. The robotic system is capable of floor survey speeds of from 1/2-inch per second up to about 30 inches per second, while the on-board processor collects, stores, and transmits information for real-time mapping of radiation intensity and the locations of the radiation for real-time display on computer monitors at a central command console.

  14. Mobile autonomous robotic apparatus for radiologic characterization

    DOEpatents

    Dudar, A.M.; Ward, C.R.; Jones, J.D.; Mallet, W.R.; Harpring, L.J.; Collins, M.X.; Anderson, E.K.

    1999-08-10

    A mobile robotic system is described that conducts radiological surveys to map alpha, beta, and gamma radiation on surfaces in relatively level open areas or areas containing obstacles such as stored containers or hallways, equipment, walls and support columns. The invention incorporates improved radiation monitoring methods using multiple scintillation detectors, the use of laser scanners for maneuvering in open areas, ultrasound pulse generators and receptors for collision avoidance in limited space areas or hallways, methods to trigger visible alarms when radiation is detected, and methods to transmit location data for real-time reporting and mapping of radiation locations on computer monitors at a host station. A multitude of high performance scintillation detectors detect radiation while the on-board system controls the direction and speed of the robot due to pre-programmed paths. The operators may revise the preselected movements of the robotic system by ethernet communications to remonitor areas of radiation or to avoid walls, columns, equipment, or containers. The robotic system is capable of floor survey speeds of from 1/2-inch per second up to about 30 inches per second, while the on-board processor collects, stores, and transmits information for real-time mapping of radiation intensity and the locations of the radiation for real-time display on computer monitors at a central command console. 4 figs.

  15. Verification survey report of the south waste tank farm training/test tower and hazardous waste storage lockers at the West Valley demonstration project, West Valley, New York

    SciTech Connect

    Weaver, Phyllis C.

    2012-08-29

    A team from ORAU's Independent Environmental Assessment and Verification Program performed verification survey activities on the South Test Tower and four Hazardous Waste Storage Lockers. Scan data collected by ORAU determined that both the alpha and alpha-plus-beta activity was representative of radiological background conditions. The count rate distribution showed no outliers that would be indicative of alpha or alpha-plus-beta count rates in excess of background. It is the opinion of ORAU that independent verification data collected support the site?s conclusions that the South Tower and Lockers sufficiently meet the site criteria for release to recycle and reuse.

  16. Good Practices for Ocupational Radiological Protection in Plutonium Facilities

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Not Measurement Sensitive DOE- STD-1128-2013 April 2013 DOE STANDARD GOOD PRACTICES FOR OCCUPATIONAL RADIOLOGICAL PROTECTION IN PLUTONIUM FACILITIES U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1128-2013 This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ ii DOE-STD-1128-2013 Foreword This Technical

  17. Radiological characterization of a vitrification facility for decommissioning

    SciTech Connect

    Asou, M. [CEA/DEN/VALRHO/UMODD, 30207 Bagnols-sur-Ceze Cedex (France); Le Goaller, C. [CEA/DEN/VALRHO/DDCO, 30207 Bagnols-sur-Ceze Cedex (France); Martin, F. [AREVA NC DAP/MOP (France)

    2007-07-01

    Cleanup operations in the Marcoule Vitrification Facility (AVM) will start in 2007. This plant includes 20 highly irradiating storage tanks for high-level liquid waste before vitrification. The objective of the cleanup phase is to significantly decrease the amount of highly radioactive waste resulting from dismantling. A comprehensive radiological survey of the plant was initiated in 2000. Most of the tanks were characterized using advanced technologies: gamma imaging, CdZnTe gamma spectroscopy, dose rate measurements and 3D calculations codes. At the same time, inspections were conducted to develop 3D geometrical models of the tanks. The techniques used and the main results obtained are described as well as lessons learned from these operations. The rinsing program was defined in 2006. Decontamination operations are expected to begin in 2007, and radiological surveys will be followed up to monitor the efficiency of the decontamination process. Specific rinsing of all tanks and equipment will be carried out from 2007 to 2009. Concentrated liquid solutions will be vitrified between 2008 and 2010; the decommissioning of AVM will be delayed until the end of 2010. This strategy aims at producing less than 5% 'B' type (long-lived intermediate-level) waste from the decommissioning operations, as well as reducing the dose rate and risks by simplified remote dismantling. The paper reviews the main options selected for decontamination, as well as the radiological characterization strategy. Some cost-related aspects will also be analyzed. (authors)

  18. Guide of Good Practices for Occupational Radiological Protection in Uranium Facilities

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    36-2009 July 2009 DOE STANDARD GUIDE OF GOOD PRACTICES FOR OCCUPATIONAL RADIOLOGICAL PROTECTION IN URANIUM FACILITIES U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1136-2009 Guide of Good Practices for Occupational Radiological Protection in Uranium Facilities i This document is available on the Department of Energy Technical Standards Program Web Site at

  19. Understanding Mechanisms of Radiological Contamination

    SciTech Connect

    Rick Demmer; John Drake; Ryan James, PhD

    2014-03-01

    Over the last 50 years, the study of radiological contamination and decontamination has expanded significantly. This paper addresses the mechanisms of radiological contamination that have been reported and then discusses which methods have recently been used during performance testing of several different decontamination technologies. About twenty years ago the Idaho Nuclear Technology Engineering Center (INTEC) at the INL began a search for decontamination processes which could minimize secondary waste. In order to test the effectiveness of these decontamination technologies, a new simulated contamination, termed SIMCON, was developed. SIMCON was designed to replicate the types of contamination found on stainless steel, spent fuel processing equipment. Ten years later, the INL began research into methods for simulating urban contamination resulting from a radiological dispersal device (RDD). This work was sponsored by the Defense Advanced Research Projects Agency (DARPA) and included the initial development an aqueous application of contaminant to substrate. Since 2007, research sponsored by the US Environmental Protection Agency (EPA) has advanced that effort and led to the development of a contamination method that simulates particulate fallout from an Improvised Nuclear Device (IND). The IND method diverges from previous efforts to create tenacious contamination by simulating a reproducible “loose” contamination. Examining these different types of contamination (and subsequent decontamination processes), which have included several different radionuclides and substrates, sheds light on contamination processes that occur throughout the nuclear industry and in the urban environment.

  20. Gnome site decontamination and decommissioning project radiation contamination clearance report, March 28, 1979-September 23, 1979

    SciTech Connect

    Berry, H.A.

    1981-08-01

    This report describes the operations and radiological activities conducted during Phase II and Phase III of the Gnome site decontamination and decommissioning (D/D) project in Carlsbad, New Mexico. The onsite radiological monitoring and documentation activities were performed for the Department of Energy, Nevada Operations (DOE/NV) by Reynolds Electrical and Engineering Co., Inc. (REECo) and EG and G, Inc., from March 28, 1979 to September 23, 1979. The monitoring program included soil sampling and analyses, portable instrument area surveys, thermoluminescent dosimeter (TLD) measurements and a post-operational aerial survey to document the final site status and to insure public and occupational health and safety. Although the analysis of data gathered during the final stages of the D/D project will provide the information necessary for DOE to return the Gnome site to the Department of the Interior, Bureau of Land Management (BLM) for unrestricted use of the land surface, there are permanent restrictions on excavation and/or drilling on the site at any depth between the surface and 1500 feet.

  1. Technical basis for radiological release of Grand Junction Office Building 2. Volume 1, dose assessment

    SciTech Connect

    Morris, R.; Warga, J.; Thorne, D.

    1997-07-01

    Building 2 on the US Department of Energy (DOE) Grand Junction Office (GJO) site is part of the GJO Remedial Action Program (GJORAP). During evaluation of Building 2 for determination of radiological release disposition, some inaccessible surface contamination measurements were detected to be greater than the generic surface contamination guidelines of DOE Order 5400.5 (which are functionally equivalent to US Nuclear Regulatory Commission [NRC] Regulatory Guide 1.86). Although the building is nominal in size, it houses the site telecommunications system, that is critical to continued GJO operations, and demolition is estimated at $1.9 million. Because unrestricted release under generic surface contamination guidelines is cost-prohibitive, supplemental standards consistent with DOE Order 5400.5 are being pursued. This report describes measurements and dose analysis modeling efforts to evaluate the radiation dose to members of the public who might occupy or demolish Building 2, a 2,480 square-foot (ft) building constructed in 1944. The north portion of the building was used as a shower facility for Manhattan Project uranium-processing mill workers and the south portion was a warehouse. Many originally exposed surfaces are no longer accessible for contamination surveys because expensive telecommunications equipment have been installed on the floors and mounted on panels covering the walls. These inaccessible surfaces are contaminated above generic contamination limits.

  2. Annual Site Environmental Report for Calendar Years 2005-2006

    SciTech Connect

    Virginia L. Finley

    2010-01-25

    Contained in the following report are data for radioactivity in the environment collected and analyzed by Princeton Plasma Physics Laboratory's Princeton Environmental, Analytical, and Radiological Laboratory (PEARL). The PEARL is located on-site and is certified for analyzing radiological and non-radiological parameters through the New Jersey Department of Environmental Protection's Laboratory Certification Program, Certification Number 12471. Non-radiological surface and ground water samples are analyzed by NJDEP certified subcontractor laboratories - QC, Inc. and Accutest Laboratory. To the best of our knowledge, these data, as contained in the "Annual Site Environmental Report for 2005 and 2006," are documented and certified to be correct.

  3. WIPP Radiological Release Report Phase 1

    Office of Environmental Management (EM)

    U.S. Department of Energy Office of Environmental Management Accident Investigation Report Phase 1 Radiological Release Event at the Waste Isolation Pilot Plant on February 14, 2014 April 2014 Radiological Release Event at the Waste Isolation Pilot Plant Radiological Release Event at the Waste Isolation Pilot Plant Disclaimer Phase 1 of this accident investigation report is an independent product of the Accident Investigation Board appointed by Matthew Moury, Deputy Assistant Secretary, Safety,

  4. Nuclear / Radiological Advisory Team | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) / Radiological Advisory Team NRAT Logo NNSA's Nuclear / Radiological Advisory Team (NRAT) provides an emergency response capability for on-scene scientific and technical advice for both domestic and international nuclear or radiological incidents. It is led by a Senior Energy Official who runs the NNSA field operation and who coordinates NNSA follow-on assets as needed. The NRAT is composed of scientists and technicians who can provide advice or conduct limited

  5. Radiological Security | National Nuclear Security Administration | (NNSA)

    National Nuclear Security Administration (NNSA)

    Global Material Security Radiological Security The program collaborates with domestic and international partners to address the threat of illicit use of high-priority radiological materials in the United States and abroad. The Radiological Security program accomplishes its mission by removing and disposing of excess or orphaned radioactive sources; promoting the replacement of radioactive sources with non-isotopic technologies, where feasible; and increasing security where high-priority

  6. Nation's Radiological Assistance Program teams practice emergency...

    National Nuclear Security Administration (NNSA)

    Home Blog Nation's Radiological Assistance Program teams practice emergency response ... of Department of Energy (DOE)National Nuclear Security Administration (NNSA) nuclear ...

  7. Cardiovascular and Interventional Radiological Society of Europe...

    Office of Scientific and Technical Information (OSTI)

    Cardiovascular and Interventional Radiological Society of Europe Guidelines on Endovascular Treatment in Aortoiliac Arterial Disease Citation Details In-Document Search Title: ...

  8. Radiological Control Programs for Special Tritium Compounds

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    APPROVAL OF CHANGE NOTICE 1 TO DEPARTMENT OF ENERGY (DOE) SUBJECT. HANDBOOK 1184-2004, RADIOLOGICAL CONTROL PROGRAMS FOR SPECIAL TRITIUM COMPOUNDS TO: Dennis Kubicki, EH-24 ...

  9. DOE Issues WIPP Radiological Release Investigation Report

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Management (EM) released the initial accident investigation report related to the ... After the entry teams determine the source of the radiological event, the accident ...

  10. Radiological Assistance Program Flight Planning Tool

    SciTech Connect

    2011-12-19

    The Radiological Assitance Program (RAP) is the National Nuclear Security Administration's (NNSA) first responder to radiological emergencies. RAP's mission is to identify and minimize radiological hazards, as well as provide radiological emergency response and technical advice to decision makers. One tool commonly used is aerial radiation detection equipment. During a response getting this equipment in the right place quickly is critical. The RAP Flight Planning Tool (a ArcGIS 10 Desktop addin) helps minimize this response time and provides specific customizable flight path information to the flight staff including maps, coordinates, and azimuths.

  11. Operating Experience Level 3: Radiologically Contaminated Respirators...

    Energy Saver

    Experience Level 3 provides information on a safety concern related to radiological contamination of launderedreconditioned respirators and parts that have been certified as...

  12. Radiological Contamination Control Training for Laboratory Research

    Energy Saver

    researchers. Course Description: This course illustrates and reinforces the skills and knowledge needed to assist personnel with radiological controls for laboratory research...

  13. Radiological Control - DOE Directives, Delegations, and Requirements

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    98-2008, Change Notice 1, Radiological Control by Diane Johnson The Department of Energy (DOE) has developed this Standard to assist line managers in meeting their responsibilities...

  14. Nuclear / Radiological Advisory Team | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    Nuclear Radiological Advisory Team (NRAT) provides an emergency response capability for on-scene scientific and technical advice for both domestic and international nuclear or ...

  15. Radiological Assistance Program Flight Planning Tool

    Energy Science and Technology Software Center

    2011-12-19

    The Radiological Assitance Program (RAP) is the National Nuclear Security Administration's (NNSA) first responder to radiological emergencies. RAP's mission is to identify and minimize radiological hazards, as well as provide radiological emergency response and technical advice to decision makers. One tool commonly used is aerial radiation detection equipment. During a response getting this equipment in the right place quickly is critical. The RAP Flight Planning Tool (a ArcGIS 10 Desktop addin) helps minimize this responsemore » time and provides specific customizable flight path information to the flight staff including maps, coordinates, and azimuths.« less

  16. Memorandum, Reporting of Radiological Sealed Sources Transactions...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    The requirements for reporting transactions involving radiological sealed sources are identified in Department of Energy (DOE) Notice (N) 234.1, Reporting of Radioactive Sealed ...

  17. Corrective Action Site 02-37-02 Background Information and Comparison to Corrective Action Site 09-99-06

    SciTech Connect

    2012-06-26

    Corrective Action Site (CAS) 02-37-02, Gas Sampling Assembly, is associated with nuclear test MULLET. MULLET was an underground safety test conducted on October 17, 1963. The experiment also involved prompt sampling of particulate material from the detonation, similar to CAS 09-99-06, Gas Sampling Assembly, which is associated with PLAYER/YORK. The sampling system at MULLET was similar to that of PLAYER/YORK and was used to convey gas from the MULLET emplacement hole (U2ag) to a sampling assembly. Beyond the sampling assembly, the system had a 'Y' junction with one branch running to a filter unit and the other running to a scrubber unit. The total system length was approximately 250 feet and is depicted on the attached drawing. According to the available background information, retrieval of the sample material from the MULLET event caused significant alpha (plutonium) contamination, limited to an area near ground zero (GZ). Test support Radiological Control Technicians did not detect contamination outside the immediate GZ area. In addition, vehicles, equipment, and workers that were contaminated were decontaminated on site. Soil contamination was addressed through the application of oil, and the site was decommissioned after the test. Any equipment that could be successfully decontaminated and had a future use was removed from the site. The contaminated equipment and temporary buildings erected to support the test were buried on site, most likely in the area under the dirt berm. The exact location of the buried equipment and temporary buildings is unknown. No information was found describing the disposition of the filter and scrubber, but they are not known to be at the site. The COMMODORE test was conducted at U2am on May 20, 1967, and formed the crater next to CAS 02-37-02. The COMMODORE test area had been surveyed prior to the test, and alpha contamination was not identified. Furthermore, alpha contamination was not identified during the COMMODORE re

  18. Corrective Action Investigation Plan for Corrective Action Unit 104: Area 7 Yucca Flat Atmospheric Test Sites, Nevada National Security Site, Nevada, Revision 0

    SciTech Connect

    Patrick Matthews

    2011-08-01

    of the total effective dose (TED) to the dose-based final action level (FAL). The presence of TED exceeding the FAL is considered a radiological contaminant of concern (COC). Anything identified as a COC will require corrective action. 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 will be used to measure external radiological dose. 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 plume, it was determined that the releases from the nuclear tests are co-located and will be investigated concurrently. A field investigation will be performed to define areas where TED exceeds the FAL and to determine whether other COCs are present at the site. The investigation will also collect information to determine the presence and nature of contamination associated with migration and excavation, as well as any potential releases discovered during the investigation. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS.

  19. Final Report - Independent Confirmatory Survey Summary and Results for the Hematite Decommissioning Project

    SciTech Connect

    E.N. Bailey

    2009-03-18

    The objectives of the confirmatory surveys were to provide independent contractor field data reviews and to generate independent radiological data for use by the NRC in evaluating the adequacy and accuracy of the licensee’s procedures and survey results.

  20. Radioactive Waste Management Complex low-level waste radiological performance assessment

    SciTech Connect

    Maheras, S.J.; Rood, A.S.; Magnuson, S.O.; Sussman, M.E.; Bhatt, R.N.

    1994-04-01

    This report documents the projected radiological dose impacts associated with the disposal of radioactive low-level waste at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. This radiological performance assessment was conducted to evaluate compliance with applicable radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the public and the environment. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses were made for both offsite receptors and individuals inadvertently intruding onto the site after closure. In addition, uncertainty and sensitivity analyses were performed. The results of the analyses indicate compliance with established radiological criteria and provide reasonable assurance that public health and safety will be protected.

  1. Environmental Survey preliminary report

    SciTech Connect

    Not Available

    1988-04-01

    This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Sandia National Laboratories conducted August 17 through September 4, 1987. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with Sandia National Laboratories-Albuquerque (SNLA). The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. This phase of the Survey involves the review of existing site environmental data, observations of the operations carried on at SNLA, and interviews with site personnel. 85 refs., 49 figs., 48 tabs.

  2. ANL=OHS/HP=83=102 FORMERLY UTILIZED MEDIAEC SITES REMEDIAL ACTION PROGRAM

    Office of Legacy Management (LM)

    ' DO E/EV=0005/40 ANL=OHS/HP=83=102 FORMERLY UTILIZED MEDIAEC SITES REMEDIAL ACTION PROGRAM RADIOLOGICAL SURVEY OF THE ALBANY METALLURGICAL RESEARCH CENTER UNITED STATES BUREAU OF MINES ALBANY, OREGON Q\OLO G/C G- 4& G <iI a,9 ' i . sr do OCCUPATIONAL HEALTH AND SAFETY DIVISION Health Physics Section ARGONNE NATIONAL LABORATORY, ARGONNE, ILLINOIS Operated by THE UNIVERSITY OF CHICAGO for the U. S. DEPARTMENT OF ENERGY under Contract W=31=109-Eng-38 Distribution Category: Remedial Action

  3. DOEIEV-0005/39 ANL-OHSIHP-83-101 FORMERLY UTILIZED MED/AEC SITES

    Office of Legacy Management (LM)

    t ,-?/ . DOEIEV-0005/39 ANL-OHSIHP-83-101 FORMERLY UTILIZED MED/AEC SITES REMEDIAL ACTION PROGRAM RADIOLOGICAL SURVEY OF THE ALBANY METALLURGICAL RESEARCH CENTER UNITED STATES BUREAU OF MINES BIOMASS FACILITY AND THE "BACK FORTY" AREA ALBANY, OREGON OCCUPATIONAL HEALTH AND SAFETY DIVISION pQ^'^'^o,,,oc/c~~ ~Health Physics Section 4,^of, ARGONNE NATIONAL LABORATORY, ARGONNE, ILLINOIS %+Y, ^I~ 60Operated by THE UNIVERSITY OF CHICAGO 0t'~ ^ for the U. S. DEPARTMENT OF ENERGY under

  4. I RADIOLOGICAL SCOPING SURVEY OF FO,RMER MONSANTO' FACILITIES

    Office of Legacy Management (LM)

    responsibility for the production of polonium in support of the development of an ... and were lim ited to trace quantities of polonium fop the analysis of environmental m o n ...

  5. Radiological Survey Data for 38 Grove Avenue, Rochelle Park,...

    Office of Legacy Management (LM)

    E a s t m a n , 0 R A. llhltrnan, NE-24 Aeros pace ATG. SYMBOL NEzE4 . - . 4 . W . rNrfif,LcstG F.e.lg DATE RTG. SYMBOT tNtTTALSSlG, N E - 7 3 ( 4 ) N E - 2 4 R F DOE F ...

  6. RADIOLOGICAL SURVEY AT 5823/5849 NORTH RAVENSWOOD AVEXJE CHICAGO...

    Office of Legacy Management (LM)

    The subcontract number 7401-37-93, was to furnish the necessary personnel, facilities and equipment required to produce special tools, dies, fixtures, etc., from materials ...

  7. RADIOLOGICAL SURVEY OF THE GUN FORGING MACHINE BUILDING ITHACA...

    Office of Legacy Management (LM)

    ... these manuals were developed to meet the requirements of DOE Order I 5700.6C and ASMB NQA-1 for Quality Assurance and contain measures to assess processes during their performance. ...

  8. NNSA to Conduct Aerial Radiological Surveys Over Washington,...

    National Nuclear Security Administration (NNSA)

    Washington, D.C. and Baltimore, MD Areas | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing...

  9. NV/YMP radiological control manual, Revision 2

    SciTech Connect

    Gile, A.L.

    1996-11-01

    The Nevada Test Site (NTS) and the adjacent Yucca Mountain Project (YMP) are located in Nye County, Nevada. The NTS has been the primary location for testing nuclear explosives in the continental US since 1951. Current activities include operating low-level radioactive and mixed waste disposal facilities for US defense-generated waste, assembly/disassembly of special experiments, surface cleanup and site characterization of contaminated land areas, and non-nuclear test operations such as controlled spills of hazardous materials at the hazardous Materials (HAZMAT) Spill Center (HSC). Currently, the major potential for occupational radiation exposure is associated with the burial of low-level nuclear waste and the handling of radioactive sources. Planned future remediation of contaminated land areas may also result in radiological exposures. The NV/YMP Radiological Control Manual, Revision 2, represents DOE-accepted guidelines and best practices for implementing Nevada Test Site and Yucca Mountain Project Radiation Protection Programs in accordance with the requirements of Title 10 Code of Federal Regulations Part 835, Occupational Radiation Protection. These programs provide protection for approximately 3,000 employees and visitors annually and include coverage for the on-site activities for both personnel and the environment. The personnel protection effort includes a DOE Laboratory Accreditation Program accredited dosimetry and personnel bioassay programs including in-vivo counting, routine workplace air sampling, personnel monitoring, and programmatic and job-specific As Low as Reasonably Achievable considerations.

  10. OFF-SITE SURVEILLANCE ACTIVITIES OF SOUTHWESTERN RADIOLOGICAL...

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    ...468 Diana Moon 82768 Knife.B 111568 Sled 82968 Ming VaSe 112068 Noggin g668 ... similar to those used by ground monitors, was used to track the radioactive effluents. ...

  11. ENERGY MEASUREMENTS GROUP EG&G SURVEY REPORT

    Office of Legacy Management (LM)

    ENERGY MEASUREMENTS GROUP EG&G SURVEY REPORT NRC-81 13 , NOVEMBER 1981 llti * Knb THE REMOTE SENSING lA6ORAORV OF THE UNITED STATES DEPARTMENT OF ENERGY AN AERIAL RADIOLOGICAL ...

  12. Federal Radiological Monitoring and Assessment Center

    Directives, Delegations, and Other Requirements [Office of Management (MA)]

    1992-12-02

    To establish Department of Energy (DOE) policy, procedures, authorities, and requirements for the establishment of a Federal Radiological Monitoring and Assessment Center (FRMAC), as set forth in the Federal Radiological Emergency Response Plan (FRERP). This directive does not cancel another directive. Canceled by DOE O 153.1.

  13. Memorandum, Reporting of Radiological Sealed Sources Transactions

    Energy.gov [DOE]

    The requirements for reporting transactions involving radiological sealed sources are identified in Department of Energy (DOE) Notice (N) 234.1, Reporting of Radioactive Sealed Sources. The data reported in accordance with DOE N 234.1 are maintained in the DOE Radiological Source Registry and Tracking (RSRT) database by the Office of Information Management, within the Office of Environment, Health, Safety and Security.

  14. Radiological Triage | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Radiological Triage NNSA stays prepared with world-class response units September is National Preparedness Month, but for the Department of Energy (DOE) and NNSA, preparedness is a priority every month of the year. NNSA can respond to an emergency at any DOE facility, and it is also the nation's premier technical resource for response to nuclear or radiological

  15. INL@Work Radiological Search & Response Training

    SciTech Connect

    Turnage, Jennifer

    2010-01-01

    Dealing with radiological hazards is just part of the job for many INL scientists and engineers. Dodging bullets isn't. But some Department of Defense personnel may have to do both. INL employee Jennifer Turnage helps train soldiers in the art of detecting radiological and nuclear material. For more information about INL's research projects, visit http://www.facebook.com/idahonationallaboratory.

  16. INL@Work Radiological Search & Response Training

    ScienceCinema

    Turnage, Jennifer

    2016-07-12

    Dealing with radiological hazards is just part of the job for many INL scientists and engineers. Dodging bullets isn't. But some Department of Defense personnel may have to do both. INL employee Jennifer Turnage helps train soldiers in the art of detecting radiological and nuclear material. For more information about INL's research projects, visit http://www.facebook.com/idahonationallaboratory.

  17. 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

    Wickline, Alfred

    2006-12-01

    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.

  18. MODARIA: Modelling and Data for Radiological Impact Assessment...

    Office of Environmental Management (EM)

    MODARIA: Modelling and Data for Radiological Impact Assessment Context and Overview MODARIA: Modelling and Data for Radiological Impact Assessment Context and Overview Presentation...

  19. Model Annex for Preparedness and Response to Radiological Transportati...

    Office of Environmental Management (EM)

    Annex for Preparedness and Response to Radiological Transportation Incidents Model Annex for Preparedness and Response to Radiological Transportation Incidents This part should...

  20. Office of Radiological Security | Y-12 National Security Complex

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Office of Radiological ... Office of Radiological Security Read more about Y-12's contributions of the Global Threat Reduction Initiative to secure the world's most vulnerable...

  1. Hawaii Department of Health Indoor and Radiological Health Branch...

    OpenEI (Open Energy Information) [EERE & EIA]

    Indoor and Radiological Health Branch Jump to: navigation, search Name: Hawaii Department of Health Indoor and Radiological Health Branch From Open Energy Information Address: 591...

  2. DOE-HDBK-1122-99; Radiological Technician Training

    Energy Saver

    ... Causes of radiological incidents and emergencies could be ... material, weather conditions, non-radiological ... area to characterize the extent of contamination. * ...

  3. Los Alamos National Security Corrective Action Plan - Radiological...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Partnership (NWP) Corrective Action Plan - Truck Fire and Radiological Release Phase I Carlsbad Field Office (CBFO) Corrective Action Plan - Truck Fire and Radiological Release

  4. Robotic Surveying

    SciTech Connect

    Suzy Cantor-McKinney; Michael Kruzic

    2007-03-01

    ZAPATA ENGINEERING challenged our engineers and scientists, which included robotics expertise from Carnegie Mellon University, to design a solution to meet our client's requirements for rapid digital geophysical and radiological data collection of a munitions test range with no down-range personnel. A prime concern of the project was to minimize exposure of personnel to unexploded ordnance and radiation. The field season was limited by extreme heat, cold and snow. Geographical Information System (GIS) tools were used throughout this project to accurately define the limits of mapped areas, build a common mapping platform from various client products, track production progress, allocate resources and relate subsurface geophysical information to geographical features for use in rapidly reacquiring targets for investigation. We were hopeful that our platform could meet the proposed 35 acres per day, towing both a geophysical package and a radiological monitoring trailer. We held our breath and crossed our fingers as the autonomous Speedrower began to crawl across the playa lakebed. We met our proposed production rate, and we averaged just less than 50 acres per 12-hour day using the autonomous platform with a path tracking error of less than +/- 4 inches. Our project team mapped over 1,800 acres in an 8-week (4 days per week) timeframe. The expertise of our partner, Carnegie Mellon University, was recently demonstrated when their two autonomous vehicle entries finished second and third at the 2005 Defense Advanced Research Projects Agency (DARPA) Grand Challenge. 'The Grand Challenge program was established to help foster the development of autonomous vehicle technology that will some day help save the lives of Americans who are protecting our country on the battlefield', said DARPA Grand Challenge Program Manager, Ron Kurjanowicz. Our autonomous remote-controlled vehicle (ARCV) was a modified New Holland 2550 Speedrower retrofitted to allow the machine

  5. Hanford Radiological Protection Support Services annual report for 1993

    SciTech Connect

    Lyon, M.; Bihl, D.E.; Fix, J.J.; Froelich, T.J.; Piper, R.K.; Olsen, P.C.

    1994-07-01

    Various Hanford Site radiation protection services provided by the Pacific Northwest Laboratory for the US Department of Energy Richland Operations Office and Hanford contractors are described in this annual report for calendar year 1993. These activities include internal dosimetry measurements and evaluations, in vivo measurements, external dosimetry measurements and evaluations, instrument calibration and evaluation, radiation source calibration, and radiological record keeping. For each of these activities, the routine program and any program changes or enhancements are described, as well as associated tasks, investigations, and studies. Program-related publications, presentations, and other staff professional activities are also described.

  6. Hanford radiological protection support services annual report for 1996

    SciTech Connect

    Lyon, M.; Bihl, D.E.; Fix, J.J.; Froelich, T.J.; Piper, R.K.; Schulze, S.A.

    1997-06-01

    Various Hanford Site radiation protection services provided by the Pacific Northwest National Laboratory for the US Department of Energy Richland Operations Office and Hanford contractors are described in this annual report for calendar year 1996. These activities include external dosimetry measurements and evaluations, internal dosimetry measurements and evaluations, in vivo measurements, radiological exposure record keeping, radiation source calibration, and instrument calibration and evaluation. For each of these activities, the routine program and any program changes or enhancements are described, as well as associated tasks, investigations, and studies. Program-related publications, presentations, and other staff professional activities are also described.

  7. Hanford radiological protection support services annual report for 1994

    SciTech Connect

    Lyon, M.; Bihl, D.E.; Fix, J.J.; Piper, R.K.; Froelich, T.J.; Olsen, P.C.

    1995-06-01

    Various Hanford Site radiation protection services provided by the Pacific Northwest Laboratory for the US Department of Energy Richland Operations Office and Hanford contractors are described in this annual report for the calendar year 1994. These activities include external dosimetry measurements and evaluations, internal dosimetry measurements and evaluations, in vivo measurements, radiological record keeping, radiation source calibration, and instrument calibration and evaluation. For each of these activities, the routine program and any program changes or enhancements are described, as well as associated tasks, investigations, and studies. Program- related publications, presentations, and other staff professional activities are also described.

  8. Assessment of the radiological impact of coal utilization. II. Radionuclides in western coal ash

    SciTech Connect

    Styron, C.E.; Bishop, C.T.; Casella, V.R.; Jenkins, P.H.; Yanko, W.H.

    1981-04-03

    A project has been initiated at Mound Facility specifically to evaluate the potential radiological impact of coal utilization. Phase I of the project included a survey of western US coal mines and an assessment of emissions from a power plant burning Western coal. Concentrations of uranium in coal from operating Western mines were slightly below the national average and roughly comparable to Eastern coal. Environmental deposition of radionuclides from stack emissions over a 20-year accumulation at a power plant burning Western coal was estimated to be 0.1 to 1.0% of measured background. Phase II of the project, the subject of the present report, has involved an interlaboratory comparison of results of radioanalytical procedures, determining partitioning coefficients for radionuclides in bottom ash and fly ash, and an assessment of the potential for migration of radionuclides from ash disposal sites. Results from the various laboratories for uranium-238, uranium-234, thorium-230, radium-226, polonium-210, thorium-232, thorium-228, and uranium-235 were generally in very good agreement. However, values for lead-210 in coal varied widely. Essentially all the nonvolatile radionuclides (uranium, radium, and thorium) from feed coal were accounted for in fly ash and bottom ash. However, 20 to 50% of the volatile radionuclides (lead and polonium) from subbituminous and lignitic coals could not be accounted for in ash, and it is assumed that this fraction exits via the stack. At the power plant burning bituminous coal, essentially all the lead and most of the polonium remained with the ash.

  9. The visual and radiological inspection of a pipeline using a teleoperated pipe crawler

    SciTech Connect

    Fogle, R.F.; Kuelske, K.; Kellner, R.

    1995-01-01

    In the 1950s, the Savannah River Site built an open, unlined retention basin to temporarily store potentially radionuclide contaminated cooling water from a chemical separations process and storm water drainage from a nearby waste management facility that stored large quantities of nuclear fission byproducts in carbon steel tanks. The retention basin was retired from service in 1972 when a new, lined basin was completed. In 1978, the old retention basin was excavated, backfilled with uncontaminated dirt, and covered with grass. At the same time, much of the underground process pipeline leading to the basin was abandoned. Since the closure of the retention basin, new environmental regulations require that the basin undergo further assessment to determine whether additional remediation is required. A visual and radiological inspection of the pipeline was necessary to aid in the remediation decision making process for the retention basin system. A teleoperated pipe crawler inspection system was developed to survey the abandoned sections of underground pipelines leading to the retired retention basin. This paper will describe the background to this project, the scope of the investigation, the equipment requirements, and the results of the pipeline inspection.

  10. The inspection of a radiologically contaminated pipeline using a teleoperated pipe crawler

    SciTech Connect

    Fogle, R.F.; Kuelske, K.; Kellner, R.A.

    1995-08-01

    In the 1950s, the Savannah River Site built an open, unlined retention basin to temporarily store potentially radionuclide contaminated cooling water from a chemical separations process and storm water drainage from a nearby waste management facility that stored large quantities of nuclear fission byproducts in carbon steel tanks. The retention basin was retired from service in 1972 when a new, lined basin was completed. In 1978, the old retention basin was excavated, backfilled with uncontaminated dirt, and covered with grass. At the same time, much of the underground process pipeline leading to the basin was abandoned. Since the closure of the retention basin, new environmental regulations require that the basin undergo further assessment to determine whether additional remediation is required. A visual and radiological inspection of the pipeline was necessary to aid in the remediation decision making process for the retention basin system. A teleoperated pipe crawler inspection system was developed to survey the abandoned sections of underground pipelines leading to the retired retention basin. This paper will describe the background to this project, the scope of the investigation, the equipment requirements, and the results of the pipeline inspection.

  11. Site Environmental Report for 2001

    SciTech Connect

    Pauer, Ron

    2002-07-01

    The mission of Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab) is to continue the long tradition of outstanding research that has made it a premier national and international multiprogram laboratory. In order to provide the highest degree of protection for the public and the environment, Berkeley Lab employs Integrated Safety Management (ISM). ISM is a comprehensive U.S. Department of Energy management system that involves five core functions (work planning, hazard and risk analysis, establishment of controls, work performance, and feedback and improvement). These five core functions are applied to all activities at Berkeley Lab. Laboratory activities are planned and conducted with full regard to protecting the public and the environment and complying with appropriate environmental laws and regulations. Both radiological and nonradiological activities are thoroughly monitored to assess their potential impact on public health and the environment. This annual Site Environmental Report covers activities for calendar year (CY) 2001. Volume I summarizes environmental protection performance and environmental monitoring activities. Volume II contains individual analytical data summarized in the first volume. Volume II is available on request. (For details, see the Preface.) Data are presented in the report using the International System of Units measuring system, more commonly referred to as the metric system. For the convenience of readers, both volumes of this report can be accessed on the Web from the Berkeley Lab Environmental Services home page, which is located at http://www.lbl.gov/ehs/esg. Readers are encouraged to comment on this report by completing either the survey card included with the distributed hard copy of the report or the survey form in the Web version of the report. The format and content of this report satisfy the requirements of United States Department of Energy (DOE) Order 231.1, Environment, Safety and Health Reporting,1 and

  12. Hanford site near-facility environmental monitoring annual report, calendar year 1996

    SciTech Connect

    Perkins, C.J.

    1997-08-05

    This document summarizes the results of the near-facility environmental monitoring results for 1996 in the 100, 200/600, and 300/400 areas of the Hanford Site in south-central Washington State. Surveillance activities included sampling and analyses of ambient air, surface water, groundwater, soil, sediments, and biota. Also, external radiation measurements and radiological surveys were taken at waste disposal sites, radiologically controlled areas, and roads. These activities were conducted to assess and control the effects of nuclear facilities and waste sites on the local environment. The monitoring implements applicable portions of DOE Orders 5400.1 (DOE 1988a), 5400.5 (DOE 1990), and 5820.2A (DOE 1988b); Washington Administrative Code (WAC) 246-247; and Title 40 Code of Federal Regulations (CFR) Part 61, Subpart H (EPA 1989). In addition, diffuse sources were monitored to determine compliance with federal, state, and/or local regulations. In general, although effects from nuclear facilities can still be observed on the Hanford Site and radiation levels were slightly elevated when compared to offsite locations, the differences are less than in previous years.

  13. Hanford Site Regional Population - 2010 Census

    SciTech Connect

    Hamilton, Erin L.; Snyder, Sandra F.

    2011-08-12

    The U.S. Department of Energy conducts radiological operations in south-central Washington State. Population dose estimates must be performed to provide a measure of the impact from site radiological releases. Results of the U.S. 2010 Census were used to determine counts and distributions for the residential population located within 50-miles of several operating areas of the Hanford Site. Year 2010 was the first census year that a 50-mile population of a Hanford Site operational area exceeded the half-million mark.

  14. Nuclear Radiological Threat Task Force Established | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration | (NNSA) Radiological Threat Task Force Established Nuclear Radiological Threat Task Force Established Washington, DC NNSA's Administrator Linton Brooks announces the establishment of the Nuclear Radiological Threat Reduction Task Force (NRTRTF) to combat the threats posed by radiological dispersion devices or "dirty bombs."

  15. Apparatus for safeguarding a radiological source

    SciTech Connect

    Bzorgi, Fariborz M

    2014-10-07

    A tamper detector is provided for safeguarding a radiological source that is moved into and out of a storage location through an access porthole for storage and use. The radiological source is presumed to have an associated shipping container approved by the U.S. Nuclear Regulatory Commission for transporting the radiological source. The tamper detector typically includes a network of sealed tubing that spans at least a portion of the access porthole. There is an opening in the network of sealed tubing that is large enough for passage therethrough of the radiological source and small enough to prevent passage therethrough of the associated shipping cask. Generally a gas source connector is provided for establishing a gas pressure in the network of sealed tubing, and a pressure drop sensor is provided for detecting a drop in the gas pressure below a preset value.

  16. DOE Issues WIPP Radiological Release Investigation Report

    Energy.gov [DOE]

    Today, the Department of Energy’s Office of Environmental Management (EM) released the initial accident investigation report related to the Feb. 14 radiological release at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico.

  17. Radiological safety training for uranium facilities

    SciTech Connect

    1998-02-01

    This handbook contains recommended training materials consistent with DOE standardized core radiological training material. These materials consist of a program management guide, instructor`s guide, student guide, and overhead transparencies.

  18. Radiological Safety Analysis Code System.

    Energy Science and Technology Software Center

    2009-12-22

    Version 03 RSAC-6.2 can be used to model complex accidents and radiological consequences to individuals from the release of radionuclides to the atmosphere. A user can generate a fission product inventory; decay and ingrow the inventory during transport through processes, facilities, and the environment; model the downwind dispersion of the activity; and calculate doses to downwind individuals. Doses are calculated through the inhalation, immersion, ground surface and ingestion pathways. New to RSAC-6.2 are the abilitiesmore » to calculate inhalation from release to a room, inhalation from resuspension of activities, and a new model for dry deposition. Doses can now be calculated as close as 10 meters from the release point. RSAC-6.2 has been subjected to extensive independent verification and validation for use in performing safety-related dose calculations to support safety analysis reports. WinRP 2.0, a windows based overlay to RSAC-6.2, assists users in creating and running RSAC-6.2 input files. RSAC-6, Rev. 6.2 (03/11/02) corrects an earlier issue with RSAC-6, compiled with F77L-EM/32 Fortran 77 Version 5.10, which would not allow the executable to run with XP or VISTA Windows operating systems. Because this version is still in use at some facilities, it is being released through RSICC in addition to the new RSAC 7 (CCC-761).« less

  19. Contained radiological analytical chemistry module

    DOEpatents

    Barney, David M.

    1989-01-01

    A system which provides analytical determination of a plurality of water chemistry parameters with respect to water samples subject to radiological contamination. The system includes a water sample analyzer disposed within a containment and comprising a sampling section for providing predetermined volumes of samples for analysis; a flow control section for controlling the flow through the system; and a gas analysis section for analyzing samples provided by the sampling system. The sampling section includes a controllable multiple port valve for, in one position, metering out sample of a predetermined volume and for, in a second position, delivering the material sample for analysis. The flow control section includes a regulator valve for reducing the pressure in a portion of the system to provide a low pressure region, and measurement devices located in the low pressure region for measuring sample parameters such as pH and conductivity, at low pressure. The gas analysis section which is of independent utility provides for isolating a small water sample and extracting the dissolved gases therefrom into a small expansion volume wherein the gas pressure and thermoconductivity of the extracted gas are measured.

  20. Contained radiological analytical chemistry module

    DOEpatents

    Barney, David M.

    1990-01-01

    A system which provides analytical determination of a plurality of water chemistry parameters with respect to water samples subject to radiological contamination. The system includes a water sample analyzer disposed within a containment and comprising a sampling section for providing predetermined volumes of samples for analysis; a flow control section for controlling the flow through the system; and a gas analysis section for analyzing samples provided by the sampling system. The sampling section includes a controllable multiple port valve for, in one position, metering out sample of a predetermined volume and for, in a second position, delivering the material sample for analysis. The flow control section includes a regulator valve for reducing the pressure in a portion of the system to provide a low pressure region, and measurement devices located in the low pressure region for measuring sample parameters such as pH and conductivity, at low pressure. The gas analysis section which is of independent utility provides for isolating a small water sample and extracting the dissolved gases therefrom into a small expansion volume wherein the gas pressure and thermoconductivity of the extracted gas are measured.

  1. Flashback: Rapid scanning for radiological threats

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Flashback: Rapid scanning for radiological threats Flashback: Rapid scanning for radiological threats The ability to identify distinct material density enables the Multi-Mode Passive Detection System (MMPDS)to quickly detect unshielded to heavily shielded nuclear threats, as well as gamma rays, with near-zero false alarms. November 1, 2015 Decision Science Decision Science Decision Sciences' Multi-Mode Passive Detection System: Rapid scanning forradiological threats Click on headline to go to

  2. Environmental Management Headquarters Corrective Action Plan - Radiological

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Release Phase I | Department of Energy I Environmental Management Headquarters Corrective Action Plan - Radiological Release Phase I The purpose of this Corrective Action Plan (CAP) is to specify U.S. Department of Energy (DOE) actions for addressing Office of Environmental Management (EM) Headquarters (HQ) issues identified in the Accident Investigation Report for the Phase 1: Radiological Release Event at the Waste Isolation Pilot Plant (WIPP) on February 14, 2014. The report identified 31

  3. Environmental Management Headquarters Corrective Action Plan - Radiological

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Release Phase II | Department of Energy II Environmental Management Headquarters Corrective Action Plan - Radiological Release Phase II The purpose of this Corrective Action Plan (CAP) is to specify U.S. Department of Energy (DOE) actions for addressing Office of Environmental Management (EM) Headquarters (HQ) issues identified in the Accident Investigation Report for the Phase 2: Radiological Release Event at the Waste Isolation Pilot Plant (WIPP) on February 14, 2014. The report identified

  4. radiological protection | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    protection NNSA Receives Excellence Award for Radiological Security Enhancements in Hawaii HONOLULU - At an official event this week, the City and County of Honolulu presented the Department of Energy's (DOE) National Nuclear Security Administration (NNSA) with the Homeland Security Excellence Award for DOE/NNSA's Office of Radiological Security's (ORS) efforts... Dedication of Radioactive Source Storage Facilities in Tajikistan (Dushanbe, Tajikistan) - On May 11, the United States' Embassy of

  5. Los Alamos responds to radiological incident

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Los Alamos responds to radiological incident Los Alamos responds to radiological incident Multiple tests indicate no health risks to public or employees. August 27, 2012 Aerial view of the Los Alamos Neutron Science Center (LANSCE). Aerial view of the Los Alamos Neutron Science Center (LANSCE). The contamination poses no danger to the public. The Laboratory is investigating the inadvertent spread of Technetium 99 by employees and contractors at the Lujan Neutron Scattering Center August 27,

  6. radiological detection | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    radiological detection Meet a Machine: RPMs keep watch 24/7 to strengthen global nuclear security Ensuring that nuclear materials are not being illicitly moved is part of NNSA's core mission to reduce nuclear and radiological threats. However, since traditional security tools - such as metal detectors, X-ray scanners, and sniffer dogs - cannot measure radiation, frontline... NNSA program strengthens national security from afar The Nuclear Smuggling Detection and Deterrence (NSDD) program is a

  7. Long-Term Hydrologic Monitoring Program, Gnome site, Eddy County, New Mexico

    SciTech Connect

    Not Available

    1982-01-01

    The Gnome site is located in Eddy County, approximately 31 miles southeast of the city of Carlsbad, New Mexico. Project Gnome, with a yield of 3.1 kilotons, was detonated December 10, 1961. It was the first nuclear detonation designed specifically for peaceful purposes and the first underground event of the Plowshare Program to take place outside the Nevada Test Site. The purpose of the Long-Term Hydrologic Monitoring Program at the Gnome site is to obtain data that will assure the public safety; inform the public, the news media, and the scientific community relative to radiological contamination; and to document compliance with federal, state, and local antipollution requirements. The Gnome site geographical setting, climate, geology, and hydrology are described. Site history, including Gnome event information and pre- and post-Gnome monitoring by the US Public Health Service and the USGS, is described. Site cleanups of 1968 and 1979 are described. Postoperational surveys indicate that the Gnome site is well below the established decontamination criteria and that no hazard exists or will likely occur during public use of the surface of the Gnome site. The Long-Term Hydrologic Monitoring Program for the Gnome site is described.

  8. Topographical mapping system for radiological and hazardous environments acceptance testing

    SciTech Connect

    Armstrong, G.A.; Dochat, G.R.

    1997-12-01

    During the summer of 1996, the Topographical Mapping System (TMS) for hazardous and radiological environments and its accompanying three-dimensional (3-D) visualization tool, the Interactive Computer-Enhanced Remote-Viewing System (ICERVS), were delivered to Oak Ridge National Laboratory (ORNL). ORNL and Mechanical Technology, Inc., performed final acceptance testing of the TMS during the next eight months. The TMS was calibrated and characterized during this period. This paper covers the calibration, characterization, and acceptance testing of the TMS. Development of the TMS and ICERVS was initiated by the US Department of Energy (DOE) for the purpose of characterization and remediation of underground storage tanks (USTs) at DOE sites across the country. DOE required a 3-D, topographical mapping system suitable for use in hazardous and radiological environments. The intended application is the mapping of the interior of USTs as part of DOE`s waste characterization and remediation efforts and to obtain baseline data on the content of the storage tank interiors as well as data on changes in the tank contents and levels brought about by waste remediation steps. Initially targeted for deployment at the Hanford Washington site, the TMS is designed to be a self-contained, compact, and reconfigurable system that is capable of providing rapid, variable-resolution mapping information in poorly characterized workspaces with a minimum of operator intervention.

  9. Los Alamos National Security Corrective Action Plan - Radiological Release

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Phase II | Department of Energy Security Corrective Action Plan - Radiological Release Phase II Los Alamos National Security Corrective Action Plan - Radiological Release Phase II Los Alamos National Security Corrective Action Plan - Radiological Release Phase II Los Alamos National Security Corrective Action Plan - Radiological Release Phase II (7.59 MB) More Documents & Publications Environmental Management Los Alamos Field Office Corrective Action Plan - Radiological Release Phase II

  10. PRELIMINARY SURVEY OF VITRO CORPORATION

    Office of Legacy Management (LM)

    status of those facilities utilized under Atomic Energy Commission (AEC) contract during ... A survey of the site was conducted, consisting of gamma-ray exposure rate measurements ...

  11. REVISED FINAL REPORT – INDEPENDENT VERIFICATION SURVEY ACTIVITIES AT THE SEPARATIONS PROCESS RESEARCH UNIT SITES, NISKAYUNA, NEW YORK – DCN 0496-SR-06-1

    SciTech Connect

    Evan Harpenau

    2011-10-10

    The Separations Process Research Unit (SPRU) complex located on the Knolls Atomic Power Laboratory (KAPL) site in Niskayuna, New York, was constructed in the late 1940s to research the chemical separation of plutonium and uranium (Figure A-1). SPRU operated as a laboratory scale research facility between February 1950 and October 1953. The research activities ceased following the successful development of the reduction oxidation and plutonium/uranium extraction processes. The oxidation and extraction processes were subsequently developed for large scale use by the Hanford and Savannah River sites (aRc 2008a). Decommissioning of the SPRU facilities began in October 1953 and continued through the 1990s.

  12. In situ radiation measurements at the former Soviet Nuclear Test Site

    SciTech Connect

    Tipton, W.J.

    1996-06-01

    A team from the Remote Sensing Laboratory conducted a series of in situ radiological measurements at the former Soviet Nuclear Test Site near Semipalatinsk, Kazakhstan, during the period of July 21-30, 1994. The survey team measured the terrestrial gamma radiation at selected areas on the site to determine the levels of natural and man-made radiation. The survey was part of a cooperative effort between the United States team and teams of radiation scientists from the National Nuclear Center of the Republic of Kazakhstan and the V.G. Khlopin Radium Institute in St. Petersburg, Russia. In addition to in situ radiation measurements made by the United States and Russian teams, soil samples were collected and analyzed by the Russian and Kazakhstani teams. All teams conducted their measurements at ten locations within the test site. The United States team also made a number of additional measurements to locate and verify the positions of three potential fallout plumes containing plutonium contamination from nonnuclear tests. In addition, the United States team made several measurements in Kurchatov City, the housing area used by personnel and their families who work(ed) at the test sites. Comparisons between the United States and Russian in situ measurements and the soil sample results are presented as well as comparisons with a Soviet aerial survey conducted in 1990-1991. The agreement between the different types of measurements made by all three countries was quite good.

  13. Shrimp and redfish studies, bryan mound brine disposal site off Freeport, Texas, 1979-1981. Volume IV. Interview sampling survey of shrimp catch and effort. Technical memo

    SciTech Connect

    Johnson, M.F.

    1981-06-01

    An interview sampling survey of shrimp catch and fishing effort was conducted at specified ports along the Texas coast to strengthen the information base required to determine the effect of the disposal of brine from the Bryan Mound salt dome off Freeport, Texas on commercial brown shrimp (Penaeus aztecus) and white shrimp (Penaeus setiferus) populations in the Gulf of Mexico. The data recorded included port number, vessel name, official vessel number, shrimp dealer number, date of landing, area fished, depth of capture, days fished, and pounds of shrimp caught by species and size categories.

  14. Long-Term Surveillance and Maintenance Requirements for Remediated FUSRAP Sites

    Energy.gov [DOE]

    This document summarizes radiological conditions at sites remediated under the Formerly Utilized Sites Remedial Action Program (FUSRAP) and transferred to the U.S. Department of Energy (DOE) for...

  15. Site Feeds - Hanford Site

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Site Feeds Site Feeds Calendar Hanford Blog Archive Search Site Feeds Site Index Weather What's New Hanford RSS Feeds Email Email Page | Print Print Page | Text Increase Font Size Decrease Font Size RSS Feed Links Site News RSS Did You Know RSS What's New RSS Event Calendar RSS Recent Videos RSS Press Releases RSS What is a feed? A feed is a document that contains summaries of web content with web links to the original versions. It may be viewed with a feed reader or news aggregator. If you

  16. Nevada Test Site Environmental Report 2004

    SciTech Connect

    BECHTEL NEVADA

    2005-10-01

    The ''Nevada Test Site Environmental Report 2004'' was prepared by Bechtel Nevada (BN) to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of non-radiological releases, implementation status of the NTS Environmental Management System, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled ''Nevada Test Site Environmental Report Summary 2004''. It was produced this year to provide a more cost-effective and wider distribution of a hardcopy summary of the ''Nevada Test Site Environmental Report 2004'' to interested DOE stakeholders.

  17. Site characterization plan for the W-058 Project

    SciTech Connect

    Rowley, C.A.

    1993-09-01

    The objective of this preoperational study plan is to characterize the proposed pipeline route for the Cross-Site Transfer System (W-058). The purpose of this study is to meet the requirements set forth in US Department of Energy (DOE) Order 5400.1, Chapter 4, (DOE 1990). The W-058 pipeline is intended to replace the existing Cross-Site Transfer System (H-2-43056). The proposed route for the W-058 project will be reviewed to provide information on documented waste sites and potentially to identify any undocumented hazards that may currently exist along the proposed route. Historical records will be researched for pertinent information. Health Physics personnel will perform a ``walk-down`` radiological survey of the proposed path. A sampling plan will be generated and will consist of actual drilling of boreholes to allow field screening for radionuclides and/or chemical contamination and the collection of samples at selected sites for laboratory analyses. The information generated from this combined effort will establish existing/potential contamination levels, aid in developing personnel safety requirements, assist in determining the need for any changes in the proposed route prior to installation/construction of the new pipeline, and satisfy the requirements of a preoperational baseline for the project.

  18. Interventional Radiology of Male Varicocele: Current Status

    SciTech Connect

    Iaccarino, Vittorio Venetucci, Pietro

    2012-12-15

    Varicocele is a fairly common condition in male individuals. Although a minor disease, it may cause infertility and testicular pain. Consequently, it has high health and social impact. Here we review the current status of interventional radiology of male varicocele. We describe the radiological anatomy of gonadal veins and the clinical aspects of male varicocele, particularly the physical examination, which includes a new clinical and ultrasound Doppler maneuver. The surgical and radiological treatment options are also described with the focus on retrograde and antegrade sclerotherapy, together with our long experience with these procedures. Last, we compare the outcomes, recurrence and persistence rates, complications, procedure time and cost-effectiveness of each method. It clearly emerges from this analysis that there is a need for randomized multicentre trials designed to compare the various surgical and percutaneous techniques, all of which are aimed at occlusion of the anterior pampiniform plexus.

  19. Emergency Response Planning for Radiological Releases

    SciTech Connect

    Biwer, B.M.; LePoire, D.J.; Lazaro, M.A.; Allison, T.; Kamboj, S.; Chen, S.Y.

    2006-07-01

    The emergency management planning tool RISK-RDD was developed to aid emergency response planners and decision makers at all levels of government to better understand and prepare for potential problems related to a radiological release, especially those in urban areas. Radioactive release scenarios were studied by using the RISK-RDD radiological emergency management program. The scenarios were selected to investigate the key aspects of radiological risk management not always considered in emergency planning as a whole. These aspects include the evaluation of both aerosolized and non-aerosolized components of an atmospheric release, methods of release, acute and chronic human health risks, and the concomitant economic impacts as a function of the risk-based cleanup level. (authors)

  20. Nevada Test Site Environmental Report 2005

    SciTech Connect

    Cathy A. Wills

    2006-10-01

    The Nevada Test Site Environmental Report 2005 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NTS Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts.

  1. The year book of diagnostic radiology 1981

    SciTech Connect

    Whitehouse, W.M.; Adams, D.F.; Bookstein, J.J.; Gabrielsen, T.O.; Holt, J.F.; Martel, W.; Silver, T.M.; Thornbury, J.R.

    1981-01-01

    The 1981 edition of the Year Book of Diagnostic Radiology fulfills the standards of excellence established by previous volumes in this series. The abstracts were carefully chosen, are concise, and are well illustrated. The book is recommended for all practicing radiologists: for the resident it is a good source from which to select articles to be carefully studied, and as review source before board examinations; for the subspecialist it provides a means to maintain contact with all areas of diagnostic radiology; and for the general radiologist, it is a convenient and reliable guide to new developments in the specialty.

  2. ASPECT Emergency Response Chemical and Radiological Mapping

    ScienceCinema

    LANL

    2016-07-12

    A unique airborne emergency response tool, ASPECT is a Los Alamos/U.S. Environmental Protection Agency project that can put chemical and radiological mapping tools in the air over an accident scene. The name ASPECT is an acronym for Airborne Spectral Photometric Environmental Collection Technology. Update, Sept. 19, 2008: Flying over storm-damaged refineries and chemical factories, a twin-engine plane carrying the ASPECT (Airborne Spectral Photometric Environmental Collection Technology) system has been on duty throughout the recent hurricanes that have swept the Florida and Gulf Coast areas. ASPECT is a project of the U.S. U.S. Environmental Protection Agencys National Decontamination Team. Los Alamos National Laboratory leads a science and technology program supporting the EPA and the ASPECT aircraft. Casting about with a combination of airborne photography and infrared spectroscopy, the highly instrumented plane provides emergency responders on the ground with a clear concept of where danger lies, and the nature of the sometimes-invisible plumes that could otherwise kill them. ASPECT is the nations only 24/7 emergency response aircraft with chemical plume mapping capability. Bob Kroutil of Bioscience Division is the project leader, and while he said the team has put in long hours, both on the ground and in the air, its a worthwhile effort. The plane flew over 320 targeted sites in four days, he noted. Prior to the deployment to the Gulf Coast, the plane had been monitoring the Democratic National Convention in Denver, Colorado. Los Alamos National Laboratory Divisions that are supporting ASPECT include, in addition to B-Division, CTN-5: Networking Engineering and IRM-CAS: Communication, Arts, and Services. Leslie Mansell, CTN-5, and Marilyn Pruitt, IRM-CAS, were recognized the the U.S. EPA for their outstanding support to the hurricane response of Gustav in Louisiana and Ike in Texas. The information from the data collected in the most recent event, Hurricane

  3. ASPECT Emergency Response Chemical and Radiological Mapping

    SciTech Connect

    LANL

    2008-05-12

    A unique airborne emergency response tool, ASPECT is a Los Alamos/U.S. Environmental Protection Agency project that can put chemical and radiological mapping tools in the air over an accident scene. The name ASPECT is an acronym for Airborne Spectral Photometric Environmental Collection Technology. Update, Sept. 19, 2008: Flying over storm-damaged refineries and chemical factories, a twin-engine plane carrying the ASPECT (Airborne Spectral Photometric Environmental Collection Technology) system has been on duty throughout the recent hurricanes that have swept the Florida and Gulf Coast areas. ASPECT is a project of the U.S. U.S. Environmental Protection Agencys National Decontamination Team. Los Alamos National Laboratory leads a science and technology program supporting the EPA and the ASPECT aircraft. Casting about with a combination of airborne photography and infrared spectroscopy, the highly instrumented plane provides emergency responders on the ground with a clear concept of where danger lies, and the nature of the sometimes-invisible plumes that could otherwise kill them. ASPECT is the nations only 24/7 emergency response aircraft with chemical plume mapping capability. Bob Kroutil of Bioscience Division is the project leader, and while he said the team has put in long hours, both on the ground and in the air, its a worthwhile effort. The plane flew over 320 targeted sites in four days, he noted. Prior to the deployment to the Gulf Coast, the plane had been monitoring the Democratic National Convention in Denver, Colorado. Los Alamos National Laboratory Divisions that are supporting ASPECT include, in addition to B-Division, CTN-5: Networking Engineering and IRM-CAS: Communication, Arts, and Services. Leslie Mansell, CTN-5, and Marilyn Pruitt, IRM-CAS, were recognized the the U.S. EPA for their outstanding support to the hurricane response of Gustav in Louisiana and Ike in Texas. The information from the data collected in the most recent event, Hurricane

  4. Closure Report for Corrective Action Unit 135: Areas 25 Underground Storage Tanks, Nevada Test Site, Nevada

    SciTech Connect

    D. H. Cox

    2001-06-01

    Corrective Action Unit (CAU) 135, Area 25 Underground Storage Tanks, was closed in accordance with the approved Corrective Action Plan (DOE/NV, 2000). CAU 135 consists of three Corrective Action Sites (CAS). Two of these CAS's were identified in the Corrective Action Investigation Data Quality Objective meeting as being improperly identified as underground storage tanks. CAS 25-02-03 identified as the Deluge Valve Pit was actually an underground electrical vault and CAS 25-02-10 identified as an Underground Storage Tank was actually a former above ground storage tank filled with demineralized water. Both of these CAS's are recommended for a no further action closure. CAS 25-02-01 the Underground Storage Tanks commonly referred to as the Engine Maintenance Assembly and Disassembly Waste Holdup Tanks and Vault was closed by decontaminating the vault structure and conducting a radiological verification survey to document compliance with the Nevada Test Site unrestricted use release criteria. The Area 25 Underground Storage Tanks, (CAS 25-02-01), referred to as the Engine Maintenance, Assembly, and Disassembly (E-MAD) Waste Holdup Tanks and Vault, were used to receive liquid waste from all of the radioactive and cell service area drains at the E-MAD Facility. Based on the results of the Corrective Action Investigation conducted in June 1999, discussed in ''The Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada'' (DOE/NV, 199a), one sample from the radiological survey of the concrete vault interior exceeded radionuclide preliminary action levels. The analytes from the sediment samples exceeded the preliminary action levels for polychlorinated biphenyls, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons as diesel-range organics, and radionuclides. The CAU 135 closure activities consisted of scabbling radiological ''hot spots'' from the concrete vault, and the drilling

  5. DOE-HDBK-1122-99; Radiological Control Technician Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ALARA Instructor's Guide 1.10-1 Course Title: Radiological Control Technician Module ... Energy, DOE-STD-1098-99, "Radiological Control Standard" 3. 10 CFR Part 835 (1998), ...

  6. DOE-HDBK-1122-99; Radiological Control Technician Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    R. L.; PNL; Richland, Wa. 3. DOE-STD-1098-99, "Radiological Control Standard." 4. 10 CFR Part 835 (1998) "Occupational Radiation Protection" 5. "The Health Physics and Radiological ...

  7. Nevada Test Site probable maximum flood study, part of US Geological Survey flood potential and debris hazard study, Yucca Mountain Site for US Department of Energy, Office of Civilian Radioactive Waste Management

    SciTech Connect

    Bullard, K.L.

    1994-08-01

    The US Geological Survey (USGS), as part of the Yucca Mountain Project (YMP), is conducting studies at Yucca Mountain, Nevada. The purposes of these studies are to provide hydrologic and geologic information to evaluate the suitability of Yucca Mountain for development as a high-level nuclear waste repository, and to evaluate the ability of the mined geologic disposal system (MGDS) to isolate the waste in compliance with regulatory requirements. In particular, the project is designed to acquire information necessary for the Department of Energy (DOE) to demonstrate in its environmental impact statement (EIS) and license application whether the MGDS will meet the requirements of federal regulations 10 CFR Part 60, 10 CFR Part 960, and 40 CFR Part 191. Complete study plans for this part of the project were prepared by the USGS and approved by the DOE in August and September of 1990. The US Bureau of Reclamation (Reclamation) was selected by the USGS as a contractor to provide probable maximum flood (PMF) magnitudes and associated inundation maps for preliminary engineering design of the surface facilities at Yucca Mountain. These PMF peak flow estimates are necessary for successful waste repository design and construction. The PMF technique was chosen for two reasons: (1) this technique complies with ANSI requirements that PMF technology be used in the design of nuclear related facilities (ANSI/ANS, 1981), and (2) the PMF analysis has become a commonly used technology to predict a ``worst possible case`` flood scenario. For this PMF study, probable maximum precipitation (PMP) values were obtained for a local storm (thunderstorm) PMP event. These values were determined from the National Weather Services`s Hydrometeorological Report No. 49 (HMR 49).

  8. Radiological Assessment of effects from Fukushima Daiichi Nuclear Power Plant

    Energy.gov [DOE]

    NNSA presentation on Radiological Assessment of effects from Fukushima Daiichi Nuclear Power Plant from May 13, 2011

  9. Office of Radiological Security | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Radiological Security NNSA Receives Excellence Award for Radiological Security Enhancements in Hawaii HONOLULU - At an official event this week, the City and County of Honolulu presented the Department of Energy's (DOE) National Nuclear Security Administration (NNSA) with the Homeland Security Excellence Award for DOE/NNSA's Office of Radiological Security's (ORS) efforts... NNSA Provides Tajikistan Specialized Vehicles to Transport Radiological Materials NNSA Program Manager Nick Cavellero,

  10. Radiological Security Program | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Radiological Security Program Armenia Secures Dangerous Radioactive Sources in Cooperation with NNSA The Department of Energy's National Nuclear Security Administration (NNSA) joined the Republic of Armenia today to announce the safe and secure removal of three unused radioactive sources from two locations in Yerevan, Armenia. The successful completion of the radioactive source recovery campaign

  11. Radiological/biological/aerosol removal system

    DOEpatents

    Haslam, Jeffery J

    2015-03-17

    An air filter replacement system for existing buildings, vehicles, arenas, and other enclosed airspaces includes a replacement air filter for replacing a standard air filter. The replacement air filter has dimensions and air flow specifications that allow it to replace the standard air filter. The replacement air filter includes a filter material that removes radiological or biological or aerosol particles.

  12. Development of radiological concentrations and unit liter doses for TWRS FSAR radiological consequence calculations

    SciTech Connect

    Cowley, W.L.

    1996-04-25

    The analysis described in this report develops the Unit Liter Doses for use in the TWRS FSAR. The Unit Liter Doses provide a practical way to calculate conservative radiological consequences for a variety of potential accidents for the tank farms.

  13. EOSO ENERGY MEASUREMENTS GROUP THE REMOT SENSIN EG&G SURVEY REPORT...

    Office of Legacy Management (LM)

    Oe. 1-G lZLq n EOSO ENERGY MEASUREMENTS GROUP THE REMOT SENSIN EG&G SURVEY REPORT LABORATO EP-F-002 Of THE UNITED STATES DECEMBER 1981 DEPARTMENT OF ENERGY AN AERIAL RADIOLOGICAL ...

  14. ENERGY MEASUREMENTS GROUP EG&G SURVEY REPORT NE-F-003

    Office of Legacy Management (LM)

    * * nEGc.G ENERGY MEASUREMENTS GROUP EG&G SURVEY REPORT NE-F-003 FEBRUARY 1983 THE REMOTE SENSING LABORATORY OF THE UNITED STATES DEPARTMENT OF ENERGY AN AERIAL RADIOLOGICAL ...

  15. Reducing Contingency through Sampling at the Luckey FUSRAP Site - 13186

    SciTech Connect

    Frothingham, David; Barker, Michelle; Buechi, Steve; Durham, Lisa

    2013-07-01

    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

  16. Recovery Act-Funded Study Assesses Contamination at Former Test Site in California

    Energy.gov [DOE]

    Workers in a study funded by $38 million from the American Recovery and Reinvestment Act to assess radiological contamination have collected more than 600 soil samples and surveyed 120 acres of...

  17. Guide of Good Practices for Occupational Radiological Protection in Plutonium Facilities

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    28-2008 December 2008 DOE STANDARD GUIDE OF GOOD PRACTICES FOR OCCUPATIONAL RADIOLOGICAL PROTECTION IN PLUTONIUM FACILITIES U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Not Measurement Sensitive DOE-STD-1128-2008 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1128-2008 iii Foreword This

  18. Paint for detection of radiological or chemical agents

    DOEpatents

    Farmer, Joseph C.; Brunk, James L.; Day, Sumner Daniel

    2010-08-24

    A paint that warns of radiological or chemical substances comprising a paint operatively connected to the surface, an indicator material carried by the paint that provides an indication of the radiological or chemical substances, and a thermo-activation material carried by the paint. In one embodiment, a method of warning of radiological or chemical substances comprising the steps of painting a surface with an indicator material, and monitoring the surface for indications of the radiological or chemical substances. In another embodiment, a paint is operatively connected to a vehicle and an indicator material is carried by the paint that provides an indication of the radiological or chemical substances.

  19. New Jersey state information handbook: Formerly Utilized Sites Remedial Action Program

    SciTech Connect

    1980-10-31

    Under the implied authority of the Atomic Energy Act of 1954, as amended, radiological surveys and research work has been conducted to determine radiological conditions at former MED/AEC sites. As of this time, 31 sites in 13 states have been identified that require or may require remedial action. This volume is one of a series produced under contract with DOE, Office of Nuclear Waste Management, by POLITECH CORPORATION to develop a legislative and regulatory data base to assist the FUSRAP management in addressing the institutional and socioeconomic issues involved in carrying out the Remedial Action Program. This Information Handbook series contains information about all relevant government agencies at the Federal and state levels, the pertinent programs they administer, each affected state legislature, and current Federal and state legislative and regulatory initiatives. This volume is a compilation of information about the state of New Jersey. It contains: a description of the state executive branch structure; a summary of relevant state statutes and regulations; a description of the structure of the state legislature, identification of the officers and committee chairmen, and a summary of recent relevant legislative action; and the full text of relevant statutes and regulations. The loose-leaf format used in these volumes will allow the material to be updated periodically as the Remedial Action Program progresses.

  20. Oregon National Register and Survey Program Webpage | Open Energy...

    OpenEI (Open Energy Information) [EERE & EIA]

    National Register and Survey Program Webpage Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: Oregon National Register and Survey Program Webpage...

  1. Title Preactivity Survey Report for Five Tonopah Test Range Explosive...

    National Nuclear Security Administration (NNSA)

    Preactivity Survey Report for Five Tonopah Test Range Explosive Ordnance Disposal Sites ... PREACTIVITY AND RECLAMATION SURVEY REPORTS FOR FIVE TONOPAH TEST RANGE EXPLOSIVE ORDNANCE ...

  2. Benchmarking survey for recycling.

    SciTech Connect

    Marley, Margie Charlotte; Mizner, Jack Harry

    2005-06-01

    This report describes the methodology, analysis and conclusions of a comparison survey of recycling programs at ten Department of Energy sites including Sandia National Laboratories/New Mexico (SNL/NM). The goal of the survey was to compare SNL/NM's recycling performance with that of other federal facilities, and to identify activities and programs that could be implemented at SNL/NM to improve recycling performance.

  3. TSD-DOSE: A radiological dose assessment model for treatment, storage, and disposal facilities

    SciTech Connect

    Pfingston, M.; Arnish, J.; LePoire, D.; Chen, S.-Y.

    1998-10-14

    Past practices at US Department of Energy (DOE) field facilities resulted in the presence of trace amounts of radioactive materials in some hazardous chemical wastes shipped from these facilities. In May 1991, the DOE Office of Waste Operations issued a nationwide moratorium on shipping all hazardous waste until procedures could be established to ensure that only nonradioactive hazardous waste would be shipped from DOE facilities to commercial treatment, storage, and disposal (TSD) facilities. To aid in assessing the potential impacts of shipments of mixed radioactive and chemically hazardous wastes, a radiological assessment computer model (or code) was developed on the basis of detailed assessments of potential radiological exposures and doses for eight commercial hazardous waste TSD facilities. The model, called TSD-DOSE, is designed to incorporate waste-specific and site-specific data to estimate potential radiological doses to on-site workers and the off-site public from waste-handling operations at a TSD facility. The code is intended to provide both DOE and commercial TSD facilities with a rapid and cost-effective method for assessing potential human radiation exposures from the processing of chemical wastes contaminated with trace amounts of radionuclides.

  4. Fixation of Radiological Contamination; International Collaborative Development

    SciTech Connect

    Rick Demmer

    2013-03-01

    A cooperative international project was conducted by the Idaho National Laboratory (INL) and the United Kingdoms National Nuclear Laboratory (NNL) to integrate a capture coating with a high performance atomizing process. The initial results were promising, and lead to further trials. The somewhat longer testing and optimization process has resulted in a product that could be demonstrated in the field to reduce airborne radiological dust and contamination.

  5. Nevada Test Site Environmental Report 2003

    SciTech Connect

    Bechtel Nevada

    2004-10-01

    The Nevada Test Site Environmental Report 2003 was prepared by Bechtel Nevada to meet the requirements and guidelines of the U.S. Department of Energy and the information needs of the public. This report is meant to be useful to members of the public, public officials, regulators, and Nevada Test Site contractors. The Executive Summary strives to present in a concise format the purpose of the document, the NTS mission and major programs, a summary of radiological releases and doses to the public resulting from site operations, a summary of non-radiological releases, and an overview of the Nevada Test Site Environmental Management System. The Executive Summary, combined with the following Compliance Summary, are written to meet all the objectives of the report and to be stand-alone sections for those who choose not to read the entire document.

  6. Enewetak radiological support project. Final report

    SciTech Connect

    Friesen, B.

    1982-09-01

    From 1972 through 1980, the Department of Energy acted in an advisory role to the Defense Nuclear Agency during planning for and execution of the cleanup of Enewetak Atoll. The Nevada Operations Office of the Department of Energy was responsible for the radiological characterization of the atoll and for certification of radiological condition of each island upon completion of the project. In-situ measurements of gamma rays emitted by americium-241 were utilized along with wet chemistry separation of plutonium from soil samples to identify and delineate surface areas requiring removal of soil. Military forces removed over 100,000 cubic yards of soil from the surface of five islands and deposited this material in a crater remaining from the nuclear testing period. Subsurface soil was excavated and removed from several locations where measurements indicated the presence of radionuclides above predetermined criteria. The methodologies of data acquisition, analysis and interpretation are described and detailed results are provided in text, figures and microfiche. The final radiological condition of each of 43 islets is reported.

  7. Corrective Action Plan for Corrective Action Unit 366: Area 11 Plutonium Valley Dispersion Sites, Nevada National Security Site, Nevada

    SciTech Connect

    2013-04-30

    year. These boundaries will be defined as follows: It is assumed that radiological contaminants are present at CAS 11-08-01 and CAS 11-08-02 within CWDs #1 and #2 at levels exceeding the FAL. Therefore, UR boundaries will be established around the perimeters of the soil covers that will be constructed at CWD #1 and CWD #2. A geophysical survey revealed buried metallic debris outside the fence and adjacent to CWD #1. Therefore, the UR boundary for CWD #1 will be expanded to include the mound containing buried material. It is assumed that radiological contaminants are present at CAS 11-23-02, CAS 11-23-03, and CAS 11-23-04, within the three High Contamination Area (HCA) boundaries associated with the 11b, 11c, and 11d test areas at levels exceeding the FAL. Therefore, the UR boundaries will be established around the perimeters of the HCAs. The TED at an area of soil impacted by radiological debris outside the fence and adjacent to the 11c test area HCA exceeds the FAL of 25 mrem/OU-yr. Because the radiological impact from the debris at this location is visible on the aerial flyover radiological survey, all other areas within this isopleth of the flyover survey are conservatively also assumed to exceed the FAL. Therefore, the UR boundaries for the 11b, 11c, and 11d test areas will be expanded to include the areas within this isopleth. The FFACO URs will all be located within the large Contamination Area (CA) that encompasses Plutonium Valley. Because access to the CA is limited and entry into the CA for post-closure inspections and maintenance would be impractical, UR warning signs will be posted along the existing CA fence. In accordance with the Soils Risk-Based Corrective Action Evaluation Process (NNSA/NSO, 2012b), an administrative UR will be implemented as a best management practice for the areas where the TED exceeds 25 millirems per Industrial Area year. This limit is based on continuous industrial use of the site and addresses exposure to industrial workers

  8. Pipe Explorer{trademark} surveying system. Innovative technology summary report

    SciTech Connect

    Not Available

    1999-06-01

    The US Department of Energy`s (DOE) Chicago Operations Office and the DOE`s Federal Energy Technology Center (FETC) developed a Large Scale Demonstration Project (LSDP) at the Chicago Pile-5 Research Reactor (CP-5) at Argonne National Laboratory-East (ANL). The objective of the LSDP is to demonstrate potentially beneficial decontamination and decommissioning (D and D) technologies in comparison with current baseline technologies. The Pipe Explorer{trademark} system was developed by Science and Engineering Associates, Inc. (SEA), Albuquerque, NM as a deployment method for transporting a variety of survey tools into pipes and ducts. Tools available for use with the system include alpha, beta and gamma radiation detectors; video cameras; and pipe locator beacons. Different versions of this technology have been demonstrated at three other sites; results of these demonstrations are provided in an earlier Innovative Technology Summary Report. As part of a D and D project, characterization radiological contamination inside piping systems is necessary before pipes can be recycled, remediated or disposed. This is usually done manually by surveying over the outside of the piping only, with limited effectiveness and risk of worker exposure. The pipe must be accessible to workers, and embedded pipes in concrete or in the ground would have to be excavated at high cost and risk of exposure to workers. The advantage of the Pipe Explorer is its ability to perform in-situ characterization of pipe internals.

  9. DOE - Office of Legacy Management -- OARDC - OH 11

    Office of Legacy Management (LM)

    FUSRAP Considered Sites Site: OARDC (OH.11) No documents available Designated Name: Not ... Radiological Survey(s): Site Status: No documents available OARDC may be an abbreviation ...

  10. DOE - Office of Legacy Management -- Oxnard Facility - 002

    Office of Legacy Management (LM)

    Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: This facility was used to produce...

  11. 2013 Environmental/Radiological Assistance Directory (ERAD) Presentations

    Energy.gov [DOE]

    November 2013 Derived Intervention and Response Levels for Tritium Oxide at the Savannah River Site May 2013 THE MARSAME METHODOLOGY Fundamentals, Benefits, and Applications March 2013 Working to Keep our Shipments Safe, Secure and Economical ANL Facility Decommissioning Training Program January 2013 DOE Corporate Operating Experience Program Radiological Reporting Annual Site Environmental Reports (ASERs) & HSS Environmental and Radiation Protection Performance Dashboards November 2012 Environmental Measurements in an Emergency: This is not a Drill! BGRR D&D Presentation for the DOE ERAD Working Group September 2012 Development of Authorized Limits for Portsmouth Oil Inventory Disposition Development of Authorized Limits for Portsmouth Oil Inventory Disposition Development of Authorized Limits for Portsmouth Oil Inventory Disposition Clearance of Real and Personal Property Under DOE Radiation Protection Directive DOE Order 458.1 June 2012 RESRAD Codes for ERAD June 27, 2012 Florida International University (FIU) D&D Knowledge Management Information Tool, June 27, 2012 May 2012 Integrated Cloud Based Environmental Data Management System DOE Order 458.1, Radiation Protection of the Public and the Environment

  12. DOE Annual Site Environmental Reports (ASER)

    Energy.gov [DOE]

    ASERs are required by DOE O 231.1B. The ASERs provide important information needed by site managers and DOE Headquarters to assess field environmental program performance, site-wide environmental monitoring and surveillance effectiveness, and confirm compliance with environmental standards and requirements. They are also the means by which DOE sites demonstrate compliance with the radiological protection requirements of DOE O 458.1. In addition, ASERs are an important means of conveying DOE's environmental protection performance to stakeholders and members of the public living near DOE sites.

  13. DOE - Office of Legacy Management -- Project Gas Buggy Site ...

    Office of Legacy Management (LM)

    1993. Sensitive Species Survey Results for the Gasbuggy and Gnome-Coach Sites, New Mexico, December 1993. Project Gasbuggy Site Restoration Final Report, July 1983. Surface ...

  14. Independent Confirmatory Survey Report for the University of Arizona Nuclear Reactor Laboratory, Tucson, Arizona

    SciTech Connect

    Nick A. Altic

    2011-11-11

    The University of Arizona (University) research reactor is a TRIGA swimming pool type reactor designed by General Atomics and constructed at the University in 1958. The reactor first went into operation in December of 1958 under U.S. Nuclear Regulatory Commission (NRC) license R-52 until final shut down on May 18, 2010. Initial site characterization activities were conducted in February 2009 during ongoing reactor operations to assess the radiological status of the Nuclear Reactor Laboratory (NRL) excluding the reactor tank, associated components, and operating systems. Additional post-shutdown characterization activities were performed to complete characterization activities as well as verify assumptions made in the Decommissioning Plan (DP) that were based on a separate activation analysis (ESI 2009 and WMG 2009). Final status survey (FSS) activities began shortly after the issuance of the FSS plan in May 2011. The contractor completed measurement and sampling activities during the week of August 29, 2011.

  15. Corrective Action Investigation Plan for Corrective Action Unit 106: Areas 5, 11 Frenchman Flat Atmospheric Sites, Nevada Test Site, Nevada, Revision 0

    SciTech Connect

    Patrick Matthews

    2010-04-01

    -based final action level. The TED will be calculated as the total of separate estimates of internal and external doses. Results from the analysis of soil samples collected from sample plots will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at the center of each sample plot will be used to measure external radiological dose. The presence and nature of contamination from other types of releases (such as migration and excavation as well as 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. The scope of the corrective action investigation for CAU 106 includes the following activities: •Conduct radiological surveys. •Collect and submit environmental samples for laboratory analysis to determine internal dose rates and the presence of contaminants of concern. •If contaminants of concern are present, collect additional samples to define the extent of the contamination and determine the area where TED at the site exceeds final action levels (i.e., corrective action boundary). •Collect samples of investigation-derived waste, as needed, for waste management purposes.

  16. The Idaho National Engineering Laboratory site environmental report for calendar year 1989

    SciTech Connect

    Hoff, D.L.; Mitchell, R.G.; Bowman, G.C.; Moore, R.

    1990-06-01

    To verify that exposures resulting from operations at the Department of Energy (DOE) nuclear facilities have remained very small, each site at which nuclear activities are underway operates an environmental surveillance program to monitor the air, water and any other pathway where radionuclides from operations might conceivably reach workers or members of the public. This report presents data collected in 1989 for the routine environmental surveillance program conducted by the Radiological and Environmental Sciences Laboratory (RESL) of DOE and the US Geological Survey (USGS) at the Idaho National Engineering Laboratory (INEL) site. The environmental surveillance program for the INEL and vicinity for 1989 included the collection and analysis of samples from potential exposure pathways. Three basic groups of samples were collected. Those collected within the INEL boundaries will be referred to as onsite samples. Samples collected outside, but near, the Site boundaries will be referred to as boundary samples or part of a group of offsite samples. Samples collected from locations considerably beyond the Site boundaries will be referred to as distant samples or part of the offsite group. With the exception of Craters of the Moon National Monument, the distant locations are sufficiently remote from the Site to ensure that detectable radioactivity is primarily due to natural background sources or sources other than INEL operations. 35 refs., 14 figs., 13 tabs.

  17. CONFIRMATORY SURVEY REPORT FOR THE SECTION 4 AREA AT THE RIO ALGOM AMBROSIA LAKE FACILITY NEW MEXICO

    SciTech Connect

    W.C. Adams

    2010-02-12

    The objectives of the confirmatory survey were to verify that remedial actions were effective in meeting established release criteria and that documentation accurately and adequately described the final radiological conditions of the RAM Ambrosia Lake, Section 4 Areas.

  18. Environmental/Radiological Assistance Directory (ERAD) | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Energy Environmental/Radiological Assistance Directory (ERAD) Environmental/Radiological Assistance Directory (ERAD) The Environmental Radiological Assistance Directory or ERAD, developed by AU-22, serves as an assistance tool to the DOE complex for protection of the public and environment from radiation. The ERAD is a combination webinar/conference call, designed to provide DOE and its contractors a forum to share information, lessons-learned, best practices, emerging trends, compliance

  19. 2012 Environmental/Radiological Assistance Directory (ERAD) Presentations |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy Environmental/Radiological Assistance Directory (ERAD) Presentations 2012 Environmental/Radiological Assistance Directory (ERAD) Presentations 2012 Environmental/Radiological Assistance Directory (ERAD) Presentations November 2012; Environmental Measurements in an Emergency: This is not a Drill!; Stephen V. Musolino; Brookhaven National Laboratory (2.44 MB) November 2012; Brookhaven Graphite Research Reactor (BGRR) D&D Presentation for the DOE ERAD Working Group;

  20. Federal Radiological Monitoring and Assessment Center | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration | (NNSA) Federal Radiological Monitoring and Assessment Center The Federal Radiological Monitoring and Assessment Center (FRMAC) is a federal asset available on request by the Department of Homeland Security (DHS) and state and local agencies to respond to a nuclear or radiological incident. The FRMAC is an interagency organization with representation from the NNSA, the Department of Defense (DOD), the Environmental Protection Agency (EPA), the Department of Health

  1. GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material |

    National Nuclear Security Administration (NNSA)

    National Nuclear Security Administration | (NNSA) GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material May 29, 2014 GTRI's Remove Program works around the world to remove excess nuclear and radiological materials that could be used for a nuclear weapon or radiological dispersal device (RDD), or "dirty bomb". Mission In 2004 NNSA established the Global Threat Reduction Initiative (GTRI) in the Office of Defense Nuclear Nonproliferation to, as quickly as possible,

  2. Surface Contamination Guidelines/Radiological Clearance of Property |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy Surface Contamination Guidelines/Radiological Clearance of Property Surface Contamination Guidelines/Radiological Clearance of Property Authorized limits govern the control and clearance of personal and real property. They are radionuclide concentrations or activity levels approved by DOE to permit the clearance of property from DOE radiological control for either restricted or unrestricted use, consistent with DOE's radiation protection framework and standards for the

  3. Radiological Weapons: How Great Is The Danger?

    SciTech Connect

    Moore, G M

    2003-06-01

    One of the underlying purposes of this paper is to provoke thinking about the interplay between the regulation of radioactive materials and the risk of their use in an radiological weapon (RW). Also considered in this paper are the types of RWs that a terrorist might use, the nature of the threat and danger posed by the various types of RWs, the essential elements that must be considered in responding to the terrorist use of an RW, and what steps may need to be taken a priori to minimize the consequences of the inevitable use of an RW. Because radiological dispersal devices (RDDs) have been the focus of so much recent concern and because RDDs are arguably the most likely of RWs to be used by a terrorist group, a major focus of this paper will be on RDDs. Radiological weapons are going to be used by some individual or group, if not this year then next year, or at some time in the foreseeable future. A policy of focusing resources solely on prevention of their use would leave any government open to significant economic disruption when the inevitable use occurs. Preplanning can limit the injuries, property damage, and economic losses that might result from the use of an RW. Moreover, a combination of efforts to prevent and to minimize the impact of RWs may significantly discourage potential users. The dangers from RWs can be dealt with while society continues to enjoy the benefits of nuclear technology that were promised under Atoms for Peace. However, some restructuring of our use of radioactive materials is necessary to ensure that the current and future uses of radioactive materials outweigh the potential disruption caused by misuse of the materials in RWs.

  4. Weld Repair of a Stamped Pressure Vessel in a Radiologically Controlled Zone

    SciTech Connect

    Cannell, Gary L.; Huth, Ralph J.; Hallum, Randall T.

    2013-08-26

    In September 2012 an ASME B&PVC Section VIII stamped pressure vessel located at the DOE Hanford Site Effluent Treatment Facility (ETF) developed a through-wall leak. The vessel, a steam/brine heat exchanger, operated in a radiologically controlled zone (by the CH2MHill PRC or CHPRC), had been in service for approximately 17 years. The heat exchanger is part of a single train evaporator process and its failure caused the entire system to be shut down, significantly impacting facility operations. This paper describes the activities associated with failure characterization, technical decision making/planning for repair by welding, logistical challenges associated with performing work in a radiologically controlled zone, performing the repair, and administrative considerations related to ASME code requirements.

  5. Radiological Source Term Estimates for the February 14, 2014...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    This document corresponds to Appendix D: Modeling Integrated Summary Report of the Technical Assessment Team Report. Radiological Source Term Estimates for the February 14, 2014 ...

  6. DOE-HDBK-1122-99; Radiological Control Technician Training

    Energy.gov [DOE] (indexed site)

    7 Interaction of Radiation with Matter Instructor's Guide 1.07-1 Course Title: Radiological Control Technician Module Title: Interaction of Radiation with Matter Module Number: ...

  7. NNSA Nuclear/Radiological Incident Response | National Nuclear...

    National Nuclear Security Administration (NNSA)

    NNSA NuclearRadiological Incident Response December 01, 2008 The National Nuclear Security Administration (NNSA) has over 60 years of nuclear weapons experience in responding to ...

  8. Fifth Anniversary of Radiological Alarm Response Training for...

    National Nuclear Security Administration (NNSA)

    Fifth Anniversary of Radiological Alarm Response Training for Local Law Enforcement and ... program for local law enforcement and other critical first responders around the country. ...

  9. ORISE: Radiological Terrorism Toolkit | How ORISE is Making a...

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Education (ORISE) distributed more than 400 radiological terrorism toolkits filled with key resources, such as training guidelines, clinical directives, details about radioactive...

  10. An Assessment Of The External Radiological Impact In Areas Of...

    OpenEI (Open Energy Information) [EERE & EIA]

    Assessment Of The External Radiological Impact In Areas Of Greece With Elevated Natural Radioactivity Jump to: navigation, search OpenEI Reference LibraryAdd to library Journal...

  11. The Readiness of the Department's Federal Radiological Monitoring...

    Energy.gov [DOE] (indexed site)

    However, we did identify issues with aging equipment and potential reliability issues that could adversely impact the timeliness of FRMAC's response to radiological emergencies. ...

  12. NNSA, Philippine Nuclear Research Institute to Prevent Radiological...

    National Nuclear Security Administration (NNSA)

    to our shared efforts to prevent nuclear and radiological terrorism and the proliferation of nuclear weapons," said NNSA Deputy Administrator for Defense Nuclear ...

  13. Trending and root cause analysis of TWRS radiological problem reports

    SciTech Connect

    Brown, R.L.

    1997-07-31

    This document provides a uniform method for trending and performing root cause analysis for radiological problem reports at Tank Waste Remediation System (TWRS).

  14. Radiological Release Event at the Waste Isolation Pilot Plant...

    Energy.gov [DOE] (indexed site)

    radiological release occurred at the Department of Energy Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. Because access to the underground was restricted following...

  15. NNSA Receives Excellence Award for Radiological Security Enhancements...

    National Nuclear Security Administration (NNSA)

    ... nuclear propulsion; and responds to nuclear and radiological emergencies in the U.S. and abroad. Visit http:nnsa.energy.gov for more information. ...

  16. DOE-HDBK-1122-99; Radiological Control Technician Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ... to enable the rescuer to avoid becoming contaminated. has facial contamination?" b. ... the nature of the injuries, the radiological conditions, the location of the injured, etc. ...

  17. DOE-HDBK-1122-99; Radiological Control Technician Training

    Energy.gov [DOE] (indexed site)

    PNL; Richland, Wa. 3. DOE-STD-1098-99, "DOE Radiological Control Standard". 4. 10 CFR Part 835 (1998) "Occupational Radiation Protection". 5. "The Health Physics and ...

  18. DOE-HDBK-1122-99; Radiological Control Technician Training

    Energy Saver

    "DOE Radiological Control Standard" (reference TSP project number SAFT- 0039). 4. 10 CFR Part 835 (1998) "Occupational Radiation Protection" Instructional Aids: 1. Overheads 2. ...

  19. DOE-HDBK-1122-99; Radiological Control Technician Training

    Energy Saver

    ... Accordingly, DOE shall ensure radiological measurements, analyses, worker monitoring results and estimates of public exposures are accurate and appropriately made. 10 CFR 835 ...

  20. DOE-HDBK-1122-99; Radiological Control Technician Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    L 2.10.13 State the requirements for removing or releasing materials from any radiological area. References: 1. 10 CFR 835, "Occupational Radiation Protection" (1998) 2. ...