National Library of Energy BETA

Sample records for radiological surveys site

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

    SciTech Connect (OSTI)

    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.

  2. An aerial radiological survey of the Central Savannah River Site, Aiken, South Carolina

    SciTech Connect (OSTI)

    Feimster, E.L.

    1991-09-01

    An aerial radiological survey was conducted over a 194-square- kilometer (75-square-mile) area encompassing the central portion of the Savannah River Site (SRS). The survey was flown during February 10--27, 1987. These radiological measurements were used as baseline data for the central area and for determining the extent of man-made radionuclide distribution. Previous SRS surveys included small portions of the area; the 1987 survey was covered during the site- wide survey conducted in 1979. Man-made radionuclides (including cobalt-60, cesium-137, protactinium-234m, and elevated levels of uranium-238 progeny) that were detected during the survey were typical of those produced by the reactor operations and material processing activities being conducted in the area. The natural terrestrial radiation levels were consistent with those measured during prior surveys of other SRS areas. 1 refs., 4 figs.

  3. Radiological survey of the inactive uranium-mill tailings at the Spook site, Converse County, Wyoming

    SciTech Connect (OSTI)

    Haywood, F.F.; Christian, D.J.; Chou, K.D.; Ellis, B.S.; Lorenzo, D.; Shinpaugh, W.H.

    1980-05-01

    Results of a radiological survey performed at the Spook site in Converse County, Wyoming, in June 1976, are presented. The mill at this site was located a short distance from the open-pit mine where the ore was obtained and where part of the tailings was dumped into the mine. Several piles of overburden or low-grade ore in the vicinity were included in the measurements of above-ground gamma exposure rate. The average exposure rate over these piles varied from 14 ..mu..R/hr, the average background exposure rate for the area, to 140 ..mu..R/hr. The average exposure rate for the tailings and former mill area was 220 ..mu..R/hr. Movement of tailings particles down dry washes was evident. The calculated concentration of /sup 226/Ra in ten holes as a function of depth is presented graphically.

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

    SciTech Connect (OSTI)

    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.

  5. Nevada Test Site Radiological Control Manual

    SciTech Connect (OSTI)

    Radiological Control Managers' Council Nevada Test Site

    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.

  6. An aerial radiological survey of Naturita, Colorado and surrounding area

    SciTech Connect (OSTI)

    Jaffe, R.J.

    1982-09-01

    An aerial radiological survey of four areas in the vicinity of the inactive uranium mill tailings site at Naturita, Colorado was conducted in September 1981. The average background radiation exposure rate (normalized to 3 feet above the ground) was about 10 to 16 microroentgens per hour ({mu}R/h). Uranium ore or tailings were detected at Naturita, Nucla, East Vancorum, and the general region downriver and downwind from the former mill tailings site.

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

    SciTech Connect (OSTI)

    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.

  8. Nevada National Security Site Radiological Control Manual

    SciTech Connect (OSTI)

    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 low-level radioactive waste and the handling of radioactive sources. Remediation of contaminated land areas may also result in radiological exposures.

  9. An aerial radiological survey of Naturita, Colorado and surrounding area. Date of survey: September 1981

    SciTech Connect (OSTI)

    Jaffe, R.J.

    1982-09-01

    An aerial radiological survey of four areas in the vicinity of the inactive uranium mill tailings site at Naturita, Colorado was conducted in September 1981. The average background radiation exposure rate (normalized to 3 feet above the ground) was about 10 to 16 microroentgens per hour ({mu}R/h). Uranium ore or tailings were detected at Naturita, Nucla, East Vancorum, and the general region downriver and downwind from the former mill tailings site.

  10. Autonomous mobile robot for radiologic surveys

    DOE Patents [OSTI]

    Dudar, Aed M. (Augusta, GA); Wagner, David G. (Augusta, GA); Teese, Gregory D. (Aiken, SC)

    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.

  11. Autonomous mobile robot for radiologic surveys

    DOE Patents [OSTI]

    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.

  12. Solar Site Survey Toolkit

    Broader source: 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.

  13. APPENDIX B: RADIOLOGICAL DATA METHODOLOGIES 1998 SITE ENVIRONMENTAL REPORTB-1

    E-Print Network [OSTI]

    APPENDIX B: RADIOLOGICAL DATA METHODOLOGIES 1998 SITE ENVIRONMENTAL REPORTB-1 APPENDIX B Radiological Data Methodologies 1. DOSE CALCULATION - ATMOSPHERIC RELEASE PATHWAY Dispersion of airborne and distance. Facility-specific radionuclide release rates (in Ci per year) were also used. All annual site

  14. Nevada Test Site Radiological Control Manual

    SciTech Connect (OSTI)

    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.

  15. C-1 2003 SITE ENVIRONMENTAL REPORT Radiological Data Methodologies

    E-Print Network [OSTI]

    Homes, Christopher C.

    C-1 2003 SITE ENVIRONMENTAL REPORT APPENDIX C Radiological Data Methodologies DOSE CALCULATION to calculate annual disper- sions for the midpoint of a given sector and distance. Facility Protection Agency Exposure Factors Handbook (EPA 1996). RADIOLOGICAL DATA PROCESSING Radiation events occur

  16. Radiological Survey of the U. S. Army Reserve Property at the Weldon Spring Site. Final Report. IR-300-302-1.02.

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal Gas &SCE-SessionsSouth DakotaRobbins and Myers Co -VANaval Ordnance -Sites »

  17. Savannah River Site Radiological Technology Center's Efforts Supporting Waste Minimization

    SciTech Connect (OSTI)

    Rosenberger, K. H.; Smith, L. S.; Bates, R. L.

    2003-02-25

    This paper describes the efforts of the newly formed Radiological Technology Center (RTC) at the Department of Energy's Savannah River Site (SRS) to support waste minimization. The formation of the RTC was based upon the highly successful ALARA Center at the DOE Hanford Site. The RTC is tasked with evaluation and dissemination of new technologies and techniques for radiological hazard reduction and waste minimization. Initial waste minimization efforts have focused on the promotion of SRS containment fabrication capabilities, new personal protective equipment and use of recyclable versus disposable materials.

  18. Radiological survey of the inactive uranium-mill tailings at Naturita, Colorado

    SciTech Connect (OSTI)

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

    1980-03-01

    Results of a radiological survey of the inactive uranium-mill site a Naturita, Colorado, conducted in May 1976, are presented. The spread of tailings was detected in the area surrounding the site by means of direct above ground gamma measurements and analysis of surface and subsurface soil samples. Radiochemical analyses of water samples in the vicinity of the tailings pile indicate local surface water contamination immediately downstream from the pile, although the /sup 226/Ra concentration in the water at that point as well below the concentration guide for drinking water. The calculated subsoil distribution of /sup 226/Ra in onsite holes is presented graphically. The tailings at this site were removed and reprocessed at another location. This operation was completed and reclamation of the site was conducted in 1978. Consequently the information in this report documents radiological conditions that no longer exist.

  19. Results of the radiological survey at 142 West Central Avenue, Maywood, New Jersey (MJ041)

    SciTech Connect (OSTI)

    Foley, R.D.; Crutcher, J.W.

    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, 142 West Central Avenue, Maywood, New Jersey (MJ041), was conducted during 1988. Results of the survey indicated scattered radiation or ''shine'' from a storage pile, located off the property, containing residual radioactive material. Lead-shielded measurements showed 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. 4 refs., 8 figs., 3 tabs.

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

    SciTech Connect (OSTI)

    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.

  1. Radiological Dose Assessment 8 2011 Site environmental report8-1

    E-Print Network [OSTI]

    Radiological Dose Assessment 8 2011 Site environmental report8-1 BNL's annual radiological dose assessment assures stakeholders that on-site facilities and operations are in compliance with federal, state and local regulations, and that the public is protected. The potential radiological dose to members

  2. Radiological Dose Assessment 8 2013 SITE ENVIRONMENTAL REPORT8-1

    E-Print Network [OSTI]

    Radiological Dose Assessment 8 2013 SITE ENVIRONMENTAL REPORT8-1 BNL's annual radiological dose assessment assures stakeholders that on-site facilities and BNL operations are in compliance with federal, state, and local regulations, and that the public is protected. The potential radiological dose

  3. Radiological Dose Assessment 8 2012 SITE ENVIRONMENTAL REPORT8-1

    E-Print Network [OSTI]

    Radiological Dose Assessment 8 2012 SITE ENVIRONMENTAL REPORT8-1 BNL's annual radiological dose assessment assures stakeholders that on-site facilities and BNL operations are in compliance with federal, state, and local regulations, and that the public is protected. The potential radiological dose

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

  6. C-1 2001 SITE ENVIRONMENTAL REPORT APPENDIX C: RADIOLOGICAL DATA METHODOLOGIES

    E-Print Network [OSTI]

    Homes, Christopher C.

    C-1 2001 SITE ENVIRONMENTAL REPORT APPENDIX C: RADIOLOGICAL DATA METHODOLOGIES DOSE CALCULATION sector and distance. Facility-specificradionuclidereleaserates(incuries per year [Ci/yr]) were also used 1996). RADIOLOGICAL DATA PROCESSING Radiation events occur in a random fashion

  7. Site survey method and apparatus

    DOE Patents [OSTI]

    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.

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

    SciTech Connect (OSTI)

    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.

  9. Results of the radiological survey at 24 Long Valley Road, Lodi, New Jersey (LJ048)

    SciTech Connect (OSTI)

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

    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 monozite 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, 24 Long Valley Road, Lodi, New Jersey (LJ048), 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. 4 refs., 8 figs., 3 tabs.

  10. Results of the radiological survey at 99 Garibaldi Avenue, Lodi, New Jersey (LJ064)

    SciTech Connect (OSTI)

    Foley, R.D.; 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, 99 Garibaldi Avenue, Lodi, New Jersey (LJ064), was conducted during 1987. 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. 4 refs., 8 figs., 3 tabs.

  11. Results of the radiological survey at 106 Columbia Lane, Lodi, New Jersey (LJ063)

    SciTech Connect (OSTI)

    Foley, R.D.; 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, 106 Columbia Lane, Lodi, New Jersey (LJ063), was conducted during 1987. 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. 4 refs., 7 figs., 3 tabs.

  12. Results of the radiological survey at 6 Branca Court, Lodi, New Jersey (LJ041)

    SciTech Connect (OSTI)

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

    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 rate 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, 6 Branca Court, Lodi, New Jersey (LJ041), was conducted during 1985 and 1986. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Act program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 6 figs., 3 tabs.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

  15. Results of the radiological survey at 2 Branca Court, Lodi, New Jersey (LJ036)

    SciTech Connect (OSTI)

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

    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 1961 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, 2 Branca Court, Lodi, New Jersey (LJ036), 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.

  16. Results of the radiological survey at 174 Essex Street, Lodi, New Jersey (LJ073)

    SciTech Connect (OSTI)

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

    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, 174 Essex Street, Lodi, New Jersey (LJ073), was conducted during 1987. 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.

  17. Results of the radiological survey at 17 Redstone Lane, Lodi, New Jersey (LJ030)

    SciTech Connect (OSTI)

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

    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, 17 Redstone Lane, Lodi, New Jersey (LJ030), 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. 4 refs., 7 figs., 3 tabs.

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

    SciTech Connect (OSTI)

    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 160 Essex Street, Lodi, New Jersey (LJ072)

    SciTech Connect (OSTI)

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

    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, 160 Essex Street, Lodi, New Jersey (LJ072), was conducted during 1987. 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. 4 refs., 10 figs., 2 tabs.

  20. Results of the radiological survey at 10 Hancock Street, Lodi, New Jersey (LJ031)

    SciTech Connect (OSTI)

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

    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 from radionuclide analyses. The survey of this site, 10 Hancock Street, Lodi, New Jersey (LJ031), 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. 4 refs., 4 figs., 3 tabs.

  1. Results of the radiological survey at 4 Branca Court, Lodi, New Jersey (LJ037)

    SciTech Connect (OSTI)

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

    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, 4 Branca Court, Lodi, New Jersey (LJ037), was conducted during 1985 and 1986. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. However, this property is apparently located directly over the old Lodi Brook streambed. This factor in combination with the elevated gamma logs of several auger holes is sufficient to recommend this site for inclusion in the DOE remedial action program. 5 refs., 5 figs., 4 tabs.

  2. Results of the radiological survey at 4 Hancock Street, Lodi, New Jersey (LJ060)

    SciTech Connect (OSTI)

    Foley, R.D.; Carier, 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 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, 4 Hancock Street, Lodi, New Jersey (LJ060), was conducted during 1985 and 1986. Gamma logging results found during this survey and during a previous survey conducted by Bechtel National, Incorporated, strongly indicated radionuclide concentrations in subsurface soil in excess of DOE remedial action criteria. This finding, coupled with the fact that adjacent properties have been found to be contaminated and that Lodi Brook apparently flows under the property, suggests that it be considered for inclusion in the DOE remedial action program. 5 refs., 4 figs., 4 tabs.

  3. Results of the radiological survey at 6 Hancock Street, Lodi, New Jersey (LJ033)

    SciTech Connect (OSTI)

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

    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, 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, 6 Hancock Street, Lodi, New Jersey (LJ033), was conducted during 1985 and 1986. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site.

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

    SciTech Connect (OSTI)

    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.

  5. Results of the radiological survey at 12 Long Valley Road, Lodi, New Jersey (LJ054)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.; 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 extracting 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, 12 Long Valley Road, Lodi, New Jersey (LJ054), was conducted during 1985 and 1986. 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 10 Long Valley Road, Lodi, New Jersey (LJ055)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.; 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 survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 10 Long Valley Road, Lodi, New Jersey (LJ055), was conducted during 1985 and 1986. 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. 4 refs., 5 figs., 3 tabs.

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

    SciTech Connect (OSTI)

    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.

  8. Results of the radiological survey at 19 Redstone Lane, Lodi, New Jersey (LJ056)

    SciTech Connect (OSTI)

    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, 19 Redstone Lane, Lodi, New Jersey (LJ056), was conducted during 1985 and 1986. 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. 4 refs., 4 figs., 3 tabs.

  9. Results of the radiological survey at 1 Branca Court, Lodi, New Jersey (LJ034)

    SciTech Connect (OSTI)

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

    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, 1 Branca Court, Lodi, New Jersey (LJ034), was conducted during 1985 and 1986. 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. 4 refs., 4 figs., 3 tabs.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

  14. Intelligent Sensor Management in Nuclear Searches and Radiological Surveys A.V. Klimenko1

    E-Print Network [OSTI]

    Tanner, Herbert G.

    Intelligent Sensor Management in Nuclear Searches and Radiological Surveys A.V. Klimenko1 , W Special nuclear materials (SNMs) are weak emitters of radiation and are difficult to detect, especially developed intelligent sensor management strategies for nuclear search and radiological surveys

  15. Radiological Dose Assessment 8 2010 SITE ENVIRONMENTAL REPORT8-1

    E-Print Network [OSTI]

    Radiological Dose Assessment 8 2010 SITE ENVIRONMENTAL REPORT8-1 DRAFT The radiological dose assessment assures stakeholders that BNL facilities and operations are in compliance with federal, state, and local regulations and the public is protected. The potential radiological dose to members of the public

  16. Results of the radiological survey at 9 Redstone Lane, Lodi, New Jersey (LJ069)

    SciTech Connect (OSTI)

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

    1989-07-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process waste and residues associated with the production and refining of thorium and thorium compounds from monozite 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. Areas residents used the sandlike waste from this thorium extraction process mixed with teas 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 investigate 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 Redstone Lane, Lodi, New Jersey (LJ069), was conducted during 1987. Measurements at the private property located at 9 Redstone Lane indicate slightly elevated gamma exposure rates in association with cinder-like material observed in logging holes. These elevated levels result from naturally occurring radioactivity present in such substances as ashes and cinders. They are not related to the deposit of residues from processing operations at the MCW site. All other radiological findings conform to the guidelines established by the DOE for the Maywood, New Jersey, area remedial action plan. 4 refs., 3 figs., 3 tabs.

  17. Results of the radiological survey at the property at Main Street and Highway 46, Lodi, New Jersey (LJ074)

    SciTech Connect (OSTI)

    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 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 measurements of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site located at the intersection of Main Street and Highway 46, Lodi, New Jersey (LJ074), was conducted during 1987. While some radiological measurements taken at the vacant lot at the intersection of Main Street and Highway 46 were greater than background levels typically encountered in the northern New Jersey area, no radiation levels nor radionuclide concentrations exceeded the applicable DOE criteria. The survey results demonstrate that the radiological condition of this property conforms to DOE guidelines for remedial action. 4 refs., 5 figs., 3 tabs.

  18. Radiological survey of the inactive uranium-mill tailings at Riverton, Wyoming

    SciTech Connect (OSTI)

    Haywood, F.F.; Lorenzo, D.; Christian, D.J.; Chou, K.D.; Ellis, B.S.; Shinpaugh, W.H.

    1980-03-01

    Results of a radiological survey performed at the Riverton, Wyoming site in July 1976, are presented. The average external gamma exposure rate at 1 m over the tailings pile was 56 ..mu..R/hr. The corresponding rate for the former mill area was 97 ..mu..R/hr. Movement of tailings particles in a dry wash is evident; but it appears that, in general, the earth cover over the tailings pile has been effective in limiting both wind and water erosion of the tailings. The calculated concentration of /sup 226/Ra as a function of depth in 15 augered holes is presented graphically. A survey of the Teton Division Lumber Company property in Riverton showed a maximum external gamma exposure rate of 270 ..mu..R/hr.

  19. C-1 2002 SITE ENVIRONMENTAL REPORT APPENDIX C: RADIOLOGICAL DATA METHODOLOGIES

    E-Print Network [OSTI]

    Homes, Christopher C.

    C-1 2002 SITE ENVIRONMENTAL REPORT APPENDIX C: RADIOLOGICAL DATA METHODOLOGIES APPENDIX C Radiological Data Methodologies DOSE CALCULATION - ATMOSPHERIC RELEASE PATHWAY The effective dose equivalent. Facility-specificradionuclidereleaserates(incu- ries per year [Ci/yr]) were also used.All annual site

  20. C-1 SITE ENVIRONMENTAL REPORT 2000 APPENDIX C: RADIOLOGICAL DATA METHODOLOGIES

    E-Print Network [OSTI]

    Homes, Christopher C.

    C-1 SITE ENVIRONMENTAL REPORT 2000 APPENDIX C: RADIOLOGICAL DATA METHODOLOGIES APPENDIX C: Radiological Data Methodologies DOSE CALCULATION - ATMOSPHERIC RELEASE PATHWAY The effective dose equivalent. Facility-specific radionu- clide release rates (in curies per year [Ci/yr]) were also used. All annual site

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

    SciTech Connect (OSTI)

    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.

  2. Multiscale spatial density smoothing: an application to large-scale radiological survey and anomaly detection

    E-Print Network [OSTI]

    Tansey, Wesley; Reinhart, Alex; Scott, James G

    2015-01-01

    We consider the problem of estimating a spatially varying density function, motivated by problems that arise in large-scale radiological survey and anomaly detection. In this context, the density functions to be estimated are the background gamma-ray energy spectra at sites spread across a large geographical area, such as nuclear production and waste-storage sites, military bases, medical facilities, university campuses, or the downtown of a city. Several challenges combine to make this a difficult problem. First, the spectral density at any given spatial location may have both smooth and non-smooth features. Second, the spatial correlation in these density functions is neither stationary nor locally isotropic. Third, the spatial correlation decays at different length scales at different locations in the support of the underlying density. Finally, at some spatial locations, there is very little data. We present a method called multiscale spatial density smoothing that successfully addresses these challenges. ...

  3. Results of the radiological survey at 105 Garibaldi Avenue, Lodi, New Jersey (LJ065)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.; 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 survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 105 Garibaldi Avenue, Lodi, New Jersey (LJ065), was conducted during 1987. 4 refs., 4 figs., 3 tabs.

  4. Results of the radiological survey at 9 Branca Court, Lodi, New Jersey (LJ042)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.; 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 survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 9 Branca Court, Lodi, New Jersey (LJ042), was conducted during 1985 and 1986. 4 refs., 7 figs., 3 tabs.

  5. Results of the radiological survey at 112 Columbia Lane, Lodi, New Jersey (LJ068)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.; 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 survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 112 Columbia Lane, Lodi, New Jersey (LJ068), was conducted during 1987. 4 refs., 6 figs., 3 tabs.

  6. Results of the radiological survey at 3 Branca Court, Lodi, New Jersey (LJ038)

    SciTech Connect (OSTI)

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

    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, 3 Branca Court, Lodi, New Jersey (LJ038), was conducted during 1985 and 1986. 4 refs., 4 figs., 3 tabs.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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 72 Sidney Stret, Lodi, New Jersey (LJ067)

    SciTech Connect (OSTI)

    Foley, R.D.; Carrier, R.F.; Floyd, L.M.; Crutcher, J.W. (Oak Ridge National Lab., TN (USA))

    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 residues 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, 72 Sidney Street, Lodi, New Jersey (LJ067), was conducted during 1987. Results indicated concentrations of {sup 232}Th slightly in excess of the DOE remedial action criterion for subsurface soil. This finding, coupled with the fact that adjacent properties have been designated by DOE for remedial action, and that the old Lodi Brook streambed is apparently beneath the property, suggests that it be considered for inclusion in the DOE remedial action program. 4 refs., 5 figs., 3 tabs.

  10. Results of the radiological survey at 5 Branca Court, Lodi, New Jersey (LJ039)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.; 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 survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 5 Branca Court, Lodi, New Jersey (LJ039), was conducted during 1985 and 1986. 4 refs., 5 figs., 3 tabs.

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

    SciTech Connect (OSTI)

    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.

  12. Background Radiation Survey of the Radiological/Nuclear Countermeasures Test and Evaluation Center

    SciTech Connect (OSTI)

    Colin Okada

    2010-09-16

    In preparation for operations at the Radiological/Nuclear Countermeasures Test and Evaluation Complex (Rad/NucCTEC), the Department of Homeland Security Domestic Nuclear Detection Office (DHS/DNDO) requested that personnel from the Remote Sensing Laboratory (RSL) conduct a survey of the present radiological conditions at the facility. The measurements consist of the exposure rate from a high-pressure ion chamber (HPIC), high-resolution spectra from a high-purity germanium (HPGe) system in an in situ configuration, and low-resolution spectra from a sodium iodide (NaI) detector in a radiation detection backpack. Measurements with these systems were collected at discrete locations within the facility. Measurements were also collected by carrying the VECTOR backpack throughout the complex to generate a map of the entire area. The area was also to be surveyed with the Kiwi (an array of eight-2-inch x 4-inch x 16-inch NaI detectors) from the Aerial Measuring Systems; however, conflicts with test preparation activities at the site prevented this from being accomplished.

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

    SciTech Connect (OSTI)

    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.

  14. B-1 1999 SITE ENVIRONMENTAL REPORT APPENDIX B: RADIOLOGICAL DATA METHODOLOGIES

    E-Print Network [OSTI]

    B-1 1999 SITE ENVIRONMENTAL REPORT APPENDIX B: RADIOLOGICAL DATA METHODOLOGIES APPENDIX B: DOSE to calculate annual dispersions for the midpoint of a given sector and distance. Facility specific radionuclide Handbook (EPA 1996). RADIOLOGICAL DATA PROCESSING Radiation events occur in a random fashion

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

    SciTech Connect (OSTI)

    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.

  16. Improving Site-Specific Radiological Performance Assessments - 13431

    SciTech Connect (OSTI)

    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 probabilistic modeling and risk analysis, to guide improvements in PA. This decision-making approach, [4, 5, 6] provides a transparent formal framework for using a value- or objective-focused approach to decision-making. DA, as an analytical means to implement structured decision making, provides a context for both understanding how uncertainty affects decisions and for targeting uncertainty reduction. The proposed DA approach improves defensibility and transparency of decision-making. The DA approach is fully consistent with the need to perform realistic modeling (rather than conservative modeling), including evaluation of site-specific factors. Instead of using generic stylized scenarios for radionuclide fate and transport and for human exposures to radionuclides, site-specific scenarios better represent the advantages and disadvantages of alternative disposal sites or engineered designs, thus clarifying their differences as well as providing a sound basis for evaluation of site performance. The full DA approach to PA is described, from explicitly incorporating societal values through stakeholder involvement to model building. Model building involves scoping by considering features, events, processes, and exposure scenarios (FEPSs), development of a conceptual site model (CSM), translation into numerical models and subsequent computation, and model evaluation. These are implemented in a cycle of uncertainty analysis, sensitivity analysis and value of information analysis so that uncertainty can be reduced until sufficient confidence is gained in the decisions to be made. This includes the traditional focus on hydrogeological processes, but also places emphasis on other FEPSs such as biotically-induced transport and human exposure phenomena. The significance of human exposure scenarios is emphasized by modifying the traditional acronym 'FEPs' to include them, hence 'FEPSs'. The radioactive waste community is also recognizing that disposal sites are to be considered a national (or even global) resource. As such, there is a pressing need to optimize their utility withi

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

    SciTech Connect (OSTI)

    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 3013 Inner Can (IC) is nearly identical.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

  1. Results of the radiological survey at Kennedy Park, Money and Sidney Streets, Lodi, New Jersey (LJ062)

    SciTech Connect (OSTI)

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

    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, Kennedy Park, Money and Sidney Streets, Lodi, New Jersey (LJ062), was conducted during 1986 and 1987. 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. 4 refs., 4 figs., 3 tabs.

  2. An In Situ Radiological Survey of Three Canyons at the Los Alamos National Laboratory

    SciTech Connect (OSTI)

    R.J. Maurer

    1999-06-01

    An in situ radiological survey of Mortandad, Ten Site, and DP Canyons at the Los Alamos National Laboratory was conducted during August 19-30, 1996. The purpose of this survey was to measure the quantities of radionuclides that remain in the canyons from past laboratory operations. A total of 65 in situ measurements were conducted using high-resolution gamma radiation detectors at 1 meter above the ground. The measurements were obtained in the streambeds of the canyons beginning near the water-release points at the laboratories and extending to the ends of the canyons. Three man-made gamma-emitting radionuclides were detected in the canyons: americium-241 ({sup 241}Am), cesium-137 ({sup 137}Cs), and cobalt-60 ({sup 60}Co). Estimated contamination levels ranged from 13.3-290.4 picocuries per gram (pCi/g)for {sup 241}Am, 4.4-327.8 pCi/g for {sup 137}Cs, and 0.4-2.6 pCi/g for {sup 60}Co.

  3. Radiological survey of the inactive uranium-mill tailings at Lakeview, Oregon

    SciTech Connect (OSTI)

    Haywood, F.F.; Burden, J.E.; Ellis, B.S.; Loy, E.T.; Shinpaugh, W.H.

    1980-06-01

    The results of the radiological survey of the inactive uranium-mill site at Lakeview, Oregon, show that the average gamma-ray exposure rate 1 m above the tailings pile and the evaporation pond area (now dry) is close to the average background level for the area (11 ..mu..R/hr). The /sup 226/Ra concentration in most of the surface soil and sediment samples is also at or below the average background value for surface soil samples in the area (0.8 pCi/g). Calculated /sup 226/Ra concentrations, based on gamma radiation measurements in shallow (1-m-deep) holes, are in agreement with the results of surface soil and sediment analyses and with gamma-ray exposure rate measurements. The tailings at this site have been stabilized by the addition of 46 to 60 cm (18 to 24 in.) of soil that supports vigorous growth of vegetation. This treatment, coupled with a low-level inventory of /sup 226/Ra in the tailings (50 Ci), has resulted in limited spread of tailings by wind and water.

  4. Results of the radiological survey at the Napp Chemical Company, 199 Main Street, Lodi, New Jersey (LJ076)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.; 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 survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, the Napp Chemical Company, 199 Main Street, Lodi, New Jersey (LJ076), was conducted during 1987. 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. 4 refs., 8 figs., 3 tabs.

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

    SciTech Connect (OSTI)

    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.

  6. ORISE: Characterization surveys

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

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

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

    SciTech Connect (OSTI)

    Barnett, J. M.; 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.

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

    SciTech Connect (OSTI)

    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. Guide to radiological accident considerations for siting and design of DOE nonreactor nuclear facilities

    SciTech Connect (OSTI)

    Elder, J.C.; Graf, J.M.; Dewart, J.M.; Buhl, T.E.; Wenzel, W.J.; Walker, L.J.; Stoker, A.K.

    1986-01-01

    This guide was prepared to provide the experienced safety analyst with accident analysis guidance in greater detail than is possible in Department of Energy (DOE) Orders. The guide addresses analysis of postulated serious accidents considered in the siting and selection of major design features of DOE nuclear facilities. Its scope has been limited to radiological accidents at nonreactor nuclear facilities. The analysis steps addressed in the guide lead to evaluation of radiological dose to exposed persons for comparison with siting guideline doses. Other possible consequences considered are environmental contamination, population dose, and public health effects. Choices of models and parameters leading to estimation of source terms, release fractions, reduction and removal factors, dispersion and dose factors are discussed. Although requirements for risk analysis have not been established, risk estimates are finding increased use in siting of major nuclear facilities, and are discussed in the guide. 3 figs., 9 tabs.

  10. Hanford Site Annual Report Radiological Dose Calculation Upgrade Evaluation

    SciTech Connect (OSTI)

    Snyder, Sandra F.

    2010-02-28

    Operations at the Hanford Site, Richland, Washington, result in the release of radioactive materials to offsite residents. Site authorities are required to estimate the dose to the maximally exposed offsite resident. Due to the very low levels of exposure at the residence, computer models, rather than environmental samples, are used to estimate exposure, intake, and dose. A DOS-based model has been used in the past (GENII version 1.485). GENII v1.485 has been updated to a Windows®-based software (GENII version 2.08). Use of the updated software will facilitate future dose evaluations, but must be demonstrated to provide results comparable to those of GENII v1.485. This report describes the GENII v1.485 and GENII v2.08 dose exposure, intake, and dose estimates for the maximally exposed offsite resident reported for calendar year 2008. The GENII v2.08 results reflect updates to implemented algorithms. No two environmental models produce the same results, as was again demonstrated in this report. The aggregated dose results from 2008 Hanford Site airborne and surface water exposure scenarios provide comparable dose results. Therefore, the GENII v2.08 software is recommended for future offsite resident dose evaluations.

  11. 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 (OSTI)

    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 sampling and laboratory analyses are completed, the data are analyzed and included in an Environmental Baseline Summary (EBS) report for title transfer or in a Baseline Environmental Analysis Report (BEAR) for lease. The data from the BEAR is then used in a Screening-Level Human Health Risk Assessment (SHHRA) or a risk calculation (RC) to assess the potential risks to future owners/occupants. If title is to be transferred, release criteria in the form of specific activity concentrations called Derived Concentration Guideline Levels (DCGLs) will be developed for the each property. The DCGLs are based on the risk model and are used with the data in the EBS to determine, with statistical confidence, that the release criteria for the property have been met. The goal of the survey and sampling efforts is to (1) document the baseline conditions of the property (real or personal) prior to title transfer or lease, (2) obtain enough information that an evaluation of radiological risks can be made, and (3) collect sufftcient data so that areas that contain minimal residual levels of radioactivity can be identified and, following radiological control procedures, be released from radiological control. (It should be noted that release from radiological control does not necessarily mean free release because DOE may maintain institutional control of the site after it is released from radiological control). To meet the goals of this document, a Data Quality Objective (DQO) process will be used to enhance data collection efficiency and assist with decision-making. The steps of the DQO process involve stating the problem, identifying the decision, identifying inputs to the decision, developing study boundaries, developing the decision rule, and optimizing the design. This document describes the DQOs chosen for surveys and sampling efforts performed for the purposes listed above. The previous version to this document focused on the requirements for radiological survey and sampling protocols that are be used for leasing. Because the primary focus at this time is on title transfer, th

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

    SciTech Connect (OSTI)

    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.

  13. radiological. survey

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4) August 20123/%2A en46Afedkcp8/%2A4/%2A en7/%2A1/%2A

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

    SciTech Connect (OSTI)

    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.

  15. Results of the radiological survey at the Firemen's Memorial Park and Fire Hall No. 2, Garibaldi Avenue and Kennedy Drive, Lodi, New Jersey (LJ066)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.; Crutcher, J.W. (Oak Ridge National Lab., TN (USA))

    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 the gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, the Firemen's Memorial Park and Fire Hall 2, Garibaldi Avenue and Kennedy Drive, Lodi, New Jersey (LJ066) was conducted during 1987. 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. 4 refs., 10 figs., 3 tabs.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    Barnett, J. M.; 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 considerations. This DQO report also updates the discussion of the Environmental Monitoring Plan for the PNNL Site air samples and how existing Hanford Site monitoring program results could be used. 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.

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

    SciTech Connect (OSTI)

    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 into one of three categories: Class 1, Class 2 or Class 3 (a fourth category is a “Non-Impacted Class” which in the case of Building 2201 only pertained to exterior surfaces of the building.) The majority of the rooms were determined to fall in the less restrictive Class 3 category, however, Rooms 102, 104, 106, and 107 were identified as containing Class 1 and 2 areas. Building 2201 was divided into “survey units” and surveyed following the requirements of the Final Status Survey Plan for each particular class. As each survey unit was completed and documented, the survey results were evaluated. Each sample (static measurement) with units of counts per minute (cpm) was corrected for the appropriate background and converted to a value with units of dpm/100 cm2. With a surface contamination value in the appropriate units, it was compared to the surface contamination limits, or in this case the derived concentration guideline level (DCGLw). The appropriate statistical test (sign test) was then performed. If the survey unit was statistically determined to be below the DCGLw, then the survey unit passed and the null hypothesis (that the survey unit is above limits) was rejected. If the survey unit was equal to or below the critical value in the sign test, the null hypothesis was not rejected. This process was performed for all survey units within Building 2201. A total of thirty-three “Class 1,” four “Class 2,” and one “Class 3” survey units were developed, surveyed, and evaluated. All survey units successfully passed the statistical test. Building 2201 meets the release criteria commensurate with the Waste Acceptance Criteria (for radiological purposes) of the U10C landfill permit residing within NNSS boundaries. Based on the thorough statistical sampling and scanning of the building’s interior, Building 2201 may be considered radiologically “clean,” or free of contamination.

  19. Radiological effluents released from nuclear rocket and ramjet engine tests at the Nevada Test Site 1959 through 1969: Fact Book

    SciTech Connect (OSTI)

    Friesen, H.N.

    1995-06-01

    Nuclear rocket and ramjet engine tests were conducted on the Nevada Test Site (NTS) in Area 25 and Area 26, about 80 miles northwest of Las Vegas, Nevada, from July 1959 through September 1969. This document presents a brief history of the nuclear rocket engine tests, information on the off-site radiological monitoring, and descriptions of the tests.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    Broader source: 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.

  3. 2010 Ecological Survey of the Pacific Northwest National Laboratory Site

    SciTech Connect (OSTI)

    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 animal species identified on the PNNL Site.

  4. The Northern Marshall Islands radiological survey: A quality control program for radiochemical and gamma spectroscopy analysis

    SciTech Connect (OSTI)

    Kehl, S.R.; Mount, M.E.; Robison, W.L.

    1995-09-01

    From 1979 to 1989, approximately 25,000 Post Northern Marshall Islands Radiological Survey (PNMIRS) samples were collected, and over 71,400 radiochemical and gamma spectroscopy analyses were performed to establish the concentration of {sup 90}Sr, {sup 137}Cs, {sup 241}Am, and plutonium isotopes in soil, vegetation, fish, and animals in the Northern Marshall Islands. While the Low Level Gamma Counting Facility (B379) in the Health and Ecological Assessment (HEA) division accounted for over 80% of all gamma spectroscopy analyses, approximately 4889 radiochemical and 5437 gamma spectroscopy analyses were performed on 4784 samples of soil, vegetation, terrestrial animal, and marine organisms by outside laboratories. Four laboratories were used by Lawrence Livermore National Laboratory (LLNL) to perform the radiochemical analyses: Thermo Analytical Norcal, Richmond, California (TMA); Nuclear Energy Services, North Carolina State University (NCSU); Laboratory of Radiation Ecology, University of Washington (LRE); and Health and Ecological Assessment (HEA) division, LLNL, Livermore, California. Additionally, LRE and NCSU were used to perform gamma spectroscopy analyses. The analytical precision and accuracy were monitored by including blind duplicates and natural matrix standards in each group of samples analyzed. On the basis of reported analytical values for duplicates and standards, 88% of the gamma and 87% of the radiochemical analyses in this survey were accepted. By laboratory, 93% of the radiochemical analyses by TMA; 88% of the gamma-ray spectrometry and 100% of the radiochemistry analyses by NCSU; 89% of the gamma spectroscopy and 87% of the radiochemistry analyses by LRE; and 90% of the radiochemistry analyses performed by HEA`s radiochemistry department were accepted.

  5. 2011 Annual Ecological Survey: Pacific Northwest National Laboratory Site

    SciTech Connect (OSTI)

    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 upland areas of the PNNL site in 2011. Efforts in 2011 to control noxious weed populations (comprising plant species designated as Class B noxious weeds by the Washington State Noxious Weed Control Board) discovered in 2009 and initially treated with herbicides in 2010 are described in Appendix B.

  6. COT"IPREITENS IVE RADIOLOGICAL SURVEY OFF-SITE PROPERTY P NIAGARA FALIS STORAGE SITE

    Office of Legacy Management (LM)

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  7. ORISE: Radiological program assessment services

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

    DOECAP-qualified auditors coordinate and conduct radiological control audits of treatment, storage and disposal facilities and other sites as requested. Radiological facility...

  8. Radiological survey of the inactive uranium-mill tailings at Ambrosia Lake, New Mexico

    SciTech Connect (OSTI)

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

    1980-06-01

    The inactive uranium-mill tailings pile at Ambrosia Lake, New Mexico, contains approximately 1520 Ci of /sup 226/Ra in 2.4 million metric tons of tailings covering an area of 43 hectares. All of the former mill buildings were intact and, at the time of this survey, several were in use. The tailings have not been stabilized, but the crusty surface is reported to be resistant to wind erosion. The average gamma-ray exposure rate 1 m above the tailings is 720 ..mu..R/h while the average rate in the former mill area is 150 ..mu..R/h. The adjacent area, between the mill site, ponds, and tailings pile, has an average exposure rate of 230 ..mu..R/h. Gamma radiation measurements outside these areas, as well as the results of analyses of surface or near-surface sediment and soil samples, show fairly wide dispersion of contamination around the site. The subsurface distribution of /sup 226/Ra in 18 holes drilled at the site, calculated from gamma-ray monitoring data, is presented graphically and compared with measured concentrations in two holes.

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

    SciTech Connect (OSTI)

    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.

  10. 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 (OSTI)

    Fournier, Sean Donovan; Beall, Patrick S [Sandia National Laboratories, Livermore, CA; 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.

  11. Radiological Control Manual

    SciTech Connect (OSTI)

    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.

  12. 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 (OSTI)

    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 allow for the safe exhumation of the Special Nuclear Material in existing SLDA trenches. (authors)

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

    SciTech Connect (OSTI)

    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 exposed individual at the closest NTS boundary to the proposed Divine Strake experiment, as estimated by the CAP88-PC model, was 0.005 mrem with wind blowing directly towards that location. Boundary dose, as modeled by NARAC, ranged from about 0.006 to 0.007 mrem. Potential doses to actual offsite populated locations were generally two to five times lower still, or about 40 to 100 times lower then the 0.1 mrem level at which EPA approval is required pursuant to Section 61.96.

  14. ORISE: Multi-Agency Radiation Survey and Site Investigation Manual

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

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  15. ORNL/TM-11118 RESULTS OF THE RADIOLOGICAL SURVEY AT METPATH INCORPORAT...

    Office of Legacy Management (LM)

    for elemental rare earths at various sites in the Teter- boro and Maywood areas of New Jersey . . . . . . 14 vii ACKNOWLEDGMENTS .J Research for this project was sponsored...

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

    SciTech Connect (OSTI)

    Barnett, J. M.; 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.

  17. Surplus Facilities Management Program. Post-remedial-action survey report for SNAP-8 Experimental Reactor Facility, Building 010 site, Santa Susana Field Laboratories, Rockwell International, Ventura County, California

    SciTech Connect (OSTI)

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

    1984-04-01

    Based on the results of the radiological assessment, the Argonne National Laboratory Radiological Survey Group arrived at the following conclusions: (1) soil contaminated with the radionuclides /sup 60/Co and /sup 152/Eu of undetermined origin was detected in the southwest quadrant of the Building 010 site. /sup 60/Co was also detected in one environmental sample taken from an area northwest of the site and in a borehole sample taken from the area that previously held the radioactive gas hold-up tanks. Uranium was detected in soil from a hole in the center of the building site and in a second hole southwest of the building site. In all cases, the radionuclide levels encountered in the soil were well below the criteria set by DOE for this site; and (2) the direct instrument readings at the surface of the site were probably the result of natural radiation (terrestrial and celestial), as well as shine from the material being stored at the nearby RMDF facility. There was no evidence that the contaminated soil under the asphalt pad contributed detectable levels to the total background readings.

  18. PRELIMINqRY RADIOLOGICAL SURVEY REPORT OF THE FORMER STATEN ISLAND WAREHOUSE SITE

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal Gas &SCE-SessionsSouth DakotaRobbins and700 GJO-2003-411-TACe - .'pJ y, 22/4 PRELIMINqRY

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

    SciTech Connect (OSTI)

    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.

  20. Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Gunnison, Colorado. Attachment 5, Supplemental radiological data: Final report

    SciTech Connect (OSTI)

    Not Available

    1992-10-01

    Diffusion coefficients for radon gas in earthen materials are required to design suitable radon-barrier covers for uranium tailings impoundments and other materials that emit radon gas. Many early measurements of radon diffusion coefficients relied on the differences in steady-state radon fluxes measured from radon source before and after installation of a cover layer of the material being tested. More recent measurements have utilized the small-sample transient (SST) technique for greater control on moistures and densities of the test soils, greater measurement precision, and reduced testing time and costs. Several of the project sites for the US Department of Energy`s Uranium Mill Tailings Remedial Action (UMTRA) Program contain radiologically contaminated subsurface material composed predominantly of cobbles, gravels andsands. Since remedial action designs require radon diffusion coefficients for the source materials as well as the cover materials, these cobbly and gravelly materials also must be tested. This report contains the following information: a description of the test materials used and the methods developed to conduct the SST radon diffusion measurements on cobbly soils; the protocol for conducting radon diffusion tests oncobbly soils; the results of measurements on the test samples; and modifications to the FITS computer code for analyzing the time-dependent radon diffusion data.

  1. An Archaeological Survey for the Bastille Pipline and Gulag Well Site in Fort Bend County Texas 

    E-Print Network [OSTI]

    Moore, William; Baxter, Edward

    2015-07-28

    An archaeological survey of a proposed natural gas pipeline (2500 feet) and well site (three acres) on the Central Unit of the Texas Department of Criminal Justice in Fort Bend County, Texas was performed by Brazos Valley Research Associates (BVRA...

  2. An archaeological survey of the 12.536 acre proposed Tiffany Park site, Brazos County, Texas 

    E-Print Network [OSTI]

    Moore, William

    2015-06-04

    An archaeological survey of the 12.536 acre site of the proposed Tiffany Park in Brazos County, Texas was conducted by Brazos Valley Research Associates in August of 1993 under Texas Antiquities Committee permit number 1293. During the course...

  3. ORNL-5680 Radiological Surveys

    Office of Legacy Management (LM)

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  4. 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 (OSTI)

    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 occurring radionuclides. The radionuclides cesium-134 and -137 were identified in only two samples at each station collected in the weeks following the destruction of the nuclear power reactor in Fukushima, Japan, on March 11, 2011. Observed gamma energy values never exceeded the local background by more than 4 ?R/h. The higher observed gamma values were coincident with wind from any of the cardinal directions, which suggests that there is no significant transport from the Clean Slate contamination areas. Annual average daily gamma values at the TTR stations are higher than at the surrounding CEMP stations, but they are equivalent to or just slightly higher than the background estimates made at locations at equivalent elevations, such as Denver, Colorado. Winds in excess of approximately 15 mph begin to resuspend soil particles and create dust, but dust generation is also affected by soil temperature, relative humidity, and soil water content. Power curves provide good predictive equations for dust concentration as a function of wind speed. However, winds in the highest wind speed category occur infrequently. iii

  5. 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 (OSTI)

    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 sewer system via this float-controlled pump. Solids in the bottom of the sump consisted of an estimated 1-ft{sup 3} coarse-grained material that varied in thickness from 0 to 4 in. with no suspended fraction. The RA consisted of removing the water in the sump and then removing and sampling the solids. The solids were mixed with grout after removal and allowed to set. The solids were then disposed off-site at an approved disposal facility. The building sump will remain until the K-1006 building is demolished. The actions for the K- 1006 sump are described in the revised Phased Construction Completion Report for Exposure Unit (EU) Z2-33, which received regulatory approval in December 2009.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

  8. Archaeological survey of the McGee Ranch vicinity, Hanford Site, Washington

    SciTech Connect (OSTI)

    Gard, H.A.; Poet, R.M.

    1992-09-01

    In response to a request for a cultural resources review from Westinghouse Hanford Company for the Action Plan for Characterization of McGee Ranch Soil, Pacific Northwest Laboratory's Hanford Cultural Resources Laboratory (HCRL) conducted an archaeological survey of the McGee Ranch vicinity, located in the northwest portion of the Hanford Site. Staff members covered 8.4 km{sup 2} and recorded 42 cultural resources; 22 sites, and 20 isolated artifacts. Only 2 sites and 3 isolates were attributed to a prehistoric Native American occupation. The historic sites date from the turn of the century to the 1940s and are representative of the settlement patterns that occurred throughout the Columbia Basin. In addition to an archaeological pedestrian survey of the project area, we conducted literature and records searches and examined available aerial photographs. Records kept at HCRL were reviewed to determine if any archaeological survey had been conducted previously within the project area. Although no survey had been conducted, portions of the area adjacent to project boundaries were surveyed in 1988 and 1990. During those surveys, historic and prehistoric cultural resources were observed, increasing the possibility that similar land usage had taken place within the current project boundaries. Literature searches established a general historical sequence for this area. Aerial photographs alerted researchers to homesteads and linear features, such as roads and irrigation ditches, that might not be apparent from ground level.

  9. Archaeological survey of the McGee Ranch vicinity, Hanford Site, Washington

    SciTech Connect (OSTI)

    Gard, H.A.; Poet, R.M.

    1992-09-01

    In response to a request for a cultural resources review from Westinghouse Hanford Company for the Action Plan for Characterization of McGee Ranch Soil, Pacific Northwest Laboratory`s Hanford Cultural Resources Laboratory (HCRL) conducted an archaeological survey of the McGee Ranch vicinity, located in the northwest portion of the Hanford Site. Staff members covered 8.4 km{sup 2} and recorded 42 cultural resources; 22 sites, and 20 isolated artifacts. Only 2 sites and 3 isolates were attributed to a prehistoric Native American occupation. The historic sites date from the turn of the century to the 1940s and are representative of the settlement patterns that occurred throughout the Columbia Basin. In addition to an archaeological pedestrian survey of the project area, we conducted literature and records searches and examined available aerial photographs. Records kept at HCRL were reviewed to determine if any archaeological survey had been conducted previously within the project area. Although no survey had been conducted, portions of the area adjacent to project boundaries were surveyed in 1988 and 1990. During those surveys, historic and prehistoric cultural resources were observed, increasing the possibility that similar land usage had taken place within the current project boundaries. Literature searches established a general historical sequence for this area. Aerial photographs alerted researchers to homesteads and linear features, such as roads and irrigation ditches, that might not be apparent from ground level.

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

    SciTech Connect (OSTI)

    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.

  11. Radiological Control Manual. Revision 0, January 1993

    SciTech Connect (OSTI)

    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.

  12. Magnetic field survey at PG&E photovoltaic sites

    SciTech Connect (OSTI)

    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.

  13. Radiological-dose assessments of atolls in the northern Marshall Islands

    SciTech Connect (OSTI)

    Robison, W.L.

    1983-04-01

    The Marshall Islands in the Equatorial Pacific, specifically Enewetak and Bikini Atolls, were the site of US nuclear testing from 1946 through 1958. In 1978, the Northern Marshall Islands Radiological Survey was conducted to evaluate the radiological conditions of two islands and ten atolls downwind of the proving grounds. The survey included aerial external gamma measurements and collection of soil, terrestrial, and marine samples for radionuclide analysis to determine the radiological dose from all exposure pathways. The methods and models used to estimate doses to a population in an environment where natural processes have acted on the source-term radionuclides for nearly 30 y, data bases developed for the models, and results of the radiological dose analyses are described.

  14. Raghavan et al: Wireless Camera and Site Survey issues over an IEEE 802.11b based wireless network test bed Wireless Camera and Site Survey issues over an IEEE 802.11b

    E-Print Network [OSTI]

    Raghavan et al: Wireless Camera and Site Survey issues over an IEEE 802.11b based wireless network test bed Wireless Camera and Site Survey issues over an IEEE 802.11b based wireless network test bed Sunil Raghavan, Henry N. Jerez, Ramiro Jordan, Chaouki T. Abdallah Electrical and Computer Engineering

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

    SciTech Connect (OSTI)

    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.

  16. Hanford Site

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

    D&D 100K Area D&D 100K Area D&D 100K Area D&D 100K Area D&D 100K Area D&D U Plant D&D (Radiological Surveys) U Plant D&D (Radiological Surveys) U Plant D&D U Plant D&D U Plant...

  17. Hanford Site

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

    stops on her tour was the site's largest groundwater treatment facility. The 200 West Pump and Treat System removes multiple chemical and radiological contaminants from...

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

    SciTech Connect (OSTI)

    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.

  19. Radiological survey and evaluation of the fallout area from the Trinity test: Chupadera Mesa and White Sands Missile Range, New Mexico

    SciTech Connect (OSTI)

    Hansen, W.R.; Rodgers, J.C.

    1985-06-01

    Current radiological conditions were evaluated for the site of the first nuclear weapons test, the Trinity test, and the associated fallout zone. The test, located on White Sands Missile Range, was conducted as part of the research with nuclear materials for the World War II Manhattan Engineer District atomic bomb project. Some residual radioactivity attributable to the test was found in the soils of Ground Zero on White Sands Missile Range and the areas that received fallout from the test. The study considered relevant information including historical records, environmental data extending back to the 1940s, and new data acquired by field sampling and measurements. Potential exposures to radiation were evaluated for current land uses. Maximum estimated doses on Chupadera Mesa and other uncontrolled areas are less than 3% of the DOE Radiation Protection Standards (RPSs). Radiation exposures during visits to the US Army-controlled Ground Zero area are less than 1 mrem per annual visit or less than 0.2% of the RPS for a member of the public. Detailed data and interpretations are provided in appendixes. 14 figs., 45 tabs.

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

    SciTech Connect (OSTI)

    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 offshore southeastern Florida by conducting a geophysical survey of pre-selected areas with subsequent post-processing and expert data interpretation by geophysicists and experienced marine biologists knowledgeable about the general project area. The second step sought to validate the benthic habitat types interpreted from the geophysical data by conducting benthic video and photographic field surveys of selected habitat types. The goal of this step was to determine the degree of correlation between the habitat types interpreted from the geophysical data and what actually exists on the seafloor based on the benthic video survey logs. This step included spot-checking selected habitat types rather than comprehensive evaluation of the entire area covered by the geophysical survey. It is important to note that non-invasive survey methods were used as part of this study and no devices of any kind were either temporarily or permanently attached to the seabed as part of the work conducted under this project.

  1. Description of the Formerly Utilized Sites Remedial Action Program

    SciTech Connect (OSTI)

    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.

  2. I COMPREHENSIVE RADIOLOGICAL SURVEY I

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal Gas &SCE-SessionsSouthReport for the t-) S/,,5 'a C O M P R E H E N SGwen} ;im I

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

    SciTech Connect (OSTI)

    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.

  4. 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 (OSTI)

    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.

  5. An Archaeological Survey of the 85 Acre Bay City High School Site in Central Matagorda County, Texas 

    E-Print Network [OSTI]

    Moore, William

    2015-06-10

    Brazos Valley Research Associates (BVRA) conducted a 100% pedestrian survey of an 85 acre tract of land, the site of the proposed Bay City Independent School District High School in north-central Matagorda County, Texas on May 23-24, 1999...

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

    Broader source: 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.

  7. 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 (OSTI)

    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).

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

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

    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...

  9. CONFIRMATORY SURVEY OF THE FUEL OIL TANK AREA HUMBOLDT BAY POWER PLANT EUREKA, CALIFORNIA

    SciTech Connect (OSTI)

    WADE C. ADAMS

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

    SciTech Connect (OSTI)

    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 inverted, yielding a velocity model that shows lateral heterogeneity similar to the 2006 DC resistivity models. Finally, we collected P-wave data along a second transect in Area 2, located north of the first line and in an area of a very minor fault that was targeted by another 2006 DC resistivity survey. The P-wave refraction velocity model shows generally high velocities, with a zone of somewhat lower velocities in the central part of the transect. The position of the low velocity zone corresponds with the location of a minor fault, though it is unclear whether the two are related. Together, these results demonstrate the value of geophysical data for mapping the subsurface extent of faults. The 2007 DC resistivity data complement the 2006 data and provide important new detail of the overlapping fault splays. The seismic data demonstrate the ability of P-wave refraction methods to identify the damage zones at faults, and they show the difficulties associated with S-wave methods in areas with caliche. Combining all of the geophysical data from the Area 7 studies, we are able to develop a coherent interpretation of the relation between the site geology, the fault, and the observations.

  11. Standardized radiological dose evaluations

    SciTech Connect (OSTI)

    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.

  12. FORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM ELIMINATION REPORT

    Office of Legacy Management (LM)

    .- - -- CONTENTS INTRODUCTION BACKGROUND Site Function Site Description Radiological History and Status ELIMINATION ANALYSIS REFERENCES ii - ,. -- Page 1 4 4 ..I - --...

  13. Radiological control manual. Revision 1

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

  15. Surveys

    Broader source: 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...

  16. An Archaeological Survey for Suemaur Exploration & Production, LLC's Hoskins Mound-Olympia and Mckinley Prospects Well Pad Sites and Access Roads in Brazoria County Texas 

    E-Print Network [OSTI]

    Moore, William

    2015-07-30

    An archaeological survey of two proposed well pad sites and access roads in the Brazoria National Wildlife Refuge in south Brazoria County, Texas was performed by Brazos Valley Research Associates (BVRA) on February 5, ...

  17. A Cultural Resources Survey of the 14 Acre Support Services Building Site for Texas A&M University in Central Brazos County, Texas 

    E-Print Network [OSTI]

    Moore, William

    2015-06-05

    An archaeological survey of the 14 acre site of the proposed Support Services Building in Brazos County, Texas was conducted in April of 1994 by Brazos Valley Research Associates (BVRA) of Bryan, Texas. The area was covered using the pedestrian...

  18. An archaeological survey of a 13.8 acre tract of land: The proposed solid waste transfer station site, Lavaca County, Texas 

    E-Print Network [OSTI]

    Moore, William

    2015-06-04

    of prehistoric or historic sites. Fieldwork was performed on February 12, 1993 by Brazos Valley Research Associates with William E. Moore acting as Principal Investigator and conducting the survey. The project was conducted under Texas Antiquities Permit Number...

  19. An Archaeological Survey for Suemaur Exploration & Production, LLC's Hoskins Mound-Pocono Prospect Well Pad Site and Access Road in Brazoria County Texas 

    E-Print Network [OSTI]

    Moore, William

    2015-07-30

    An archaeological survey of a proposed well pad site and access road in the Brazoria National Wildlife Refuge in south Brazoria County, Texas was performed by Brazos Valley Research Associates (BVRA) on February 5, 2010. The area investigated...

  20. Routine Radiological Environmental Monitoring Plan. Volume 1

    SciTech Connect (OSTI)

    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.

  1. 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 (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

  3. 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 (OSTI)

    Bolch, W.E. [University of Florida; Hurtado, J.L. [University of Florida; Lee, C. [University of Florida; Manger, Ryan P [ORNL; Hertel, Nolan [Georgia Institute of Technology; Burgett, E. [Georgia Institute of Technology; Dickerson, W. [Armed Force Radiobiological Research Institute

    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 conducted in a low background, and possibly mobile, facility positioned at the triage location. Net count rate data are provided in both tabular and graphical format within a series of eight handbooks available at the CDC website (http://www.bt.cdc.gov/radiation/clinicians/evaluation).

  4. An Archaeological Survey of a Proposed School Site in Central Montgomery County, Texas 

    E-Print Network [OSTI]

    Moore, William

    2015-07-07

    An archaeological evaluation of a proposed school site (17 acres) in central Montgomery County, Texas was performed by Brazos Valley Research Associates (BVRA) in April 2003 with William E. Moore the Principal Investigator. This project falls under...

  5. ALMA Memo 470 RFI Survey at the ALMA Site at Chajnantor

    E-Print Network [OSTI]

    Groppi, Christopher

    system consisted of an antenna, a preamplifier, and a spectrum analyzer (Figure 1). The antenna 2 and 3). A PC provided data storage and test sequencing in communication with the spectrum analyzer survey. Figure 3: Biconical antenna with preamps, rotor, and tripod. #12;5 Figure 4: Spectrum analyzer

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

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

    2005-02-01

    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.

  9. 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 (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

  11. Regional Radiological Security Partnership in Southeast Asia – Increasing the Sustainability of Security Systems at the Site-Level by Using a Model Facility Approach

    SciTech Connect (OSTI)

    Chamberlain, Travis L.; Dickerson, Sarah; Ravenhill, Scott D.; Murray, Allan; Morris, Frederic A.; Herdes, Gregory A.

    2009-10-07

    In 2004, Australia, through the Australian Nuclear Science and Technology Organisation (ANSTO), created the Regional Security of Radioactive Sources (RSRS) project and partnered with the U.S. Department of Energy’s Global Threat Reduction Initiative (GTRI) and the International Atomic Energy Agency (IAEA) to form the Southeast Asian Regional Radiological Security Partnership (RRSP). The intent of the RRSP is to cooperate with countries in Southeast Asia to improve the security of their radioactive sources. This Southeast Asian Partnership supports objectives to improve the security of high risk radioactive sources by raising awareness of the need and developing national programs to protect and control such materials, improve the security of such materials, and recover and condition the materials no longer in use. The RRSP has utilized many tools to meet those objectives including: provision of physical protection upgrades, awareness training, physical protection training, regulatory development, locating and recovering orphan sources, and most recently - development of model security procedures at a model facility. This paper discusses the benefits of establishing a model facility, the methods employed by the RRSP, and three of the expected outcomes of the Model Facility approach. The first expected outcome is to increase compliance with source security guidance materials and national regulations by adding context to those materials, and illustrating their impact on a facility. Second, the effectiveness of each of the tools above is increased by making them part of an integrated system. Third, the methods used to develop the model procedures establishes a sustainable process that can ultimately be transferred to all facilities beyond the model. Overall, the RRSP has utilized the Model Facility approach as an important tool to increase the security of radioactive sources, and to position facilities and countries for the long term secure management of those sources.

  12. Roadmap: Radiologic Imaging Sciences -Nuclear Medicine (with AAS Radiologic Technology) -

    E-Print Network [OSTI]

    Sheridan, Scott

    Roadmap: Radiologic Imaging Sciences - Nuclear Medicine (with AAS Radiologic Technology) - Bachelor Safety 3 C #12;Roadmap: Radiologic Imaging Sciences - Nuclear Medicine (with AAS Radiologic Technology of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-NMRT] Regional College Catalog Year: 2013-2014 Page 1

  13. Roadmap: Radiologic Imaging Sciences -Nuclear Medicine (with AAS Radiologic Technology) -

    E-Print Network [OSTI]

    Sheridan, Scott

    Roadmap: Radiologic Imaging Sciences - Nuclear Medicine (with AAS Radiologic Technology) - Bachelor Imaging Sciences - Nuclear Medicine (with AAS Radiologic Technology) - Bachelor of Radiologic and Imaging of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-NMRT] Regional College Catalog Year: 2012-2013 Page 1

  14. ORISE: Radiological program assessment services

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformationJesseworkSURVEY UNIVERSEHow ORISE is Making aDoseRadiological program assessment

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

    SciTech Connect (OSTI)

    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 and citizens – all have to be part of the decision process when siting a new waste management facility. The opinions of the young respondents were significantly influenced by their level of environmental knowledge.

  16. Radiological Assistance Program

    Broader source: Directives, Delegations, and 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.

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

    SciTech Connect (OSTI)

    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. Web Toolbox Guide for Creating Web Surveys Main web tools page: http://www.webservices.uiuc.edu bookmark this site

    E-Print Network [OSTI]

    Liberzon, Daniel

    Web Toolbox Guide for Creating Web Surveys Main web tools page: http, feedback, etc) 2. Create a New Web Survey (FYI..."surveys" are almost identical to "forms"--use survey use the html options in many fields (in both event descriptions as well as forms and surveys). Here

  19. Survey of HEPA filter applications and experience at Department of Energy sites

    SciTech Connect (OSTI)

    Carbaugh, E.H.

    1981-11-01

    Results indicated that approximately 58% of the filters surveyed were changed out in the 1977 to 1979 study period and some 18% of all filters were changed out more than once. Most changeouts (60%) were due to the existence of a high pressure drop across the filter, indicative of filter plugging. The next most recurrent reasons for changeout and their percentage changeouts were leak test failure (15%) and preventive maintenance service life limit (12%). An average filter service life was calculated to be 3.0 years with a 2.0-year standard deviation. The labor required for filter changeout was calculated as 1.5 manhours per filter changed. Filter failures occurred with approximately 12% of all installed filters. Most failures (60%) occurred for unknown reasons and handling or installation damage accounted for an additional 20% of all failures. Media ruptures, filter frame failures and seal failures occurred with approximately equal frequency at 5 to 6% each. Subjective responses to the questionnaire indicate problems are: need for improved acid and moisture resistant filters; filters more readily disposable as radioactive waste; improved personnel training in filter handling and installation; and need for pretreatment of air prior to HEPA filtration.

  20. Radiation Shielding and Radiological Protection

    E-Print Network [OSTI]

    Shultis, J. Kenneth

    Radiation Shielding and Radiological Protection J. Kenneth Shultis Richard E. Faw Department Shielding and Radiological Protection .. Example Calculations for Distributed Sources

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

    SciTech Connect (OSTI)

    Carpenter, P.J. [Northern Illinois Univ., DeKalb, IL (United States). Dept. of Geology]|[Oak Ridge National Lab., TN (United States); Doll, W.E. [Oak Ridge National Lab., TN (United States); Phillips, B.E. [Paducah Gaseous Diffusion Plant, KY (United States)

    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.

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

    SciTech Connect (OSTI)

    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.

  3. DOE standard: Radiological control

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

  5. Site Energy Surveys 

    E-Print Network [OSTI]

    Lockett, W., Jr.; Guide, J. J.

    1981-01-01

    Operating improvements and selected investments have already improved US refining and petrochemical energy utilization efficiency by about 20%, compared to 1972 operating efficiencies. This is equivalent to saving well over 250,000 B/D of crude...

  6. radiological. survey | National Nuclear Security Administration

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power AdministrationRobust,Field-effectWorkingLosThe 26thI D- 6 0 4 2 r m m m m port m fmProjectImagesradiation

  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...

  8. 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...

  9. NEVADA TEST SITE RADIOLOGICAL CONTROL MANUAL

    Office of Scientific and Technical Information (OSTI)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield MunicipalTechnical Report:Speeding accessby aLED Street LightingFromJune 2013TEC

  10. 2010 Radiological Monitoring Results Associated with the Advance Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    mike lewis

    2011-02-01

    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.

  11. 2013 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2014-02-01

    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.

  12. 2012 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2013-02-01

    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.

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

    SciTech Connect (OSTI)

    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.

  14. NV/YMP RADIOLOGICAL CONTROL MANUAL

    SciTech Connect (OSTI)

    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.

  15. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY The Radiological Research Accelerator Facility

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 1 The Radiological Research Accelerator Facility for Radiological Research (CRR). Using the mi- crobeam facility, 10% of the cells were irradiated through particle beam as well as the first fo- cused microbeam in the new microbeam facility. · Another significant

  16. Radiological worker training

    SciTech Connect (OSTI)

    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.

  17. 324 Building Baseline Radiological Characterization

    SciTech Connect (OSTI)

    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.

  18. A Cultural Resources Survey of the Site of the Proposed Henderson Land Company Section 4 Commercial Site in Central Walker, Texas 

    E-Print Network [OSTI]

    Moore, William

    2015-06-30

    not reveal evidence of a prehistoric site. Courthouse research conducted as part of a separate environmental assessment indicated that no standing structures were ever present in the project area. Therefore, it is recommended that construction be allowed...

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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 Appendix F of this report. The requirements are summarized in Section 5.2 of this report. The proposed post-closure requirements consist of visual inspections to determine the condition of postings and radiological surveys to verify contamination has not migrated. NNSA/NSO requests the following: (1) A Notice of Completion from the Nevada Division of Environmental Protection to NNSA/NSO for closure of CAU 547; and (2) The transfer of CAU 547 from Appendix III to Appendix IV, Closed Corrective Action Units, of the FFACO.

  2. Radiological Control Technician Training

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested PartiesBuildingBudget ||Department ofRequest7of 9 Radiological Control

  3. Bibliography of publications related to the Yucca Mountain Site Characterization Project prepared by U.S. Geological Survey personnel through April 1991

    SciTech Connect (OSTI)

    Glanzman, V.M.

    1991-11-01

    Personnel of the US Geological Survey have participated in nuclear-waste management studies in the State of Nevada since the mid-1970`s. A bibliography of publications prepared principally for the US Department of Energy Yucca Mountain Site Characterization Project (formerly Nevada Nuclear Waste Storage Investigations) through April 1991 contains 475 entries in alphabetical order. The listing includes publications prepared prior to the inception of the Nevada Nuclear Waste Storage Investigations Project in April 1977 and selected publications of interest to the Yucca Mountain region. 480 refs.

  4. Roadmap: Radiologic Imaging Sciences Nuclear Medicine (with certification and ATS Radiologic Technology)

    E-Print Network [OSTI]

    Sheridan, Scott

    Roadmap: Radiologic Imaging Sciences ­ Nuclear Medicine (with certification and ATS Radiologic Technology) ­ Bachelor of Radiologic Imaging Sciences Technology [RE-BRIT-RIS-NMHO] Regional College Catalog technology; successfully completed the certification exam for the American Registry of Radiologic Technology

  5. 2011 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    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.

  6. Radiological Monitoring Continues at WIPP

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

    investigate this event. WIPP is developing a plan to safely re-enter the WIPP underground facility. Radiological professionals from other DOE locations and National Laboratories...

  7. BASF's Energy Survey Methodology 

    E-Print Network [OSTI]

    Theising, T. R.

    2005-01-01

    Methodology Thomas R. Theising BASF Corporation operates several dozen manufacturing Sites within NAFTA and periodically conducts Energy Surveys at each Site. Although these manufacturing sites represent a variety of industries, BASF has found success.... The discovery phase is the ?Energy Survey? itself. These Surveys involve plant personnel from various functions within Site operations. BASF applies the Pareto Principle in a variety of fashions: 20% of the operation consumes 80% of the energy, lets focus...

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

    SciTech Connect (OSTI)

    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.

  9. Smart Radiological Dosimeter

    DOE Patents [OSTI]

    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.

  10. Radiological Control Technician Training

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested PartiesBuildingBudget ||Department ofRequest7of 9 Radiological Control8 of 9

  11. Radiological Control Technician Training

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested PartiesBuildingBudget ||Department ofRequest7of 9 Radiological Control8 of 99

  12. Radiological Technician Training

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested PartiesBuildingBudget ||Department ofRequest7of 9 Radiological Control8 ofDOE

  13. Assessment of SRS radiological liquid and airborne contaminants and pathways

    SciTech Connect (OSTI)

    Jannik, G.T.

    1997-04-01

    This report compiles and documents the radiological critical-contaminant/critical-pathway analysis performed for SRS. The analysis covers radiological releases to the atmosphere and to surface water, which are the principal media that carry contaminants off site. During routine operations at SRS, limited amounts of radionuclides are released to the environment through atmospheric and/or liquid pathways. These releases potentially result in exposure to offsite people. Though the groundwater beneath an estimated 5 to 10 percent of SRS has been contaminated by radionuclides, there is no evidence that groundwater contaminated with these constituents has migrated offsite (Arnett, 1996). Therefore, with the notable exception of radiological source terms originating from shallow surface water migration into site streams, onsite groundwater was not considered as a potential exposure pathway to offsite people.

  14. The Radiological Research Accelerator THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY

    E-Print Network [OSTI]

    The Radiological Research Accelerator Facility #12;84 THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY Director: David J. Brenner, Ph.D., D.Sc., Manager: Stephen A. Marino, M.S. An NIH SupportedV/µm 4 He ions using the microbeam facility (Exp. 73) also continued. The transformation frequency

  15. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY The Radiological Research Accelerator Facility

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 71 The Radiological Research Accelerator Facility the irradiated cells. Both the microbeam and the track segment facilities continue to be utilized in various investigations of this phenomenon. The single- particle microbeam facility provides precise control of the number

  16. Radiological Research Accelerator Facility Service Request Form

    E-Print Network [OSTI]

    Radiological Research Accelerator Facility Service Request Form National Institute of Biomedical Imaging and Bioengineering Radiological Research Accelerator Facility Service request form Estimate when(s) to control for this experiment (if more than one, please prioritize): Radiological Research Accelerator

  17. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY #12;115 THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY An NIH-Supported Resource Center WWW.RARAF.ORG Director: David J. Brenner, Ph.D., D.Sc. Manager delighted that NIH funding for continued development of our single-particle microbeam facility was renewed

  18. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY

    E-Print Network [OSTI]

    175 THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY #12;176 #12;177 THE RADIOLOGICAL RESEARCH the microbeam and the track-segment facilities have been utilized in various investigations. Table 1 lists-segment facility. Samples are treated with graded doses of radical scavengers to observe changes in the cluster

  19. Radiological Dose Calculations for Fusion Facilities

    SciTech Connect (OSTI)

    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. Radiological Threat Reduction | ornl.gov

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

    Removal of radiological materials from unstable regions around the world, safely packaging and transporting those materials to a more stable state; and Protecting radiological...

  1. 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...

  2. Post-remedial-action survey report for Kinetic Experiment Water Boiler Reactor Facility, Santa Susana Field Laboratories, Rockwell International, Ventura County, California

    SciTech Connect (OSTI)

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

    1981-10-01

    Rockwell International's Santa Susana Laboratories in Ventura County, California, have been the site of numerous federally-funded contracted projects involving the use of radioactive materials. Among these was the Kinetics Experiment Water Boiler (KEWB) Reactor which was operated under the auspices of the US Atomic Energy Commission (AEC). The KEWB Reactor was last operated in 1966. The facility was subsequently declared excess and decontamination and decommissioning operations were conducted during the first half of calendar year 1975. The facility was completely dismantled and the site graded to blend with the surrounding terrain. During October 1981, a post-remedial-action (certification) survey of the KEWB site was conducted on the behalf of the US Department of Energy by the Radiological Survey Group (RSG) of the Occupational Health and Safety Division's Health Physics Section (OHS/HP) of Argonne National Laboratory (ANL). The survey confirmed that the site was free from contamination and could be released for unrestricted use.

  3. The radiological impact of the 2000 Hanford Fire (24-Command Fire) 

    E-Print Network [OSTI]

    Henderson, Ashley David

    2001-01-01

    into more populated areas. This paper examines the radiological impact of the 24-Command Fire, which occurred on the Hanford Site in late June 2000. Several different approaches are compared against each other to determine the validity of the results...

  4. Radiological characterization of main cooling reservoir bottom sediments at The South Texas Project Electrical Generating Station 

    E-Print Network [OSTI]

    Blankinship, David Randle

    1993-01-01

    The South Texas Project Electrical Generating Station (STPEGS operating license directs that an effective radiological environmental monitoring program be established. Site- specific data should then augment the generation of an accurate dose model...

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

    SciTech Connect (OSTI)

    Wickline, Alfred

    2005-12-01

    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 alternatives.

  6. 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 (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

  9. The Radiological Research Accelerator Facility

    SciTech Connect (OSTI)

    Hall, E.J.; Marino, S.A.

    1993-05-01

    The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which is used to generate a variety of well-characterized radiation beams for research in radiobiology, radiological physics, and radiation chemistry. It is part of the Center for Radiological Research (CRR) - formerly the Radiological Research Laboratory of Columbia University, and its operation is supported as a National Facility by the US Department of Energy (DOE). As such, RARAF is available to all potential users on an equal basis and scientists outside the CRR are encouraged to submit proposals for experiments at RARAF. The operation of the Van de Graaff is supported by the DOE, but the research projects themselves must be supported separately. This report provides a listing and brief description of experiments performed at RARAF during the May 1, 1992 through April 30, 1993.

  10. Radiological cleanup of Enewetak Atoll

    SciTech Connect (OSTI)

    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.

  11. Radiological Protection for DOE Activities

    Broader source: Directives, Delegations, and 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)

  12. Radiological assessment. A textbook on environmental dose analysis

    SciTech Connect (OSTI)

    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.

  13. Roadmap: Radiologic Technology Radiology Department Management Technology Associate of Technical Study

    E-Print Network [OSTI]

    Sheridan, Scott

    Roadmap: Radiologic Technology ­ Radiology Department Management Technology ­ Associate-Nov-13/LNHD This roadmap is a recommended semester-by-semester plan of study for this major. However

  14. Radiological Work Planning and Procedure

    SciTech Connect (OSTI)

    KURTZ, J.E.

    2000-01-01

    Each facility is tasked with maintaining personnel radiation exposure as low as reasonably achievable (ALARA). A continued effort is required to meet this goal by developing and implementing improvements to technical work documents (TWDs) and work performance. A review of selected TWDs from most facilities shows there is a need to incorporate more radiological control requirements into the TWD. The Radioactive Work Permit (RWP) provides a mechanism to place some of the requirements but does not provide all the information needed by the worker as he/she is accomplishing the steps of the TWD. Requiring the engineers, planners and procedure writers to put the radiological control requirements in the work steps would be very easy if all personnel had a strong background in radiological work planning and radiological controls. Unfortunately, many of these personnel do not have the background necessary to include these requirements without assistance by the Radiological Control organization at each facility. In addition, there seems to be confusion as to what should be and what should not be included in the TWD.

  15. 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 (OSTI)

    Patrick Matthews

    2011-08-01

    CAU 104 comprises the 15 CASs listed below: (1) 07-23-03, Atmospheric Test Site T-7C; (2) 07-23-04, Atmospheric Test Site T7-1; (3) 07-23-05, Atmospheric Test Site; (4) 07-23-06, Atmospheric Test Site T7-5a; (5) 07-23-07, Atmospheric Test Site - Dog (T-S); (6) 07-23-08, Atmospheric Test Site - Baker (T-S); (7) 07-23-09, Atmospheric Test Site - Charlie (T-S); (8) 07-23-10, Atmospheric Test Site - Dixie; (9) 07-23-11, Atmospheric Test Site - Dixie; (10) 07-23-12, Atmospheric Test Site - Charlie (Bus); (11) 07-23-13, Atmospheric Test Site - Baker (Buster); (12) 07-23-14, Atmospheric Test Site - Ruth; (13) 07-23-15, Atmospheric Test Site T7-4; (14) 07-23-16, Atmospheric Test Site B7-b; (15) 07-23-17, Atmospheric Test Site - Climax These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on April 28, 2011, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 104. The releases at CAU 104 consist of surface-deposited radionuclides from 30 atmospheric nuclear tests. The presence and nature of contamination at CAU 104 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the total effective dose (TED) 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.

  16. Corrective Action Site 02-37-02 Background Information and Comparison to Corrective Action Site 09-99-06

    SciTech Connect (OSTI)

    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-entry survey, and routine surveys around the crater lip did not identify alpha contamination. Background information includes several radiological surveys conducted after these two tests. The MULLET area has been surveyed frequently. The early surveys indicate the area as both contaminated and containing buried radioactive material. A survey conducted in 1970 found the radiological/chemical piping partially intact, including the 'Y' junction, and shows two runs of intact piping running past the U2am crater lip. The survey focused on the piping system itself and detected alpha contamination from 4 counts per minute (cpm) to 900,000 cpm. The highest value was at a pipe flange between a dirt pile and a dirt berm within the current site fence line. All readings were direct, and no smears were taken. A 1972 survey was essentially a repeat of the 1970 survey; however, it does not show the 'Y' junction nor does it show piping extending past the U2am crater lip. It also shows a new fence line separating the radiological/chemical piping from the U2am crater area with all piping within the fence. Alpha contamination was detected on pipe flanges during the survey, but alpha contamination was not detected on the dirt pile or the dirt berm. All readings were direct, and no smears were taken. Additional surveys were conducted in 1986, 1990, 1992, 1993, and 1996. One of the surveys focused on determining the extent of soil contamination around GZ. An alpha contamination plume extending approximately 200 feet south of GZ was detected in a swath approximately 100 feet wide. The maximum measurement was 15,000 cpm alpha. All surveys show the piping within the fence line. Recent surveys (2007 and 2008) were performed around the current fence line by the demarcation group. No removable contamination was identified during these surveys. In late 2008, a visual inspection of the site was conducted by the National Security Technologies, LLC, Environmental Restoration group. All piping is within the fence line. Photos taken during this site visit are attached.

  17. Environmental Survey preliminary report

    SciTech Connect (OSTI)

    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.

  18. Remaining Sites Verification Package for the 126-F-2, 183-F Clearwells, Waste Site Reclassification Form 2006-017

    SciTech Connect (OSTI)

    R. A. Carlson

    2006-05-04

    The 126-F-2 site is the clearwell facility formerly used as part of the reactor cooling water treatment at the 183-F facility. During demolition operations in the 1970s, potentially contaminated debris was disposed in the eastern clearwell structure. The site has been remediated by removing all debris in the clearwell structure to the Environmental Restoration Disposal Facility. The results of radiological surveys and visual inspection of the remediated clearwell structure show neither residual contamination nor the potential for contaminant migration beyond the clearwell boundaries. The results of verification sampling at the remediation waste staging area demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River.

  19. 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...

  20. Nuclear / Radiological Advisory Team | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    Radiological Advisory Team | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering...

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

    National Nuclear Security Administration (NNSA)

    Radiological Threat Task Force Established | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing...

  2. Radiological characterization of a vitrification facility for decommissioning

    SciTech Connect (OSTI)

    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)

  3. Final Report - Independent Confirmatory Survey Summary and Results for the Hematite Decommissioning Project

    SciTech Connect (OSTI)

    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.

  4. Mobile autonomous robotic apparatus for radiologic characterization

    DOE Patents [OSTI]

    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.

  5. Mobile autonomous robotic apparatus for radiologic characterization

    DOE Patents [OSTI]

    Dudar, Aed M. (Dearborn, MI); Ward, Clyde R. (Aiken, SC); Jones, Joel D. (Aiken, SC); Mallet, William R. (Cowichan Bay, CA); Harpring, Larry J. (North Augusta, SC); Collins, Montenius X. (Blackville, SC); Anderson, Erin K. (Pleasanton, CA)

    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.

  6. Annual Site Environmental Report for Calendar Years 2005-2006

    SciTech Connect (OSTI)

    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.

  7. International Data on Radiological Sources

    SciTech Connect (OSTI)

    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.

  8. Departmental Radiological Emergency Response Assets

    Broader source: Directives, Delegations, and 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.

  9. Radiological science involves technologists use

    E-Print Network [OSTI]

    Sibille, Etienne

    English Composition II Mathematics MATH 0110 Fundamentals of Mathematics THE HUMAN EXPERIENCE Students new Clinical Experience Radiographic Procedures II Radiation Protection II Radiographic Film ProcessingRadiological science involves technologists use X-rays to see the inside of the human body. Health

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

    SciTech Connect (OSTI)

    Wickline, Alfred

    2006-12-01

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

  11. Radiological Training for Tritium Facilities

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested PartiesBuildingBudget ||Department ofRequest7of 9 Radiological Control8

  12. Understanding Mechanisms of Radiological Contamination

    SciTech Connect (OSTI)

    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.

  13. Radioactive Waste Management Complex low-level waste radiological performance assessment

    SciTech Connect (OSTI)

    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.

  14. Hanford site near-facility environmental monitoring annual report, calendar year 1996

    SciTech Connect (OSTI)

    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.

  15. ORISE: REAC/TS Radiological Incident Medical Consultation

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformationJesseworkSURVEY UNIVERSEHow ORISE is Making a DifferenceRadiological Incident

  16. BUSINESS PLAN LBNL Main Site

    E-Print Network [OSTI]

    Eisen, Michael

    Materials Does your facility have on site (for any purpose) at any one me, hazardous materials at or above substance speci ed in 40 CFR Part 355, Appendix A or B; or handle radiological materials in quan es Storage (UST) Does your facility own or operate underground storage tanks? Yes Hazardous Waste Is your

  17. NV/YMP radiological control manual, Revision 2

    SciTech Connect (OSTI)

    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.

  18. Site Environmental Report for 2001

    SciTech Connect (OSTI)

    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 the operating contract between the University of California Office of the President (UCOP) and DOE.

  19. In situ radiation measurements at the former Soviet Nuclear Test Site

    SciTech Connect (OSTI)

    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.

  20. Air Quality 4 4-1 2003 SITE ENVIRONMENTAL REPORT

    E-Print Network [OSTI]

    Homes, Christopher C.

    at the Central Steam Facility. 4.1 RADIOLOGICAL EMISSIONS Federal air quality laws and DOE regulations monitoring is conducted. Figure 4-1 indicates the locations of the monitored facilities for radiological emis radioactive and nonradioactive emissions at several facilities on site to ensure compliance

  1. ORISE: Radiological Assessment and Monitoring System (RAMS)

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

    place. Radiological data is then normalized so it can be readily incorporated into geographic information systems tools, which are used by local, state and federal decision...

  2. Operating Experience Level 3: Radiologically Contaminated Respirators...

    Energy Savers [EERE]

    Experience Level 3 provides information on a safety concern related to radiological contamination of launderedreconditioned respirators and parts that have been certified as...

  3. 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:...

  4. Hanford Site

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

    and demolishing facilities, including the U Plant Canyon (a former chemical separations facility) and surrounding facilities. In this photo, radiological control technicians...

  5. Hanford Site Regional Population - 2010 Census

    SciTech Connect (OSTI)

    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.

  6. Radiological Training for Tritium Facilities

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested PartiesBuildingBudget ||Department ofRequest7of 9 Radiological Control8DOE

  7. NNSA to Conduct Aerial Radiological Surveys Over Washington,...

    National Nuclear Security Administration (NNSA)

    occurring background radiation. A twin-engine Bell 412 helicopter, operated by the Remote Sensing Laboratory Aerial Measuring System from Joint Base Andrews, will be...

  8. I RADIOLOGICAL SCOPING SURVEY OF FO,RMER MONSANTO' FACILITIES

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal Gas &SCE-SessionsSouth DakotaRobbins and MyersHr. Anthony V. Andolina: lHeader5s I -I a.d

  9. Letter: Katy Trail Radiological Survey at Southeast Drainage.

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal Gas &SCE-SessionsSouth DakotaRobbins and MyersHr. Anthony V. Andolina:I 1 '\ LI g.3LTSI9

  10. Health and Safety Research Division RESULTS OF THE RADIOLOGICAL SURVEY

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal Gas &SCE-SessionsSouthReport for the t-) S/,,5 'a C O M P R E H E N SGwen N

  11. Health and Safety Research Divlsion RESULTS OF THE RADIOLOGICAL SURVEY

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal Gas &SCE-SessionsSouthReport for the t-) S/,,5 'a C O M P R E H E N SGwen Nu+'.nop-s'

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformationJessework usesof EnergyY-12 National Security Complex| National

  13. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY RARAF -Table of Contents

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 75 RARAF - Table of Contents RARAF Professional FOR RADIOLOGICAL RESEARCH · ANNUAL REPORT 2005 76 The Radiological Research Accelerator Facility AN NIH .................................................................................................................................................72 Development of Facilities

  14. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY RARAF -Table of Contents

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 65 RARAF - Table of Contents RARAF Professional FOR RADIOLOGICAL RESEARCH · ANNUAL REPORT 2006 66 The Radiological Research Accelerator Facility AN NIH..................................................................................................................................................66 Development of facilities

  15. Siting evaluations for the ignitor fusion experiment: Preliminary radiological assessments

    E-Print Network [OSTI]

    Coppi, Bruno

    Ignitor is a proposed compact high-magnetic field tokamak aimed at studying plasma burning conditions in Deuterium-Tritium plasmas. Localisation of this experiment in Italy has seen growing attention during the last years. ...

  16. Federal Radiological Monitoring and Assessment Center

    Broader source: Directives, Delegations, and 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.

  17. INL@Work Radiological Search & Response Training

    ScienceCinema (OSTI)

    Turnage, Jennifer

    2013-05-28

    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.

  18. Memorandum, Reporting of Radiological Sealed Sources Transactions

    Broader source: 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.

  19. Hanford radiological protection support services annual report for 1994

    SciTech Connect (OSTI)

    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.

  20. Unified Resolve 2014: A Proof of Concept for Radiological Support...

    Office of Environmental Management (EM)

    Concept for Radiological Support to Incident Commanders Unified Resolve 2014: A Proof of Concept for Radiological Support to Incident Commanders Daniel Blumenthal*, U.S....

  1. Radiological Source Term Estimates for the February 14, 2014...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Radiological Source Term Estimates for the February 14, 2014 WIPP Release Event Radiological Source Term Estimates for the February 14, 2014 WIPP Release Event This document was...

  2. An Archaeological Survey of the Site of the Proposed Onalaska Junior/Senior High School in West-Central Polk, Texas 

    E-Print Network [OSTI]

    Moore, William

    2015-06-25

    A Phase I archaeological survey of a 75 acre tract in west-central Polk County, Texas was conducted in January of 2002 by Brazos Valley Research Associates (BVRA) in Bryan, Texas under Antiquities Permit 2783 issued by the Archeology Division, Texas...

  3. Operations Improvement Surveys 

    E-Print Network [OSTI]

    Guide, J. J.; O'Brien, W. J.

    1984-01-01

    Exxon Chemical Company developed unique site-wide energy optimization technology in the mid1970's. This technology was applied by means of site energy surveys which were carried out at every major Exxon facility throughout the world during the 1976...

  4. Site characterization plan for the W-058 Project

    SciTech Connect (OSTI)

    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.

  5. Nevada Test Site Environmental Report 2004

    SciTech Connect (OSTI)

    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.

  6. REVISED FINAL REPORT – INDEPENDENT VERIFICATION SURVEY ACTIVITIES AT THE SEPARATIONS PROCESS RESEARCH UNIT SITES, NISKAYUNA, NEW YORK – DCN 0496-SR-06-1

    SciTech Connect (OSTI)

    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.

  7. Closure Report for Corrective Action Unit 135: Areas 25 Underground Storage Tanks, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    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 removal of the cement-lined vault sump. Field activities began on November 28, 2000, and ended on December 4, 2000. After verification samples were collected, the vault was repaired with cement. The concrete vault sump, soil excavated beneath the sump, and compactable hot line trash were disposed at the Area 23 Sanitary Landfill. The vault interior was field surveyed following the removal of waste to verify that unrestricted release criteria had been achieved. Since the site is closed by unrestricted release decontamination and verification, post-closure care is not required.

  8. Site Index - Hanford Site

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

    Flow Compensation Claim Process Presentations Related Information Vocational Rehabilitation Visitor Control Site Access Beryllium Program Beryllium Program Beryllium...

  9. An Archaeological Survey at the Yates Drilling Company South Morton Unit "12" Number 1 Well Site and Access Road in the Bienville National Forest Smith County Mississippi 

    E-Print Network [OSTI]

    Moore, William; Baxter, Edward

    2015-07-15

    September 6, 2005 for the Yates Drilling Company of Artesia, New Mexico. A check of the site records at the Mississippi Department of Archives and History (MDAH) in Jackson, Mississippi and reports on file at the Bienville National Forest (Ranger District...

  10. A Phase I Archaeological Survey of the Samedan Oil Corporation C.O. Noble Heirs "A" Number 1 Well Site in Southwest Cameron Parish, Louisiana 

    E-Print Network [OSTI]

    Moore, William

    2015-07-03

    areas by use of a helicopter. In the marsh area, shell middens are the only site type known to occur and may occur anywhere shell food resources have been present in the past (McGuff and Roberson 1974:10). According to McGuff and Roberson 1974...

  11. An Archaeological Survey of Two Proposed Well Sites for the Tom Green County Fresh Water District Number 2 in Tom Green County Texas 

    E-Print Network [OSTI]

    Moore, William

    2015-07-24

    permit 4131. No evidence of an archaeological site was found through a surface inspection of the area or during subsurface investigation with a backhoe, and no artifacts were collected. Copies of the report are on file at the Texas Historical Commission...

  12. Reducing Contingency through Sampling at the Luckey FUSRAP Site - 13186

    SciTech Connect (OSTI)

    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 volume estimate and the associated contingency costs. (authors)

  13. Nevada Test Site Environmental Report 2005

    SciTech Connect (OSTI)

    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.

  14. Hanford Site

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

    pipeline Surveying Pipeline Surveying Pipeline Demolishing Pipeline Demolishing Pipeline Demolishing Pipeline Demolishing Pipeline Demolishing Pipeline Demolishing Pipeline...

  15. Hanford Site

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

    Sedimentation Basin Demolition Sedimentation Basin Demolition Surveying Pipeline Surveying Pipeline Demolishing Pipeline Demolishing Pipeline Demolishing Pipeline Demolishing...

  16. Hanford Site

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

    tunnel Surveying Pipeline Surveying Pipeline Demolishing Pipeline Demolishing Pipeline Demolishing Pipeline Demolishing Pipeline Demolishing Pipeline Demolishing Pipeline...

  17. Radiological safety training for uranium facilities

    SciTech Connect (OSTI)

    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. Apparatus for safeguarding a radiological source

    DOE Patents [OSTI]

    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.

  19. Authorized Limits for the Release of a 25 Ton Locomotive, Serial Number 21547, at the Area 25 Engine Maintenance, Assembly, and Disassembly Facility, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    Jeremy Gwin and Douglas Frenette

    2010-04-08

    This document contains process knowledge and radiological data and analysis to support approval for release of the 25-ton locomotive, Serial Number 21547, at the Area 25 Engine Maintenance, Assembly, and Disassembly (EMAD) Facility, located on the Nevada Test Site (NTS). The 25-ton locomotive is a small, one-of-a-kind locomotive used to move railcars in support of the Nuclear Engine for Rocket Vehicle Application project. This locomotive was identified as having significant historical value by the Nevada State Railroad Museum in Boulder City, Nevada, where it will be used as a display piece. A substantial effort to characterize the radiological conditions of the locomotive was undertaken by the NTS Management and Operations Contractor, National Security Technologies, LLC (NSTec). During this characterization process, seven small areas on the locomotive had contamination levels that exceeded the NTS release criteria (limits consistent with U.S. Department of Energy [DOE] Order DOE O 5400.5, “Radiation Protection of the Public and the Environment”). The decision was made to perform radiological decontamination of these known accessible impacted areas to further the release process. On February 9, 2010, NSTec personnel completed decontamination of these seven areas to within the NTS release criteria. Although all accessible areas of the locomotive had been successfully decontaminated to within NTS release criteria, it was plausible that inaccessible areas of the locomotive (i.e., those areas on the locomotive where it was not possible to perform radiological surveys) could potentially have contamination above unrestricted release limits. To access the majority of these inaccessible areas, the locomotive would have to be disassembled. A complete disassembly for a full radiological survey could have permanently destroyed parts and would have ruined the historical value of the locomotive. Complete disassembly would also add an unreasonable financial burden for the contractor. A decision was reached between the NTS regulator and NSTec, opting for alternative authorized limits from DOE Headquarters. In doing so, NSTec personnel performed a dose model using the DOE-approved modeling code RESRAD-BUILD v3.5 to evaluate scenarios. The parameters used in the dose model were conservative. NSTec’s Radiological Engineering Calculation, REC-2010-001, “Public Dose Estimate from the EMAD 25 Ton Locomotive,” concluded that the four scenarios evaluated were below the 25-millirem per year limit, the “likely” dose scenarios met the “few millirem in a year” criteria, and that the EMAD 25-ton locomotive met the radiological requirements to be released with residual radioactivity to the public.

  20. Assessment of the radiological impact of a decommissioning nuclear power plant in Italy

    E-Print Network [OSTI]

    A. Petraglia; C. Sabbarese; M. De Cesare; N. De Cesare; F. Quinto; F. Terrasi; A. D'Onofrio; P. Steier; L. K. Fifield; A. M. Esposito

    2012-07-17

    The assessment of the radiological impact of a decommissioning Nuclear Power Plant is presented here through the results of an environmental monitoring survey carried out in the area surrounding the Garigliano Power Plant. The levels of radioactivity in soil, water, air and other environmental matrices are shown, in which {\\alpha}, {\\beta} and {\\gamma} activity and {\\gamma} equivalent dose rate are measured. Radioactivity levels of the samples from the Garigliano area are analyzed and then compared to those from a control zone situated more than 100 km away. Moreover, a comparison is made with a previous survey held in 2001. The analyses and comparisons show no significant alteration in the radiological characteristics of the area surroundings the plant, with an overall radioactivity depending mainly from the global fallout and natural sources.

  1. Assessment of the radiological impact of a decommissioning nuclear power plant in Italy

    E-Print Network [OSTI]

    Petraglia, A; De Cesare, M; De Cesare, N; Quinto, F; Terrasi, F; D'Onofrio, A; Steier, P; Fifield, L K; Esposito, A M; 10.1051/radiopro/2012010

    2012-01-01

    The assessment of the radiological impact of a decommissioning Nuclear Power Plant is presented here through the results of an environmental monitoring survey carried out in the area surrounding the Garigliano Power Plant. The levels of radioactivity in soil, water, air and other environmental matrices are shown, in which {\\alpha}, {\\beta} and {\\gamma} activity and {\\gamma} equivalent dose rate are measured. Radioactivity levels of the samples from the Garigliano area are analyzed and then compared to those from a control zone situated more than 100 km away. Moreover, a comparison is made with a previous survey held in 2001. The analyses and comparisons show no significant alteration in the radiological characteristics of the area surroundings the plant, with an overall radioactivity depending mainly from the global fallout and natural sources.

  2. Radiological engineering evaluation of the delay line air scrubber located at the Clinton P. Anderson Meson Physics Facility (LAMPF) 

    E-Print Network [OSTI]

    Huneycutt, Scott Edward

    1996-01-01

    the scrubbing efficiency of the scrubber. The scrubbing efficiency was then used to predict the dose rates in the scrubber area and compare those values with measurements from radiological surveys. The third objective was to determine if the shield blocks were...

  3. Contained radiological analytical chemistry module

    DOE Patents [OSTI]

    Barney, David M. (Scotia, NY)

    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.

  4. Contained radiological analytical chemistry module

    DOE Patents [OSTI]

    Barney, David M. (Scotia, NY)

    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.

  5. New Jersey state information handbook: Formerly Utilized Sites Remedial Action Program

    SciTech Connect (OSTI)

    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.

  6. Recovery Act-Funded Study Assesses Contamination at Former Test Site in California

    Broader source: 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...

  7. Benchmarking survey for recycling.

    SciTech Connect (OSTI)

    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.

  8. CENTER FOR RADIOLOGICAL RESEARCH ANNUAL REPORT 2004 RARAF -Table of Contents

    E-Print Network [OSTI]

    RADIOLOGICAL RESEARCH ACCELERATOR FACILITY The Radiological Research Accelerator Facility AN NIHCENTER FOR RADIOLOGICAL RESEARCH · ANNUAL REPORT 2004 RARAF - Table of Contents RARAF Staff ...................................................................................................................................................67 Development of Facilities

  9. CONFIRMATORY SURVEY OF THE DEFENSE LOGISTICS AGENCY, DEFENSE NATIONAL STOCKPILE CENTER NEW HAVEN DEPOT, NEW HAVEN, INDIANA

    SciTech Connect (OSTI)

    E.M. Harpenau

    2010-02-19

    The objectives of the radiological confirmatory survey were to collect adequate radiological data for use in evaluating the radiological condition of NHD land areas, warehouses, and support buildings. The data generated from the confirmatory survey activities were used to evaluate the results of the Final Status Survey Report (FSSR) submitted by Cabrera Services (Cabrera 2009). Cabrera has stated that all radioactive materials have been removed and that remediation of the open land areas and structure surfaces was complete, and that the NHD meets the criteria for unrestricted use.

  10. 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 (OSTI)

    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).

  11. INEEL Radiological Control Performance Indicator Report - Quarterly

    SciTech Connect (OSTI)

    Hinckley, Frank Leroy

    1999-02-01

    This document provides a report of an analysis of the Radiological Control Program through the fourth quarter of Calendar Year (CY-98) and is the annual report for the Idaho National Engineering and Environmental Laboratory (INEEL). This Performance Indicator Report is provided in accordance with Article 133 of the INEEL Radiological Control Manual. The INEEL collective occupational radiation deep dose is 63.034 person-rem year to date, compared to a goal of 83.1 person-rem. During the fourth quarter, all areas experienced deletions of work resulting from the Maintenance Stand Down. This reduction in work is a primary factor in the difference in the year end dose and the ALARA goal. The work will be completed during CY-99. Beginning in CY-98, a numeric Radiological Performance Index (RPI) is being used to compare radiological performance. The RPI takes into consideration frequency and severity of events such as skin contaminations, clothing contaminations, spills, exposures to radiation exceeding limits, and positive internal dose. The RPI measures the cost of these events in cents per hour of radiological work performed. To make the RPI meaningful, tables have been prepared to show the facility that contributes to the values used. The data are compared on a quarterly basis to the prior year to show measurable performance.

  12. Corrective Action Plan for Corrective Action Unit 366: Area 11 Plutonium Valley Dispersion Sites, Nevada National Security Site, Nevada

    SciTech Connect (OSTI)

    2013-04-30

    This Corrective Action Plan has been prepared for Corrective Action Unit (CAU) 366, Area 11 Plutonium Valley Dispersion Sites, in accordance with the Federal Facility Agreement and Consent Order (FFACO, 1996 as amended). CAU 366 consists of the following six Corrective Action Sites (CASs) located in Area 11 of the Nevada National Security Site: · CAS 11-08-01, Contaminated Waste Dump #1 · CAS 11-08-02, Contaminated Waste Dump #2 · CAS 11-23-01, Radioactively Contaminated Area A · CAS 11-23-02, Radioactively Contaminated Area B · CAS 11-23-03, Radioactively Contaminated Area C · CAS 11-23-04, Radioactively Contaminated Area D Site characterization activities were performed in 2011 and 2012, and the results are presented in Appendix A of the Corrective Action Decision Document (CADD) for CAU 366 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2012a). The following closure alternatives were recommended in the CADD: · No further action for CAS 11-23-01 · Closure in place for CASs 11-08-01, 11-08-02, 11-23-02, 11-23-03, and 11-23-04 The scope of work required to implement the recommended closure alternatives includes the following: · Non-engineered soil covers approximately 3 feet thick will be constructed at CAS 11-08-01 over contaminated waste dump (CWD) #1 and at CAS 11-08-02 over CWD #2. · FFACO use restrictions (URs) will be implemented for the areas where the total effective dose (TED) exceeds the final action level (FAL) of 25 millirems per Occasional Use Area year (mrem/OU-yr). The FAL is based on an assumption that the future use of the site includes occasional work activities and that workers will not be assigned to the area on a regular basis. A site worker under this scenario is assumed to be on site for a maximum of 80 hours per year for 5 years. The FFACO UR boundaries will encompass the areas where a worker would be exposed to 25 millirems of radioactivity per year if they are present for 80 hours per 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 who would regularly be assigned to the work area for an entire career (250 days

  13. The Idaho National Engineering Laboratory site environmental report for calendar year 1989

    SciTech Connect (OSTI)

    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.

  14. Nevada Test Site Environmental Report 2003

    SciTech Connect (OSTI)

    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.

  15. Interventional Radiology of Male Varicocele: Current Status

    SciTech Connect (OSTI)

    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.

  16. Pipe Explorer{trademark} surveying system. Innovative technology summary report

    SciTech Connect (OSTI)

    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.

  17. Preliminary Site Characterization Report, Rulsion Site, Colorado

    SciTech Connect (OSTI)

    NONE

    1996-08-01

    This report is a summary of environmental information gathered during a review of the documents pertaining to Project Rulison and interviews with personnel who worked on the project. Project Rulison was part of Operation Plowshare (a program designed to explore peaceful uses for nuclear devices). The project consisted of detonating a 43-kiloton nuclear device on September 10, 1969, in western Colorado to stimulate natural gas production. Following the detonation, a reentry well was drilled and several gas production tests were conducted. The reentry well was shut-in after the last gas production test and was held in standby condition until the general cleanup was undertaken in 1972. A final cleanup was conducted after the emplacement and testing wells were plugged in 1976. However, some surface radiologic contamination resulted from decontamination of the drilling equipment and fallout from the gas flaring during drilling operations. With the exception of the drilling effluent pond, all surface contamination at the Rulison Site was removed during the cleanup operations. All mudpits and other excavations were backfilled, and both upper and lower drilling pads were leveled and dressed. This report provides information regarding known or suspected areas of contamination, previous cleanup activities, analytical results, a review of the regulatory status, the site`s physical environment, and future recommendations for Project Ruhson. Based on this research, several potential areas of contamination have been identified. These include the drilling effluent pond and mudpits used during drilling operations. In addition, contamination could migrate in the gas horizon.

  18. ASPECT Emergency Response Chemical and Radiological Mapping

    ScienceCinema (OSTI)

    LANL

    2009-09-01

    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 Ike, was sent to the EPA Region 6 Rapid Needs Assessment and the State of Texas Joint Field Office in Austin, Texas. It appears that though there is considerable damage in Galveston and Texas City, there are fewer chemical leaks than during either hurricanes Katrina or Rita. Specific information gathered from the data was reported out to the U.S. Environmental Protection Agency Headquarters, the Federal Emergency Management Agency, the Department of Homeland Security, and the State of Texas Emergency Management Agency.

  19. Corrective Action Investigation Plan for Corrective Action Unit 106: Areas 5, 11 Frenchman Flat Atmospheric Sites, Nevada Test Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Patrick Matthews

    2010-04-01

    Corrective Action Unit (CAU) 106 is located in Area 5 of the Nevada Test Site, which is approximately 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 106 comprises the five corrective action sites (CASs) listed below: •05-23-02, GMX Alpha Contaminated Area •05-23-05, Atmospheric Test Site - Able •05-45-01, Atmospheric Test Site - Hamilton •05-45-04, 306 GZ Rad Contaminated Area •05-45-05, 307 GZ Rad Contaminated Area These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 19, 2010, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 106. The presence and nature of contamination at CAU 106 will be evaluated based on information collected from a field investigation. The CAU includes land areas impacted by the release of radionuclides from a weapons-effect tower test (CAS 05-45-01), a weapons-related airdrop test (CAS 05-23-05), “equation of state” experiments (CAS 05-23-02), and unknown support activities at two sites (CAS 05-45-04 and CAS 05-45-05). Surface-deposited radiological contamination will be evaluated based on a comparison of the total effective dose (TED) at sample plot locations to the dose-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.

  20. Anticipated Radiological Dose to Worker for Plutonium Stabilization and Handling at PFP Project W-460

    SciTech Connect (OSTI)

    WEISS, E.V.

    2000-03-06

    This report provides estimates of the expected whole body and extremity radiological dose, expressed as dose equivalent (DE), to workers conducting planned plutonium (Pu) stabilization processes at the Hanford Site Plutonium Finishing Plant (PFP). The report is based on a time and motion dose study commissioned for Project W-460, Plutonium Stabilization and Handling, to provide personnel exposure estimates for construction work in the PFP storage vault area plus operation of stabilization and packaging equipment at PFP.

  1. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY RARAF Table of Contents

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 118 RARAF Table of Contents RARAF Professional ANNUAL REPORT 2008 119 The Radiological Research Accelerator Facility AN NIH-SUPPORTED RESOURCE CENTER................................................................................................................................................119 Development of Facilities

  2. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY RARAF -Table of Contents

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 113 RARAF - Table of Contents RARAF Professional · ANNUAL REPORT 2007 114 The Radiological Research Accelerator Facility AN NIH-SUPPORTED RESOURCE CENTER................................................................................................................................................114 Development of Facilities

  3. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY RARAF -Table of Contents

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 117 RARAF - Table of Contents RARAF Professional RESEARCH · ANNUAL REPORT 2010 118 The Radiological Research Accelerator Facility AN NIH-SUPPORTED RESOURCE................................................................................................................................................117 Development of Facilities

  4. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY RARAF Table of Contents

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY RARAF Table of Contents RARAF Professional Staff RESEARCH ANNUAL REPORT 2009 The Radiological Research Accelerator Facility AN NIH-SUPPORTED RESOURCE................................................................................................................................................101 Development of Facilities

  5. Nuclear and Radiological Engineering and Medical Physics Programs

    E-Print Network [OSTI]

    Weber, Rodney

    Nuclear and Radiological Engineering and Medical Physics Programs The George W. Woodruff School #12 Year Enrollment - Fall Semester Undergraduate Graduate #12; Nuclear Power Industry Radiological Engineering Industry Graduate School DOE National Labs Nuclear Navy #12; 104 Operating Nuclear Power plants

  6. Radiological Assessment of effects from Fukushima Daiichi Nuclear Power Plant

    Broader source: Energy.gov [DOE]

    NNSA presentation on Radiological Assessment of effects from Fukushima Daiichi Nuclear Power Plant from May 13, 2011

  7. Corrective Action Investigation Plan for Corrective Action Unit 106: Areas 5, 11 Frenchman Flat Atmospheric Sites, Nevada National Security Site, Nevada

    SciTech Connect (OSTI)

    Patrick Matthews

    2011-07-01

    Corrective Action Unit 106 comprises the four corrective action sites (CASs) listed below: • 05-20-02, Evaporation Pond • 05-23-05, Atmospheric Test Site - Able • 05-45-04, 306 GZ Rad Contaminated Area • 05-45-05, 307 GZ Rad Contaminated Area These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 19, 2010, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 106. The presence and nature of contamination at CAU 106 will be evaluated based on information collected from a field investigation. The CAU includes land areas impacted by the release of radionuclides from groundwater pumping during the Radionuclide Migration study program (CAS 05-20-02), a weapons-related airdrop test (CAS 05-23-05), and unknown support activities at two sites (CAS 05-45-04 and CAS 05-45-05). The presence and nature of contamination from surface-deposited radiological contamination from CAS 05-23-05, Atmospheric Test Site - Able, and other types of releases (such as migration and excavation as well as any potential releases discovered during the investigation) from the remaining three CASs 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 the total effective dose at the site exceeds final action levels (i.e., corrective action boundary). • Collect samples of investigation-derived waste, as needed, for waste management purposes.

  8. Toxicology profiles of chemical and radiological contaminants at Hanford

    SciTech Connect (OSTI)

    Harper, B.L.; Strenge, D.L.; Stenner, R.D.; Maughan, A.D.; Jarvis, M.K.

    1995-07-01

    This document summarizes toxicology information required under Section 3.3 (Toxicity Assessment) of HSRAM, and can also be used to develop the short toxicology profiles required in site assessments (described in HSRAM, Section 3.3.5). Toxicology information is used in the dose-response step of the risk assessment process. The dose-response assessment describes the quantitative relationship between the amount of exposure to a substance and the extent of toxic injury or disease. Data are derived from animal studies or, less frequently, from studies in exposed human populations. The risks of a substance cannot be ascertained with any degree of confidence unless dose-response relations are quantified. This document summarizes dose-response information available from the US Environmental Protection Agency (EPA). The contaminants selected for inclusion in this document represent most of the contaminants found at Hanford (both radiological and chemical), based on sampling and analysis performed during site investigations, and historical information on waste disposal practices at the Hanford Site.

  9. Site Index - Hanford Site

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefieldSulfateSciTechtail.Theory ofDidDevelopment Top Scientific ImpactTechnologies |Site Index Site Index

  10. Radiological Control Manual Environment, Safety, Health, and Quality Division

    E-Print Network [OSTI]

    Wechsler, Risa H.

    ............................................................................................................................................8 128 Facility Modifications and Radiological Design ConsiderationsRadiological Control Manual Environment, Safety, Health, and Quality Division SLAC-I-720-0A05Z-001 and published by ESHQ Publishing Document Title: Radiological Control Manual Original Publication Date: 1

  11. CENTER FOR RADIOLOGICAL RESEARCH ANNUAL REPORT 2001 RARAF Staff Photo

    E-Print Network [OSTI]

    RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 77 The Radiological Research Accelerator Facility AN NIHCENTER FOR RADIOLOGICAL RESEARCH ·ANNUAL REPORT 2001 76 RARAF Staff Photo RARAF staff (l-r): Dr and the track segment facilities continue to be utilized in various investigations of this phenomenon

  12. Proposed Drill Sites

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Lane, Michael

    Proposed drill sites for intermediate depth temperature gradient holes and/or deep resource confirmation wells. Temperature gradient contours based on shallow TG program and faults interpreted from seismic reflection survey are shown, as are two faults interpreted by seismic contractor Optim but not by Oski Energy, LLC.

  13. Proposed Drill Sites

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Lane, Michael

    2013-06-28

    Proposed drill sites for intermediate depth temperature gradient holes and/or deep resource confirmation wells. Temperature gradient contours based on shallow TG program and faults interpreted from seismic reflection survey are shown, as are two faults interpreted by seismic contractor Optim but not by Oski Energy, LLC.

  14. Status of activities on the inactive uranium mill tailings sites remedial action program. Office of the Assistant Secretary for Environment

    SciTech Connect (OSTI)

    Not Available

    1981-04-01

    This report on the status of the Office of Environment's program for inactive uranium mill tailings sites is an analysis of the current status and a forecast of future activities of the Office of Environment. The termination date for receipt of information was September 30, 1980. Aerial radiological surveys and detailed ground radiological assessments of properties within the communities in the vicinity of the designated processing sites in Canonsburg, Pennsylvania, Salt Lake City, Utah, and Boise, Idaho led to the designation of an initial group of vicinity properties for remedial action. The potential health effects of the residual radioactive materials on or near these properties were estimated, and the Assistant Secretary for Environment recommended priorities for performing remedial action to the Department's Assistant Secretary for Nuclear Energy. In designating these properties and establishing recommended priorities for performing remedial action, the Office of Environment consulted with the Environmental Protection Agency, the Nuclear Regulatory Commission, representatives from the affected State and local governments, and individual property owners. After notifying the Governors of each of the affected States and the Navajo Nation of the Secretary of Energy's designation of processing sites within their areas of jurisdiction and establishment of remedial action priorities, a Sample Cooperative Agreement was developed by the Department in consultation with the Nuclear Regulatory Commission and provided to the affected States and the Navajo Nation for comments. During September 1980, a Cooperative Agreement with the Commonwealth of Pennsylvania for the designated Canonsburg processing site was executed by the Department. It is anticipated that a Cooperative Agreement between the State of Utah and the Department to perform remedial actions at the designated Salt Lake City site will be executed in the near future.

  15. Paint for detection of radiological or chemical agents

    DOE Patents [OSTI]

    Farmer, Joseph C. (Tracy, CA); Brunk, James L. (Martinez, CA); Day, Sumner Daniel (Danville, CA)

    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.

  16. Hazelwood Interim Storage Site environmental monitoring summary, Hazelwood, Missouri, calendar year 1984

    SciTech Connect (OSTI)

    Not Available

    1985-07-01

    The Hazelwood Interim Storage Site (HISS) is located at 9200 Latty Avenue, Hazelwood, Missouri. The property on which the HISS is situated is owned by the Jarboe Realty and Investment Company and is leased to Futura Coatings, Inc. Radiological surveys in 1977 and 1982 indicated uranium and thorium contamination and elevated radiation levels in the soil on this property and several others in the immediate vicinity. As part of the research and development program authorized by Congress under the 1984 Energy and Water Appropriations Act, Bechtel National, Inc. (BNI) is conducting remedial action on-site and at the vicinity properties. The work is being performed as part of the US Department of Energy (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP). Jarboe Realty and Investment Company has agreed to permit DOE to store contaminated material from the FY 1984 and 1985 Latty Avenue cleanup on its property. The contaminated material will be added to the existing pile created during the earlier site cleanup. The pile will then be covered to prevent erosion or migration of contamination. The property will be maintained as the HISS by DOE until final disposition for these materials is determined. BNI is conducting a surveillance monitoring program at the HISS during the interim storage period to detect potential migration of contaminants from the storage pile via air, water, and sediment. This summary provides these monitoring data for calendar year 1984. 6 refs., 4 tabs.

  17. Land and water use characteristics in the vicinity of the Savannah River Site

    SciTech Connect (OSTI)

    Hamby, D.M.

    1991-03-01

    Routine operations at the Savannah River Site (SRS) result in the release of small amounts of radionuclides to the atmosphere and to the Savannah River. The resulting radiological doses to the offsite maximum individual and the offsite population within 50 miles of the SRS are estimated on a yearly basis. These estimates are generated using dose models prescribed for the commercial nuclear power industry by the Nuclear Regulatory Commission (NRC). The NRC provides default values for dose model parameters for facilities not having enough data to develop site-specific values. A survey of land and water use characteristics for the Savannah River area has been conducted to determine as many site-specific values as possible for inclusion in the dose models used at the SRS. These site parameters include local characteristics of meat, milk, and vegetable production; river recreational activities; and meat, milk, and vegetable consumption rates. The report that follows describes the origin of the NRC default values, the methodology for deriving regional data, the results of the study, and the derivations of region-specific usage and consumption rates. 33 refs., 3 figs., 8 tabs.

  18. Nevada Test Site Environmental Report 2007

    SciTech Connect (OSTI)

    Cathy Wills

    2008-09-01

    The Nevada Test Site Environmental Report 2007 (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. It was prepared by National Security Technologies, LLC (NSTec). 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 nonradiological releases, implementation status of the NTS Environmental Management System, a summary of compliance with environmental regulations, pollution prevention and waste minimization accomplishments, 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 2007. This NTSER was prepared to satisfy DOE Order 231.1A, Environment, Safety and Health Reporting. 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. This report meets these objectives for the NTS and three offsite Nevada facilities mentioned in this report.

  19. Closure Report for Corrective Action Unit 118: Area 27 Super Kukla Facility, Nevada Test Site, Nevada with ROTC 1, Revision 0

    SciTech Connect (OSTI)

    Mark Burmeister

    2007-09-01

    This CR provides documentation and justification for the closure of CAU 118 without further corrective action. This justification is based on process knowledge and the results of the investigative and closure activities conducted in accordance with the CAU 118 SAFER Plan: Streamlined Approach for Environmental Restoration (SAFER) Plan for CAU 118: Area 27 Super Kukla Facility, Nevada Test Site, Nevada (NNSA/NSO, 2006). The SAFER Plan provides information relating to site history as well as the scope and planning of the investigation. This CR also provides the analytical and radiological survey data to confirm that the remediation goals were met as specified in the CAU 118 SAFER Plan (NNSA/NSO, 2006). The Nevada Division of Environmental Protection (NDEP) approved the CAU 118 SAFER Plan (Murphy, 2006), which recommends closure in place with use restrictions (URs).

  20. Savannah River Site environmental report for 1993 summary pamphlet

    SciTech Connect (OSTI)

    Karapatakis, L.

    1994-05-01

    This pamphlet summarizes the impact of 1993 Savannah River Site operations on the environment and the off-site public. It includes an overview of site operations; the basis for radiological and nonradiological monitoring; 1993 radiological releases and the resulting dose to the off-site population; and results of the 1993 nonradiological program. The Savannah River Site Environmental Report for 1993 describes the findings of the environmental monitoring program for 1993. The report contains detailed information about site operations,the environmental monitoring and surveillance programs, monitoring and surveillance results, environmental compliance activities, and special programs. The report is distributed to government officials, members of the US Congress, universities, government facilities, environmental and civic groups, the news media, and interested individuals.

  1. Hanford Site

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

    Simulation Test Site Simulation Test Site Sen. Murray Press Conference Sen. Murray Press Conference Sen. Murray Press Conference Sen. Murray Press Conference Sen. Murray Press...

  2. School of Nursing MSN/PhD Career Plans Survey

    E-Print Network [OSTI]

    Plotkin, Joshua B.

    or more graduates indicated their annual fulltime salary in their responses. Adult Acute Care Nurse Radiology, New York, NY Average Salary: $90,825 Adult Health Nurse Practitioner HospitalSchool of Nursing MSN/PhD Career Plans Survey Class of 2010 RESPONSE RATE

  3. 2013 Environmental/Radiological Assistance Directory (ERAD) Presentations

    Office of Energy Efficiency and Renewable Energy (EERE)

    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

  4. Fixation of Radiological Contamination; International Collaborative Development

    SciTech Connect (OSTI)

    Rick Demmer

    2013-03-01

    A cooperative international project was conducted by the Idaho National Laboratory (INL) and the United Kingdom’s 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. Enewetak radiological support project. Final report

    SciTech Connect (OSTI)

    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.

  6. Radiological health aspects of commercial uranium conversion, enrichment, and fuel fabrication

    SciTech Connect (OSTI)

    Stoetzel, G.A.; Hoenes, G.R.; Cummings, F.M.; McCormack, W.D.

    1982-11-01

    Detailed information concerning occupational exposures, health physics practices, and regulatory procedures at commercial conversion, enrichment and fuel fabrication facilities is given. Sites visits were the primary source of information, which is divided into four sections. The first section discusses health physics practices that are common to the conversion, enrichment, and fuel fabrication phases of the commercial uranium industry. The next three sections review process descriptions, radiological health practices, and regulatory procedures for the three phases. Nonradiological exposures are considered only as they influence the interpretation of the health effects of radiological exposures. The review of regulatory procedures indicates the types of exposure evaluation records being kept on uranium workers and the responsibility for maintaining the records.

  7. Weld Repair of a Stamped Pressure Vessel in a Radiologically Controlled Zone

    SciTech Connect (OSTI)

    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.

  8. Brookhaven National Laboratory site environmental report for calendar year 1996

    SciTech Connect (OSTI)

    Schroeder, G.L.; Paquette, D.E.; Naidu, J.R.; Lee, R.J.; Briggs, S.L.K.

    1998-01-01

    This report documents the results of the Environmental Monitoring Program at Brookhaven National Laboratory and summarizes information about environmental compliance for 1996. To evaluate the effect of Brookhaven National Laboratory`s operations on the local environment, measurements of direct radiation, and of a variety of radionuclides and chemical compounds in the ambient air, soil, sewage effluent, surface water, groundwater, fauna, and vegetation were made at the Brookhaven National Laboratory site and at adjacent sites. The report also evaluates the Laboratory`s compliance with all applicable guides, standards, and limits for radiological and non-radiological emissions and effluents to the environment.

  9. Remaining Sites Verification Package for 132-DR-1, 1608-DR Effluent Pumping Station, Waste Site Reclassification Form 2005-035

    SciTech Connect (OSTI)

    R. A. Carlson

    2005-09-22

    Radiological characterization, decommissioning and demolition of the 132-DR-1 site, 1608-DR Effluent Pumping Station was performed in 1987. The current site conditions achieve the remedial action objectives and the corresponding remedial action goals established in the Remaining Sites ROD. Residual concentrations support future land uses that can be represented by a rural-residential scenario and pose no threat to groundwater or the Columbia River based on RESRAD modeling.

  10. Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado

    SciTech Connect (OSTI)

    Not Available

    1992-02-01

    This appendix assesses the present conditions and data gathered about the two inactive uranium mill tailings sites near Rifle, Colorado, and the designated disposal site six miles north of Rifle in the area of Estes Gulch. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill, tailings, and disposal site so that the Remedial Action Contractor (RAC) may complete final designs for the remedial actions.

  11. Analysis of concentrating PV-T systems for the commercial/industrial sector. Volume II. PV-T state-of-the-art survey and site/application pair selection and analysis

    SciTech Connect (OSTI)

    Schwinkendorf, W.E.

    1984-09-01

    As part of a project to develop feasibility assessments, design procedures, and reference designs for total energy systems that could use actively cooled concentrating photovoltaic collectors, a survey was conducted to provide an overview of available photovoltaic-thermal (PV-T) technology. General issues associated with the design and installation of a PV-T system are identified. Electrical and thermal efficiencies for the line-focus Fresnel, the linear parabolic trough, and the point-focus Fresnel collectors are specified as a function of operating temperature, ambient temperature, and insolation. For current PV-T technologies, the line-focus Fresnel collector proved to have the highest thermal and electrical efficiencies, lowest array cost, and lowest land area requirement. But a separate feasibility analysis involving 11 site/application pairs showed that for most applications, the cost of the photovoltaic portion of a PV-T system is not recovered through the displacement of an electrical load, and use of a thermal-only system to displace the thermal load would be a more economical alternative. PV-T systems are not feasible for applications that have a small thermal load, a large steam requirement, or a high load return temperature. SAND82-7157/3 identifies the technical issues involved in designing a photovoltaic-thermal system and provides guidance for resolving such issues. Detailed PV-T system designs for three selected applications and the results of a trade-off study for these applications are presented in SAND82-7157/4. A summary of the major results of this entire study and conclusions concerning PV-T systems and applications is presented in SAND82-7157/1.

  12. ALARA Center of Technology promotes good radiological work practices at Hanford

    SciTech Connect (OSTI)

    Waggoner, L.O., Westinghouse Hanford, Richland, WA

    1997-10-31

    The central Radiological Control Organization, originally under the previous Management and Operations contractor (Westinghouse Hanford Company) decided that a significant improvement in ALARA implementation would result if examples of engineered controls used for radiological work were assembled in one location to provide a ``showcase`` for workers and managers. The facility would be named the ALARA Center of Technology (ACT) and would include the latest technologies used to accomplish radiological work, as well as proven techniques, tools, and equipment. A location for the Center was selected in the 200 East Area of Hanford in a central location to be easily accessible to all facilities and contractors. Since there was little money available for this project, a decision was made to contact several vendors and request loans of their tools, equipment, and materials. In return, the center would help market products on site and assist with product demonstrations when the vendors visited Hanford. Out of 28 vendors originally contacted, 16 responded with offers to loan products. This included a containment tent, several glove bags, BEPA filtered vacuum cleaners, portable ventilation systems, fixatives, temporary shielding, pumps, and several special tools. Vendors who could not provide products sent videos and brochures. Westinghouse Hanford Company began using the ACT in June 1996. Fluor Daniel Hanford, Inc., the present Management and Integrating Contractor for the Hanford Site, held the formal opening ceremony of the ALARA Center of Technology on October 1, 1996. The Center now has about 1200 ft{sup 2} of floor space fi Iled with tools, equipment and material used to perform radiological work.

  13. Evaluation of Cavity Collapse and Surface Crater Formation at the Norbo Underground Nuclear Test in U8c, Nevada Nuclear Security Site, and the Impact on Stability of the Ground Surface

    SciTech Connect (OSTI)

    Pawloski, G A

    2012-06-18

    Lawrence Livermore National Laboratory (LLNL) Containment Program performed a review of nuclear test-related data for the Norbo underground nuclear test in U8c to assist in evaluating this legacy site as a test bed for application technologies for use in On-Site Inspections (OSI) under the Comprehensive Nuclear Test Ban Treaty. This request is similar to one made for the Salut site in U8c (Pawloski, 2012b). Review of the Norbo site is complicated because the test first exhibited subsurface collapse, which was not unusual, but it then collapsed to the surface over one year later, which was unusual. Of particular interest is the stability of the ground surface above the Norbo detonation point. Proposed methods for on-site verification include radiological signatures, artifacts from nuclear testing activities, and imaging to identify alteration to the subsurface hydrogeology due to the nuclear detonation. Aviva Sussman from the Los Alamos National Laboratory (LANL) has also proposed work at this site. Both proposals require physical access at or near the ground surface of specific underground nuclear test locations at the Nevada Nuclear Security Site (NNSS), formerly the Nevada Test Site (NTS), and focus on possible activities such as visual observation, multispectral measurements, and shallow and deep geophysical surveys.

  14. Federal Radiological Monitoring and Assessment Center Monitoring Manual Volume 1, Operations

    SciTech Connect (OSTI)

    NSTec Aerial Measurement Systems

    2012-07-31

    The Monitoring division is primarily responsible for the coordination and direction of: Aerial measurements to delineate the footprint of radioactive contaminants that have been released into the environment. Monitoring of radiation levels in the environment; Sampling to determine the extent of contaminant deposition in soil, water, air and on vegetation; Preliminary field analyses to quantify soil concentrations or depositions; and Environmental and personal dosimetry for FRMAC field personnel, during a Consequence Management Response Team (CMRT) and Federal Radiological Monitoring and Assessment Center (FRMAC) response. Monitoring and sampling techniques used during CM/FRMAC operations are specifically selected for use during radiological emergencies where large numbers of measurements and samples must be acquired, analyzed, and interpreted in the shortest amount of time possible. In addition, techniques and procedures are flexible so that they can be used during a variety of different scenarios; e.g., accidents involving releases from nuclear reactors, contamination by nuclear waste, nuclear weapon accidents, space vehicle reentries, or contamination from a radiological dispersal device. The Monitoring division also provides technicians to support specific Health and Safety Division activities including: The operation of the Hotline; FRMAC facility surveys; Assistance with Health and Safety at Check Points; and Assistance at population assembly areas which require support from the FRMAC. This volume covers deployment activities, initial FRMAC activities, development and implementation of the monitoring and assessment plan, the briefing of field teams, and the transfer of FRMAC to the EPA.

  15. Closure Report for Corrective Action Unit 566: EMAD Compound, Nevada National Security Site, Nevada with ROTC-1, Revision 0

    SciTech Connect (OSTI)

    Mark Krauss

    2011-06-01

    This Closure Report (CR) presents information supporting the closure of Corrective Action Unit (CAU) 566: EMAD Compound, Nevada National Security Site, Nevada. Corrective Action Unit 566 comprises Corrective Action Site (CAS) 25-99-20, EMAD Compound, located within Area 25 of the Nevada National Security Site. The purpose of this CR is to provide documentation supporting the completed corrective actions and provide data confirming that the closure objectives for CAU 566 were met. To achieve this, the following actions were performed: • Review the current site conditions, including the concentration and extent of contamination. • Implement any corrective actions necessary to protect human health and the environment. • Properly dispose of corrective action and investigation wastes. • Document Notice of Completion and closure of CAU 566 issued by the Nevada Division of Environmental Protection. From October 2010 through May 2011, closure activities were performed as set forth in the Streamlined Approach for Environmental Restoration Plan for CAU 566: EMAD Compound, Nevada National Security Site, Nevada. The purposes of the activities as defined during the data quality objectives process were as follows: • Determine whether contaminants of concern (COCs) are present. • If COCs are present, determine their nature and extent, implement appropriate corrective actions, and properly dispose of wastes. Analytes detected during the closure activities were evaluated against final action levels (FALs) to determine COCs for CAU 566. Assessment of the data from collected soil samples, and from radiological and visual surveys of the site, indicates the FALs were exceeded for polychlorinated biphenyls (PCBs), semivolatile organic compounds (SVOCs), and radioactivity. Corrective actions were implemented to remove the following: • Radiologically contaminated soil assumed greater than FAL at two locations • Radiologically contaminated soil assumed greater than FAL with lead shot • PCB-contaminated soil • Radiologically contaminated filters and equipment • Fuels, lubricants, engine coolants, and oils • Lead debris • Electrical and lighting components assumed to be potential source materials, including - fluorescent light bulbs - mercury switches (thermostats) - circuit boards - PCB-containing ballasts Closure of CAU 566 was achieved through a combination of removal activities and closure in place. Corrective actions to remove COCs, and known and assumed potential source materials, were implemented as was practical. The PCBs remaining at the site are bounded laterally, but not vertically, within CAS 25-99-20 based upon step-out sampling; the sources (e.g., PCB transformer oils, diesel fuel from locomotive reservoirs) have been removed; the practice of the application of PCB-containing oils for soil stabilization has ceased; and the COCs are not readily mobile in the environment. Closure in place is necessary, and future land use of the site will be restricted from intrusive activities. This will effectively eliminate inadvertent contact by humans with the contaminated media. The DOE, National Nuclear Security Administration Nevada Site Office, provides the following recommendations: • No further corrective action is required at CAS 25-99-20. • Closure in place of CAS 25-99-20. • A use restriction is required at CAU 566. • A Notice of Completion to the DOE, National Nuclear Security Administration Nevada Site Office, is requested from the Nevada Division of Environmental Protection for closure of CAU 566. • Corrective Action Unit 566 should be moved from Appendix III to Appendix IV of the Federal Facility Agreement and Consent Order.

  16. Radiological and Nuclear Security in A Global Context

    E-Print Network [OSTI]

    Jones, Nick

    2010-01-01

    This paper considers the state of nuclear and radiological security in the UK and abroad and reports on the methods that could be employed by terrorists with radiological or nuclear material to cause destruction. It is shown that despite current safeguards that problems arise due to materials that are unaccounted for and poor implementation of detection regimes in some geographical regions. The prospect of a future terrorist event that involves nuclear or radiological materials seems likely despite best efforts of prevention.

  17. Savannah River Site ALARA Program appraisals

    SciTech Connect (OSTI)

    Johnson, J.R.

    1992-01-01

    ALARA Program audits are recommended in PNL-6566, Health Physics Manual of Good Practices for Reducing Radiation Exposure to Levels that are As Low As Reasonably Achievable (ALARA).'' The Department of Energy (DOE) Order 5480.11, Radiation Protection For Occupational Workers,'' requires contractors to conduct internal audits of all functional elements of the radiological protection program, which includes the ALARA program, as often as necessary, but at a minimum every three years. At the Savannah River Site (SRS), these required audits are performed as part of the Health Protection Internal Appraisal Program. This program was established to review the Site radiological protection program, which includes the ALARA program, on an ongoing basis and to provide recommendations for improvement directly to senior Health Protection management. This paper provides an overview of the SRS Health Protection Internal Appraisal program. In addition, examples of specific performance criteria and detailed appraisal guidelines used ALARA appraisals are provided.

  18. Savannah River Site ALARA Program appraisals

    SciTech Connect (OSTI)

    Johnson, J.R.

    1992-06-01

    ALARA Program audits are recommended in PNL-6566, ``Health Physics Manual of Good Practices for Reducing Radiation Exposure to Levels that are As Low As Reasonably Achievable (ALARA).`` The Department of Energy (DOE) Order 5480.11, ``Radiation Protection For Occupational Workers,`` requires contractors to conduct internal audits of all functional elements of the radiological protection program, which includes the ALARA program, as often as necessary, but at a minimum every three years. At the Savannah River Site (SRS), these required audits are performed as part of the Health Protection Internal Appraisal Program. This program was established to review the Site radiological protection program, which includes the ALARA program, on an ongoing basis and to provide recommendations for improvement directly to senior Health Protection management. This paper provides an overview of the SRS Health Protection Internal Appraisal program. In addition, examples of specific performance criteria and detailed appraisal guidelines used ALARA appraisals are provided.

  19. Accident Investigations of the February 14, 2014, Radiological...

    Office of Environmental Management (EM)

    Room 7 of the underground. Inspections of the mine on April 30, 2014, established that fire behaviors might have been associated with the radiological release event. Because of...

  20. Silver-Mordenite for Radiologic Gas Capture from Complex Streams...

    Office of Scientific and Technical Information (OSTI)

    Journal Article: Silver-Mordenite for Radiologic Gas Capture from Complex Streams: Dual Catalytic CH3I Decomposition and I Confinement Citation Details In-Document Search Title:...

  1. Handling and Packaging a Potentially Radiologically Contaminated Patient

    Broader source: Energy.gov [DOE]

    The purpose of this procedure is to provide guidance to EMS care providers for properly handling and packaging potentially radiologically contaminated patients.

  2. Review of the Hanford Tank Farms Radiological Controls Activity...

    Energy Savers [EERE]

    Independent Oversight Review of the Hanford Tank Farms Radiological Controls Activity-Level Implementation May 2011 December 2012 Office of Safety and Emergency Management...

  3. Radiological Release Event at the Waste Isolation Pilot Plant...

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

    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...

  4. SU-E-E-06: Teaching Medical Physics in a Radiology Museum

    SciTech Connect (OSTI)

    Bednarek, D; Rudin, S [University at Buffalo, Buffalo, NY (United States)

    2014-06-01

    Purpose: To enhance the learning process in the teaching of medical physics by providing a venue to experience the historical equipment and devices of radiology. Methods: We have created a museum by assembling a large collection of equipment and artifacts related to radiology and medical physics. As part of a learning-in-context educational approach, classes for a survey course in medical physics are held in the museum so that students are able to visually and tangibly experience the implements of radiology, while related topics are discussed. The students learn how x-ray equipment and techniques evolved throughout the years and they learn to appreciate the differences and similarities between current x-ray technology and that of the early days. The collection contains items dating from the era of the discovery of x-rays up to recent times and includes gas x-ray tubes, hand-held fluoroscopes, generators, spark-gap kV meters, stereoscopes, glass-plate radiographs, a photofluorographic unit, wood-interspaced grid, flat-panel detector, linear-accelerator klystron, and brachytherapy radium applicators, as well as an extensive library containing some of the seminal literature of the field so that students can delve deeper into the technology. In addition to the classes, guided tours are provided for radiologic-technology, bioengineering, physics and medical students, as well as group and individual tours for the general public. Results: Student course assessments have consistently included positive expressions of their experience in the museum. Numerous students have volunteered to assist with display preparation and have learned by researching the content. Many individuals have been attracted on a walk-in basis and have expressed a deep curiosity in the technology, with positive feedback. Conclusion: The museum and its artifacts have been invaluable in stimulating interest in the history and technology of medical physics. Students and visitors alike obtain a deeper appreciation of the contribution physics has made to medicine.

  5. Bachelor of Science, Radiologic Sciences, Diagnostic Radiology Emphasis, 2014-2015 Name ID# Date

    E-Print Network [OSTI]

    Barrash, Warren

    Information Technology In Radiologic Sciences RADSCI 350 Imaging Pathophysiology RADSCI 370 Junior Recitation 200 Civic and Ethical Foundations 3 DLN BIOL 227 Human Anatomy and Physiology 4 DLN CHEM 101, 101L-4 BIOL 228 Human Anatomy and Physiology 4 BUSCOM 201 Business Communication 3 HLTHST 101 Medical

  6. WIPP Radiological Relase Report Phase 2

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirley Ann Jackson About Us ShirleyU.S. DRIVE Vehicle Technologies Office:Vote Phase 2 Radiological

  7. WIPP Radiological Release Report Phase 1

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirley Ann Jackson About Us ShirleyU.S. DRIVE Vehicle Technologies Office:Vote Phase 2 Radiological

  8. Radiological Safety Training for Accelerator Facilities

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested PartiesBuildingBudget ||Department ofRequest7of 9 Radiological Control8 of

  9. Radiological Safety Training for Uranium Facilities

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested PartiesBuildingBudget ||Department ofRequest7of 9 Radiological Control8 ofDOE

  10. Nuclear / Radiological Advisory Team | National Nuclear Security

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformationJessework usesofPublications64NewsroomNontoxicAdministration / Radiological

  11. TRACKING SITE

    Energy Science and Technology Software Center (OSTI)

    003235MLTPL00 AASG Geothermal Data submissions tracking application and site.  https://github.com/usgin/aasgtrack 

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

    SciTech Connect (OSTI)

    Grant Evenson

    2012-05-01

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

  13. Site Recommendation Subsurface Layout

    SciTech Connect (OSTI)

    C.L. Linden

    2000-06-28

    The purpose of this analysis is to develop a Subsurface Facility layout that is capable of accommodating the statutory capacity of 70,000 metric tons of uranium (MTU), as well as an option to expand the inventory capacity, if authorized, to 97,000 MTU. The layout configuration also requires a degree of flexibility to accommodate potential changes in site conditions or program requirements. The objective of this analysis is to provide a conceptual design of the Subsurface Facility sufficient to support the development of the Subsurface Facility System Description Document (CRWMS M&O 2000e) and the ''Emplacement Drift System Description Document'' (CRWMS M&O 2000i). As well, this analysis provides input to the Site Recommendation Consideration Report. The scope of this analysis includes: (1) Evaluation of the existing facilities and their integration into the Subsurface Facility design. (2) Identification and incorporation of factors influencing Subsurface Facility design, such as geological constraints, thermal loading, constructibility, subsurface ventilation, drainage control, radiological considerations, and the Test and Evaluation Facilities. (3) Development of a layout showing an available area in the primary area sufficient to support both the waste inventories and individual layouts showing the emplacement area required for 70,000 MTU and, if authorized, 97,000 MTU.

  14. Infrastructure to support ultra high throughput biodosimetry screening after a radiological event

    E-Print Network [OSTI]

    Brenner, David Jonathan

    GUY GARTY1 , ANDREW KARAM2 , & DAVID J. BRENNER3 1 Radiological Research Accelerator Facility, Radiological Research Accelerator Facility, Nevis Laboratories, Columbia UniverInfrastructure to support ultra high throughput biodosimetry screening after a radiological event

  15. Closure Report for Corrective Action Unit 539: Areas 25 and 26 Railroad Tracks Nevada National Security Site, Nevada with ROTC-1, Revision 0

    SciTech Connect (OSTI)

    Mark Kauss

    2011-06-01

    This Closure Report (CR) presents information supporting the closure of Corrective Action Unit (CAU) 539: Areas 25 and 26 Railroad Tracks, Nevada National Security Site, Nevada. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management. The corrective action sites (CASs) within CAU 539 are located within Areas 25 and 26 of the Nevada National Security Site. Corrective Action Unit 539 comprises the following CASs: • 25-99-21, Area 25 Railroad Tracks • 26-99-05, Area 26 Railroad Tracks The purpose of this CR is to provide documentation supporting the completed corrective actions and provide data confirming that the closure objectives for CASs within CAU 539 were met. To achieve this, the following actions were performed: • Reviewed documentation on historical and current site conditions, including the concentration and extent of contamination. • Conducted radiological walkover surveys of railroad tracks in both Areas 25 and 26. • Collected ballast and soil samples and calculated internal dose estimates for radiological releases. • Collected in situ thermoluminescent dosimeter measurements and calculated external dose estimates for radiological releases. • Removed lead bricks as potential source material (PSM) and collected verification samples. • Implemented corrective actions as necessary to protect human health and the environment. • Properly disposed of corrective action and investigation wastes. • Implemented an FFACO use restriction (UR) for radiological contamination at CAS 25-99-21. The approved UR form and map are provided in Appendix F and will be filed in the DOE, National Nuclear Security Administration Nevada Site Office (NNSA/NSO), Facility Information Management System; the FFACO database; and the NNSA/NSO CAU/CAS files. From November 29, 2010, through May 2, 2011, closure activities were performed as set forth in the Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 539: Areas 25 and 26 Railroad Tracks, Nevada Test Site, Nevada. The purposes of the activities as defined during the data quality objectives process were as follows: • Determine whether contaminants of concern (COCs) are present. • If COCs are present, determine their nature and extent, implement appropriate corrective actions, and properly dispose of wastes. Analytes detected during the closure activities were evaluated against final action levels (FALs) to determine COCs for CAU 539. Assessment of the data generated from closure activities revealed the following: • At CAS 26-99-05, the total effective dose for radiological releases did not exceed the FAL of 25 millirem per Industrial Area year. Potential source material in the form of lead bricks was found at three locations. A corrective action of clean closure was implemented at these locations, and verification samples indicated that no further action is necessary. • At CAS 25-99-21, the total effective dose for radiological releases exceeds the FAL of 25 millirem per Industrial Area year. Potential source material in the form of lead bricks was found at eight locations. A corrective action was implemented by removing the lead bricks and soil above FALs at these locations, and verification samples indicated that no further action is necessary. Pieces of debris with high radioactivity were identified as PSM and remain within the CAS boundary. A corrective action of closure in place with a UR was implemented at this CAS because closure activities showed evidence of remaining soil contamination and radioactive PSM. Future land use will be restricted from surface and intrusive activities. Closure activities generated waste streams consisting of industrial solid waste, recyclable materials, low-level radioactive waste, and mixed low-level radioactive waste. Wastes were disposed of in the appropriate onsite landfills. The NNSA/NSO prov

  16. Nuclear and Radiological Forensics and Attribution Overview

    SciTech Connect (OSTI)

    Smith, D K; Niemeyer, S

    2005-11-04

    The goal of the U.S. Department of Homeland Security (DHS) Nuclear and Radiological Forensics and Attribution Program is to develop the technical capability for the nation to rapidly, accurately, and credibly attribute the origins and pathways of interdicted or collected materials, intact nuclear devices, and radiological dispersal devices. A robust attribution capability contributes to threat assessment, prevention, and deterrence of nuclear terrorism; it also supports the Federal Bureau of Investigation (FBI) in its investigative mission to prevent and respond to nuclear terrorism. Development of the capability involves two major elements: (1) the ability to collect evidence and make forensic measurements, and (2) the ability to interpret the forensic data. The Program leverages the existing capability throughout the U.S. Department of Energy (DOE) national laboratory complex in a way that meets the requirements of the FBI and other government users. At the same time the capability is being developed, the Program also conducts investigations for a variety of sponsors using the current capability. The combination of operations and R&D in one program helps to ensure a strong linkage between the needs of the user community and the scientific development.

  17. CENTER FOR RADIOLOGICAL RESEARCH ANNUAL REPORT 2012 Research Using RARAF

    E-Print Network [OSTI]

    at RARAF January 1 - December 31, 2012 #12;THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY Page97CENTER FOR RADIOLOGICAL RESEARCH · ANNUAL REPORT 2012 Page96 Research Using RARAF For almost two Facilities continue to be utilized in various investigations of this phenomenon. Research into bystander

  18. A Data Warehouse for Integrating Radiologic and Pathologic Data

    E-Print Network [OSTI]

    Rubin, Daniel L.

    A Data Warehouse for Integrating Radiologic and Pathologic Data Daniel L. Rubin, MD, MSa,b , Terry the medical enterprise. Our objective is to describe the design, methodology, and implementation of a data warehouse to integrate and make accessible the types of medical data pertinent to radiology research

  19. Current Trends in Gamma Ray Detection for Radiological Emergency Response

    SciTech Connect (OSTI)

    Mukhopadhyay, S., Guss, P., Maurer, R.

    2011-08-18

    Passive and active detection of gamma rays from shielded radioactive materials, including special nuclear materials, is an important task for any radiological emergency response organization. This article reports on the current trends and status of gamma radiation detection objectives and measurement techniques as applied to nonproliferation and radiological emergencies.

  20. FRMAC Interactions During a Radiological or Nuclear Event

    SciTech Connect (OSTI)

    Wong, C T

    2011-01-27

    During a radiological or nuclear event of national significance the Federal Radiological Emergency Monitoring and Assessment Center (FRMAC) assists federal, state, tribal, and local authorities by providing timely, high-quality predictions, measurements, analyses and assessments to promote efficient and effective emergency response for protection of the public and the environment from the consequences of such an event.

  1. FINAL REPORT FOR INDEPENDENT CONFIRMATORY SURVEY SUMMARY AND RESULTS FOR THE HEMATITE DECOMMISSIONING PROJECT, FESTUS, MISSOURI

    SciTech Connect (OSTI)

    Bailey, Erika N.; Lee, Jason D.

    2012-09-21

    ORAU conducted confirmatory surveys of the Hematite site during the period of June 12 through June 13, 2012. The survey activities included in-process inspections, document review, walkover surveys, sampling activities, and laboratory analysis of split samples. WEC was forthcoming with information relating to practices, procedures, and surface scan results. Scans performed by the WEC technician were extremely thorough and methodical. The WEC and ORAU technicians identified the same areas of elevated activity with comparable detector responses. WEC sampling of re-use soils, waste soils, sediments, and groundwater were conducted under ORAU observation. The sampling efforts observed by ORAU were performed in accordance with site-specific procedures and in a manner sufficient to provide quality supporting data. Three observations were made during groundwater sampling activities. First, the water level indicator was re-used without submitting rinse blank. Second, bubbles created during tubing extraction could indicate the presence of volatilized organic compounds. Third, samplers did not use a photo ionization detector prior to sample collection to indicate the presence of volatile organic vapors. Results of split samples indicated a high level of comparability between the WEC and ORAU/ORISE radiological laboratories. Analytical practices and procedures appear to be sufficient in providing quality radiochemical data. All concentrations from the Soil Re-Use Area and sediment samples are below Uniform radionuclide-specific derived concentration guideline level (DCGL{sub W}) limits; thus, comparisons to the less conservative stratified geometry were not required. Results were compared to individual DCGLs and using the sum of fractions approach. Both composite soil samples collected from the Waste Handling Area (Bins 1 and 4) were well below the prescribed USEI waste acceptance criteria.

  2. A Web-Based Annotation System for Lung Cancer Radiology Reports

    E-Print Network [OSTI]

    Chen, Xiang

    2012-01-01

    Results in Radiology Reports. Journal of Digital Imagingfrom pathology reports into a Disease Knowledgefor Lung Cancer Radiology Reports A thesis submitted in

  3. Effectiveness of Shallow Temperatures Surveys to Target a Geothermal...

    Open Energy Info (EERE)

    Effectiveness of Shallow Temperatures Surveys to Target a Geothermal Reservoir at Previously Explored Site at Mcgee Mountain, Nevada Jump to: navigation, search OpenEI Reference...

  4. Verification survey of the 17th Street Drainage Area, Santa Susana Field Laboratory, The Boeing Company, Ventura County, California

    SciTech Connect (OSTI)

    John R. Morton

    2000-04-14

    An independent (third-party) verification of contractor remedial actions of the subject site verifies that remedial actions have been effective in meeting established and site-specific guidelines and that the documentation accurately and adequately describes the radiological conditions at the site.

  5. Facility Approvals, Security Surveys, and Nuclear Materials Surveys

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

    1988-02-03

    To establish the Department of Energy (DOE) requirements for granting facility approvals prior to permitting safeguards and security interests on the premises and the conduct of on-site security and/or nuclear material surveys of facilities with safeguards and security interests. Cancels DOE O 5630.7 and DOE O 5634.1. Canceled by DOE 5634.1B.

  6. Hanford Site

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

    Subcontract for characterization work issued Subcontract for characterization work issued Recovery Act Projects Underway Recovery Act Projects Underway Hanford Site New Hires...

  7. Hanford Site

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

    Treatment Record Groundwater Treatment Resin HAMMER Site-Wide Safety Standards Helicopter Removes Truck on ALE Highly Radioactive Sludge Removal Complete HSS Beryllium Out...

  8. Hanford Site

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

    Well Drilling Wells are drilled at the Hanford Site to support detecting and treating contamination in the groundwater. Search Search Search Filter: Well Drilling All Galleries 284...

  9. Hanford Site

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

    tour the Hanford Site to learn about cleanup technologies that could be used at Fukushima. Search Search Search Filter: TEPCO Visit All Galleries 284 East Explosive...

  10. Hanford Site

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

    HAMMER Site-Wide Safety Standards Helicopter Removes Truck on ALE Highly Radioactive Sludge Removal Complete HSS Beryllium Out Brief Improving Access to Tank C-107 K Basins...

  11. Hanford Site

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

    Secretary Ernest Moniz Visits Hanford United States Department of Energy Secretary Dr. Ernest Moniz visited the Hanford Site in southeastern Washington state on June 19, 2013....

  12. Recovery from chemical, biological, and radiological incidents :

    SciTech Connect (OSTI)

    Franco, David Oliver; Yang, Lynn I.; Hammer, Ann E.

    2012-06-01

    To restore regional lifeline services and economic activity as quickly as possible after a chemical, biological or radiological incident, emergency planners and managers will need to prioritize critical infrastructure across many sectors for restoration. In parallel, state and local governments will need to identify and implement measures to promote reoccupation and economy recovery in the region. This document provides guidance on predisaster planning for two of the National Disaster Recovery Framework Recovery Support Functions: Infrastructure Systems and Economic Recovery. It identifies key considerations for infrastructure restoration, outlines a process for prioritizing critical infrastructure for restoration, and identifies critical considerations for promoting regional economic recovery following a widearea disaster. Its goal is to equip members of the emergency preparedness community to systematically prioritize critical infrastructure for restoration, and to develop effective economic recovery plans in preparation for a widearea CBR disaster.

  13. Site environmental report for 1994. Environmental report, January--December 1994

    SciTech Connect (OSTI)

    1994-12-31

    This document is the 1994 site environmental report for the Rocky Flats Environmental Technology Site for January thru December. Compliance programs, radiological and nonradiological monitoring, and significant issues and events are described. In addition, the methodology for radiation dose assessment and the Environmental Restoration, Waste Management, and Quality Assurance programs are discussed.

  14. Geophex Airborne Unmanned Survey System

    SciTech Connect (OSTI)

    Won, I.L.; Keiswetter, D.

    1995-12-31

    Ground-based surveys place personnel at risk due to the proximity of buried unexploded ordnance (UXO) items or by exposure to radioactive materials and hazardous chemicals. The purpose of this effort is to design, construct, and evaluate a portable, remotely-piloted, airborne, geophysical survey system. This non-intrusive system will provide stand-off capability to conduct surveys and detect buried objects, structures, and conditions of interest at hazardous locations. During a survey, the operators remain remote from, but within visual distance of, the site. The sensor system never contacts the Earth, but can be positioned near the ground so that weak geophysical anomalies can be detected. The Geophex Airborne Unmanned Survey System (GAUSS) is designed to detect and locate small-scale anomalies at hazardous sites using magnetic and electromagnetic survey techniques. The system consists of a remotely-piloted, radio-controlled, model helicopter (RCH) with flight computer, light-weight geophysical sensors, an electronic positioning system, a data telemetry system, and a computer base-station. The report describes GAUSS and its test results.

  15. Evaluation of Cavity Collapse and Surface Crater Formation at the Salut Underground Nuclear Test in U20ak, Nevada National Security Site, and the Impact of Stability of the Ground Surface

    SciTech Connect (OSTI)

    Pawloski, G A

    2012-04-25

    At the request of Jerry Sweeney, the LLNL Containment Program performed a review of nuclear test-related data for the Salut underground nuclear test in U20ak to assist in evaluating this legacy site as a test bed for application technologies for use in On-Site Inspections (OSI) under the Comprehensive Nuclear Test Ban Treaty. Review of the Salut site is complicated because the test experienced a subsurface, rather than surface, collapse. Of particular interest is the stability of the ground surface above the Salut detonation point. Proposed methods for on-site verification include radiological signatures, artifacts from nuclear testing activities, and imaging to identify alteration to the subsurface hydrogeologogy due to the nuclear detonation. Sweeney's proposal requires physical access at or near the ground surface of specific underground nuclear test locations at the Nevada Nuclear Test Site (NNSS, formerly the Nevada Test Site), and focuses on possible activities such as visual observation, multispectral measurements, and shallow, and deep geophysical surveys.

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

    SciTech Connect (OSTI)

    Wickline, Alfred

    2006-12-01

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

  17. Investigation of CTBT OSI Radionuclide Techniques at the DILUTED WATERS Nuclear Test Site

    SciTech Connect (OSTI)

    Baciak, James E.; Milbrath, Brian D.; Detwiler, Rebecca S.; Kirkham, Randy R.; Keillor, Martin E.; Lepel, Elwood A.; Seifert, Allen; Emer, Dudley; Floyd, Michael

    2012-11-01

    Under the Comprehensive Nuclear-Test-Ban Treaty (CTBT), a verification regime that includes the ability to conduct an On-Site Inspection (OSI) will be established. The Treaty allows for an OSI to include many techniques, including the radionuclide techniques of gamma radiation surveying and spectrometry and environmental sampling and analysis. Such radioactivity detection techniques can provide the “smoking gun” evidence that a nuclear test has occurred through the detection and quantification of indicative recent fission products. An OSI faces restrictions in time and manpower, as dictated by the Treaty; not to mention possible logistics difficulties due to the location and climate of the suspected explosion site. It is thus necessary to have a good understanding of the possible source term an OSI will encounter and the proper techniques that will be necessary for an effective OSI regime. One of the challenges during an OSI is to locate radioactive debris that has escaped an underground nuclear explosion (UNE) and settled on the surface near and downwind of ground zero. To support the understanding and selection of sampling and survey techniques for use in an OSI, we are currently designing an experiment, the Particulate Release Experiment (PRex), to simulate a small-scale vent from an underground nuclear explosion. PRex will occur at the Nevada National Security Site (NNSS). The project is conducted under the National Center for Nuclear Security (NCNS) funded by the National Nuclear Security Agency (NNSA). Prior to the release experiment, scheduled for Spring of 2013, the project scheduled a number of activities at the NNSS to prepare for the release experiment as well as to utilize the nuclear testing past of the NNSS for the development of OSI techniques for CTBT. One such activity—the focus of this report—was a survey and sampling campaign at the site of an old UNE that vented: DILUTED WATERS. Activities at DILUTED WATERS included vehicle-based survey, in situ measurements with high-purity germanium (HPGe) and hand-held LaBr3 systems, soil sampling with a variety of tools, and laboratory gamma spectrometric analysis of those samples. A further benefit of the measurement campaign was to gain familiarity with the many logistical aspects of performing radiological field work at NNSS ahead of the PRex. Many practical lessons concerning the proper methodologies and logistics of using the surveying and sampling equipment were noted. These Lessons Learned are compiled together in Appendix A. The vehicle-based survey was successful in that it found a previously unknown hotspot (determined to be 232Th) while it demonstrated that a better method for keeping a serpentine track without staking was needed. Some of the soil sampling equipment was found to be impractical for the application, though core sampling would not be the correct way to take soil samples for a fresh vent deposit (as opposed to an old site like DILUTED WATERS). Due to the site’s age, 137Cs was the only fission radioisotope identified, though others were searched for. While not enough samples were taken and analyzed to definitively link the 137Cs to DILUTED WATERS as opposed to other NNSS activities, results were consistent with the historical DILUTED WATERS plume. MDAs were compared for soil sampling and in situ measurements.

  18. INTERAGENCY REPORT APOLLO 17 LANDING SITE GEOLOGY

    E-Print Network [OSTI]

    Rathbun, Julie A.

    INTERAGENCY REPORT APOLLO 17 LANDING SITE GEOLOGY UNITED STATES DEPARTMENT OF THE INTERIOR GEOLOGICAL SURVEY ASTROGEOLOGY #73 JUNE 1975 Prepared under NASA Contract T-5874A and W13,130 NATIONAL STATES DEPARTMENT OF THE INTERIOR GEOLOGICAL SURVEY INTERAGENCY REPORT: ASTROGEOLOGY 73 Part I

  19. Summary of comments received from workshops on radiological criteria for decommissioning

    SciTech Connect (OSTI)

    Caplin, J.; Page, G.; Smith, D.; Wiblin, C.

    1994-01-01

    The Nuclear Regulatory Commission (NRC) is conducting an enhanced participatory rulemaking to establish radiological criteria for site cleanup and decommissioning of NRC-licensed facilities. Open public meetings were held during 1993 in Chicago, IL, San Francisco, CA, Boston, MA, Dallas, TX, Philadelphia, PA, Atlanta, GA, and Washington, DC. Interested parties were invited to provide input on the rulemaking issues before the NRC staff develops a draft proposed rule. This report summarizes 3,635 comments categorized from transcripts of the seven workshops and 1,677 comments from 100 NRC docketed letters from individuals and organizations. No analysis or response to the comments is included. The comments reflect a broad spectrum of viewpoints on the issues related to radiological criteria for site cleanup and decommissioning. The NRC also held public meetings on the scope of the Generic Environmental Impact Statement (GEIS) during July 1993. The GEIS meetings were held in Washington, DC., San Francisco, CA, Oklahoma City, OK, and Cleveland, OH. Related comments from these meetings were reviewed and comments which differed substantially from those from the workshops are also summarized in the body of the report. A summary of the comments from the GEIS scoping meetings is included as an Appendix.

  20. Nevada National Security Site Environmental Report 2011

    SciTech Connect (OSTI)

    Cathy Wills, ed

    2012-09-12

    This report 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. It was prepared by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This and previous years reports, called Annual Site Environmental Reports (ASERs), Nevada Test Site Environmental Reports (NTSERs), and, beginning in 2010, Nevada National Security Site Environmental Reports (NNSSERs), are posted on the NNSA/NSO website at http://www.nv.energy.gov/library/publications/aser.aspx. This NNSSER was prepared to satisfy DOE Order DOE O 231.1B, 'Environment, Safety and Health Reporting.' 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 NNSA/NSO Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts. This NNSSER summarizes data and compliance status for calendar year 2011 at the Nevada National Security Site (NNSS) (formerly the Nevada Test Site) and its two support facilities, the North Las Vegas Facility (NLVF) and the Remote Sensing Laboratory-Nellis (RSL-Nellis). It also addresses environmental restoration (ER) projects conducted at the Tonopah Test Range (TTR). Through a Memorandum of Agreement, NNSA/NSO is responsible for the oversight of TTR ER projects, and the Sandia Site Office of NNSA (NNSA/SSO) has oversight of all other TTR activities. NNSA/SSO produces the TTR annual environmental report available at http://www.sandia.gov/news/publications/environmental/index.html.

  1. Nevada Test Site Environmental Report 2006 and Site Description (Volume 1)

    SciTech Connect (OSTI)

    Cathy Wills

    2007-10-01

    The Nevada Test Site Environmental Report 2006 (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. It was prepared by National Security Technologies, LLC (NSTec). 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 nonradiological releases, implementation status of the NTS Environmental Management System, a summary of compliance with environmental regulations, pollution prevention and waste minimization accomplishments, 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 2006 produced to be a more cost-effective means of distributing information contained in the NTSER to interested DOE stakeholders.

  2. Chapter 3: Building Siting

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    : Building Siting Site Issues at LANL Site Inventory and Analysis Site Design Transportation and Parking LANL | Chapter 3 Site Issues at LANL Definitions and related documents...

  3. Survey Data 

    E-Print Network [OSTI]

    Unknown

    2011-08-17

    Knowledge of surface sediment distribution in Galveston Bay is important because it allows us to better understand how the bay works and how human activities impact the bay and its ecosystems. In this project, six areas of bay bottom were surveyed...

  4. Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado. Volume 2, Appendices D and E: Final report

    SciTech Connect (OSTI)

    Not Available

    1992-02-01

    This appendix assesses the present conditions and data gathered about the two inactive uranium mill tailings sites near Rifle, Colorado, and the designated disposal site six miles north of Rifle in the area of Estes Gulch. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill, tailings, and disposal site so that the Remedial Action Contractor (RAC) may complete final designs for the remedial actions.

  5. Site Management Guide (Blue Book)

    SciTech Connect (OSTI)

    2014-03-01

    The U.S. Department of Energy (Department) Office of Legacy Management (LM), established in 2003, manages the Department’s postclosure responsibilities and ensures the future protection of human health and the environment. During World War II and the Cold War, the Federal government developed and operated a vast network of industrial facilities for the research, production, and testing of nuclear weapons, as well as other scientific and engineering research. These processes left a legacy of radioactive and chemical waste, environmental contamination, and hazardous facilities and materials at well over 100 sites. Since 1989, the Department has taken an aggressive accelerated cleanup approach to reduce risks and cut costs. At most Departmental sites undergoing cleanup, some residual hazards will remain at the time cleanup is completed due to financial and technical impracticality. However, the Department still has an obligation to protect human health and the environment after cleanup is completed. LM fulfills DOE’s postclosure obligation by providing long-term management of postcleanup sites which do not have continuing missions. LM is also responsible for sites under the Formerly Utilized Sites Remedial Action Program (FUSRAP). Currently, the U.S. Army Corps of Engineers (USACE) is responsible for site surveys and remediation at FUSRAP sites. Once remediation is completed, LM becomes responsible for long-term management. LM also has responsibility for uranium processing sites addressed by Title II of the Uranium Mill Tailings Radiation Control Act (UMTRCA). UMTRCA Title II sites are sites that were commercially owned and are regulated under a U.S. Nuclear Regulatory Commission (NRC) license. For license termination, the owner must conduct an NRC-approved cleanup of any on-site radioactive waste remaining from former uranium ore-processing operations. The site owner must also provide full funding for inspections and, if necessary, ongoing maintenance. Once site cleanup is complete, LM accepts title to these sites on behalf of the United States and assumes long-term management.

  6. Bayesian Network Analysis of Radiological Dispersal Device Acquisitions 

    E-Print Network [OSTI]

    Hundley, Grant Richard

    2012-02-14

    It remains unlikely that a terrorist organization could produce or procure an actual nuclear weapon. However, the construction of a radiological dispersal device (RDD) from commercially produced radioactive sources and conventional explosives could...

  7. The purpose of this survey is to gather information needed to develop guidelines for ecological restoration project planning in Minnesota. We are asking you to provide cost and time estimates for site preparation,

    E-Print Network [OSTI]

    Sprott, Julien Clinton

    1 The purpose of this survey is to gather information needed to develop guidelines for ecological indicate which services & supplies are provided in-house, purchased/ hired out, or not offered or performed to page 7. Provided In-House Purchased/ Hired out Not Offered/ Not Performed A. Project Management

  8. Surveillance of Site A and Plot M

    SciTech Connect (OSTI)

    Golchert, N.W.

    1991-05-01

    The results of the environmental surveillance program conducted at Site A/Plot M in the Palos Forest Preserve area for CY 1990 are presented. The surveillance program is the ongoing remedial action that resulted from the 1976-1978 radiological characterization of the site. That study determined that very low levels of hydrogen-3 (as tritiated water) had migrated from the burial ground and were present in two nearby hand-pumped picnic wells. The current program consists of sample collection and analysis of air, surface and subsurface water, and bottom sediment. The results of the analyses are used to determine the migration pathway of water from the burial ground (plot M) to the hand-pumped picnic wells, establish if buries radionuclides other than hydrogen-3 have migrated, and generally characterize the radiological environment of the area. Tritiated water continues to be detected in a number of wells, boreholes, dolomite holes, and a surface stream. Analyses since 1984 have indicated the presence of low levels of strontium-90 in water from a number of boreholes next to Plot M. The results of the surveillance program continues to indicate that the radioactivity remaining at Site A/Plot M does not endanger the health or safety of the public visiting the site or those living in the vicinity. 20 refs., 7 figs., 15 tabs.

  9. Hanford Site

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

    Media Visit to Hazardous Burial Ground Members of the media out at one of the most hazardous burial grounds on site to take a look at work funded by Recovery Act funds. Search...

  10. Hanford Site

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

    McCluskey Room progress Hanford workers continue progress toward demolition of the Plutonium Finishing Plant. Crews worked to remove the face of the glove box that was the site of...

  11. Hanford Site

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

    waste site, BC, BC Control Area Area: BC Control Area Description: After removing contaminated soils, the 140-acre area was revegetated with seed and about 280,000 pounds of mulch...

  12. Hanford Site

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

    is one of nine former plutonium production reactors along the Columbia River at the Hanford Site. The work is part of the ongoing effort to decommission and prepare the K East...

  13. COACHE Faculty Job Satisfaction Survey SURVEY INSTRUMENT

    E-Print Network [OSTI]

    Johnson Jr.,, Ray

    2011-2012 Survey Instrument Theme Benchmark Question Responses Historic Data Available EligibleCOACHE Faculty Job Satisfaction Survey SURVEY INSTRUMENT 2011-12 © 2011 President & Fellows in Higher Education Faculty Job Satisfaction Survey 2011-2012 Survey Instrument Theme Benchmark Question

  14. Antiplatelet and Anticoagulant Drugs in Interventional Radiology

    SciTech Connect (OSTI)

    Altenburg, Alexander; Haage, Patrick, E-mail: patrick.haage@helios-kliniken.de [University Hospital Witten/Herdecke, Department of Diagnostic and Interventional Radiology, HELIOS Klinikum Wuppertal (Germany)

    2012-02-15

    In treating peripheral arterial disease, a profound knowledge of antiplatelet and anticoagulative drug therapy is helpful to assure a positive clinical outcome and to anticipate and avoid complications. Side effects and drug interactions may have fatal consequences for the patient, so interventionalists should be aware of these risks and able to control them. Aspirin remains the first-line agent for antiplatelet monotherapy, with clopidogrel added where dual antiplatelet therapy is required. In case of suspected antiplatelet drug resistance, the dose of clopidogrel may be doubled; prasugrel or ticagrelor may be used alternatively. Glycoprotein IIb/IIIa inhibitors (abciximab or eptifibatide) may help in cases of hypercoagulability or acute embolic complications. Desmopressin, tranexamic acid, or platelet infusions may be used to decrease antiplatelet drug effects in case of bleeding. Intraprocedurally, anticoagulant therapy treatment with unfractionated heparin (UFH) still is the means of choice, although low molecular-weight heparins (LMWH) are suitable, particularly for postinterventional treatment. Adaption of LMWH dose is often required in renal insufficiency, which is frequently found in elderly patients. Protamine sulphate is an effective antagonist for UFH; however, this effect is less for LMWH. Newer antithrombotic drugs, such as direct thrombin inhibitors or factor X inhibitors, have limited importance in periprocedural treatment, with the exception of treating patients with heparin-induced thrombocytopenia (HIT). Nevertheless, knowing pharmacologic properties of the newer drugs facilitate correct bridging of patients treated with such drugs. This article provides a comprehensive overview of antiplatelet and anticoagulant drugs for use before, during, and after interventional radiological procedures.

  15. Multi-site environmental assessments

    SciTech Connect (OSTI)

    Tillman, J.E.

    1993-06-01

    When a commercial or industrial property transfer occurs today, there is almost always an environmental assessment performed. These assessments are requested by buyers, sellers, lenders, insurers, corporate counsel and corporate managers responsible for environmental problems. The scope of these assessments varies widely depending on the objectives, types of sites and number of sites involved. When a single site is being evaluated, the assessment can be highly customized with a great deal of attention paid to the specific use, history of the site, and adjacent properties. In contrast, when multiple sites must be evaluated the luxury of time required to customize each assessment is not always practical. A standardized approach may be the only option to accomplish the assessments in a timely and cost effective manner. Properly performed, a standardized approach can provide adequate and useful comparative data between sites. If the sites are similar in nature standardized data sets provide far more insight about the nature of contamination than can be achieved with data from a single site. Defining the objective of the environmental assessment is necessary to design the type of survey to be performed. In many acquisitions, assessments are done to let the buyers know whether they are buying into a current liability that could cost them hundreds of thousands of dollars to clean up. This objective requires an assessment that provides for thorough coverage of the site until a problem is identified; no characterization is required.

  16. Summary of the HANFORD SITE

    E-Print Network [OSTI]

    ................................................................................7 Hanford Federal Facility Agreement and Consent Order ........................................................................................................11 Facility Decommissioning........................................................................................................23 Potential Radiological Doses from 2004 Hanford Operations

  17. Site Map

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefieldSulfateSciTechtail.Theory ofDidDevelopment Top Scientific ImpactTechnologies |Site Index Site

  18. Site Map

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefieldSulfateSciTechtail.Theory ofDidDevelopment Top Scientific ImpactTechnologies |Site IndexSite Map

  19. Washington Energy Facility Site Evalutation Council - Siting...

    Open Energy Info (EERE)

    Washington Energy Facility Site Evalutation Council - Siting and Review Process Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: Washington Energy...

  20. Corrective Action Investigation Plan for Corrective Action Unit 552: Area 12 Muckpile and Ponds, Nevada Test Site, Nevada, Rev. No.: 1 with ROTC 1 and 2

    SciTech Connect (OSTI)

    David A. Strand

    2005-01-01

    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) 552: Area 12 Muckpile and Ponds, Nevada Test Site (NTS), Nevada. 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. The NTS is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Corrective Action Unit 552 is comprised of the one Corrective Action Site which is 12-23-05, Ponds. One additional CAS, 12-06-04, Muckpile (G-Tunnel Muckpile), was removed from this CAU when it was determined that the muckpile is an active site. A modification to the FFACO to remove CAS 12-06-04 was approved by the Nevada Division of Environmental Protection (NDEP) on December 16, 2004. The G-Tunnel ponds were first identified in the 1991 Reynolds Electrical & Engineering Co., Inc. document entitled, ''Nevada Test Site Inventory of Inactive and Abandoned Facilities and Waste Sites'' (REECo, 1991). Corrective Action Unit 552 is being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Therefore, additional information will be obtained by conducting a corrective action investigation (CAI) prior to evaluating and selecting the corrective action alternatives for the site. The CAI will include field inspections, radiological surveys, and sampling of appropriate media. Data will also be obtained to support investigation-derived waste (IDW) disposal and potential future waste management decisions.

  1. Nevada National Security Site Environmental Report 2010

    SciTech Connect (OSTI)

    C. Wills, ed.

    2011-09-13

    This NNSSER was prepared to satisfy DOE Order DOE O 231.1B, “Environment, Safety and Health Reporting.” 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 NNSA/NSO Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts. This NNSSER summarizes data and compliance status for calendar year 2010 at the Nevada National Security Site (NNSS) (formerly the Nevada Test Site) and its two support facilities, the North Las Vegas Facility (NLVF) and the Remote Sensing Laboratory–Nellis (RSL-Nellis). It also addresses environmental restoration (ER) projects conducted at the Tonopah Test Range (TTR). Through a Memorandum of Agreement, NNSA/NSO is responsible for the oversight of TTR ER projects, and the Sandia Site Office of NNSA (NNSA/SSO) has oversight of all other TTR activities. NNSA/SSO produces the TTR annual environmental report available at http://www.sandia.gov/news/publications/environmental/index.html.

  2. Nevada Test Site Environmental Report 2009

    SciTech Connect (OSTI)

    Cathy Wills, ed.

    2010-09-13

    The Nevada Test Site Environmental Report 2009 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. It was prepared by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This and previous years’ Nevada Test Site Environmental Reports (NTSERs) are posted on the NNSA/NSO website at http://www.nv.doe.gov/library/publications/aser.aspx. This NTSER was prepared to satisfy DOE Order DOE O 231.1A, “Environment, Safety and Health Reporting.” 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 NNSA/NSO Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts. This NTSER summarizes data and compliance status for calendar year 2009 at the Nevada Test Site (NTS) and its two support facilities, the North Las Vegas Facility (NLVF) and the Remote Sensing Laboratory (RSL)-Nellis. It also addresses environmental restoration (ER) projects conducted at the Tonopah Test Range (TTR). Through a Memorandum of Agreement, NNSA/NSO is responsible for the oversight of TTR ER projects, and the Sandia Site Office of NNSA (NNSA/SSO) has oversight of all other TTR activities. NNSA/SSO produces the TTR annual environmental report available at http://www.sandia.gov/news/publications/environmental/index.html.

  3. Risk-Based Radioactive Liquid Effluent Monitoring Requirements at the U. S. Department of Energy's Savannah River Site

    SciTech Connect (OSTI)

    Jannik, G.T.

    2001-07-13

    For Department of Energy (DOE) facilities, clear regulatory guidance exists for structuring radiological air emissions monitoring programs. However, there are no parallel regulations for radiological liquid effluent monitoring programs. In order to bridge this gap and to technically justify liquid effluent monitoring decisions at DOE's Savannah River Site, a graded, risk-basked approach has been established to determine the monitoring and sampling criteria to be applied at each liquid discharge point.

  4. ORISE: Radiological Assessment and Monitoring System (RAMS)

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

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  5. ORISE: Radiological Terms Quick Reference Guide

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

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  6. Site Environmental Report for 2007 Volume I

    E-Print Network [OSTI]

    Lackner, Regina E.

    2008-01-01

    Radiological Dose Assessment West side of the Advanced Light Source FacilityRadiological Health Branch Steve Hsu Kent Prendergast California Department of Toxic Substances Control Facility

  7. Site Environmental Report for 2008, Volume 1

    E-Print Network [OSTI]

    Lackner, Regina

    2009-01-01

    Radiological Dose Assessment West side of the Advanced Light Source FacilityRadiological Health Branch Steve Hsu Kent Prendergast California Department of Toxic Substances Control Facility

  8. Environmental Radiological Effluent Monitoring and Environmental Surveillance

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum12, 2015 InfographiclighbulbsDepartment ofServices3 Annual Site Environmental

  9. Visual Sample Plan (VSP) Statistical Software as Related to the CTBTO’s On-Site Inspection Procedure

    SciTech Connect (OSTI)

    Pulsipher, Trenton C.; Walsh, Stephen J.; Pulsipher, Brent A.; Milbrath, Brian D.

    2010-09-01

    In the event of a potential nuclear weapons test the Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO) is commissioned to conduct an on-site investigation (OSI) of the suspected test site in an effort to find confirmatory evidence of the nuclear test. The OSI activities include collecting air, surface soil, and underground samples to search for indications of a nuclear weapons test - these indicators include radionuclides and radioactive isotopes Ar and Xe. This report investigates the capability of the Visual Sample Plan (VSP) software to contribute to the sampling activities of the CTBTO during an OSI. VSP is a statistical sampling design software, constructed under data quality objectives, which has been adapted for environmental remediation and contamination detection problems for the EPA, US Army, DoD and DHS among others. This report provides discussion of a number of VSP sample designs, which may be pertinent to the work undertaken during an OSI. Examples and descriptions of such designs include hot spot sampling, combined random and judgment sampling, multiple increment sampling, radiological transect surveying, and a brief description of other potentially applicable sampling methods. Further, this work highlights a potential need for the use of statistically based sample designs in OSI activities. The use of such designs may enable canvassing a sample area without full sampling, provide a measure of confidence that radionuclides are not present, and allow investigators to refocus resources in other areas of concern.

  10. The Current and Historical Distribution of Special Status Amphibians at the Livermore Site and Site 300

    SciTech Connect (OSTI)

    Hattem, M V; Paterson, L; Woollett, J

    2008-08-20

    65 surveys were completed in 2002 to assess the current distribution of special status amphibians at the Lawrence Livermore National Laboratory's (LLNL) Livermore Site and Site 300. Combined with historical information from previous years, the information presented herein illustrates the dynamic and probable risk that amphibian populations face at both sites. The Livermore Site is developed and in stark contrast to the mostly undeveloped Site 300. Yet both sites have significant issues threatening the long-term sustainability of their respective amphibian populations. Livermore Site amphibians are presented with a suite of challenges inherent of urban interfaces, most predictably the bullfrog (Rana catesbeiana), while Site 300's erosion issues and periodic feral pig (Sus scrofa) infestations reduce and threaten populations. The long-term sustainability of LLNL's special status amphibians will require active management and resource commitment to maintain and restore amphibian habitat at both sites.

  11. 5 SURVEY PLANNING AND DESIGN 5.1 Introduction

    E-Print Network [OSTI]

    surveys have multiple objectives, this manual focuses on those aspects related to supporting the final assessment and providing data to complete the site prioritization scoring process (CERCLA and RCRA sites only information needed when conducting a preliminary risk assessment (as noted above for CERCLA and RCRA sites

  12. Surveillance of Site A and Plot M report for 1989

    SciTech Connect (OSTI)

    Golchert, N.W.

    1990-04-01

    The results of the environmental monitoring program conducted at Site A/Plot M in the Palos Park Forest Preserve area for CY 1989 are presented. The monitoring program is the ongoing remedial action that resulted from the 1976--1978 radiological characterization of the site. That study had determined that very low levels of hydrogen-3 migrated from the burial ground and was present in two nearby hand-pumped picnic wells. The current program consists of sample collection and analysis of air, surface and subsurface water, and bottom sediment. The results of the analyses are used to determine the migration pathway of water from the burial ground to the hand-pumped picnic wells, establish if buried radionuclides other than hydrogen-3 have migrated, and generally characterize the radiological environment of the area. 16 refs., 6 figs., 15 tabs.

  13. Environmental Survey preliminary report, Solar Energy Research Institute, Golden, Colorado

    SciTech Connect (OSTI)

    Not Available

    1988-10-01

    This report presents the preliminary findings of the first phase of the Environmental Survey of the US Department of Energy's (DOE) Solar Energy Research Institute (SERI), conducted December 14 through 18, 1987. 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. The team includes outside experts supplied by private contractors. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with SERI. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data, observations of the operations carried on at SERI, and interviews with site personnel. 33 refs., 22 figs., 21 tabs.

  14. Analytical methods for removing radiological constituents prior to organic analysis

    SciTech Connect (OSTI)

    Hakonson, K.; Monagle, M.; Cournoyer, M.

    1997-12-31

    Within the Department of Energy (DOE), there is a need to analyze mixed waste materials (i.e. materials that are contaminated with both radiological and hazardous components). As part of the technical support the Organic Analysis Group provides for programs within Los Alamos National Laboratory, methods are under development for radiologically contaminated oil samples being tested for polychlorinated biphenyls and other semivolatile constituents. Radionuclides are removed from oil samples by filtering the samples through a commercials available solid phase extraction cartridge. An aliquot of the eluent is then analyzed to quantitate the residual radioactivity.

  15. Hanford Radiological Protection Support Services Annual Report for 2000

    SciTech Connect (OSTI)

    Lynch, Timothy P.; Bihl, Donald E.; Johnson, Michelle L.; Maclellan, Jay A.; Piper, Roman K.

    2001-05-07

    During calendar year 2000, the Pacific Northwest National Laboratory performed its customary radiological protection support services in support of the U.S. Department of Energy Richland Operations Office and the Hanford contractors. These services included: 1) external dosimetry, 2) internal dosimetry, 3) in vivo monitoring, 4) radiological records, 5) instrument calibration and evaluation, and 6) calibration of radiation sources traceable to the National Institute of Standards and Technology. Each program summary describes the routine operations, program changes and improvements, program assessments, supporting technical studies, and professional activities.

  16. Tillman Creek Mitigation Site As-Build Report.

    SciTech Connect (OSTI)

    Gresham, Doug [Otak, Inc.

    2009-05-29

    This as-built report describes site conditions at the Tillman Creek mitigation site in South Cle Elum, Washington. This mitigation site was constructed in 2006-2007 to compensate for wetland impacts from the Yakama Nation hatchery. This as-built report provides information on the construction sequence, as-built survey, and establishment of baseline monitoring stations.

  17. Tonopah Test Range Air Monitoring: CY2012 Meteorological, Radiological, and Airborne Particulate Observations

    SciTech Connect (OSTI)

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

    2013-07-01

    In 1963, the Atomic Energy Commission (AEC), predecessor to the US Department of Energy (DOE), 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 dispersal of plutonium over the ground surface downwind of the test ground zero. Three tests, Clean Slate 1, 2, and 3, were conducted on the TTR in Cactus Flat; the fourth, Double Tracks, was conducted in Stonewall Flat on the NTTR. DOE is working to clean up and close all four sites. Substantial cleaned up has been accomplished at Double Tracks and Clean Slate 1. Cleanup of Clean Slate 2 and 3 is on the DOE planning horizon for some time in the next several years. The Desert Research Institute installed two monitoring stations, number 400 at the Sandia National Laboratories Range Operations Center and number 401 at Clean Slate 3, in 2008 and a third monitoring station, number 402 at Clean Slate 1, in 2011 to measure radiological, meteorological, and dust conditions. The primary objectives of the data collection and analysis effort are to (1) monitor the concentration of radiological parameters in dust particles suspended in air, (2) determine whether winds are re-distributing radionuclides or contaminated soil material, (3) evaluate the controlling meteorological conditions if wind transport is occurring, and (4) measure ancillary radiological, meteorological, and environmental parameters that might provide insight to the above assessments. The following observations are based on data collected during CY2012. The mean annual concentration of gross alpha and gross beta is highest at Station 400 and lowest at Station 401. This difference may be the result of using filter media at Station 400 with a smaller pore size than the media used at the other two stations. Average annual gamma exposure at Station 401 is slightly greater than at Station 400 and 402. Average annual gamma exposure at all three TTR stations are in the upper range to slightly higher than values reported for the CEMP stations surrounding the TTR. At higher wind speeds, the saltation counts are greater at Station 401 than at Station 402 while the suspended particulate concentrations are greater at Station 402 than at Statin 401. Although these observations seem counterintuitive, they are likely the result of differences in the soil material present at the two sites. Station 401 is located on an interfluve elevated above two adjacent drainage channels where the soil surface is likely to be composed of coarser material. Station 402 is located in finer sediments at the playa edge and is also subject to dust from a dirt road only 500 m to the north. During prolonged high wind events, suspended dust concentrations at Station 401 peaked with the initial winds then decreased whereas dust concentrations at Station 402 peaked with each peak in the wind speed. This likely reflects a limited PM10 source that is quickly expended at Station 401 relative to an abundant PM10 source at Station 402. In CY2013, to facilitate comparisons between radiological analyses of collected dust, the filter media at all three stations will be standardized. In addition, a sequence of samples will be collected at Station 400 using both types of filter media to enable development of a mathematical relationship between the results derived from the two filter types. Additionally, having acquired approximately four years of observations at Stations 400 and 401 and a year of observations at Station 402, a period-of-record analysis of the radiological and airborne dust conditions will be undertaken.

  18. A survey of the wetlands and floodplains of the borrow area and wetland/shorebird complex for the remedial action at the chemical plant area of the Weldon Spring Site

    SciTech Connect (OSTI)

    Van Lonkhuyzen, R.; Yin, S.; Hlohowskyj, I.

    1995-02-01

    The US Department of Energy is conducting cleanup operations at the Weldon Spring site, St. Charles, Missouri, that will include development of a 77-ha (191-acre) soil borrow area. Eight wetlands, including riverine and palustrine emergent wetland types and totaling 0.9 ha (2.2 acres), will be eliminated during excavation of the borrow area. A 23-ha (57-acre) wetland/shorebird complex will be created at the Busch Conservation Area. The complex will include 2 ha (5 acres) of palustrine emergent wetland as mitigation for wetland losses in the borrow area.

  19. Health care facility-based decontamination of victims exposed to chemical, biological, and radiological materials

    E-Print Network [OSTI]

    Koenig, Kristi L MD

    2008-01-01

    radiological exposures may also present first to healthcare facilities.facility-based decontamination of victims exposed to chemical, biological, and radiologicalfacility-based decontamination of victims exposed to chemical, biological, and radiological

  20. Surface with two paint strips for detection and warning of chemical warfare and radiological agents

    DOE Patents [OSTI]

    Farmer, Joseph C.

    2013-04-02

    A system for warning of corrosion, chemical, or radiological substances. The system comprises painting a surface with a paint or coating that includes an indicator material and monitoring the surface for indications of the corrosion, chemical, or radiological substances.

  1. Method for warning of radiological and chemical substances using detection paints on a vehicle surface

    DOE Patents [OSTI]

    Farmer, Joseph C. (Tracy, CA)

    2012-03-13

    A system for warning of corrosion, chemical, or radiological substances. The system comprises painting a surface with a paint or coating that includes an indicator material and monitoring the surface for indications of the corrosion, chemical, or radiological substances.

  2. Paint for detection of corrosion and warning of chemical and radiological attack

    DOE Patents [OSTI]

    Farmer, Joseph C. (Tracy, CA)

    2010-08-24

    A system for warning of corrosion, chemical, or radiological substances. The system comprises painting a surface with a paint or coating that includes an indicator material and monitoring the surface for indications of the corrosion, chemical, or radiological substances.

  3. CRITICAL RADIONUCLIDE AND PATHWAY ANALYSIS FOR THE SAVANNAH RIVER SITE

    SciTech Connect (OSTI)

    Jannik, T.

    2011-08-30

    This report is an update to the analysis, Assessment of SRS Radiological Liquid and Airborne Contaminants and Pathways, that was performed in 1997. An electronic version of this large original report is included in the attached CD to this report. During the operational history (1954 to the present) of the Savannah River Site (SRS), many different radionuclides have been released to the environment from the various production facilities. However, as will be shown by this updated radiological critical contaminant/critical pathway analysis, only a small number of the released radionuclides have been significant contributors to potential doses and risks to offsite people. The analysis covers radiological releases to the atmosphere and to surface waters, the principal media that carry contaminants offsite. These releases potentially result in exposure to offsite people. The groundwater monitoring performed at the site shows that an estimated 5 to 10% of SRS has been contaminated by radionuclides, no evidence exists from the extensive monitoring performed that groundwater contaminated with these constituents has migrated off the site (SRS 2011). Therefore, with the notable exception of radiological source terms originating from shallow surface water migration into site streams, onsite groundwater was not considered as a potential exposure pathway to offsite people. In addition, in response to the Department of Energy's (DOE) Order 435.1, several Performance Assessments (WSRC 2008; LWO 2009; SRR 2010; SRR 2011) and a Comprehensive SRS Composite Analysis (SRNO 2010) have recently been completed at SRS. The critical radionuclides and pathways identified in these extensive reports are discussed and, where applicable, included in this analysis.

  4. DECOMMISSIONING CHALLENGES AT THE ROCKY FLATS ENVIRONMENTAL TECHNOLOGY SITE

    SciTech Connect (OSTI)

    Dorr, K. A.; Hoover, J.

    2002-02-25

    This paper presents a discussion of the demolition of the Building 788 cluster at the Rocky Flats Environmental Technology Site (RFETS) in Golden, Colorado. The Building 788 Cluster was a Resource Conservation and Recovery Act (RCRA) permitted storage facilities and ancillary structures. Topics covered include the methods employed for Project Planning, Regulatory Compliance, Waste Management, Hazard Identification, Radiological Controls, Risk Management, Field Implementation, and Cost Schedule control, and Lessons Learned and Project Closeout.

  5. Tonopah Test Range Air Monitoring: CY2013 Meteorological, Radiological, and Airborne Particulate Observations

    SciTech Connect (OSTI)

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

    2014-10-01

    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). This test resulted in radionuclide-contaminated soils at Clean Slate I, II, and III. This report documents observations made during on-going monitoring of radiological, meteorological, and dust conditions at stations installed adjacent to Clean Slate I and Clean Slate III and at the TTR Range Operations Control center. The primary objective of the monitoring effort is to determine if winds blowing across the Clean Slate sites are transporting particles of radionuclide-contaminated soils beyond both the physical and administrative boundaries of the sites. Results for the calendar year (CY) 2013 monitoring include: (1) the gross alpha and gross beta values from the monitoring stations are approximately equivalent to the highest values observed during the CY2012 reporting at the surrounding Community Environmental Monitoring Program (CEMP) stations (this was the latest documented data available at the time of this writing); (2) only naturally occurring radionuclides were identified in the gamma spectral analyses; (3) the ambient gamma radiation measurements indicate that the average annual gamma exposure is similar at all three monitoring stations and periodic intervals of increased gamma values appear to be associated with storm fronts passing through the area; and (4) the concentrations of both resuspended dust and saltated sand particles generally increase with increasing wind speed. However, differences in the observed dust concentrations are likely due to differences in the soil characteristics immediately adjacent to the monitoring stations. Neither the resuspended particulate radiological analyses nor the ambient gamma radiation measurements suggest wind transport of radionuclide-contaminated soils.

  6. Dr. Keith Schiager, Director Radiological Health

    Office of Legacy Management (LM)

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  7. Radiological Security Partnership Information | National Nuclear Security

    National Nuclear Security Administration (NNSA)

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  8. Radiological risk assessment of environmental radon

    SciTech Connect (OSTI)

    Khalid, Norafatin; Majid, Amran Ab; Yahaya, Redzuwan; Yasir, Muhammad Samudi

    2013-11-27

    Measurements of radon gas ({sup 222}Rn) in the environmental are important to assess indoor air quality and to study the potential risk to human health. Generally known that exposure to radon is considered the second leading cause of lung cancer after smoking. The environmental radon concentration depends on the {sup 226}Ra concentration, indoor atmosphere, cracking on rocks and building materials. This study was carried out to determine the indoor radon concentration from selected samples of tin tailings (amang) and building materials in an airtight sealed homemade radon chamber. The radiological risk assessment for radon gas was also calculated based on the annual exposure dose, effective dose equivalent, radon exhalation rates and fatal cancer risk. The continuous radon monitor Sun Nuclear model 1029 was used to measure the radon concentration emanates from selected samples for 96 hours. Five types of tin tailings collected from Kampar, Perak and four samples of building materials commonly used in Malaysia dwellings or building constructions were analysed for radon concentration. The indoor radon concentration determined in ilmenite, monazite, struverite, xenotime and zircon samples varies from 219.6 ± 76.8 Bq m{sup ?3} to 571.1 ± 251.4 Bq m{sup ?3}, 101.0 ± 41.0 Bq m{sup ?3} to 245.3 ± 100.2 Bq m{sup ?3}, 53.1 ± 7.5 Bq m{sup ?3} to 181.8 ± 9.7 Bq m{sup ?3}, 256.1 ± 59.3 Bq m{sup ?3} to 652.2 ± 222.2 Bq m{sup ?3} and 164.5 ± 75.9 Bq m{sup ?3} to 653.3 ± 240.0 Bq m{sup ?3}, respectively. Whereas, in the building materials, the radon concentration from cement brick, red-clay brick, gravel aggregate and cement showed 396.3 ± 194.3 Bq m{sup ?3}, 192.1 ± 75.4 Bq m{sup ?3}, 176.1 ± 85.9 Bq m{sup ?3} and 28.4 ± 5.7 Bq m{sup ?3}, respectively. The radon concentration in tin tailings and building materials were found to be much higher in xenotime and cement brick samples than others. All samples in tin tailings were exceeded the action level for radon gas of 148 Bq m{sup ?3} proposed by EPA except monazite 0.15 kg, struverite 0.15 kg and 0.25 kg. Whereas, all building material samples have exceeded the radon concentration in concrete and building materials of 3 to 7 Bq m{sup ?3} estimated by ICRP. The annual effective dose, effective dose equivalent, and radon exhalation rates in tin tailings were calculated to be in the range of 2.47 to 11.46 mSv, 5.94 to 1090.56 mSv y{sup ?1}, and 0.23 to 1.18 mBq kg{sup ?1} h{sup ?1}. For building materials, the calculated risk assessment of the annual effective dose, effective dose equivalent, radon exhalation rates and fatal cancer risk were 0.72 to 10.00 mSv, 1.73 to 24.00 mSv y{sup ?1}, 0.010 to 0.06 mBq kg{sup ?1} h{sup ?1} and 40 to 550 chances of persons will suffer the cancer per million (1 × 10{sup 6}), respectively.

  9. Sacandaga Site

    Office of Legacy Management (LM)

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  10. Site Map

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

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  11. ARM - Sites

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

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  12. Site Map

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

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  13. Annual Site Environmental Report, 2004

    SciTech Connect (OSTI)

    Nuckolls, H.; /SLAC

    2006-04-19

    This report provides information about environmental programs during 2004 at the Stanford Linear Accelerator Center (SLAC). Seasonal activities that span calendar years are also included. Production of an annual site environmental report (ASER) is a requirement established by the United States Department of Energy (DOE) for all management and operating (M&O) contractors throughout the DOE complex. SLAC is a federally-funded, research and development center with Stanford University as the M&O contractor. The most noteworthy information in this report is summarized in this section. This summary demonstrates the effective application of SLAC environmental management in meeting the site's integrated safety management system (ISMS) goals. For normal daily activities, all SLAC managers and supervisors are responsible for ensuring that proper procedures are followed so that worker safety and health are protected; the environment is protected; and compliance is ensured. Throughout 2004, SLAC focused on these activities through the SLAC management systems (described in Chapter 3). These systems were also the way SLAC approached implementing ''greening of the government'' initiatives such as Executive Order 13148. The management systems at SLAC are effective, supporting compliance with all relevant statutory and regulatory requirements. There were no reportable releases to the environment from SLAC operations during 2004. In addition, many improvements were continued during 2004, in waste minimization, recycling, decreasing air emission rates, stormwater drain system, groundwater restoration, and planning for a chemical management system to manage chemical use better. Program-specific details discussed are: (1) Air Quality--SLAC operates its air quality management program in compliance with its established permit conditions: 2004 was the seventh consecutive year the air quality management program operated without receiving any notices of violation (NOVs) from regulators. (2) Hazardous Waste--The Environmental Health Division of the San Mateo County Health Services Agency is the California certified unified permitting agency (CUPA) responsible for overseeing hazardous materials and waste management at SLAC. The CUPA made no facility inspections of SLAC during 2004. (3) Stormwater and Industrial Wastewater--SLAC operates its industrial and sanitary wastewater management program in compliance with established permit conditions: 2004 was the eighth consecutive year the program operated without receiving any NOVs from program regulators. During 2004 the last 32 unauthorized discharge connections to the stormwater system were eliminated. (4) Hazardous Materials Program--Although SLAC has been successful in meeting the regulatory requirements for managing hazardous materials, it has decided to pursue a more active strategy in reducing its use of such materials. The cornerstone of this effort is the implementation of a chemical management system (CMS). (5) Environmental Radiological Program--In 2004, no radiological incidents occurred that increased radiation levels or released radioactivity to the environment. In addition to managing its radioactive wastes safely and responsibly, SLAC worked to reduce the amount of waste generated. As detailed in Chapter 5, SLAC has implemented programs and systems to ensure compliance with all radiological requirements related to the environment. (6) Groundwater Protection and Environmental Restoration--In general, environmental concerns at SLAC are limited in number, small in scale and are actively being managed or eliminated. The Environmental Restoration Program continued work on site characterization and evaluation of remedial alternatives at four sites with volatile organic compounds (VOCs) in groundwater and several areas with polychlorinated biphenyls (PCBs) and lead in soil.

  14. Environmental Survey preliminary report, Fermi National Accelerator Laboratory, Batavia, Illinois

    SciTech Connect (OSTI)

    Not Available

    1988-10-01

    This report presents the preliminary findings from the first phase of the Environmental Survey of the US Department of Energy (DOE) Fermi National Accelerator Laboratory (Fermilab), conducted September 14 through 25, 1987. 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 participants for the Survey team are being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with Fermilab. 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 performed at Fermilab, and interviews with site personnel. 110 refs., 26 figs., 41 tabs.

  15. Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Mexican Hat, Utah: Appendix D. Final report

    SciTech Connect (OSTI)

    NONE

    1988-07-01

    This appendix is an assessment of the present conditions of the inactive uranium mill site near Mexican Hat, Utah. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan. Plan is to characterize the conditions at the mill and tailings site so that the Remedial Action Contractor may complete final designs of the remedial action.

  16. Health and Safety Research Division RESULTS FROM A RADIOLOGICAL SURVEY ON YARDEORO AVENUE,

    Office of Legacy Management (LM)

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  17. ORNL/TM-11118 RESULTS OF THE RADIOLOGICAL SURVEY AT METPATH INCORPORATED,

    Office of Legacy Management (LM)

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  18. RADIOLOGICAL SURVEY AT 5823/5849 NORTH RAVENSWOOD AVEXJE CHICAGO, ILLINOIS

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal Gas &SCE-SessionsSouth DakotaRobbins and700 GJO-2003-411-TACe - .'pJ3u44 2004,. . Rh '

  19. RADIOLOGICAL SURVEY OF THE GUN FORGING MACHINE BUILDING ITHACA GUN COMPANY

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal Gas &SCE-SessionsSouth DakotaRobbins and700 GJO-2003-411-TACe - .'pJ3u44 2004,. . Rh

  20. RADIOLOGICAL SURVEY OF A PORTION OF PROPERTY OWNED BY MODERN LANDFILL, INC. -

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal Gas &SCE-SessionsSouthReport for the t-) S/,,5 'a C O M1 the RFSOGorPLEASE5 R A D I

  1. Radiological Survey Data for 38 Grove Avenue, Rochelle Park, l'lew Jersey

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal Gas &SCE-SessionsSouthReport for the t-) S/,,5 'a C O M1 the RFSOGorPLEASE5 R A DY-t7sEP

  2. The RABiT: A Rapid Automated Biodosimetry Tool for radiological triage. II. Technological developments

    E-Print Network [OSTI]

    Brenner, David Jonathan

    , & DAVID J. BRENNER3 1 Radiological Research Accelerator Facility, 2 Department of Mechanical EngineeringThe RABiT: A Rapid Automated Biodosimetry Tool for radiological triage. II. Technological, and 3 Center for Radiological Research, Columbia University, New York, NY, USA (Received 14 September

  3. Preclosure radiological safety analysis for the exploratory shaft facilities; Yucca Mountain Site Characterization Project

    SciTech Connect (OSTI)

    Ma, C.W.; Miller, D.D.; Jardine, L.J. [Bechtel National, Inc., San Francisco, CA (United States)

    1992-06-01

    This study assesses which structures, systems, and components of the exploratory shaft facility (ESF) are important to safety when the ESF is converted to become part of the operating waste repository. The assessment follows the methodology required by DOE Procedure AP-6.10Q. Failures of the converted ESF during the preclosure period have been evaluated, along with other underground accidents, to determine the potential offsite radiation doses and associated probabilities. The assessment indicates that failures of the ESF will not result in radiation doses greater than 0.5 rem at the nearest unrestricted area boundary. Furthermore, credible accidents in other underground facilities will not result in radiation doses larger than 0.5 rem, even if any structure, system, or component of the converted ESF fails at the same time. Therefore, no structure, system, or component of the converted ESF is important to safety.

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

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal Gas &SCE-SessionsSouthReport for the Weldon Spring,7=cr5rnP 7694 i+lJNew

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

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal Gas &SCE-SessionsSouthReport for the Weldon Spring,7=cr5rnP 7694 i+lJNewS e T B ~ I L L

  6. Radiological and Chemical Uptake in Game Species at the Weldon Spring Site, July 1995, Rev. 1.

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal Gas &SCE-SessionsSouth DakotaRobbins and700 GJO-2003-411-TACe -' RIDGE NATIONAL :UN4 , RR

  7. Assessment of various geophysical techniques for Plains Indian archaeological site investigations 

    E-Print Network [OSTI]

    Klaff, Tamir Lee

    1993-01-01

    selected along the banks of Lake Sharpe, South Dakota for surveying. These sites were surveyed using geophysical techniques identified as having the most potential to rapidly locate anomalies characteristic of buried archaeological features, ground...

  8. Hanford Site environmental surveillance data report for calendar year 1996

    SciTech Connect (OSTI)

    Bisping, L.E.

    1997-09-01

    Environmental surveillance at the Hanford Site collects data that provides a historical record of radionuclide and radiation levels attributable to natural causes, worldwide fallout, and Hanford operations. Data are also collected to monitor several chemicals and metals in Columbia River water and sediment. In addition, Hanford Site wildlife samples were also collected for metals analysis. Pacific Northwest National Laboratory publishes an annual environmental report for the Hanford Site each calendar year. The Hanford Site Environmental Report for Calendar Year 1996 describes the site mission and activities, general environmental features, radiological and chemical releases from operations, status of compliance with environmental regulations, status of programs to accomplish compliance, and environmental monitoring activities and results. The report includes a summary of offsite and onsite environmental monitoring data collected during 1996 by PNNL`s Environmental Monitoring Program. Appendix A of that report contains data summaries created from river monitoring and sediment data. This volume contains the actual raw data used to create the summaries. The data volume also includes Hanford Site drinking water radiological data.

  9. Annual Site Environmental Report: 2006

    SciTech Connect (OSTI)

    Nuckolls, H.; /SLAC

    2008-02-22

    This report provides information about environmental programs during the calendar year (CY) of 2006 at the Stanford Linear Accelerator Center (SLAC), Menlo Park, California. Activities that span the calendar year; i.e., stormwater monitoring covering the winter season of 2006/2007 (October 2006 through May 2007), are also included. Production of an annual site environmental report (ASER) is a requirement established by the United States Department of Energy (DOE) for all management and operating (M&O) contractors throughout the DOE complex. SLAC is a federally-funded research and development center with Stanford University as the M&O contractor. SLAC continued to follow the path to self-declare an environmental management system under DOE Order 450.1, 'Environmental Protection Program' and effectively applied environmental management in meeting the site's integrated safety and environmental management system goals. For normal daily activities, all SLAC managers and supervisors are responsible for ensuring that proper procedures are followed so that Worker safety and health are protected; The environment is protected; and Compliance is ensured. Throughout 2006, SLAC focused on these activities through the SLAC management systems. These systems were also the way SLAC approached implementing 'greening of the government' initiatives such as Executive Order 13148. The management systems at SLAC are effective, supporting compliance with all relevant statutory and regulatory requirements. The SLAC Office of Assurance was created during 2006 in response to DOE Order 226.1. During 2006, there were no reportable releases to the environment from SLAC operations, and there were no Notice of Violations issued to SLAC from any of the regulatory agencies that oversee SLAC. In addition, many improvements in waste minimization, recycling, stormwater drain system, groundwater restoration, and SLAC's chemical management system (CMS) were continued during 2006 to better manage chemical use. Program-specific details are discussed below. SLAC operates its air quality management program in compliance with its established permit conditions. The Bay Area Air Quality Management District (BAAQMD) did not conduct a facility inspection of SLAC during 2006, though it did visit the site on four different occasions. The BAAQMD did compliment SLAC for the overall configuration of SLAC's gasoline dispensing facility and of SLAC's asbestos/demolition notification program during two of the visits. DOE awarded SLAC the 2006 Best in Class for Pollution Prevention and Environmental Stewardship Accomplishment in recognition of SLAC's CMS program which manages the procurement and use of chemicals. As an example of the efficiency of the CMS, SLAC reviewed its use of gases and associated tanks and phased out numerous gas tanks that were no longer needed or were not acceptable for long-term storage, in turn, reducing SLAC's on-site chemical inventory. As part of SLAC's waste minimization and management efforts, more than one thousand tons of municipal solid waste was recycled by SLAC during 2006. SLAC operates its industrial and sanitary wastewater management program in compliance with established permit conditions. During 2006, SLAC obtained a new facility-wide wastewater discharge permit which replaced four separate permits that were previously issued to SLAC. In 2006, no radiological incidents occurred that increased radiation levels or released radioactivity to the environment. In addition to managing its radioactive wastes safely and responsibly, SLAC worked to reduce the amount of waste generated. SLAC has implemented programs and systems to ensure compliance with all radiological requirements related to the environment. The Environmental Restoration Program continued work on site characterization and evaluation of remedial alternatives at four sites with volatile organic compounds in groundwater and several areas with polychlorinated biphenyls and low concentrations of lead in soil. SLAC is regulated under a site cleanup requirements order (board or

  10. INEEL Radiological Control Performance Indicator Report - Quarterly for CY-99

    SciTech Connect (OSTI)

    Hinckley, Frank Leroy

    2000-02-01

    This Performance Indicator Report is provided in accordance with Article 133 of the INEEL Radiological Control Manual. The INEEL collective occupational radiation deep dose is 63.034 person-rem year to date, compared to a goal of 83.1 person-rem. During the fourth quarter, all areas experienced deletions of work resulting from the Maintenance Stand Down. This reduction in work is a primary factor in the difference in the year end dose and the ALARA goal. The work will be completed during CY-99. Beginning in CY-98, a numeric Radiological Performance Index (RPI) is being used to compare radiological performance. The RPI takes into consideration frequency and severity of events such as skin contaminations, clothing contaminations, spills, exposures to radiation exceeding limits, and positive internal dose. The RPI measures the cost of these events in cents per hour of radiological work performed. To make the RPI meaningful, tables have been prepared to show the facility that contributes to the values used. The data are compared on a quarterly basis to the prior year to show measurable performance.

  11. Radiological safety training for accelerator facilities: DOE handbook

    SciTech Connect (OSTI)

    1997-03-01

    This program management guide describes the proper implementation standard for core training as outline in the DOE Radiological Control (RadCon) Manual. Its purpose is to assist DOE employees and Managing and Operating (M&O) contractors having responsibility for implementing the core training recommended by the RadCon Manual.

  12. CENTER FOR RADIOLOGICAL RESEARCH ANNUAL REPORT 2011 Research Using RARAF

    E-Print Network [OSTI]

    understanding the cellular response to DNA damage and low dose radiation risk assessment. Yigal Horowitz of BenCENTER FOR RADIOLOGICAL RESEARCH ANNUAL REPORT 2011 1 Research Using RARAF For over a decade, many in various investigations of this phenomenon. Research into bystander effects in 3-D systems continued

  13. BACHELOR OF SCIENCE IN RADIOLOGICAL SCIENCE (Suggested 4 Year Plan)

    E-Print Network [OSTI]

    Benos, Panayiotis "Takis"

    Credits per term 16 Credits per term 18 Credits per academic year 34 FOURTH YEAR, 1ST TERM FOURTH YEAR, 2ND TERM FOURTH YEAR, 3rd TERM (Summer) Radiographic Procedures III Radiation Biology General ReviewBACHELOR OF SCIENCE IN RADIOLOGICAL SCIENCE (Suggested 4 Year Plan) Please note

  14. Radiological Laboratory, Utility, Office Building LEED Strategy & Achievement

    SciTech Connect (OSTI)

    Seguin, Nicole R. [Los Alamos National Laboratory

    2012-07-18

    Missions that the Radiological Laboratory, utility, Office Building (RLUOB) supports are: (1) Nuclear Materials Handling, Processing, and Fabrication; (2) Stockpile Management; (3) Materials and Manufacturing Technologies; (4) Nonproliferation Programs; (5) Waste Management Activities - Environmental Programs; and (6) Materials Disposition. The key capabilities are actinide analytical chemistry and material characterization.

  15. EA-1919: Recycle of Scrap Metals Originating from Radiological Areas

    Broader source: Energy.gov [DOE]

    This Programmatic EA evaluates alternatives for the management of scrap metal originating from DOE radiological control areas, including the proposed action to allow for the recycle of uncontaminated scrap metal that meets the requirements of DOE Order 458.1. (Metals with volumetric radioactive contamination are not included in the scope of this Programmatic EA.)

  16. Savannah River Site 1992 ALARA goals

    SciTech Connect (OSTI)

    Smith, L.S.

    1992-06-01

    The ALARA Goals for the Savannah River Site (SRS) for 1992 have been established by the operating Divisions/Departments and totaled for the anticipated scope of sitewide work. Goals for maximum individual exposure and personnel contamination cases have been reduced from 1991 actual data. The goal for assimilations of radionuclides remains at zero. The 633.20 rem cumulative exposure goal is constituted of special work operations and base routine operations, respectively 244.68 rem and 388.52 rem. The cumulative exposure goal is an increase of 50% over the 1991 data to support the start up to K Reactor, operations of FB Line and scheduled special work. The 633.20 rem is 4% less than the 1990 data. Additionally, three reduction goals have been established to demonstrate a decrease in the Site overall radiological hazard. These reduction goals are for the size of airborne activity and contamination areas and the number of contamination events occurring outside a radiologically controlled area (RCA). The ALARA program is documented in the recently revised SRS ALARA Guide (October 1991).

  17. Savannah River Site 1992 ALARA goals

    SciTech Connect (OSTI)

    Smith, L.S.

    1992-01-01

    The ALARA Goals for the Savannah River Site (SRS) for 1992 have been established by the operating Divisions/Departments and totaled for the anticipated scope of sitewide work. Goals for maximum individual exposure and personnel contamination cases have been reduced from 1991 actual data. The goal for assimilations of radionuclides remains at zero. The 633.20 rem cumulative exposure goal is constituted of special work operations and base routine operations, respectively 244.68 rem and 388.52 rem. The cumulative exposure goal is an increase of 50% over the 1991 data to support the start up to K Reactor, operations of FB Line and scheduled special work. The 633.20 rem is 4% less than the 1990 data. Additionally, three reduction goals have been established to demonstrate a decrease in the Site overall radiological hazard. These reduction goals are for the size of airborne activity and contamination areas and the number of contamination events occurring outside a radiologically controlled area (RCA). The ALARA program is documented in the recently revised SRS ALARA Guide (October 1991).

  18. Lake Survey DETROIT, MICH.

    E-Print Network [OSTI]

    ; · Lake Survey Center DETROIT, MICH. NOAA TM NOS LSC 06 NOAA Technical Memorandum NOS LSC 06 U. S Winter 1971_72 R. A. Ass.,i Lake Survey Center National Ocean Survey, NOAA Detroit, Michigan I ABSTRACT

  19. Hanford Site Environmental Surveillance Data Report for Calendar Year 2008

    SciTech Connect (OSTI)

    Bisping, Lynn E.

    2009-08-11

    Environmental surveillance on and around the Hanford Site, located in southeastern Washington State, is conducted by the Pacific Northwest National Laboratory, which is operated by Battelle for the U.S. Department of Energy. The environmental surveillance data collected for this report provide a historical record of radionuclide and radiation levels attributable to natural causes, worldwide fallout, and Hanford Site operations. Data were also collected to monitor several chemicals and metals in Columbia River water, sediment, and wildlife. These data are included in this appendix. This report is the first of two appendices that support "Hanford Site Environmental Report for Calendar Year 2008" (PNNL-18427), which describes the Hanford Site mission and activities, general environmental features, radiological and chemical releases from operations, status of compliance with environmental regulations, status of programs to accomplish compliance, Hanford Site cleanup and remediation efforts, and environmental monitoring activities and results.

  20. Hanford Site Environmental Surveillance Data Report for Calendar Year 2007

    SciTech Connect (OSTI)

    Bisping, Lynn E.

    2008-10-13

    Environmental surveillance on and around the Hanford Site, located in southeastern Washington State, is conducted by the Pacific Northwest National Laboratory, which is operated by Battelle for the U.S. Department of Energy. The environmental surveillance data collected for this report provide a historical record of radionuclide and radiation levels attributable to natural causes, worldwide fallout, and Hanford Site operations. Data were also collected to monitor several chemicals and metals in Columbia River water, sediment, and wildlife. These data are included in this appendix. This report is the first of two appendices that support "Hanford Site Environmental Report for Calendar Year 2007" (PNNL-17603), which describes the Hanford Site mission and activities, general environmental features, radiological and chemical releases from operations, status of compliance with environmental regulations, status of programs to accomplish compliance, Hanford Site cleanup and remediation efforts, and environmental monitoring activities and results.

  1. Transuranic (TRU) Waste Site Certification/ Recertification

    Broader source: Energy.gov [DOE]

    Supporting Technical Document for the Radiological Release Accident Investigation Report (Phase II Report)

  2. Savannah River Site environmental report for 1989

    SciTech Connect (OSTI)

    Cummins, C.L.; Martin, D.K.; Todd, J.L.

    1989-01-01

    The purpose of this report is to meet three of the primary objectives of the Savannah River Site (SRS) environmental monitoring program. These objectives are to assess actual or potential exposures to populations form the presence of radioactive and nonradioactive materials from normal operations or nonroutine occurrences; to demonstrate compliance with applicable authorized limits and legal requirements; and to communicate results of the monitoring program to the public. This 1989 report contains descriptions of radiological and nonradiological monitoring programs, it provides data obtained from these programs, and it describes various environmental research activities ongoing at the site. Also included are summaries of environmental management and compliance activities, a summary of National Environmental Policy Act activities, and a listing of environmental permits issued by regulatory agencies.

  3. Argonne National Laboratory-East site environmental report for calendar year 1995

    SciTech Connect (OSTI)

    Golchert, N.W.; Kolzow, R.G.

    1996-09-01

    This report presents the environmental report for the Argonne National Laboratory-East for the year of 1995. Topics discussed include: general description of the site including climatology, geology, seismicity, hydrology, vegetation, endangered species, population, water and land use, and archaeology; compliance summary; environmental program information; environmental nonradiological program information; ground water protection; and radiological monitoring program.

  4. Environmental surveillance report for the Nevada Test Site (January 1980-December 1980)

    SciTech Connect (OSTI)

    Scoggins, W.A.

    1981-01-01

    Results are presented for the environmental surveillance program at the Nevada Test Site as conducted by the Department of Energy (DOE) onsite radiological safety contractor from January 1980 through December 1980. The results and evaluations of measurements of radioactivity in air and water, and of direct gamma radiation exposure rates are presented. Relevancy to DOE concentration guides (CG'S) is established.

  5. Environmental Survey preliminary report, Argonne National Laboratory, Argonne, Illinois

    SciTech Connect (OSTI)

    Not Available

    1988-11-01

    This report presents the preliminary findings of the first phase of the Environmental Survey of the United States Department of Energy's (DOE) Argonne National Laboratory (ANL), conducted June 15 through 26, 1987. 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. The team includes outside experts supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with ANL. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data, observations of the operations carried on at ANL, and interviews with site personnel. The Survey team developed a Sampling and Analysis (S A) Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The S A Plan will be executed by the Oak Ridge National Laboratory (ORNL). When completed, the S A results will be incorporated into the Argonne National Laboratory Environmental Survey findings for inclusion in the Environmental Survey Summary Report. 75 refs., 24 figs., 60 tabs.

  6. Environmental Survey preliminary report, Rocky Flats Plant, Golden, Colorado

    SciTech Connect (OSTI)

    Not Available

    1987-06-01

    This report presents the preliminary findings of the Environmental Survey of the United States Department of Energy (DOE), Rocky Flats Plant (RFP), conducted August 11 through 22, 1986. The Survey is being conducted by an 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 supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the RFP. The Survey covers all environmental media and all areas of environmental regulations. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data observations of the operations carried on at RFP, 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 activates. The Sampling and Analysis Plan is being executed by DOE's Oak Ridge National Laboratory. When completed, the results will be incorporated into the RFP Environmental Survey Interim Report. The Interim Report will reflect the final determinations of the RFP Survey. 75 refs., 24 figs., 33 tabs.

  7. Surveillance of Site A and Plot M

    SciTech Connect (OSTI)

    Golchert, N.W.

    1993-05-01

    The results of the environmental surveillance program conducted at Site A/Plot M in the Palos Forest Preserve area for CY 1992 are presented. The surveillance program is the ongoing remedial action that resulted from the 1976--1978 radiological characterization of the site. That study determined that very low levels of hydrogen-3 (as tritiated water) had migrated from the burial ground and were present in two nearby hand-pumped picnic wells. The current program consists of sample collection and analysis of air, surface and subsurface water, and bottom sediment. The results of the analyses are used to (1) determine the migration pathway of water from the burial ground (Plot M) to the hand-pumped picnic wells, (2) establish if buried radionuclides other than hydrogen-3 have migrated, and (3) generally characterize the radiological environment of the area. Hydrogen-3 in the Red Gate Woods picnic wells was still detected this year, but the average and maximum concentrations were significantly less than found earlier. Tritiated water continues to be detected in a number of wells, boreholes, dolomite holes, and a surface stream. For many years it was the only radionuclide found to have migrated in measurable quantities. Analyses since 1984 have indicated the presence of low levels of strontium-90 in water from a number of boreholes next to Plot M. The available data does not allow a firm conclusion as to whether the presence of this nuclide represents recent migration or movement that may have occurred before Plot M was capped. The results of the surveillance program continue to indicate that the radioactivity remaining at Site A/Plot M does not endanger the health or safety of the public visiting the site, using the picnic area, or living in the vicinity.

  8. Method for warning of radiological and chemical agents using detection paints on a vehicle surface

    DOE Patents [OSTI]

    Farmer, Joseph C. (Tracy, CA); Brunk, James L. (Martinez, CA); Day, S. Daniel (Danville, CA)

    2012-03-27

    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.

  9. Aerial vehicle with paint for detection of radiological and chemical warfare agents

    DOE Patents [OSTI]

    Farmer, Joseph C.; Brunk, James L.; Day, S. Daniel

    2013-04-02

    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.

  10. Nevada National Security Site Environmental Report 2012

    SciTech Connect (OSTI)

    Wills, Cathy

    2013-09-11

    This report 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. It was prepared by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) (formerly designated as the Nevada Site Office [NNSA/NSO]). The new field office designation occurred in March 2013. Published reports cited in this 2012 report, therefore, may bear the name or authorship of NNSA/NSO. This and previous years’ reports, called Annual Site Environmental Reports (ASERs), Nevada Test Site Environmental Reports (NTSERs), and, beginning in 2010, Nevada National Security Site Environmental Reports (NNSSERs), are posted on the NNSA/NFO website at http://www.nv.energy.gov/library/publications/aser.aspx. This NNSSER was prepared to satisfy DOE Order DOE O 231.1B, “Environment, Safety and Health Reporting.” 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 NNSA/NFO Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts. This NNSSER summarizes data and compliance status for calendar year 2012 at the Nevada National Security Site (NNSS) (formerly the Nevada Test Site) and its two support facilities, the North Las Vegas Facility (NLVF) and the Remote Sensing Laboratory–Nellis (RSL-Nellis). It also addresses environmental restoration (ER) projects conducted at the Tonopah Test Range (TTR) and the Nevada Test and Training Range (NTTR). Through a Memorandum of Agreement, NNSA/NFO is responsible for the oversight of these ER projects, and the Sandia Site Office of NNSA (NNSA/SSO) has oversight of all other TTR and NTTR activities. NNSA/SSO produces the TTR annual environmental report available at http://www.sandia.gov/news/publications/environmental/index.html.

  11. Overview of the U.S. Department of Energy Formerly Utilized Sites Remedial Action Program - 12189

    SciTech Connect (OSTI)

    Clayton, Christopher; Kothari, Vijendra; Starr, Ken; Gillespie, Joey; Widdop, Michael; none,

    2012-02-26

    The U.S. Department of Energy (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP) was established in 1974 to address residual radiological contamination at sites where work was performed for the Manhattan Engineer District and U.S. Atomic Energy Commission. Initially, FUSRAP activities began with a records search for sites that had the potential to contain residual radiological contamination; 46 sites were identified that were eligible for and required remediation. Remedial action began in 1979. In 1997, Congress assigned responsibility for the remediation of FUSRAP sites to the U.S. Army Corps of Engineers (USACE). DOE retains responsibility for determining if sites are eligible for FUSRAP remediation and for providing long-term surveillance and maintenance (LTS&M) of remediated FUSRAP sites. DOE LTS&M activities are designed to ensure that FUSRAP sites remain protective of human health and the environment and to preserve knowledge regarding FUSRAP sites. Additional elements include eligibility determinations, transition of remediated sites from USACE to DOE, LTS&M operations such as inspections and institutional controls management, stakeholder support, preservation of records, and real property and reuse. DOE maintains close coordination with USACE and regulators to ensure there is no loss of protectiveness when sites transition to DOE for LTS&M.

  12. Corrective Action Investigation Plan for Corrective Action Unit 224: Decon Pad and Septic Systems Nevada Test Site, Nevada, Rev. No.: 0, with ROTC 1 and 2

    SciTech Connect (OSTI)

    David A. Strand

    2004-04-01

    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) 224: Decon Pad and Septic Systems, Nevada Test Site (NTS), Nevada. 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 (DoD). The NTS is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Corrective Action Unit 224 is comprised of the nine Corrective Action Sites (CASs) listed below: 02-04-01, Septic Tank (Buried); 03-05-01, Leachfield; 05-04-01, Septic Tanks (4)/Discharge Area; 06-03-01, Sewage Lagoons (3); 06-05-01, Leachfield; 06-17-04, Decon Pad and Wastewater Catch; 06-23-01, Decon Pad Discharge Piping; 11-04-01, Sewage Lagoon; and 23-05-02, Leachfield. Corrective Action Sites 06-05-01, 06-23-01, and 23-05-02 were identified in the 1991 Reynolds Electrical & Engineering Co., Inc. (REECo) inventory (1991). The remaining sites were identified during review of various historical documents. Additional information will be obtained by conducting a corrective action investigation (CAI) prior to evaluating and selecting a corrective action alternative for each CAS. The CAI will include field inspections, radiological and geological surveys, and sample collection. Data will also be obtained to support investigation-derived waste (IDW) disposal and potential future waste management decisions.

  13. Corrective Action Decision Document/Closure Report for Corrective Action Unit 367: Area 10 Sedan, Ess and Uncle Unit Craters Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Patrick Matthews

    2011-06-01

    Corrective Action Unit 367 comprises four corrective action sites (CASs): • 10-09-03, Mud Pit • 10-45-01, U-10h Crater (Sedan) • 10-45-02, Ess Crater Site • 10-45-03, Uncle Crater Site The purpose of this Corrective Action Decision Document/Closure Report is to provide justification and documentation of the corrective actions and site closure activities implemented at CAU 367. A corrective action of closure in place with use restrictions was completed at each of the three crater CASs (10-45-01, 10-45-02, and 10-45-03); corrective actions were not required at CAS 10-09-03. In addition, a limited soil removal corrective action was conducted at the location of a potential source material release. Based on completion of these correction actions, no additional corrective action is required at CAU 367, and site closure is considered complete. Corrective action investigation (CAI) activities were performed from February 2010 through March 2011, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 367: Area 10 Sedan, Ess and Uncle Unit Craters, Nevada Test Site, Nevada. The approach for the CAI was divided into two facets: investigation of the primary release of radionuclides, and investigation of non-test or other releases (e.g., migration in washes and potential source material). Based on the proximity of the Uncle, Ess, and Sedan craters, the impact of the Sedan test on the fallout deposited from the two earlier tests, and aerial radiological surveys, the CAU 367 investigation was designed to study the releases from the three crater CASs as one combined release (primary release). Corrective Action Site 10-09-03, Mud Pit, consists of two mud pits identified at CAU 367. The mud pits are considered non-test releases or other releases and were investigated independent of the three crater CASs. The purpose of the CAI was to fulfill data needs as defined during the data quality objective (DQO) process. The CAU 367 dataset of investigation results was evaluated based on a data quality assessment. This assessment demonstrated the dataset is complete and acceptable for use in fulfilling the DQO data needs. Analytes detected during the CAI were evaluated against final action levels (FALs) established in this document. For the primary release, radiological doses exceeding the FAL of 25 millirem per year were not found to be present in the surface or shallow subsurface soil outside the default contamination boundary. However, it was assumed that radionuclides are present in subsurface media within each of the three craters (Sedan, Ess, and Uncle) due to prompt injection of radionuclides from the tests. Based on the assumption of radiological dose exceeding the FAL, corrective actions were undertaken that consisted of implementing a use restriction and posting warning signs at each crater CAS. These use restrictions were recorded in the FFACO database; the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Facility Information Management System; and the NNSA/NSO CAU/CAS files. With regard to other releases, no contaminants of concern were identified at the mud pits or any of the other release locations, with one exception. Potential source material in the form of lead was found at one location. A corrective action of clean closure was implemented at this location, and verification samples indicated that no further action is necessary. Therefore, NNSA/NSO provides the following recommendations: • A Notice of Completion to NNSA/NSO is requested from the Nevada Division of Environmental Protection for closure of CAU 367. • Corrective Action Unit 367 should be promoted from Appendix III to Appendix IV of the FFACO.

  14. Waterborne Release Monitoring and Surveillance Programs at the Savannah River Site

    SciTech Connect (OSTI)

    Blanchard, A.

    1999-03-26

    This report documents the liquid release environmental compliance programs currently in place at the Savannah river Site (SRS). Included are descriptions of stream monitoring programs, which measure chemical parameters and radionuclides in site streams and the Savannah river and test representative biological communities within the streams for chemical and radiological uptake. This report also explains the field sampling and analytical capabilities that are available at SRS during both normal and emergency conditions.

  15. Hanford Site environmental surveillance data report for calendar year 1995

    SciTech Connect (OSTI)

    Bisping, L.E.

    1996-07-01

    Environmental surveillance at the Hanford Site collects data that provides a historical record of radionuclide and radiation levels attributable to natural causes, worldwide fallout, and Hanford operations. Data are also collected to monitor several chemicals and metals in Columbia River Water and Sediment. Pacific Northwest National Laboratory publishes an annual environmental report for the Hanford Site each calendar year. The Hanford Site Environmental Report for Calendar Year 1995 describes the Site mission and activities, general environmental features, radiological and chemical releases from operations, status of compliance with environmental regulations, status of programs to accomplish compliance, and environmental monitoring activities and results. The report includes a summary of offsite and onsite environmental monitoring data collected during 1995 by PNNL`s Environmental Monitoring Program. Appendix A of that report contains data summaries created from raw surface, river monitoring data, and chemical air data. This volume contains the actual raw data used to create the summaries. The data volume also includes Hanford Site drinking water radiological data.

  16. Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 113: Reactor Maintenance, Assembly, and Disassembly Building Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    J. L. Smith

    2001-01-01

    This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the action necessary for the closure in place of Corrective Action Unit (CAU) 113 Area 25 Reactor Maintenance, Assembly, and Disassembly Facility (R-MAD). CAU 113 is currently listed in Appendix III of the Federal Facility Agreement and Consent Order (FFACO) (NDEP, 1996). The CAU is located in Area 25 of the Nevada Test Site (NTS) and consists of Corrective Action Site (CAS) 25-04-01, R-MAD Facility (Figures 1-2). This plan provides the methodology for closure in place of CAU 113. The site contains radiologically impacted and hazardous material. Based on preassessment field work, there is sufficient process knowledge to close in place CAU 113 using the SAFER process. At a future date when funding becomes available, the R-MAD Building (25-3110) will be demolished and inaccessible radiologic waste will be properly disposed in the Area 3 Radiological Waste Management Site (RWMS).

  17. GEODETIC SURVEY SPECIAL PUBLICATIONS

    E-Print Network [OSTI]

    . SP #4 OUT OF PRINT U.S. COAST AND GEODETIC SURVEY. ... GEODESY. THE TRANSCONTINENTAL TRIANGULATION

  18. STEP Participant Survey Report

    Broader source: Energy.gov [DOE]

    STEP Participant Survey Report, from the Tool Kit Framework: Small Town University Energy Program (STEP).

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

    SciTech Connect (OSTI)

    Mark Krauss

    2011-09-01

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

  20. Hydrogeological influences on radionuclide migration from the major radioactive waste burial sites at Chernobyl (A review)

    SciTech Connect (OSTI)

    Dgepo, S.P.; Skalsky, A.S.; Bugai, D.A.; Marchuk, V.V. [Inst. of Geological Sciences, Kiev (Ukraine); Waters, R.D. [Sandia National Labs., Albuquerque, NM (United States)

    1994-03-01

    This paper summarizes the recent hydrogeological investigations of several research organizations on waste confinement at the major radioactive waste (RW) burial sites immediately adjacent to the Chernobyl Nuclear Power Plant (Ch. NPP). Hydrogeological conditions and radiologic ground-water contamination levels are described. Ongoing ground-water monitoring practices are evaluated. The chemical and physical characteristics of the radionuclides within the burial sites are considered. Ground water and radionuclide transport modeling studies related to problems of the RW disposal sites are also reviewed. Current concerns on future impacts of the RW burial sites on the hydrological environment and water resources of the Ch.NPP area are discussed.