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Sample records for decommissioning aberdeen proving

  1. Geophysics: Building E5375 decommissioning, Aberdeen Proving Ground

    SciTech Connect

    McGinnis, M.G.; McGinnis, L.D.; Miller, S.F.; Thompson, M.D.

    1992-08-01

    Building E5375 was one of ten potentially contaminated sites in the Canal Creek area of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May 1992. Noninvasive geophysical surveys, including magnetics, electrical resistivity, and ground-penetrating radar (GPR), were conducted around the perimeter of the building to guide a sampling program prior to decommissioning and dismantling. Several anomalies wear, noted: (1) An underground storage tank located 25 ft east of Building E5375 was identified with magnetic, resistivity, and GPR profiling. (2) A three-point resistivity anomaly, 12 ft east of the northeast comer of Building E5374 (which borders Building E5375) and 5 ft south of the area surveyed with the magnetometer, may be caused by another underground storage tank. (3) A 2,500-gamma magnetic anomaly near the northeast corner of the site has no equivalent resistivity anomaly, although disruption in GPR reflectors was observed. (4) A one-point magnetic anomaly was located at the northeast comer, but its source cannot be resolved. A chaotic reflective zone to the east represents the radar signature of Building E5375 construction fill.

  2. Geophysics: Building E5282 decommissioning, Aberdeen Proving Ground

    SciTech Connect

    Thompson, M.D.; McGinnis, M.G.; McGinnis, L.D.; Miller, S.F.

    1992-08-01

    This report discusses Building E5282 which was one of 10 potentially contaminated sites in the Canal Creek area of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May of 1992. Noninvasive geophysical surveys, including magnetics, electrical resistivity, and ground-penetrating radar (GPR), were conducted around the perimeter of the building to guide a sampling program prior to decommissioning and dismantling. Magnetic surveys identified small, complicated, multiple anomalies west, north, and northeast of the building that may be caused by construction fill. Two underground storage tanks, at the northeast and southeast corners, were identified. A large magnetic anomaly complex east of the building was caused by aboveground pipes and unexploded ordnance fragments scattered at the surface. Electrical resistivity profiling showed a broad, conductive terrain superimposed over magnetic anomalies on the north and west. A broad, high-resistivity, nonmagnetic area centered 25 ft east of the building has an unknown origin, but it may be due to nonconductive organic liquids, construction fill, or a buried concrete slab; GPR imaging showed this area as a highly reflective zone at a depth of about 5 ft. The GPR data also showed a small-diameter pipe oriented north-south located east of the building.

  3. Geophysics: Building E5190 decommissioning, Aberdeen Proving Ground

    SciTech Connect

    Miller, S.F.; Thompson, M.D.; McGinnis, M.G.; McGinnis, L.D.

    1992-07-01

    Building E5190 is one of ten potentially contaminated sites in the Canal Creek area of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May 1992. A noninvasive geophysical survey, including the complementary technologies of magnetics, electrical resistivity, and ground-penetrating radar, was conducted around the perimeter as a guide to developing a sampling and monitoring program prior to decommissioning and dismantling the building. The magnetics surveys indicated that multistation, positive magnetic sources are randomly distributed north and west of the building. Two linear trends were noted: one that may outline buried utility lines and another that is produced by a steel-covered trench. The resistivity profiling indicated three conductive zones: one due to increased moisture in a ditch, one associated with buried utility lines, and a third zone associated with the steel-covered trench. Ground-penetrating radar imaging detected two significant anomalies, which were correlated with small-amplitude magnetic anomalies. The objectives of the study -- to detect and locate objects and to characterize a located object were achieved.

  4. Geophysics: Building E5440 decommissioning, Aberdeen Proving Ground

    SciTech Connect

    McGinnis, L.D.; Miller, S.F.; Thompson, M.D.; McGinnis, M.G.

    1992-11-01

    Building E5440 was one of ten potentially contaminated sites in the Canal Creek and Westwood areas of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May 1992. Noninvasive geophysical surveys, including magnetics, electrical resistivity, and ground-penetrating radar (GPR), were conducted around the perimeter of the building to guide a sampling program prior to decommissioning and dismantling. The results show several complex geophysical signatures. Isolated, one-point, magnetic anomalies surrounding the building may be associated with construction fill. A 10-ft-wide band of strongly magnetic positive anomalies bordering the north side of the building obliterates small magnetic sources that might otherwise be seen. A prominent magnetic nose'' extending northward from this band toward a standpipe at 100N,63E may be connected to an underground tank. The southeast corner of the site is underlain by a rectangular, magnetized source associated with strong radar images. A magnetic lineament extending south from the anomaly may be caused by a buried pipe; the anomaly itself may be caused by subsurface equipment associated with a manhole or utility access pit. A 2,500-gamma, positive magnetic anomaly centered at 0N,20E, which is also the location of a 12 [Omega]-m resistivity minimum, may be caused by a buried vault. It appears on radar imaging as a strong reflector.

  5. Geophysics: Building E5481 decommissioning, Aberdeen Proving Ground

    SciTech Connect

    Thompson, M.D.; McGinnis, M.G.; McGinnis, L.D.; Miller, S.F.

    1992-11-01

    Building E5481 is one of ten potentially contaminated sites in the Canal Creek and Westwood areas of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May of 1992. Noninvasive geophysical surveys, including magnetics, electrical resistivity, and ground-penetrating radar, were conducted around the perimeter of the building to guide a sampling program prior to decommissioning and dismantling. The building is located on the northern margin of a landfill that was sited in a wetland. The large number of magnetic sources surrounding the building are believed to be contained in construction fill that had been used to raise the grade. The smaller anomalies, for the most part, are not imaged with ground radar or by electrical profiling. A conductive zone trending northwest to southeast across the site is spatially related to an old roadbed. Higher resistivity areas in the northeast and east are probably representive of background values. Three high-amplitude, positive, rectangular magnetic anomalies have unknown sources. The features do not have equivalent electrical signatures, nor are they seen with radar imaging.

  6. Geophysics: Building E5032 decommissioning, Aberdeen Proving Ground

    SciTech Connect

    McGinnis, L.D.; Miller, S.F.

    1991-07-01

    integration of data from surveys using three geophysical technologies has provided information used to define the locations of buried utilities, tanks, vaults, and debris near building E5032 at the Aberdeen Proving Ground. Ground penetrating radar (GPR) profiles indicate the presence of buried pipes, tanks, reinforcement rods (rebar), and remnants of railroad tracks. A magnetic map constructed from a detailed magnetic survey on the north side of the building outlines buried iron-rich objects that are interpreted to be iron pipes, tank, and other debris of uncertain origin at relatively shallow depths. Horizontal electrical resistivity surveys and vertical electrical resistivity soundings essentially corroborated the findings obtained with the magnetometer and GPR. In addition, a highly resistance layer was observed on the east side of the building where a former railroad bed with a thick grave fill is believed to immediately underlie the lawn. The resistivity data show no evidence of a conductive leachate plume. Geophysical measurements from three techniques over a buried concrete slab approximately 130 ft north of Building E5032 give geophysical signatures interpreted to be due to the presence of a large iron tank or vault. An attempt was made to gather meaningful magnetic data on the east, west, and south sides of the building; however, the quality of subsurface interpretations in those areas was poor because of the influence of surficial iron lids, pipes, grates, and the effects of the corrugated iron building itself. 11 figs., 1 tab.

  7. Evaluation of decommissioning alternatives for the Pilot Plant Complex, Aberdeen Proving Ground

    SciTech Connect

    Rueda, J.; Zimmerman, R.E.

    1995-09-01

    This report presents an evaluation of four decommissioning alternatives for the Pilot Plant Complex (PPC), an inactive chemical weapons research, development, and production facility consisting of nine buildings located in the Edgewood Area of the Aberdeen Proving Ground in Maryland. Decommissioning the PPC involves six steps: (1) assessing existing conditions; (2) dismantling the aboveground portions of the buildings (including the floor slabs, paved roads, and sidewalks within the PPC); (3) reducing the size of the demolition debris and sealing the debris in containers for later testing and evaluation; (4) testing and evaluating the debris; (5) conducting site operation and maintenance activities; and (6) recycling or disposing of the debris with or without prior treatment, as appropriate.

  8. Geophysics: Building E5375 decommissioning, Aberdeen Proving Ground. Interim progress report

    SciTech Connect

    McGinnis, M.G.; McGinnis, L.D.; Miller, S.F.; Thompson, M.D.

    1992-08-01

    Building E5375 was one of ten potentially contaminated sites in the Canal Creek area of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May 1992. Noninvasive geophysical surveys, including magnetics, electrical resistivity, and ground-penetrating radar (GPR), were conducted around the perimeter of the building to guide a sampling program prior to decommissioning and dismantling. Several anomalies wear, noted: (1) An underground storage tank located 25 ft east of Building E5375 was identified with magnetic, resistivity, and GPR profiling. (2) A three-point resistivity anomaly, 12 ft east of the northeast comer of Building E5374 (which borders Building E5375) and 5 ft south of the area surveyed with the magnetometer, may be caused by another underground storage tank. (3) A 2,500-gamma magnetic anomaly near the northeast corner of the site has no equivalent resistivity anomaly, although disruption in GPR reflectors was observed. (4) A one-point magnetic anomaly was located at the northeast comer, but its source cannot be resolved. A chaotic reflective zone to the east represents the radar signature of Building E5375 construction fill.

  9. Environmental geophysics: Building E3640 Decommissioning, Aberdeen Proving Ground, Maryland. Interim progress report

    SciTech Connect

    McGinnis, L.D.; Miller, S.F.; Borden, H.M.; Benson, M.A.; Thompson, M.D.; Padar, C.A.; Daudt, C.R.

    1995-01-01

    Building E3640 is a potentially contaminated site in the Edgewood area of Aberdeen Proving Ground. Noninvasive geophysical survey techniques, including magnetics, EM-31, EM-61, and ground-penetrating radar, were used as part of a sampling and monitoring program prior to decommissioning and dismantling of the building. Complex and large-amplitude anomalies caused by aboveground metal in this area obscure many smaller features produced by subsurface sources. No underground storage tanks were found in the areas surveyed. Major anomalies produced by subsurface sources include the following: EM-61 and EM-31 lineaments caused by a water line extending north from the south fence; a broad positive magnetic anomaly caused by magnetic fill north of the material and drum storage area and northeast of E3640; a 30-ft-wide band of EM-31 anomalies extending from the front gate to the southeast comer of E3640 and a coincident EM-61 anomaly produced by buried utilities; ground-penetrating radar images along three lines extending from a sump at the northeast comer of E3640 to the eastern fence; and EM-61, EM-31, and magnetic anomalies caused by overhead and underground pipes extending south from the north fence. Smaller, unidentified, localized anomalies observed throughout the survey area are also described in this report.

  10. Geophysics: Building E5282 decommissioning, Aberdeen Proving Ground. Interim progress report

    SciTech Connect

    Thompson, M.D.; McGinnis, M.G.; McGinnis, L.D.; Miller, S.F.

    1992-08-01

    This report discusses Building E5282 which was one of 10 potentially contaminated sites in the Canal Creek area of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May of 1992. Noninvasive geophysical surveys, including magnetics, electrical resistivity, and ground-penetrating radar (GPR), were conducted around the perimeter of the building to guide a sampling program prior to decommissioning and dismantling. Magnetic surveys identified small, complicated, multiple anomalies west, north, and northeast of the building that may be caused by construction fill. Two underground storage tanks, at the northeast and southeast corners, were identified. A large magnetic anomaly complex east of the building was caused by aboveground pipes and unexploded ordnance fragments scattered at the surface. Electrical resistivity profiling showed a broad, conductive terrain superimposed over magnetic anomalies on the north and west. A broad, high-resistivity, nonmagnetic area centered 25 ft east of the building has an unknown origin, but it may be due to nonconductive organic liquids, construction fill, or a buried concrete slab; GPR imaging showed this area as a highly reflective zone at a depth of about 5 ft. The GPR data also showed a small-diameter pipe oriented north-south located east of the building.

  11. Geophysics: Building E5190 decommissioning, Aberdeen Proving Ground. Interim progress report

    SciTech Connect

    Miller, S.F.; Thompson, M.D.; McGinnis, M.G.; McGinnis, L.D.

    1992-07-01

    Building E5190 is one of ten potentially contaminated sites in the Canal Creek area of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May 1992. A noninvasive geophysical survey, including the complementary technologies of magnetics, electrical resistivity, and ground-penetrating radar, was conducted around the perimeter as a guide to developing a sampling and monitoring program prior to decommissioning and dismantling the building. The magnetics surveys indicated that multistation, positive magnetic sources are randomly distributed north and west of the building. Two linear trends were noted: one that may outline buried utility lines and another that is produced by a steel-covered trench. The resistivity profiling indicated three conductive zones: one due to increased moisture in a ditch, one associated with buried utility lines, and a third zone associated with the steel-covered trench. Ground-penetrating radar imaging detected two significant anomalies, which were correlated with small-amplitude magnetic anomalies. The objectives of the study -- to detect and locate objects and to characterize a located object were achieved.

  12. Geophysics: Building E5481 decommissioning, Aberdeen Proving Ground. Interim progress report

    SciTech Connect

    Thompson, M.D.; McGinnis, M.G.; McGinnis, L.D.; Miller, S.F.

    1992-11-01

    Building E5481 is one of ten potentially contaminated sites in the Canal Creek and Westwood areas of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May of 1992. Noninvasive geophysical surveys, including magnetics, electrical resistivity, and ground-penetrating radar, were conducted around the perimeter of the building to guide a sampling program prior to decommissioning and dismantling. The building is located on the northern margin of a landfill that was sited in a wetland. The large number of magnetic sources surrounding the building are believed to be contained in construction fill that had been used to raise the grade. The smaller anomalies, for the most part, are not imaged with ground radar or by electrical profiling. A conductive zone trending northwest to southeast across the site is spatially related to an old roadbed. Higher resistivity areas in the northeast and east are probably representive of background values. Three high-amplitude, positive, rectangular magnetic anomalies have unknown sources. The features do not have equivalent electrical signatures, nor are they seen with radar imaging.

  13. Geophysics: Building E5440 decommissioning, Aberdeen Proving Ground. Interim progress report

    SciTech Connect

    McGinnis, L.D.; Miller, S.F.; Thompson, M.D.; McGinnis, M.G.

    1992-11-01

    Building E5440 was one of ten potentially contaminated sites in the Canal Creek and Westwood areas of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May 1992. Noninvasive geophysical surveys, including magnetics, electrical resistivity, and ground-penetrating radar (GPR), were conducted around the perimeter of the building to guide a sampling program prior to decommissioning and dismantling. The results show several complex geophysical signatures. Isolated, one-point, magnetic anomalies surrounding the building may be associated with construction fill. A 10-ft-wide band of strongly magnetic positive anomalies bordering the north side of the building obliterates small magnetic sources that might otherwise be seen. A prominent magnetic ``nose`` extending northward from this band toward a standpipe at 100N,63E may be connected to an underground tank. The southeast corner of the site is underlain by a rectangular, magnetized source associated with strong radar images. A magnetic lineament extending south from the anomaly may be caused by a buried pipe; the anomaly itself may be caused by subsurface equipment associated with a manhole or utility access pit. A 2,500-gamma, positive magnetic anomaly centered at 0N,20E, which is also the location of a 12 {Omega}-m resistivity minimum, may be caused by a buried vault. It appears on radar imaging as a strong reflector.

  14. Interim progress report -- geophysics: Decommissioning of Buildings E5974 and E5978, Aberdeen Proving Ground

    SciTech Connect

    McGinnis, M.G.; McGinnis, L.D.; Miller, S.F.; Thompson, M.D.

    1992-11-01

    Buildings E5974 and E5978, located near the mouth of Canal Creek, were among 10 potentially contaminated sites in the Westwood and Canal Creek areas of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May of 1992. Noninvasive geophysical surveys, including the complementary technologies of magnetics, electrical resistivity, and ground-penetrating radar, were conducted around the perimeters of the buildings to guide a sampling program prior to decommissioning and dismantling. The magnetic anomalies and the electrically conductive areas around these buildings have a spatial relationship similar to that observed in low-lying sites in the Canal Creek area; they are probably associated with construction fill. Electrically conductive terrain is dominant on the eastern side of the site, and resistive terrain predominates on the west. The smaller magnetic anomalies are not imaged with ground radar or by electrical profiling. The high resistivities in the northwest quadrant are believed to be caused by a natural sand lens. The causes of three magnetic anomalies in the high-resistivity area are unidentified, but they are probably anthropogenic.

  15. Preliminary assessment of risk from toxic materials that might be mobilized in the decommissioning of Aberdeen Proving Ground Building E5032

    SciTech Connect

    Rosenblatt, D.H.; Brubaker, K.L.

    1991-12-01

    Aberdeen Proving Ground Building E5032 is scheduled for decommissioning, that is, for demolition. Because the building was formerly used for small-scale operations with incendiary and toxic chemical agents, it presents unusual concerns for occupational and public health safety during the demolition. For this reason, an anticipatory risk assessment was conducted, taking into consideration the building`s history, properties of potential residual contaminants (particularly chemical and incendiary agents), and assumptions relating to meteorological conditions and envisioned modes of demolition. Safe maximum levels in concrete floors for the worst case were estimated to be: white phosphorus, 3200 mg/kg; mustard, 94 mg/kg; nerve agent GA (tabun), 6 mg/kg; cyanide, 500 mg/kg; and sulfide, 1400 mg/kg. These values will serve as planning guidance for the activities to follow. It is emphasized that the estimates must be reviewed, and perhaps revised, after sampling and analysis are completed, the demolition methodology is chosen, and dust emissions are measured under operating conditions.

  16. Preliminary assessment of risk from toxic materials that might be mobilized in the decommissioning of Aberdeen Proving Ground Building E5032

    SciTech Connect

    Rosenblatt, D.H.; Brubaker, K.L.

    1991-12-01

    Aberdeen Proving Ground Building E5032 is scheduled for decommissioning, that is, for demolition. Because the building was formerly used for small-scale operations with incendiary and toxic chemical agents, it presents unusual concerns for occupational and public health safety during the demolition. For this reason, an anticipatory risk assessment was conducted, taking into consideration the building's history, properties of potential residual contaminants (particularly chemical and incendiary agents), and assumptions relating to meteorological conditions and envisioned modes of demolition. Safe maximum levels in concrete floors for the worst case were estimated to be: white phosphorus, 3200 mg/kg; mustard, 94 mg/kg; nerve agent GA (tabun), 6 mg/kg; cyanide, 500 mg/kg; and sulfide, 1400 mg/kg. These values will serve as planning guidance for the activities to follow. It is emphasized that the estimates must be reviewed, and perhaps revised, after sampling and analysis are completed, the demolition methodology is chosen, and dust emissions are measured under operating conditions.

  17. Geophysics: Building E5476 decommissiong, Aberdeen Proving Ground

    SciTech Connect

    Miller, S.F.; Thompson, M.D.; McGinnis, M.G.; McGinnis, L.D.

    1992-11-01

    Building E5476 was one of ten potentially contaminated sites in the Canal Creek and Westwood areas of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May of 1992. Noninvasive geophysical surveys, including magnetics, electrical resistivity, and ground-penetrating radar, were conducted around the perimeter of the building to guide a sampling program prior to decommissioning and dismantling. The large number of magnetic sources surrounding the building are believed to be contained in construction fill. The smaller anomalies, for the most part, were not imaged with ground radar or by electrical profiling. Large magnetic anomalies near the southwest comer of the building are due to aboveground standpipes and steel-reinforced concrete. Two high-resistivity areas, one projecting northeast from the building and another south of the original structure, may indicate the presence of organic pore fluids in the subsurface. A conductive lineament protruding from the south wall that is enclosed by the southem, high-resistivity feature is not associated with an equivalent magnetic anomaly. Magnetic and electrical anomalies south of the old landfill boundary are probably not associated with the building. The boundary is marked by a band of magnetic anomalies and a conductive zone trending northwest to southeast. The cause of high resistivities in a semicircular area in the southwest comer, within the landfill area, is unexplained.

  18. Unexploded ordnance issues at Aberdeen Proving Ground: Background information

    SciTech Connect

    Rosenblatt, D.H.

    1996-11-01

    This document summarizes currently available information about the presence and significance of unexploded ordnance (UXO) in the two main areas of Aberdeen Proving Ground: Aberdeen Area and Edgewood Area. Known UXO in the land ranges of the Aberdeen Area consists entirely of conventional munitions. The Edgewood Area contains, in addition to conventional munitions, a significant quantity of chemical-munition UXO, which is reflected in the presence of chemical agent decomposition products in Edgewood Area ground-water samples. It may be concluded from current information that the UXO at Aberdeen Proving Ground has not adversely affected the environment through release of toxic substances to the public domain, especially not by water pathways, and is not likely to do so in the near future. Nevertheless, modest but periodic monitoring of groundwater and nearby surface waters would be a prudent policy.

  19. Initial building investigations at Aberdeen Proving Ground, Maryland: Building E5190

    SciTech Connect

    Brubaker, K.L.; Dougherty, J.M.; Tome, C.

    1993-10-01

    As part of a building decommissioning and demolition program at Aberdeen Proving Ground, a detailed inspection of each target building is conducted in order to characterize and describe the state of the building as it currently exists and to identify areas potentially contaminated with toxic or other hazardous substances. Room surfaces, drains and sumps, remaining equipment, and such associated exterior aboveground and underground appurtenances as tanks and pipelines are among the features, generically termed compartments, that may be potentially contaminated. Detailed drawings are prepared to illustrate the existing structure of each building. This report presents the results of the inspection of building E5190 in the Edgewood/Canal Creek area of Aberdeen Proving Ground. This building houses a 10,000-gal tank formerly used to store xylene. Eleven potentially contaminated compartments were identified in this building and its vicinity.

  20. Initial building investigations at Aberdeen Proving Ground, Maryland: Building E5375

    SciTech Connect

    Brubaker, K.L.; Dougherty, J.M.; Tome, C.

    1993-06-01

    As part of a building decommissioning and demolition program at Aberdeen Proving Ground, a detailed inspection of each target building is being conducted in order to characterize and describe the state of the building as it currently exists and to identify areas potentially contaminated with toxic or other hazardous substances. Room surfaces, drains and sumps, remaining equipment, and such associated exterior aboveground and underground appurtenances as tanks and pipelines are among the features, generically termed compartments, that may be potentially contaminated. Detailed drawings are being prepared for each building to illustrate the existing structure. This report presents the results of the inspection of Building E5375 in the Edgewood/Canal Creek area of Aberdeen Proving Ground. Nine potentially contaminated compartments were identified in this building and its vicinity.

  1. Aberdeen area fire training area hydrologic assessment, Aberdeen Proving Ground. Final report, September 1989-July 1991

    SciTech Connect

    Whitten, C.B.; Miller, S.P.; Derryberry, N.A.; Wade, R.

    1992-12-01

    In 1986, the US Environmental Protection Agency (EPA) issued a Hazardous Waste Management Permit to Aberdeen Proving Ground (APG), Maryland. The permit required a Resource Conservation and Recovery Act (RCRA) Facility Assessment (RFA) of sites in the Aberdeen Area (AA) of APG. Recommendations from a draft RFA report suggested further investigations at the Fire Training Area (FTA). This study is in response to the recommendations. Three soil borings and twelve groundwater monitor wells were installed. Three rounds of groundwater sampling and analyses were conducted. APG lies in the Coastal Plain Physiographic Province which is underlain by sediments consisting of three major units, the Potomac Group, the Talbot Formation, and Recent (Holocene) sediments. The Lower Cretaceous sediments of the Potomac Group lie unconformably on the older Precambrian rocks. In the early 1960's fire training was initiated and training has been conducted as often as once a week. Trenches were ignited after being filled with oil and water. The exercises concluded in 1989. During the RFA shallow boring soil gas surveys were conducted for volatile organic compound (VOC) contamination at the FTA. Deeper borings were conducted for monitor wells and geologic mapping. Sampling and monitoring of groundwater, surface water, and soils was conducted. Analyses of groundwater from the monitor wells and two supply wells indicate the AFTA is contributing chemical contaminants to the upper aquifer, which is at a depth of approximately 30 feet below ground surface. ....Aberdeen Proving Ground, Maryland, Hydrogeology, Groundwater, Site characterization, Groundwater contamination.

  2. Geophysical study of the Building 103 Dump, Aberdeen Proving Ground

    SciTech Connect

    McGinnis, L.D.; Miller, S.F.; Thompson, M.D.; McGinnis, M.G.

    1992-12-01

    The Building 103 Dump is one of ten potentially contaminated sites in the Canal Creek and Westwood areas of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May of 1992. Noninvasive geophysical surveys, including magnetics, resistivity, ground-penetrating radar, and seismic refraction, were conducted. These surveys indicate that much of the area is free of debris. However, prominent magnetic and resistivity anomalies occur along well-defined lineaments, suggestive of a dendritic stream pattern. Prior to the onset of dumping, the site was described as a ``sand pit,`` which suggests that headward erosion of Canal Creek tributaries cut into the surficial aquifer. Contaminants dumped into the landfill would have direct access to the surficial aquifer and thus to Canal Creek. Seismic refraction profiling indicates 6--12 ft of fill material now rests on the former land surface. Only the northern third of the former landfill was geophysically surveyed.

  3. Ecological effects of soil contamination at Aberdeen Proving Ground, Maryland

    SciTech Connect

    Kuperman, R.G.; Dunn, C.P. )

    1994-06-01

    Assessment of the ecological condition of contaminated soil was conducted in portions of the U.S. Army's Aberdeen Proving Ground, Maryland as part of an ecological risk assessment. This area is covered by open fields, woods and nontidal marshes. Chemicals disposed of in open burning pits included methylphosphonothioic acid, dichlorodiethyl sulfide, and titanium tetrachloride and sulfur trioxide/chlorosulfonic acid. Previous soil analysis showed extensive surface soil contamination with metals, nitrate, PCBs and pesticides. This assessment included characterizing soil biota, biologically-mediated processes in soil and aboveground biomass. Field surveys of the soil invertebrate communities showed significant reductions in the total abundance of animals, reductions in the abundance of several taxonomic and functional groups of soil invertebrates, and changes in the activity of epigeic arthropods in contaminated areas when compared with the local [open quotes]background[close quotes] area. Laboratory toxicity tests also demonstrated that microbial activity and success of egg hatching of ground beetle Harpalus pensylvanicus were reduced in contaminated soils. These results suggest that impacts to soil ecosystems should be explicitly considered in ecological risk assessment.

  4. Environmental geophysics, offshore Bush River Peninsula, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Miller, S.F.; Kuecher, G.J.; Davies, B.E.

    1995-11-01

    Geophysical studies in shallow waters adjacent to the Bush River Peninsula, Edgewood Area of Aberdeen Proving Ground, Maryland, have delineated the extent of waste disposal sites and established a hydrogeologic framework, which may control contaminant transport offshore. These studies indicate that during the Pleistocene Epoch, alternating stands of high and low sea levels resulted in a complex pattern of shallow channel-fill deposits around the Bush River Peninsula. Ground-penetrating radar studies reveal paleochannels greater than 50 ft deep. Some of the paleochannels are also imaged with marine seismic reflection. Conductivity highs measured with the EM-31 are also indicative of paleochannels. This paleochannel depositional system is environmentally significant because it may control the shallow groundwater flow regime beneath the peninsula. Magnetic, conductivity, and side-scan sonar anomalies outline anthropogenic anomalies in the study area. On the basis of geophysical data, underwater anthropogenic materials do exist in some isolated areas, but large-scale offshore dumping has not occurred in the area studied.

  5. Environmental geophysics at Beach Point, Aberdeen Proving Ground, Maryland

    SciTech Connect

    McGinnis, L.D.; Daudt, C.R.; Thompson, M.D.; Miller, S.F.; Mandell, W.A.; Wrobel, J.

    1994-07-01

    Geophysical studies at Beach Point Peninsula, in the Edgewood area of Aberdeen Proving Ground, Maryland, provide diagnostic signatures of the hydrogeologic framework and possible contaminant pathways. These studies permit construction of the most reasonable scenario linking dense, nonaqueous-phase liquid contaminants introduced at the surface with their pathway through the surficial aquifer. Subsurface geology and contaminant presence were identified by drilling, outcrop mapping, and groundwater sampling and analyses. Suspected sources of near-surface contaminants were defined by magnetic and conductivity measurements. Negative conductivity anomalies may be associated with unlined trenches. Positive magnetic and conductivity anomalies outline suspected tanks and pipes. The anomalies of greatest concern are those spatially associated with a concrete slab that formerly supported a mobile clothing impregnating plant. Resistivity and conductivity profiling and depth soundings were used to identify an electrical anomaly extending through the surficial aquifer to the basal pleistocene unconformity, which was mapped by using seismic reflection methods. The anomaly may be representative of a contaminant plume connected to surficial sources. Major activities in the area included liquid rocket fuel tests, rocket fuel fire suppression tests, pyrotechnic material and smoke generator tests, and the use of solvents at a mobile clothing impregnating plant.

  6. Depleted uranium risk assessment at Aberdeen Proving Ground

    SciTech Connect

    Ebinger, M.H.; Myers, O.B.; Kennedy, P.L.; Clements, W.H.

    1993-03-01

    The Environmental Science Group at Los Alamos and the Test and Evaluation Command (TECOM) are assessing the risk of depleted uranium (DU) testing at Aberdeen Proving Ground (APG). Conceptual and mathematical models of DU transfer through the APG ecosystem have been developed in order to show the mechanisms by which DU migrates or remains unavailable to different flora and fauna and to humans. The models incorporate actual rates of DU transfer between different ecosystem components as much as possible. Availability of data on DU transport through different pathways is scarce and constrains some of the transfer rates that can be used. Estimates of transfer rates were derived from literature sources and used in the mass-transfer models when actual transfer rates were unavailable. Objectives for this risk assessment are (1) to assess if DU transports away from impact areas; (2) to estimate how much, if any, DU migrates into Chesapeake Bay; (3) to determine if there are appreciable risks to the ecosystems due to DU testing; (4) to estimate the risk to human health as a result of DU testing.

  7. Depleted uranium risk assessment at Aberdeen Proving Ground

    SciTech Connect

    Ebinger, M.H. ); Myers, O.B.; Kennedy, P.L.; Clements, W.H. . Dept. of Fishery and Wildlife Biology)

    1993-01-01

    The Environmental Science Group at Los Alamos and the Test and Evaluation Command (TECOM) are assessing the risk of depleted uranium (DU) testing at Aberdeen Proving Ground (APG). Conceptual and mathematical models of DU transfer through the APG ecosystem have been developed in order to show the mechanisms by which DU migrates or remains unavailable to different flora and fauna and to humans. The models incorporate actual rates of DU transfer between different ecosystem components as much as possible. Availability of data on DU transport through different pathways is scarce and constrains some of the transfer rates that can be used. Estimates of transfer rates were derived from literature sources and used in the mass-transfer models when actual transfer rates were unavailable. Objectives for this risk assessment are (1) to assess if DU transports away from impact areas; (2) to estimate how much, if any, DU migrates into Chesapeake Bay; (3) to determine if there are appreciable risks to the ecosystems due to DU testing; (4) to estimate the risk to human health as a result of DU testing.

  8. A consolidated environmental monitoring plan for Aberdeen Proving Ground, Maryland

    SciTech Connect

    Ebinger, M.H.; Hansen, W.R.

    1997-04-01

    The US Army operates facilities in Edgewood and Aberdeen under several licenses from the Nuclear Regulatory Commission (NRC). Compliance with each license is time consuming and could potentially result in duplicated efforts to demonstrate compliance with existing environmental regulations. The goal of the ERM plan is to provide the sampling necessary to ensure that operations at Edgewood and Aberdeen are within applicable regulatory guidelines and to provide a means of ensuring that adverse effects to the environment are minimized. Existing sampling plans and environmental data generated from those plans are briefly reviewed as part of the development of the present ERM plan. The new ERM plan was designed to provide data that can be used for assessing risks to the environment and to humans using Aberdeen and Edgewood areas. Existing sampling is modified and new sampling is proposed based on the results of the long-term DU fate study. In that study, different environmental pathways were identified that would show transport of DU at Aberdeen. Those pathways would also be impacted by other radioactive constituents from Aberdeen and Edgewood areas. The ERM plan presented in this document includes sampling from Edgewood and Aberdeen facilities. The main radioactive constituents of concern at Edgewood are C, P, N, S, H, I, Co, Cs, Ca, Sr and U that are used in radiolabeling different compounds and tracers for different reactions and syntheses. Air and water sampling are the thrust of efforts at the Edgewood area.

  9. Environmental geophysics at J-Field, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Daudt, C.R.; McGinnis, L.D.; Miller, S.F.; Thompson, M.D.

    1994-11-01

    Geophysical data collected at J-Field, Aberdeen Proving Ground, Maryland, were used in the characterization of the natural hydrogeologic framework of the J-Field area and in the identification of buried disturbances (trenches and other evidences of contamination). Seismic refraction and reflection data and electrical resistivity data have aided in the characterization of the leaky confining unit at the base of the surficial aquifer (designated Unit B of the Tertiary Talbot Formation). Excellent reflectors have been observed for both upper and lower surfaces of Unit B that correspond to stratigraphic units observed in boreholes and on gamma logs. Elevation maps of both surfaces and an isopach map of Unit B, created from reflection data at the toxic burning pits site, show a thickening of Unit B to the east. Abnormally low seismic compressional-wave velocities suggest that Unit B consists of gassy sediments whose gases are not being flushed by upward or downward moving groundwater. The presence of gases suggests that Unit B serves as an efficient aquitard that should not be penetrated by drilling or other activities. Electromagnetic, total-intensity magnetic, and ground-penetrating radar surveys have aided in delineating the limits of two buried trenches, the VX burning pit and the liquid smoke disposal pit, both located at the toxic burning pits site. The techniques have also aided in determining the extent of several other disturbed areas where soils and materials were pushed out of disposal pits during trenching activities. Surveys conducted from the Prototype Building west to the Gunpowder River did not reveal any buried trenches.

  10. Geophysics: Building E5476 decommissiong, Aberdeen Proving Ground. Interim progress report

    SciTech Connect

    Miller, S.F.; Thompson, M.D.; McGinnis, M.G.; McGinnis, L.D.

    1992-11-01

    Building E5476 was one of ten potentially contaminated sites in the Canal Creek and Westwood areas of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May of 1992. Noninvasive geophysical surveys, including magnetics, electrical resistivity, and ground-penetrating radar, were conducted around the perimeter of the building to guide a sampling program prior to decommissioning and dismantling. The large number of magnetic sources surrounding the building are believed to be contained in construction fill. The smaller anomalies, for the most part, were not imaged with ground radar or by electrical profiling. Large magnetic anomalies near the southwest comer of the building are due to aboveground standpipes and steel-reinforced concrete. Two high-resistivity areas, one projecting northeast from the building and another south of the original structure, may indicate the presence of organic pore fluids in the subsurface. A conductive lineament protruding from the south wall that is enclosed by the southem, high-resistivity feature is not associated with an equivalent magnetic anomaly. Magnetic and electrical anomalies south of the old landfill boundary are probably not associated with the building. The boundary is marked by a band of magnetic anomalies and a conductive zone trending northwest to southeast. The cause of high resistivities in a semicircular area in the southwest comer, within the landfill area, is unexplained.

  11. 33 CFR 334.140 - Chesapeake Bay; U.S. Army Proving Ground Reservation, Aberdeen, Md.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ..., the patrol boat may operate a distinctive rotating blue and red light, public address system, sound a..., eel pot, crab pot, and all other types of nets fastened by means of poles, stakes, weights, or anchors. Permits to fish and crab within the restricted waters of Aberdeen Proving Ground may be obtained...

  12. 33 CFR 334.140 - Chesapeake Bay; U.S. Army Proving Ground Reservation, Aberdeen, Md.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ..., the patrol boat may operate a distinctive rotating blue and red light, public address system, sound a..., eel pot, crab pot, and all other types of nets fastened by means of poles, stakes, weights, or anchors. Permits to fish and crab within the restricted waters of Aberdeen Proving Ground may be obtained...

  13. Remedial investigation report for J-Field, Aberdeen Proving Ground, Maryland. Volume 3: Ecological risk assessment

    SciTech Connect

    Hlohowskyj, I.; Hayse, J.; Kuperman, R.; Van Lonkhuyzen, R.

    2000-02-25

    The Environmental Management Division of the U.S. Army Aberdeen Proving Ground (APG), Maryland, is conducting a remedial investigation (RI) and feasibility study (FS) of the J-Field area at APG, pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. As part of that activity, Argonne National Laboratory (ANL) conducted an ecological risk assessment (ERA) of the J-Field site. This report presents the results of that assessment.

  14. Site investigation of Cluster 3, Edgewood Area, Aberdeen Proving Ground, Maryland. Final report

    SciTech Connect

    Sharp, M.K.; Kean, T.B.

    1995-08-01

    The Waterways Experiment Station (WES) is currently involved in investigating several sites at the Edgewood Area (EA) of Aberdeen Proving Ground (APG), Maryland. These investigations consist of placing monitoring wells and periodically collecting samples for laboratory analysis. Additionally, several of the sites are to be investigated geophysically to determine if any anomalous areas exist. One of the sites, Cluster 3, a suspected landfill area is the focus of this report. Geophysical surveys were conducted to help delineate any anomalies indicative of buried waste, waste containers, boundaries of burial trenches, and the depth to water table. The geophysical methods utilized at the site were electromagnetic induction (EM), magnetics, and seismic refraction.

  15. Ehrlichia chaffeensis (Rickettsiales: Ehrlichieae) infection in Amblyomma americanum (Acari: Ixodidae) at Aberdeen Proving Ground, Maryland.

    PubMed

    Stromdahl, E Y; Randolph, M P; O'Brien, J J; Gutierrez, A G

    2000-05-01

    Human monocytic ehrlichiosis (HME) is a sometimes fatal, emerging tick-borne disease caused by the bacterium Ehrlichia chaffeensis. It is frequently misdiagnosed because its symptoms mimic those of the flu. Current evidence indicates that Amblyomma americanum (L.), the lone star tick, is the major vector of HME. To determine if E. chaffeensis is present in ticks at Aberdeen Proving Ground, MD, questing A. americanum ticks were collected from 33 sites. Nucleic acid was extracted from 34 adult and 81 nymphal pools. Sequences diagnostic for E. chaffeensis from three different loci (16S rRNA, 120-kDa protein, and a variable-length polymerase chain reaction [PCR] target, or VLPT) were targeted for amplification by the PCR. Fifty-two percent of the collection sites yielded pools infected with E. chaffeensis, confirming the presence and widespread distribution of E. chaffeensis at Aberdeen Proving Ground. Analysis with the both the 120-kDa protein primers and the VLPT primers showed that genetic variance exists. A novel combination of variance for the two loci was detected in two tick pools. The pathogenic implications of genetic variation in E. chaffeensis are as yet unknown.

  16. Ecological survey of M-Field, Edgewood Area Aberdeen Proving Ground, Maryland

    SciTech Connect

    Downs, J.L.; Eberhardt, L.E.; Fitzner, R.E.; Rogers, L.E.

    1991-12-01

    An ecological survey was conducted on M-Field, at the Edgewood Area, Aberdeen Proving Ground, Maryland. M-Field is used routinely to test army smokes and obscurants, including brass flakes, carbon fibers, and fog oils. The field has been used for testing purposes for the past 40 years, but little documented history is available. Under current environmental regulations, the test field must be assessed periodically to document the presence or potential use of the area by threatened and endangered species. The M-Field area is approximately 370 acres and is part of the US Army's Edgewood Area at Aberdeen Proving Ground in Harford County, Maryland. The grass-covered field is primarily lowlands with elevations from about 1.0 to 8 m above sea level, and several buildings and structures are present on the field. The ecological assessment of M-Field was conducted in three stages, beginning with a preliminary site visit in May to assess sampling requirements. Two field site visits were made June 3--7, and August 12--15, 1991, to identify the biota existing on the site. Data were gathered on vegetation, small mammals, invertebrates, birds, large mammals, amphibians, and reptiles.

  17. Ecological survey of M-Field, Edgewood Area Aberdeen Proving Ground, Maryland

    SciTech Connect

    Downs, J.L.; Eberhardt, L.E.; Fitzner, R.E.; Rogers, L.E.

    1991-12-01

    An ecological survey was conducted on M-Field, at the Edgewood Area, Aberdeen Proving Ground, Maryland. M-Field is used routinely to test army smokes and obscurants, including brass flakes, carbon fibers, and fog oils. The field has been used for testing purposes for the past 40 years, but little documented history is available. Under current environmental regulations, the test field must be assessed periodically to document the presence or potential use of the area by threatened and endangered species. The M-Field area is approximately 370 acres and is part of the US Army`s Edgewood Area at Aberdeen Proving Ground in Harford County, Maryland. The grass-covered field is primarily lowlands with elevations from about 1.0 to 8 m above sea level, and several buildings and structures are present on the field. The ecological assessment of M-Field was conducted in three stages, beginning with a preliminary site visit in May to assess sampling requirements. Two field site visits were made June 3--7, and August 12--15, 1991, to identify the biota existing on the site. Data were gathered on vegetation, small mammals, invertebrates, birds, large mammals, amphibians, and reptiles.

  18. Evaluation of depleted uranium in the environment at Aberdeen Proving Grounds, Maryland and Yuma Proving Grounds, Arizona. Final report

    SciTech Connect

    Kennedy, P.L.; Clements, W.H.; Myers, O.B.; Bestgen, H.T.; Jenkins, D.G.

    1995-01-01

    This report represents an evaluation of depleted uranium (DU) introduced into the environment at the Aberdeen Proving Grounds (APG), Maryland and Yuma Proving Grounds (YPG) Arizona. This was a cooperative project between the Environmental Sciences and Statistical Analyses Groups at LANL and with the Department of Fishery and Wildlife Biology at Colorado State University. The project represents a unique approach to assessing the environmental impact of DU in two dissimilar ecosystems. Ecological exposure models were created for each ecosystem and sensitivity/uncertainty analyses were conducted to identify exposure pathways which were most influential in the fate and transport of DU in the environment. Research included field sampling, field exposure experiment, and laboratory experiments. The first section addresses DU at the APG site. Chapter topics include bioenergetics-based food web model; field exposure experiments; bioconcentration by phytoplankton and the toxicity of U to zooplankton; physical processes governing the desorption of uranium from sediment to water; transfer of uranium from sediment to benthic invertebrates; spead of adsorpion by benthic invertebrates; uptake of uranium by fish. The final section of the report addresses DU at the YPG site. Chapters include the following information: Du transport processes and pathway model; field studies of performance of exposure model; uptake and elimination rates for kangaroo rates; chemical toxicity in kangaroo rat kidneys.

  19. Air monitoring for volatile organic compounds at the Pilot Plant Complex, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Schneider, J.F.; O`Neill, H.J.; Raphaelian, L.A.; Tomczyk, N.A.; Sytsma, L.F.; Cohut, V.J.; Cobo, H.A.; O`Reilly, D.P.; Zimmerman, R.E.

    1995-03-01

    The US Army`s Aberdeen Proving Ground has been a test site for a variety of munitions, including chemical warfare agents (CWA). The Pilot Plant Complex (PPC) at Aberdeen was the site of development, manufacture, storage, and disposal of CWA. Deterioration of the buildings and violations of environmental laws led to closure of the complex in 1986. Since that time, all equipment, piping, and conduit in the buildings have been removed. The buildings have been declared free of surface CWA contamination as a result of air sampling using the military system. However, no air sampling has been done to determine if other hazardous volatile organic compounds are present in the PPC, although a wide range of toxic and/or hazardous materials other than CWA was used in the PPC. The assumption has been that the air in the PPC is not hazardous. The purpose of this air-monitoring study was to screen the indoor air in the PPC to confirm the assumption that the air does not contain volatile organic contaminants at levels that would endanger persons in the buildings. A secondary purpose was to identify any potential sources of volatile organic contaminants that need to be monitored in subsequent sampling efforts.

  20. Contamination source review for Building E5974, Edgewood Area, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Billmark, K.A.; Emken, M.E.; O`Reilly, D.P.; Smits, M.P.; Draugelis, A.K.; Rueda, J.; Zimmerman, R.E.

    1995-09-01

    This report documents the results of a contamination source review of Building E5974 at the Aberdeen Proving Ground (APG) in Maryland. The primary mission at APG has been the testing and evaluation of US Army warfare materials. Since its beginning in 1917, the Edgewood Area of APG has been the principal location for chemical warfare agent research, development, and testing in the US. APG was also used for producing chemical warfare agents during both world wars, and it has been a center for the storage of chemical warfare material. An attempt was made to identify and define areas of toxic or hazardous contaminants and to assess the physical condition and accessibility of APG buildings. The information obtained from this review may be used to assist the US Army in planning for the future use or disposition of the buildings. The contamination source review consisted of the following tasks: historical records search, physical inspection, photographic documentation, geophysical investigation, and collection of air samples.

  1. Environmental geophysics at Kings Creek Disposal Site and 30th Street Landfill, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Davies, B.E.; Miller, S.F.; McGinnis, L.D.; Daudt, C.R.; Thompson, M.D.; Stefanov, J.E.; Benson, M.A.; Padar, C.A.

    1995-01-01

    Geophysical studies on the Bush River Peninsula in the Edgewood Area of Aberdeen Proving Ground, Maryland, delineate landfill areas and provide diagnostic signatures of the hydrogeologic framework and possible contaminant pathways. These studies indicate that, during the Pleistocene Epoch, alternating stands of high and low seal levels resulted in a complex pattern of shallow channel-fill deposits in the Kings Creek area. Ground-penetrating radar studies reveal a paleochannel greater than 50 ft deep, with a thalweg trending offshore in a southwest direction into Kings Creek. Onshore, the ground-penetrating radar data indicate a 35-ft-deep branch to the main channel, trending to the north-northwest directly beneath the 30th Street Landfill. Other branches are suspected to meet the offshore paleochannel in the wetlands south and east of the 30th Street Landfill. This paleochannel depositional system is environmentally significant because it may control the shallow groundwater flow regime beneath the site. Electromagnetic surveys have delineated the pre-fill lowland area currently occupied by the 30th Street Landfill. Magnetic and conductive anomalies outline surficial and buried debris throughout the study area. On the basis of geophysical data, large-scale dumping has not occurred north of the Kings Creek Disposal Site or east of the 30th Street Landfill.

  2. Environmental geophysics at the Southern Bush River Peninsula, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Davies, B.E.; Miller, S.F.; McGinnis, L.D.

    1995-05-01

    Geophysical studies have been conducted at five sites in the southern Bush River Peninsula in the Edgewood Area of Aberdeen Proving Ground, Maryland. The goals of the studies were to identify areas containing buried metallic objects and to provide diagnostic signatures of the hydrogeologic framework of the site. These studies indicate that, during the Pleistocene Epoch, alternating stands of high and low sea level resulted in a complex pattern of channel-fill deposits. Paleochannels of various sizes and orientations have been mapped throughout the study area by means of ground-penetrating radar and EM-31 techniques. The EM-31 paleochannel signatures are represented onshore either by conductivity highs or lows, depending on the depths and facies of the fill sequences. A companion study shows the features as conductivity highs where they extend offshore. This erosional and depositional system is environmentally significant because of the role it plays in the shallow groundwater flow regime beneath the site. Magnetic and electromagnetic anomalies outline surficial and buried debris throughout the areas surveyed. On the basis of geophysical measurements, large-scale (i.e., tens of feet) landfilling has not been found in the southern Bush River Peninsula, though smaller-scale dumping of metallic debris and/or munitions cannot be ruled out.

  3. Contamination source review for Building E5485, Edgewood Area, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Billmark, K.A.; Hayes, D.C.; Draugelis, A.K.; Rueda, J.; Zimmerman, R.E.

    1995-09-01

    This report was prepared by Argonne National Laboratory (ANL) to document the results of a contamination source review of Building E5485 at the Aberdeen Proving Ground (APG) in Maryland. This report may be used to assist the US Army in planning for the future use or disposition of this building. The review included a historical records search, physical inspection, photographic documentation, geophysical investigation, and collection of air samples. Building E5485 (APG designation) is located in the drainage basin of the west branch of Canal Creek in the Edgewood Area of APG. The building was constructed in 1922 and used as a fan house for agent operations in Building E5487 from 1925 to 1966. Building E5485 was then used as a laboratory to support manufacturing and storage of flammable agents and chemical warfare agents from 1966 until 1967, when it was placed on the inactive list. Air quality samples were collected upwind, downwind, and inside Building E5485 in November 1994. Analytical results showed no distinguishable difference in hydrocarbon and chlorinated solvent levels between the two background samples and the sample collected inside Building E5485. These results indicate that Building E5485 is not a source of volatile organic compound contamination.

  4. Contamination source review for Building E5978, Edgewood Area, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Mosqueda, G.; Dougherty, J.; Draugelis, A.K.; Rueda, J.; Zimmerman, R.E.

    1995-09-01

    This report documents the results of a contamination source review of Building E5978 at the Aberdeen Proving Group (APG) in Maryland. The primary mission at APG has been the testing and evaluation of US Army warfare materials. Since its beginning in 1917, the Edgewood Area of APG has been the principal location for chemical warfare agent research, development, and testing in the US. APG was also used for producing chemical warfare agents during both world wars, and it has been a center for the storage of chemical warfare material. An attempt was made to identify and define areas of toxic or hazardous contaminants and to assess the physical condition and accessibility of APG buildings. The information obtained from this review may be used to assist the US Army in planning for the future use or disposition of the buildings. The contamination source review consisted of the following tasks: historical records search, physical inspection, photographic documentation, geophysical investigation, and collection of air samples for the presence of volatile organic compounds.

  5. Contamination source review for Building E3162, Edgewood Area, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Miller, G.A.; Draugelis, A.K.; Rueda, J.; Zimmerman, R.E.

    1995-09-01

    This report was prepared by Argonne National Laboratory (ANL) to document the results of a contamination source review for Building E3162 at the Aberdeen Proving Ground (APG) in Maryland. The report may be used to assist the US Army in planning for the future use or disposition of this building. The review included a historical records search, physical inspection, photographic documentation, geophysical investigation, and collection of air samples. The field investigations were performed by ANL during 1994 and 1995. Building E3162 (APG designation) is part of the Medical Research Laboratories Building E3160 Complex. This research laboratory complex is located west of Kings Creek, east of the airfield and Ricketts Point Road, and south of Kings Creek Road in the Edgewood Area of APG. The original structures in the E3160 Complex were constructed during World War 2. The complex was originally used as a medical research laboratory. Much of the research involved wound assessment involving chemical warfare agents. Building E3162 was used as a holding and study area for animals involved in non-agent burns. The building was constructed in 1952, placed on inactive status in 1983, and remains unoccupied. Analytical results from these air samples revealed no distinguishable difference in hydrocarbon and chlorinated solvent levels between the two background samples and the sample taken inside Building E3162.

  6. Contamination source review for Building E3642, Edgewood Area, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Booher, M.N.; O`Reilly, D.P.; Draugelis, A.K.; Rueda, J.; Zimmerman, R.E.

    1995-09-01

    Many of the APG facilities constructed between 1917 and the 1960s are no longer used because of obsolescence and their poor state of repair. Because many of these buildings were used for research, development, testing, and/or pilot-scale production of chemical warfare agents and other military substances, the potential exists for portions of these buildings to be contaminated with these substances, their degradation products, and other laboratory or industrial chemicals. These buildings and associated structures or appurtenances may contribute to environmental concerns at APG. The US Army Aberdeen Proving Ground (APG) commissioned Argonne National Laboratory (ANL) to conduct a contamination source review to identify and define areas of toxic or hazardous contaminants and to assess the physical condition and accessibility of APG buildings. The information obtained from the review may be used to assist the US Army in planning for the future use or disposition of the buildings. The contamination source review consisted of the following tasks: historical records search, physical inspection, photographic documentation, geophysical investigation and review of available records regarding underground storage tanks associated with the building. This report provides the results of the contamination source review for Building E3642.

  7. An accelerated remedial strategy developed for J-Field, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Yuen, C.R.; Martino, L.; Patton, T.; Wrobel, J.

    1995-06-01

    For an installation with many disposal sites and multiple contaminant sources, successful remediation at minimum cost can be complicated by insufficient geologic and hydrogeologic information, incomplete records of historical disposal activities, and uncertainty about the effectiveness of different investigative methods. To reduce these uncertainties and to increase the probability of successful remediation at minimum cost, a ``Phased and pilot`` accelerated remedial strategy has been developed for the J-Field area of Aberdeen Proving Ground, Maryland. The strategy includes four phases. First, the most contaminated site is selected as a pilot for detailed investigation. Second, the most contaminated areas within the pilot site are chosen as a pilot source area for interim action study, and a remedial action is developed to remove the primary contaminant sources. The subsequent sitewide investigation uses the effective tools developed in the first phase. Third, a cleanup operation is initiated in the pilot source area, while a sitewide feasibility study is developed by taking advantage of lessons learned in the interim action. Fourth, a sitewide cleanup operation proceeds.

  8. Remedial investigation report for J-Field, Aberdeen Proving Ground, Maryland. Volume 1: Remedial investigation results

    SciTech Connect

    Yuen, C. R.; Martino, L. E.; Biang, R. P.; Chang, Y. S.; Dolak, D.; Van Lonkhuyzen, R. A.; Patton, T. L.; Prasad, S.; Quinn, J.; Rosenblatt, D. H.; Vercellone, J.; Wang, Y. Y.

    2000-03-14

    This report presents the results of the remedial investigation (RI) conducted at J-Field in the Edgewood Area of Aberdeen Proving Ground (APG), a U.S. Army installation located in Harford County, Maryland. Since 1917, activities in the Edgewood Area have included the development, manufacture, and testing of chemical agents and munitions and the subsequent destruction of these materials at J-Field by open burning and open detonation. These activities have raised concerns about environmental contamination at J-Field. This RI was conducted by the Environmental Conservation and Restoration Division, Directorate of Safety, Health and Environmental Division of APG, pursuant to requirements outlined under the Comprehensive Environmental Response, Compensation, and Liability Act, as amended (CERCLA). The RI was accomplished according to the procedures developed by the U.S. Environmental Protection Agency (EPA 1988). The RI provides a comprehensive evaluation of the site conditions, nature of contaminants present, extent of contamination, potential release mechanisms and migration pathways, affected populations, and risks to human health and the environment. This information will be used as the basis for the design and implementation of remedial actions to be performed during the remedial action phase, which will follow the feasibility study (FS) for J-Field.

  9. Contamination source review for Building E2370, Edgewood Area, Aberdeen Proving Ground, Maryland

    SciTech Connect

    O`Reilly, D.P.; Glennon, M.A.; Draugelis, A.K.; Rueda, J.; Zimmerman, R.E.

    1995-09-01

    The US Army Aberdeen Proving Ground (APG) commissioned Argonne National Laboratory (ANL) to conduct a contamination source review to identify and define areas of toxic or hazardous contaminants and to assess the physical condition and accessibility of APG buildings. The information obtained from this review may be used to assist the US Army in planning for the future use or disposition of the buildings. The contamination source review consisted of the following tasks: historical records search, physical inspection, photographic documentation, and geophysical investigation. This report provides the results of the contamination source review for Building E2370. Many of the APG facilities constructed between 1917 and the 1960s are no longer used because of obsolescence and their poor state of repair. Because many of these buildings were used for research, development, testing, and/or pilot-scale production of chemical warfare agents and other military substances, the potential exists for portions of the buildings to be contaminated with these substances, their degradation products, and other laboratory or industrial chemicals. These buildings and associated structures or appurtenances may contribute to environmental concerns at APG.

  10. Contamination source review for Building E7995, Edgewood Area, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Booher, M.N.; Miller, G.A.; Draugelis, A.K.; Glennon, M.A.; Rueda, J.; Zimmerman, R.E.

    1995-09-01

    The US Army Aberdeen Proving Ground (APG) commissioned Argonne National Laboratory (ANL) to conduct a contamination source review to identify and define areas of toxic or hazardous contaminants and to assess the physical condition and accessibility of APG buildings. The information obtained from the review may be used to assist the US Army in planning for the future use or disposition, of the buildings. The source contamination review consisted of the following tasks: historical records search, physical inspection, photographic documentation, geophysical investigation, investigation of potential hazardous materials facilities (HMFs), and review of available records regarding underground storage tanks. This report provides the results of the contamination source review for Building E7995. any of the APG facilities constructed between 1917 and the 1960s are no longer used because of obsolescence and their poor state of repair. Because many of these buildings were used for research, development, testing, and/or pilot-scale production of chemical warfare agents and other military substances, the potential exists for portions of the buildings to be contaminated with these substances, their degradation products, and other laboratory or industrial chemicals. These buildings, and associated structures or appurtenances, may contribute to environmental concerns at APG.

  11. Natural attenuation of chlorinated volatile organic compounds in a freshwater tidal wetland, Aberdeen Proving Ground, Maryland

    USGS Publications Warehouse

    Lorah, Michelle M.; Olsen, Lisa D.; Smith, Barrett L.; Johnson, Mark A.; Fleck, William B.

    1997-01-01

    Ground-water contaminant plumes that are flowing toward or currently discharging to wetland areas present unique remediation problems because of the hydrologic connections between ground water and surface water and the sensitive habitats in wetlands. Because wetlands typically have a large diversity of microorganisms and redox conditions that could enhance biodegradation, they are ideal environments for natural attenuation of organic contaminants, which is a treatment method that would leave the ecosystem largely undisturbed and be cost effective. During 1992-97, the U.S. Geological Survey investigated the natural attenuation of chlorinated volatile organic compounds (VOC's) in a contaminant plume that discharges from a sand aquifer to a freshwater tidal wetland along the West Branch Canal Creek at Aberdeen Proving Ground, Maryland. Characterization of the hydrogeology and geochemistry along flowpaths in the wetland area and determination of the occurrence and rates of biodegradation and sorption show that natural attenuation could be a feasible remediation method for the contaminant plume that extends along the West Branch Canal Creek.

  12. Contamination source review for Building E3180, Edgewood Area, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Zellmer, S.D.; Smits, M.P.; Rueda, J.; Zimmerman, R.E.

    1995-09-01

    This report was prepared by Argonne National Laboratory (ANL) to document the results of a contamination source review of Building E3180 at the Aberdeen Proving Ground (APG) in Maryland. The report may be used to assist the US Army in planning for the future use or disposition of this building. The review included a historical records search, physical inspection, photographic documentation, geophysical investigation, collection of air samples, and review of available records regarding underground storage tanks associated with Building E3180. The field investigations were performed by ANL during 1994. Building,E3180 (current APG designation) is located near the eastern end of Kings Creek Road, north of Kings Creek, and about 0.5 miles east of the airstrip within APG`s Edgewood Area. The building was constructed in 1944 as a facsimile of a Japanese pillbox and used for the development of flame weapons systems until 1957 (EAI Corporation 1989). The building was not used from 1957 until 1965, when it was converted and used as a flame and incendiary laboratory. During the 1970s, the building was converted to a machine (metal) shop and used for that purpose until 1988.

  13. Contamination source review for Building E3641, Edgewood Area, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Zellmer, S.D.; Draugelis, A.K.; Rueda, J.; Zimmerman, R.E.

    1995-09-01

    This report documents the results of a contamination source review of Building E3641 at the Aberdeen Proving Ground (APG) in Maryland. The primary mission at APG has been the testing and evaluation of US Army warfare materials. Since its beginning in 1917, the Edgewood Area of APG has been the principal location for chemical warfare agent research, development, and testing in the US. APG was also used for producing chemical warfare agents during both world wars, and it has been a center for the storage of chemical warfare material. An attempt was made to identify and define areas of toxic or hazardous contaminants and to assess the physical condition and accessibility of APG buildings. The information obtained from this review may be used to assist the US Army in planning for the future use or disposition of the buildings. The contamination source review consisted of the following tasks: historical records search, physical inspection, photographic documentation, geophysical investigation, and review of available records regarding underground storage tanks associated with each building.

  14. Hydrogeologic and chemical data for the O-Field area, Aberdeen Proving Ground, Maryland

    USGS Publications Warehouse

    Nemoff, P.R.; Vroblesky, D.A.

    1989-01-01

    O-Field, located at the Edgewood area of Aberdeen Proving Ground , Maryland, was periodically used for disposal of munitions, waste chemicals, and chemical-warfare agents from World War II through the 1950' s. This report includes various physical, geologic, chemical, and hydrologic data obtained from well-core, groundwater, surface water, and bottom-sediment sampling sites at and near the O-Field disposal area. The data are presented in tables and hydrographs. Three site-location maps are also included. Well-core data include lithologic logs for 11 well- cluster sites, grain-size distributions, various chemical characteristics, and confining unit characteristics. Groundwater data include groundwater chemistry, method blanks for volatile organic carbon, available data on volatile and base/neutral organics, and compilation of corresponding method blanks, chemical-warfare agents, explosive-related products, radionuclides, herbicides, and groundwater levels. Surface-water data include field-measured characteristics; concentrations of various inorganic constituents including arsenic; selected organic constituents with method blanks; detection limits of organics; and a compilation of information on corresponding acids, volatiles, and semivolatiles. Bottom- sediment data include inorganic properties and constituents; organic chemistry; detection limits for organic chemicals; a compilation of information on acids, volatiles, and semivolatiles; and method blanks corresponding to acids, volatiles, and semivolatiles. A set of 15 water- level hydrographs for the period March 1986 through September 1987 also is included in the report. (USGS)

  15. Hydrogeology and soil gas at J-Field, Aberdeen Proving Ground, Maryland

    USGS Publications Warehouse

    Hughes, W.B.

    1993-01-01

    Disposal of chemical warfare agents, munitions, and industrial chemicals in J-Field, Aberdeen Proving Ground, Maryland, has contaminated soil, groundwater and surface water. Seven exploratory borings and 38 observation wells were drilled to define the hydrogeologic framework at J-Field and to determine the type, extent, and movement of contaminants. The geologic units beneath J-Field consist of Coastal Plain sediments of the Cretaceous Patapsco Formation and Pleistocene Talbot Formation. The Patapsco Formation contains several laterally discontinuous aquifers and confining units. The Pleistocene deposits were divided into 3 hydrogeologic units--a surficial aquifer, a confining unit, and a confined aquifer. Water in the surficial aquifer flows laterally from topographically high areas to discharge areas in marshes and streams, and vertically to the underlying confined aquifer. In offshore areas, water flows from the deeper confined aquifers upward toward discharge areas in the Gunpowder River and Chesapeake Bay. Analyses of soil-gas samples showed high relative-flux values of chlorinated solvents, phthalates, and hydrocarbons at the toxic-materials disposal area, white-phosphorus disposal area, and riot-control-agent disposal area. The highest flux values were located downgradient of the toxic materials and white phosphorus disposal areas, indicating that groundwater contaminants are moving from source areas beneath the disposal pits toward discharge points in the marshes and estuaries. Elevated relative-flux values were measured upgradient and downgradient of the riot-control agent disposal area, and possibly result from soil and (or) groundwater contamination.

  16. Phase II environmental geophysics at J-Field, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Davies, B.E.; Thompson, M.D.; Yuen, C.R.

    1995-09-01

    Geophysical studies were conducted at eight sites on the tip of Gunpowder Neck (J-Field) in the Edgewood Area of Aberdeen Proving Ground, Maryland. The results of the studies were used to delineate the extent of three former burning pits and help determine the necessity of further investigation at five potential areas of concern (PAOCs). Intensive investigations were performed at the three former burning pits and two of the PAOCs by using electromagnetic (EM-31 and EM-61), total field magnetometry, and ground-penetrating radar geophysical techniques. The successful integration of the four data sets characterized the extent, the approximate depth and nature of fill material, and the location of metallic debris at the three former burning pits. At the two PAOC sites that were intensively investigated, no continuous areas of metallic debris, indicating organized burials, were present. Less extensive exploratory profiles conducted at three other PAOC sites indicated the presence of buried metal objects, but they were inconclusive in defining the nature and extent of buried materials.

  17. Contamination source review for Building E1489, Edgewood Area, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Billmark, K.A.; Hayes, D.C.; Draugelis, A.K.

    1995-09-01

    This report was prepared by Argonne National Laboratory (ANL) to document the results of a contamination source review of Building E1489 at the Aberdeen Proving Ground (APG) in Maryland. This report may be used to assist the U.S. Army-in planning for the future use or disposition of this building. The review included a historical records search, physical inspection, photographic documentation, and geophysical investigation. The field investigations were performed in 1994-1995. Building E1489 located in J-Field on the Gunpowder Peninsula in APG`s Edgewood Area housed a power generator that supplied electricity to a nearby observation tower. Building E1489 and the generator were abandoned in 1974, demolished by APG personnel and removed from real estate records. A physical inspection and photographic documentation of Building E1489 were completed by ANL staff during November 1994. In 1994, ANL staff conducted geophysical surveys in the immediate vicinity of Building E1489 by using several nonintrusive methods. Survey results suggest the presence of some underground objects near Building E1489, but they do not provide conclusive evidence of the source of geophysical anomalies observed during the survey. No air monitoring was conducted at the site, and no information on underground storage tanks associated with Building E1489 was available.

  18. Contamination source review for Building E3236, Edgewood Area, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Zellmer, S.D.; Smits, M.P.; Draugelis, A.K.; Glennon, M.A.; Rueda, J.; Zimmerman, R.E.

    1995-09-01

    The US Army Aberdeen Proving Ground (APG) commissioned Argonne National Laboratory (ANL) to conduct a contamination source review to identify and define areas of toxic or hazardous contaminants and to assess the physical condition and accessibility of APG buildings. The information obtained from the review may be used to assist the US Army in planning for the future use or disposition of the buildings. The contamination source review consisted of the following tasks: historical records search, physical inspection, photographic documentation, geophysical investigation, and review of available records regarding underground storage tanks associated with each building. This report provides the results of the contamination source review for Building E3236. Many of the APG facilities constructed between 1917 and the 1960s are no longer used because of obsolescence and their poor state of repair. Because many of these buildings were used for research, development, testing, and/or pilot- scale production of chemical warfare agents and other military substances, the potential exists for portions of the buildings to be contaminated with these substances, their degradation products, and other laboratory or industrial chemicals. These buildings and associated structures or appurtenances may contribute to environmental concerns at APG.

  19. Contamination source review for Building E6891, Edgewood Area, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Zellmer, S.D.; Draugelis, A.K.; Rueda, J.; Zimmerman, R.E.

    1995-09-01

    The US Army Aberdeen Proving Ground (APG) commissioned Argonne National Laboratory (ANL) to conduct a contamination source review to identify and define areas of toxic or hazardous contaminants and to assess the physical condition and accessibility of various APG buildings. This report provides the results of the contamination source review for Building E6891. The information obtained from this review may be used to assist the US Army in planning for the future use or disposition of the buildings. The contamination source review consisted of the following tasks: historical records search, physical inspection, photographic documentation, geophysical investigation, and collection of air samples. This building is part of the Lauderick Creek Concrete Slab Test Site, located in the Lauderick Creek Area in the Edgewood Area. Many of the APG facilities constructed between 1917 and the 1960s are no longer used because of obsolescence and their poor state of repair. Because many of these buildings were used for research, development, testing, and/or pilot-scale production of chemical warfare agents and other military substances the potential exists` for portions of the buildings to be contaminated with these substances, their degradation products, and other laboratory or industrial chemicals. These buildings and associated structures or appurtenances may contribute to environmental concerns at APG.

  20. Review of analytical results from the proposed agent disposal facility site, Aberdeen Proving Ground

    SciTech Connect

    Brubaker, K.L.; Reed, L.L.; Myers, S.W.; Shepard, L.T.; Sydelko, T.G.

    1997-09-01

    Argonne National Laboratory reviewed the analytical results from 57 composite soil samples collected in the Bush River area of Aberdeen Proving Ground, Maryland. A suite of 16 analytical tests involving 11 different SW-846 methods was used to detect a wide range of organic and inorganic contaminants. One method (BTEX) was considered redundant, and two {open_quotes}single-number{close_quotes} methods (TPH and TOX) were found to lack the required specificity to yield unambiguous results, especially in a preliminary investigation. Volatile analytes detected at the site include 1, 1,2,2-tetrachloroethane, trichloroethylene, and tetrachloroethylene, all of which probably represent residual site contamination from past activities. Other volatile analytes detected include toluene, tridecane, methylene chloride, and trichlorofluoromethane. These compounds are probably not associated with site contamination but likely represent cross-contamination or, in the case of tridecane, a naturally occurring material. Semivolatile analytes detected include three different phthalates and low part-per-billion amounts of the pesticide DDT and its degradation product DDE. The pesticide could represent residual site contamination from past activities, and the phthalates are likely due, in part, to cross-contamination during sample handling. A number of high-molecular-weight hydrocarbons and hydrocarbon derivatives were detected and were probably naturally occurring compounds. 4 refs., 1 fig., 8 tabs.

  1. Meeting on Solute/Solvent Interactions Held in Aberdeen Proving Ground, Maryland on May 29-30, 1991

    DTIC Science & Technology

    1992-01-01

    J. Taylor, Tetrahedxon Letters, 29, 1587 (1988). 6. G. M. Brown & 0. A. W. Strydom, Acta Crystallogr, Sewt. B 30,801 (1974). 7. P. Marsh & D. E...APPENDIX 3 ORGANIZATIONS OF AUTHORS IN THESE PROCEEDINGS Central Michigan University 49 Instituto de Quimica Fisica 33 La Sierra University, Riverside 71...Aberdeen Proving Gd, MD Joxe-Luis Abbud Christopher Cramer Instituto de Quimica Fisica SMCCR-RSP-C "Rocasolano" U.S. Army Chemical RD&E Center Conajo

  2. Work plan for conducting an ecological risk assessment at J-Field, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Hlohowskyj, I.; Hayse, J.; Kuperman, R.

    1995-03-01

    The Environmental Management Division of Aberdeen Proving Ground (APG), Maryland, is conducting a remedial investigation and feasibility study (RI/FS) of the J-Field area at APG pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. J-Field is within the Edgewood Area of APG in Harford County, Maryland, and activities at the Edgewood Area since World War II have included the development, manufacture, testing, and destruction of chemical agents and munitions. The J-Field site was used to destroy chemical agents and munitions by open burning and open detonation. This work plan presents the approach proposed to conduct an ecological risk assessment (ERA) as part of the RI/FS program at J-Field. This work plan identifies the locations and types of field studies proposed for each area of concern (AOC), the laboratory studies proposed to evaluate toxicity of media, and the methodology to be used in estimating doses to ecological receptors and discusses the approach that will be used to estimate and evaluate ecological risks at J-Field. Eight AOCs have been identified at J-Field, and the proposed ERA is designed to evaluate the potential for adverse impacts to ecological receptors from contaminated media at each AOC, as well as over the entire J-Field site. The proposed ERA approach consists of three major phases, incorporating field and laboratory studies as well as modeling. Phase 1 includes biotic surveys of the aquatic and terrestrial habitats, biological tissue sampling and analysis, and media toxicity testing at each AOC and appropriate reference locations. Phase 2 includes definitive toxicity testing of media from areas of known or suspected contamination or of media for which the Phase 1 results indicate toxicity or adverse ecological effects. In Phase 3, the uptake models initially developed in Phase 2 will be finalized, and contaminant dose to each receptor from all complete pathways will be estimated.

  3. Potential health impacts from range fires at Aberdeen Proving Ground, Maryland.

    SciTech Connect

    Willians, G.P.; Hermes, A.M.; Policastro, A.J.; Hartmann, H.M.; Tomasko, D.

    1998-03-01

    This study uses atmospheric dispersion computer models to evaluate the potential for human health impacts from exposure to contaminants that could be dispersed by fires on the testing ranges at Aberdeen Proving Ground, Maryland. It was designed as a screening study and does not estimate actual human health risks. Considered are five contaminants possibly present in the soil and vegetation from past human activities at APG--lead, arsenic, trichloroethylene (TCE), depleted uranium (DU), and dichlorodiphenyltrichloroethane (DDT); and two chemical warfare agents that could be released from unexploded ordnance rounds heated in a range fire--mustard and phosgene. For comparison, dispersion of two naturally occurring compounds that could be released by burning of uncontaminated vegetation--vinyl acetate and 2-furaldehyde--is also examined. Data from previous studies on soil contamination at APG are used in conjunction with conservative estimates about plant uptake of contaminants, atmospheric conditions, and size and frequency of range fires at APG to estimate dispersion and possible human exposure. The results are compared with US Environmental Protection Agency action levels. The comparisons indicate that for all of the anthropogenic contaminants except arsenic and mustard, exposure levels would be at least an order of magnitude lower than the corresponding action levels. Because of the compoundingly conservative nature of the assumptions made, they conclude that the potential for significant human health risks from range fires is low. The authors recommend that future efforts be directed at fire management and control, rather than at conducting additional studies to more accurately estimate actual human health risk from range fires.

  4. Contamination source review for Building E5032, Edgewood Area, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Booher, M.N.; O`Reilly, D.P.; Smits, M.P.

    1995-09-01

    This report by Argonne National Laboratory (ANL) documents results of a contamination source review of Building E5032 at the Aberdeen Proving Ground (APG) in Maryland. The review included a historical records search, physical inspection, photographic documentation, geophysical investigation, and review of available records regarding underground storage tanks associated with Building E5032. The field investigations were performed by ANL during 1994 and 1995. Building E5032 (APG designation), originally known as Building 99, is located at the northwest comer of the intersection of Hoadley Road and Magnolia Road in the Edgewood Area of APG. It was constructed during World War I as an incendiary bomb filling plant and in 1920s and 1930s maintained as a filling facility. During World War II the building was a pilot plant for the development of a dry white phosphorus filling process. Since then the building has been used for white phosphorus filling pilot studies. Most of the dry filling methods were developed in Building E5032 between 1965 and 1970. Other filling operations in Building E5032 have included mustard during the period shortly after World War II and triethyl aluminum (TEA) during the late 1960s and early 1970s. During the World War II period, the building was connected to the sanitary sewer system with one large and at least one small interior sump. There are also seven sumps adjacent to the exterior of the building: two on the west elevation, four near the four bays on the south elevation, and one at the northeast corner of the building. All of these sumps are connected with the chemical sewer system and received most, if not all, of the production operation wastewater. The discharge from this system was released into the east branch of Canal Creek; the discharge pipe was located southeast of Building E5032. There are no records indicating the use of Building E5032 after 1974, and it is assumed that the building has been out of service since that time.

  5. Contamination source review for Building E3613, Edgewood Area, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Billmark, K.A.; Emken, M.E.; Muir-Ploense, K.L.

    1995-09-01

    This report was prepared by Argonne National Laboratory (ANL) to document the results of a contamination source review of Building E3613 at the Aberdeen Proving Ground (APG) in Maryland. The report may be used to assist the U.S. Army in planning for the future use or disposition of this building, The review included a historical records search, physical inspection, photographic documentation, geophysical investigation, and collection of air samples. The field investigations were performed by ANL during 1994 and 1995. Building E3613 (APG designation) is located in the Canal Creek Area of APG. The building was constructed in 1954 for use as a change house, office, and storage building in support of the white phosphorus smoke program. The building has not been used since 1988. During an inspection in 1988, asbestos was listed as the only potential contaminant. The physical inspection and photographic documentation of Building E3613 were completed in November 1994. At the time of the inspection, Building E3613 was inactive and in disrepair. The single-story, rectangular structure contains five rooms and measures 16 ft 2 in. by 32 ft. The building is wood frame construction with a gabled roof. The exterior walls and roof are constructed of wood covered with asphalt sheeting. The building rests on a concrete foundation. The interior walls are 6-in.-thick wood, and the ceiling is assumed to be white drywall nailed to a wooden frame. Overhead steam pipes supported by vertical pipes traverse the area. Two concrete footings for guy wires that support the overhead steam pipes are located north and west of the building. Four additional vertical pipes exit the ground east of the building.

  6. Geophysical survey at cluster 6, Westwood Area, US Army Aberdeen Proving Ground. Final report

    SciTech Connect

    Simms, J.E.; Harrelson, D.W.; Sharp, M.K.

    1995-05-01

    A geophysical investigation was conducted at Cluster 6 Site 5, located in Westwood Area of the U.S. Army Aberdeen Proving Ground. This site is the former Westwood Area Radioactive Material Disposal Facility (WRMDF) which was used for processing and packaging radioactive waste material prior to disposal. Original structures at the site included Building 3013 and adjacent concrete slabs where the waste handling work was performed, a small equipment shed, and a wastewater holding and drain system which included tanks in a concrete pit. Discharge of wastewater from the tanks was to Reardon Inlet, located a short distance south of the tank pit. Possible release of radioactive waste to the environment would have been due to either spillage, leakage, or discharge from the wastewater system. Two terra cotta pipelines, one on the western end and one of the eastern end, extended from Building 3013 to Reardon Inlet. The east pipeline handled low-level radioactive wastewater. The west pipeline was the original wastewater line and it is presumed that radioactive wastewater was not discharged through this line. After radioactive waste handling activities were discontinued at WRMDF, the west pipeline system was upgraded to include a septic tank, sand filter bed, and a chlorine contact chamber. The structures associated with the WRMDF were removed during the early 1970`s, including the concrete tank pit. Both pipelines are visible near the edge of Reardon inlet, suggesting that the pipes and related structures have not been removed. Geophysical surveys, including magnetics, electromagnetics (EM), and ground penetrating radar, were performed to identify the location of the two terra cotta pipes, septic tank, and sand filter bed.

  7. A deer study at Aberdeen Proving Ground: Project planning, data assimilation, and risk assessment

    SciTech Connect

    Whaley, J.; Leach, G.; Lee, R.

    1995-12-31

    For more than 75 years, Aberdeen Proving Ground (APG) has been in the business of research, development, and testing of munitions and military vehicles for the US Army. Currently, APG is on the National Priorities List and an installation wide human health risk assessment is underway. Like many Department of the Army facilities, APG has an active hunting program. Hunters harvest approximately 800 whitetail deer (Odocoileus virginanus) from APG annually. To assure public safety, the authors completed a study during the 1993 hunting season to identify any potential human health hazards associated with consumption of venison from APG. This paper will discuss the unique strategy behind the experimental design, the actual assimilation of the data, and the results of the human health risk assessment to establish an appropriate contaminant levels in APG deer. Also, based on information in the literature, the authors considered gender, age, and season in the study design. The list of chemicals for residue analysis included explosives, PCBs, organochlorine pesticides, and metals (As, Cd, Cr, Pb, Hg). Of the 150 deer sampled, metals were the only chemicals detected. The authors compared these data to metal levels in deer collected from an off post background site. Metal levels did not differ significantly between APG deer and off post deer. Finally, the authors completed a health risk assessment of eating deer harvested from both APG and off post. From a survey distributed to the hunters, they incorporated actual consumption data into the exposure assessment. Their findings concluded that the risk of eating APG deer was no higher than eating off post deer; however, total arsenic levels in muscle did appear to elevate the risk.

  8. Investigation of soil contamination at the Riot Control Burning Pit area in J-Field, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Wang, Ying-Ya; Yuen, C.R.; Martino, L.

    1996-05-01

    A remedial investigation was conducted to identify soil contamination in the Riot Control Burning Pit area in J-field, Aberdeen Proving Ground, Maryland. The investigation included geophysical surveys to delineate the filled section of the pit, soil-gas surveys to locate the organic contamination area, field X-ray fluorescence measurements along the burning pit to identify the major metal contamination, and surface and subsurface soil analyses to investigate the nature and extent of contamination. This paper presents the results of this investigation

  9. Hydrogeologic, soil, and water-quality data for j-field, Aberdeen Proving Ground, Maryland, 1989-94

    USGS Publications Warehouse

    Phelan, D.J.

    1996-01-01

    Disposal of chemical-warfare agents, munitions, and industrial chemicals in J-Field, Aberdeen Proving Ground, Maryland, has resulted in ground-water, surface-water, and soil contamination. This report presents data collected by the U.S. Geological Survey from Novembr 1989 through September 1994 as part of a remedial investigation of J-Field in response to the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Hydrogeologic data, soil-gas and soil-quality data, and water-qualtiy data are included.

  10. Toxicity of sediments surrounding the Gunpowder Neck Superfund Site at Aberdeen Proving Ground, Maryland. Final report, August 1992-December 1993

    SciTech Connect

    Haley, M.V.; Anthony, J.S.; Chester, N.A.; Kurnas, C.W.

    1995-07-01

    From the late 1940s through the 1960s, the standard practice for disposing of toxic chemicals at Aberdeen Proving Ground, MD, was open burning. This disposal site has since been placed on the National Priority List (NPt) by U.S. Environmental Protection Agency. In the spring 1992, sediment samples were taken from waterways that surround that disposal area. Chemical analysis and sediment toxicity assays (Ampelisca abdita) were conducted. Toxicity comparison, with sediment leachate from an Adapted Toxicity Characteristic teaching Procedure (ATCLP), were made using Daphnia magna and a fluorescent bacterium Photobacterium phosphoreum in MICROTOX assays. Amphipods showed a wide range of mortality in mud as well as coarser sediments indicating substrate preference is not critical to the outcome of the assay. Toxicity results from the leachates showed the sediments were not toxic to daphnia and MICROTOX assays.

  11. Ground-water flow and the potential effects of remediation at Graces Quarters, Aberdeen Proving Ground, Maryland

    USGS Publications Warehouse

    Tenbus, F.J.; Fleck, W.B.

    1996-01-01

    Ground water in the east-central part of Graces Quarters, a former open-air chemical-agent test facility at Aberdeen Proving Ground, Maryland, is contaminated with chlorinated volatile organic compounds. The U.S. Geological Survey's finite- difference model was used to help understand ground-water flow and simulate the effects of alternative remedial actions to clean up the ground water. Scenarios to simulate unstressed conditions and three extraction well con- figurations were used to compare alternative remedial actions on the contaminant plume. The scenarios indicate that contaminants could migrate from their present location to wetland areas within 10 years under unstressed conditions. Pumping 7 gal/min (gallons per minute) from one well upgradient of the plume will not result in containment or removal of the highest contaminant concentrations. Pumping 7 gal/min from three wells along the central axis of the plume should result in containment and removal of dissolved contami- nants, as should pumping 7 gal/min from three wells at the leading edge of the plume while injecting 7 gal/min back into an upgradient well.

  12. An optimized groundwater extraction system for the toxic burning pits area of J-Field, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Quinn, J.J.; Johnson, R.L.; Patton, T.L.; Martino, L.E.

    1996-06-01

    Testing and disposal of chemical warfare agents, munitions, and industrial chemicals at the J-Field area of the Aberdeen Proving Ground (APG) have resulted in contamination of soil and groundwater. The discharge of contaminated groundwater to on-site marshes and adjacent estuaries poses a potential risk to ecological receptors. The Toxic Burning Pits (TBP) area is of special concern because of its disposal history. This report describes a groundwater modeling study conducted at J-Field that focused on the TBP area. The goal of this modeling effort was optimization of the groundwater extraction system at the TBP area by applying linear programming techniques. Initially, the flow field in the J-Field vicinity was characterized with a three-dimensional model that uses existing data and several numerical techniques. A user-specified border was set near the marsh and used as a constraint boundary in two modeled remediation scenarios: containment of the groundwater and containment of groundwater with an impermeable cap installed over the TBP area. In both cases, the objective was to extract the minimum amount of water necessary while satisfying the constraints. The smallest number of wells necessary was then determined for each case. This optimization approach provided two benefits: cost savings, in that the water to be treated and the well installation costs were minimized, and minimization of remediation impacts on the ecology of the marsh.

  13. Thermal energy supply optimization for aberdeen proving ground - edgewood area. Distribution system condition assessment and recommendations. Final report

    SciTech Connect

    VanBlaricum, V.L.; Marsh, C.P.; Hock, V.F.

    1995-05-01

    This report documents the results of a study by the U.S. Army Construction Engineering Research Laboratories to assess the condition of the steam heat distribution system at Aberdeen Proving Ground (APG)-Edgewood Area (EA), MD. This report documents the portion of the study that addressed widespread corrosion and deterioration existing throughout the aging system. A physical inventory of the steam distribution system piping and manholes was conducted. A visual condition assessment of a significant portion of the system was performed. Factors that impact the deterioration of the system were assessed, including soil chemistry, cathodic protection, and chemistry of the products conveyed by the system. The authors developed a detailed set of recommendations that includes (1) replacement or rehabilitation of severely deteriorated, unsafe or improperly functioning components. (2) implementation of an effective ongoing maintenance program tailored to the specific corrosion and deterioration problems at APG-EA, and (3) recommendations to ensure that new construction is performed in accordance with current Army standards and guidance.

  14. Temporal and vertical variation of hydraulic head in aquifers in the Edgewood area, Aberdeen Proving Ground, Maryland

    USGS Publications Warehouse

    Donnelly, Colleen A.; Tenbus, Fredrick J.

    1998-01-01

    Water-level data and interpretations from previous hydrogeological studies conducted by the U.S. Geological Survey in the Edgewood Area of Aberdeen Proving Ground (APG), Maryland, were compared to determine similarities and differences among the aquifers. Because the sediments that comprise the shallow aquifers are discontinuous, the shallow ground-water-flow systems are local rather than extensive across the Edgewood Area. Hydrogeologic cross sections, hydrographs of water levels, and vertical gradients calculated from previous studies in the Canal Creek area, Graces Quarters, the O-Field area, Carroll Island, and the J-Field area, over periods of record ranging from 1 to 10 years during 1986-97, were used to determine recharge and discharge areas, connections between aquifers, and hydrologic responses of aquifers to natural and anthropogenic stress. Each of the aquifers in the study areas exhibited variation of hydraulic head that was attributed to seasonal changes in recharge. Upward hydraulic gradients and seasonal reversals of vertical hydraulic gradients between aquifers indicate the potential for local ground-water discharge from most of the aquifers that were studied in the Edgewood Area. Hydraulic head in individual aquifers in Graces Quarters and Carroll Island responded to offsite pumping during part of the period of record. Hydraulic head in most of the confined aquifers responded to tidal loading effects from nearby estuaries.

  15. Environmental geophysics of the Pilot Plant on the west branch of Canal Creek, Aberdeen Proving Ground, Maryland

    SciTech Connect

    McGinnis, L.D.; Miller, S.F.; Daudt, C.R.; Thompson, M.D.; Borden, H.; Benson, M.; Wrobel, J.

    1994-05-01

    Plans to demolish and remediate the Pilot Plant complex in the Edgewood Area of Aberdeen Proving Ground have served to initiate a series of nonintrusive, environmental-geophysical studies. The studies are assisting in the location and identification of pipes, tanks, trenches, and liquid waste in the subsurface. Multiple databases have been integrated to provide support for detection of underground utilities and to determine the stratigraphy and lithology of the subsurface. The studies were conducted within the double security fence and exterior to the double fence, down gradient toward the west branch of Canal Creek. To determine if contaminants found in the creek were associated with the Pilot Plant, both the east and west banks were included in the study area. Magnetic, conductivity, inductive emf, and ground-penetrating-radar anomalies outline buried pipes, trenches, and various pieces of hardware associated with building activities. Ground-penetrating-radar imagery also defines a paleovalley cut 30 ft into Potomac Group sediments of Cretaceous age. The paleovalley crosses the site between Building E5654 and the Pilot Plant fence. The valley is environmentally significant because it may control the pathways of contaminants. The Pilot Plant complex was used to manufacture CC2 Impregnite and incapacitating agents; it also served as a production facility for nerve agents.

  16. Long-term fate of depleted uranium at Aberdeen and Yuma Proving Grounds: Human health and ecological risk assessments

    SciTech Connect

    Ebinger, M.H.; Beckman, R.J.; Myers, O.B.; Kennedy, P.L.; Clements, W.; Bestgen, H.T.

    1996-09-01

    The purpose of this study was to evaluate the immediate and long-term consequences of depleted uranium (DU) in the environment at Aberdeen Proving Ground (APG) and Yuma Proving Ground (YPG) for the Test and Evaluation Command (TECOM) of the US Army. Specifically, we examined the potential for adverse radiological and toxicological effects to humans and ecosystems caused by exposure to DU at both installations. We developed contaminant transport models of aquatic and terrestrial ecosystems at APG and terrestrial ecosystems at YPG to assess potential adverse effects from DU exposure. Sensitivity and uncertainty analyses of the initial models showed the portions of the models that most influenced predicted DU concentrations, and the results of the sensitivity analyses were fundamental tools in designing field sampling campaigns at both installations. Results of uranium (U) isotope analyses of field samples provided data to evaluate the source of U in the environment and the toxicological and radiological doses to different ecosystem components and to humans. Probabilistic doses were estimated from the field data, and DU was identified in several components of the food chain at APG and YPG. Dose estimates from APG data indicated that U or DU uptake was insufficient to cause adverse toxicological or radiological effects. Dose estimates from YPG data indicated that U or DU uptake is insufficient to cause radiological effects in ecosystem components or in humans, but toxicological effects in small mammals (e.g., kangaroo rats and pocket mice) may occur from U or DU ingestion. The results of this study were used to modify environmental radiation monitoring plans at APG and YPG to ensure collection of adequate data for ongoing ecological and human health risk assessments.

  17. Work plan for focused feasibility study of the toxic burning pits area at J-Field, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Biang, C.; Benioff, P.; Martino, L.; Patton, T.

    1995-03-01

    The Environmental Management Division (EMD) of Aberdeen Proving Ground (APG), Maryland, is conducting a remedial investigation and feasibility study (RI/FS) of the J-Field area at APG pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act, as amended (CERCIA). J-Field is within the Edgewood Area of APG in Harford County, Maryland. Since World War II, activities in the Edgewood Area have included the development, manufacture, testing, and destruction of chemical agents and munitions. These materials were destroyed at J-Field by open burning and open detonation (OB/OD). Considerable archival information about J-Field exists as a result of efforts by APG staff to characterize the hazards associated with the site. Contamination of J-Field was first detected during an environmental survey of the Edgewood Area conducted in 1977 and 1978 by the US Army Toxic and Hazardous Materials Agency (USATHAMA)(predecessor to the US Army Environmental Center). As part of a subsequent USATHAMA environmental survey, 11 wells were installed and sampled at J-Field. Contamination at J-Field was also detected during a munitions disposal survey conducted by Princeton Aqua Science in 1983. The Princeton Aqua Science investigation involved the installation and sampling of nine wells and the collection and analysis of surficial and deep composite soil samples. In 1986, a Resource Conservation and Recovery Act (RCRA) permit (MD3-21-0021355) requiring a basewide RCRA Facility Assessment (RFA) and a hydrogeologic assessment of J-Field was issued by the US Environmental Protection Agency (EPA). In 1987, the US Geological Survey (USGS) began a two-phased hydrogeologic assessment in which data were collected to model groundwater flow at J-Field. Soil gas investigations were conducted, several well clusters were installed, a groundwater flow model was developed, and groundwater and surface water monitoring programs were established that continue today-

  18. Collecting single and multichannel seismic-reflection data in shallow water near Aberdeen Proving Ground, Chesapeake Bay, Maryland

    SciTech Connect

    Haeni, F.P.; Banks, W.L.; Versteeg, R.J.

    1995-12-31

    In August and September 1994, single- and multi-channel seismic-reflection data were collected by the U.S. Geological Survey (USGS), in cooperation with the U.S. Army and the U.S. Army Corps of Engineers (COE), to support a regional hydrogeologic framework study at Aberdeen Proving Ground (APG), Maryland. Data were collected in Chesapeake Bay, as well as in the Bush, Gunpowder, and Sassafras Rivers, which are tributaries to Chesapeake Bay. Data were collected along the shoreline in very shallow water, usually less than 1 m. Approximately 100 km of single-channel seismic-reflection data were collected using a water gun and an electromechanical plate as sound sources; about 50 percent of these data contained usable geologic information. A prominent channel in the Quaternary sediments at a depth of 61 m is clearly evident, and the depth to bedrock ranges from approximately 184 to 223 m. Approximately 14 km of multi-channel data were collected in the Gunpowder and Bush Rivers and in Chesapeake Bay; about 40 percent of these data showed subsurface reflectors, often in small, discontinuous segments. Data were processed using established processing techniques. Numerous reflectors were present in the data that were continuous over long distances. The multi-channel data contained more detail and significantly less noise than the single-channel data. The quality and continuity of the single- and multi-channel data were best in shallow water (less than 1 m) where the presence of gassing organic sediments was at a minimum.

  19. Ground-water flow and the possible effects of remedial actions at J-Field, Aberdeen Proving Ground, Maryland

    USGS Publications Warehouse

    Hughes, W.B.

    1995-01-01

    J-Field, located in the Edgewood Area of Aberdeen Proving Ground, Md, has been used since World War II to test and dispose of explosives, chemical warfare agents, and industrial chemicals resulting in ground-water, surface-water, and soil contami- nation. The U.S. Geological Survey finite-difference model was used to better understand ground-water flow at the site and to simulate the effects of remedial actions. A surficial aquifer and a confined aquifer were simulated with the model. A confining unit separates these units and is represented by leakance between the layers. The area modeled is 3.65 mi2; the model was constructed with a variably spaced 40 X 38 grid. The horizontal and lower boundaries of the model are all no-flow boundaries. Steady-state conditions were used. Ground water at the areas under investigation flows from disposal pit areas toward discharge areas in adjacent estuaries or wetlands. Simulations indicate that capping disposal areas with an impermeable cover effectively slows advective ground water flow by 0.7 to 0.5 times. Barriers to lateral ground-water flow were simulated and effectively prevented the movement of ground water toward discharge areas. Extraction wells were simulated as a way to contain ground-water contamination and to extract ground water for treatment. Two wells pumping 5 gallons per minute each at the toxic-materials disposal area and a single well pumping 2.5 gallons per minute at the riot-control-agent disposal area effectively contained contamination at these sites. A combi- nation of barriers to horizontal flow east and south of the toxic-materials disposal area, and a single extraction well pumping at 5 gallons per minute can extract contaminated ground water and prevent pumpage of marsh water.

  20. Hydrogeologic setting, hydraulic properties, and ground-water flow at the O-Field area of Aberdeen Proving Ground, Maryland

    USGS Publications Warehouse

    Banks, W.S.; Smith, B.S.; Donnelly, C.A.

    1996-01-01

    The U.S. Army disposed chemical agents, laboratory materials, and unexploded ordnance at O-Field in the Edgewood area of Aberdeen Proving Ground, Maryland, from before World War II until at least the 1950's. Soil, ground water, surface water,and wetland sediments in the O-Field area were contaminated from the disposal activity. A ground-water-flow model of the O-Field area was constructed by the U.S. Geological Survey (USGS) in 1989 to simulate flow in the central and southern part of the Gunpowder Neck. The USGS began an additional study of the contamination in the O-Field area in cooperation with the U.S. Army in 1990 to (1) further define the hydrogeologic framework of the O-Field area, (2) characterize the hydraulic properties of the aquifers and confining units, and (3) define ground-water flow paths at O-Field based on the current data and simulations of ground-water flow. A water-table aquifer, an upper confining unit, and an upper confined aquifer comprise the shallow ground-water aquifer system of the O-Field area. A lower confining unit, through which ground-water movement is negligible, is considered a lower boundary to the shallow aquifer system. These units are all part of the Pleistocene Talbot Formation. The model developed in the previous study was redesigned using the data collected during this study and emphasized New O-Field. The current steady-state model was calibrated to water levels of June 1993. The rate of ground-water flow calculated by the model was approximately 0.48 feet per day (ft/d) and the rate determined from chlorofluorocarbon dates was approximately 0.39 ft/d.

  1. Assessment of volatile organic compounds in surface water at West Branch Canal Creek, Aberdeen Proving Ground, Maryland, 1999

    USGS Publications Warehouse

    Olsen, Lisa D.; Spencer, Tracey A.

    2000-01-01

    The U.S. Geological Survey (USGS) collected 13 surface-water samples and 3 replicates from 5 sites in the West Branch Canal Creek area at Aberdeen Proving Ground from February through August 1999, as a part of an investigation of ground-water contamination and natural attenuation processes. The samples were analyzed for volatile organic compounds, including trichloroethylene, 1,1,2,2-tetrachloroethane, carbon tetrachloride, and chloroform, which are the four major contaminants that were detected in ground water in the Canal Creek area in earlier USGS studies. Field blanks were collected during the sampling period to assess sample bias. Field replicates were used to assess sample variability, which was expressed as relative percent difference. The mean variability of the surface-water replicate analyses was larger (35.4 percent) than the mean variability of ground-water replicate analyses (14.6 percent) determined for West Branch Canal Creek from 1995 through 1996. The higher variability in surface-water analyses is probably due to heterogeneities in the composition of the surface water rather than differences in sampling or analytical procedures. The most frequently detected volatile organic compound was 1,1,2,2- tetrachloroethane, which was detected in every sample and in two of the replicates. The surface-water contamination is likely the result of cross-media transfer of contaminants from the ground water and sediments along the West Branch Canal Creek. The full extent of surface-water contamination in West Branch Canal Creek and the locations of probable contaminant sources cannot be determined from this limited set of data. Tidal mixing, creek flow patterns, and potential effects of a drought that occurred during the sampling period also complicate the evaluation of surface-water contamination.

  2. Remedial investigation sampling and analysis plan for J-Field, Aberdeen Proving Ground, Maryland. Volume 1: Field Sampling Plan

    SciTech Connect

    Benioff, P.; Biang, R.; Dolak, D.; Dunn, C.; Martino, L.; Patton, T.; Wang, Y.; Yuen, C.

    1995-03-01

    The Environmental Management Division (EMD) of Aberdeen Proving Ground (APG), Maryland, is conducting a remedial investigation and feasibility study (RI/FS) of the J-Field area at APG pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. J-Field is within the Edgewood Area of APG in Harford County, Maryland (Figure 1. 1). Since World War II activities in the Edgewood Area have included the development, manufacture, testing, and destruction of chemical agents and munitions. These materials were destroyed at J-Field by open burning and open detonation (OB/OD). Considerable archival information about J-Field exists as a result of efforts by APG staff to characterize the hazards associated with the site. Contamination of J-Field was first detected during an environmental survey of the Edgewood Area conducted in 1977 and 1978 by the US Army Toxic and Hazardous Materials Agency (USATHAMA) (predecessor to the US Army Environmental Center [AEC]). As part of a subsequent USATHAMA -environmental survey, 11 wells were installed and sampled at J-Field. Contamination at J-Field was also detected during a munitions disposal survey conducted by Princeton Aqua Science in 1983. The Princeton Aqua Science investigation involved the installation and sampling of nine wells and the collection and analysis of surficial and deep composite soil samples. In 1986, a Resource Conservation and Recovery Act (RCRA) permit (MD3-21-002-1355) requiring a basewide RCRA Facility Assessment (RFA) and a hydrogeologic assessment of J-Field was issued by the US Environmental Protection Agency (EPA). In 1987, the US Geological Survey (USGS) began a two-phased hydrogeologic assessment in data were collected to model, groundwater flow at J-Field. Soil gas investigations were conducted, several well clusters were installed, a groundwater flow model was developed, and groundwater and surface water monitoring programs were established that continue today.

  3. Optimization of ground-water withdrawal at the old O-Field area, Aberdeen Proving Ground, Maryland

    USGS Publications Warehouse

    Banks, William S.L.; Dillow, Jonathan J.A.

    2001-01-01

    The U.S. Army disposed of chemical agents, laboratory materials, and unexploded ordnance at the Old O-Field landfill at Aberdeen Proving Ground, Maryland, beginning prior to World War II and continuing until at least the 1950?s. Soil, ground water, surface water, and wetland sediments in the Old O-Field area were contaminated by the disposal of these materials. The site is in the Atlantic Coastal Plain, and is characterized by a complex series of Pleistocene and Holocene sediments formed in various fluvial, estuarine, and marine-marginal hydrogeologic environments. A previously constructed transient finite-difference ground-water-flow model was used to simulate ground-water flow and the effects of a pump-and-treat remediation system designed to prevent contaminated ground water from flowing into Watson Creek (a tidal estuary and a tributary to the Gunpowder River). The remediation system consists of 14 extraction wells located between the Old O-Field landfill and Watson Creek.Linear programming techniques were applied to the results of the flow-model simulations to identify optimal pumping strategies for the remediation system. The optimal management objective is to minimize total withdrawal from the water-table aquifer, while adhering to the following constraints: (1) ground-water flow from the landfill should be prevented from reaching Watson Creek, (2) no extraction pump should be operated at a rate that exceeds its capacity, and (3) no extraction pump should be operated at a rate below its minimum capacity, the minimum rate at which an Old O-Field pump can function. Water withdrawal is minimized by varying the rate and frequency of pumping at each of the 14 extraction wells over time. This minimizes the costs of both pumping and water treatment, thus providing the least-cost remediation alternative while simultaneously meeting all operating constraints.The optimal strategy identified using this objective and constraint set involved operating 13 of the 14

  4. Simulation of ground-water flow and transport of chlorinated hydrocarbons at Graces Quarters, Aberdeen Proving Ground, Maryland

    USGS Publications Warehouse

    Tenbus, Frederick J.; Fleck, William B.

    2001-01-01

    Military activity at Graces Quarters, a former open-air chemical-agent facility at Aberdeen Proving Ground, Maryland, has resulted in ground-water contamination by chlorinated hydrocarbons. As part of a ground-water remediation feasibility study, a three-dimensional model was constructed to simulate transport of four chlorinated hydrocarbons (1,1,2,2-tetrachloroethane, trichloroethene, carbon tetrachloride, and chloroform) that are components of a contaminant plume in the surficial and middle aquifers underlying the east-central part of Graces Quarters. The model was calibrated to steady-state hydraulic head at 58 observation wells and to the concentration of 1,1,2,2-tetrachloroethane in 58 observation wells and 101direct-push probe samples from the mid-1990s. Simulations using the same basic model with minor adjustments were then run for each of the other plume constituents. The error statistics between the simulated and measured concentrations of each of the constituents compared favorably to the error statisticst,1,2,2-tetrachloroethane calibration. Model simulations were used in conjunction with contaminant concentration data to examine the sources and degradation of the plume constituents. It was determined from this that mixed contaminant sources with no ambient degradation was the best approach for simulating multi-species solute transport at the site. Forward simulations were run to show potential solute transport 30 years and 100 years into the future with and without source removal. Although forward simulations are subject to uncertainty, they can be useful for illustrating various aspects of the conceptual model and its implementation. The forward simulation with no source removal indicates that contaminants would spread throughout various parts of the surficial and middle aquifers, with the100-year simulation showing potential discharge areas in either the marshes at the end of the Graces Quarters peninsula or just offshore in the estuaries. The

  5. Inorganic and organic ground-water chemistry in the Canal Creek area of Aberdeen Proving Ground, Maryland

    USGS Publications Warehouse

    Lorah, M.M.; Vroblesky, D.A.

    1989-01-01

    Groundwater chemical data were collected from November 1986 through April 1987 in the first phase of a 5-year study to assess the possibility of groundwater contamination in the Canal Creek area of Aberdeen Proving Ground, Maryland. Water samples were collected from 87 observation wells screened in Coastal Plain sediments; 59 samples were collected from the Canal Creek aquifer, 18 from the overlying surficial aquifer, and 10 from the lower confined aquifer. Dissolved solids, chloride, iron, manganese, fluoride, mercury, and chromium are present in concentrations that exceed the Federal maximum contaminant levels for drinking water. Elevated chloride and dissolved-solids concentrations appear to be related from contaminant plumes but also could result from brackish-water intrusion. Excessive concentrations of iron and manganese were the most extensive water quality problems found among the inorganic constituents and are derived from natural dissolution of minerals and oxide coatings in the aquifer sediments. Volatile organic compounds are present in the Canal Creek and surficial aquifers, but samples from the lower confined aquifer do not show any evidence of contamination by inorganic or organic chemicals. The volatile organic contaminants detected in the groundwater and their maximum concentrations (in micrograms/L) include 1,1,2,2- tetrachloroethane (9,000); carbon tetrachloride (480); chloroform (460); 1,1,2-trichloroethane (80); 1,2-dichloroethane (990); 1,1-dichloroethane (3.1); tetrachloroethylene (100); trichloroethylene (1,800); 1,2-trans- dichloroethylene (1,200); 1,1-dichloroethylene (4.4); vinyl chloride (140); benzene (70); and chlorobenzene (39). On the basis of information on past activities in the study area, some sources of the volatile organic compounds include: (1) decontaminants and degreasers; (2) clothing-impregnating operations; (3) the manufacture of impregnite material; (4) the manufacture of tear gas; and (5) fuels used in garages and at

  6. Installation restoration research program: Assessment of geophysical methods for subsurface geologic mapping, cluster 13, Edgewood Area, Aberdeen Proving Ground, Maryland. Final report

    SciTech Connect

    Butler, D.K.; Sharp, M.K.; Sjostrom, K.J.; Simms, J.E.; Llopis, J.L.

    1996-10-01

    Seismic refraction, electrical resistivity, and transient electromagnetic surveys were conducted at a portion of Cluster 13, Edgewood Area of Aberdeen Proving Ground, Maryland. Seismic refraction cross sections map the topsoil layer and the water table (saturated zone). The water table elevations from the seismic surveys correlate closely with water table elevations in nearby monitoring wells. Electrical resistivity cross sections reveal a very complicated distribution of sandy and clayey facies in the upper 10 - 15 m of the subsurface. A continuous surficial (topsoil) layer correlates with the surficial layer of the seismic section and nearby boring logs. The complexity and details of the electrical resistivity cross section correlate well with boring and geophysical logs from nearby wells. The transient electromagnetic surveys map the Pleistocene-Cretaceous boundary, the saprolite, and the top of the Precambrian crystalline rocks. Conducting the transient electromagnetic surveys on a grid pattern allows the construction of a three-dimensional representation of subsurface geology (as represented by variations of electrical resistivity). Thickness and depth of the saprolitic layer and depth to top of the Precambrian rocks are consistent with generalized geologic cross sections for the Edgewood Area and depths projected from reported depths at the Aberdeen Proving Ground NW boundary using regional dips.

  7. Biomonitoring and hazard assessment evaluation of contaminated groundwater at Aberdeen Proving Ground-Edgewood area Beach Point Penincula. Annual report, 31 July 1993-30 July 1994

    SciTech Connect

    Burton, D.T.; Herriott, R.S.; Turley, S.D.

    1994-08-30

    Contaminated groundwater, which contained multiple heavy metals and chlorinated aliphatic hydrocarbons, from the surficial aquifer (well CC-33B) at Beach Point located in the Canal Creek Area of the U.S. Army Aberdeen Proving Ground-Edgewood Area, Aberdeen, Maryland, was evaluated for toxicity and environmental hazard. Toxicity was detected at various groundwater concentrations by 7 of 9 biomonitoring systems. when estimated maximum acceptable toxicant concentrations (MATC) were established, the data for algae, invertebrates and fish suggested that the groundwater would not be harmful at a concentration of 10% groundwater by volume. Likewise, no genotoxicity (Ames and SEC assays), develop- mental toxicity (FETAX), or chronic histopathology (9-month fish test) occurred at 10% groundwater by volume. The groundwater was considered to be a potentially excessive hazardous material to the benthic biota of the Bush River when a number of conservative assumptions (contaminant distribution and discharge rate of the aquifer) were used in the hazard assessment. However, the potential water quality impacts were judged to be minimal if a mixing zone were to be granted by the State of Maryland which allows for local exceedences of water quality standards.

  8. Superfund Record of Decision (EPA Region 3): USA Aberdeen Proving Ground, Edgewood, MD. (First remedial action), September 1991

    SciTech Connect

    Not Available

    1991-09-27

    The 17,000-acre USA Aberdeen - Edgewood site is a military ordnance installation in Edgewood, Maryland. The 4.5-acre Old O-Field site, which is the focus of the Record of Decision (ROD), is a fenced hazardous waste and ordnance disposal area. From 1949 to the mid-1970's, several decontamination and clean-up operations were conducted as a result of munitions explosions. These operations included the application of 1,000 barrels of decontaminating agent non-corrosive containing chlorinated hydrocarbons; soaking the field with several hundred gallons of fuel oil and setting the field ablaze; dispersing lime into the surrounding trees to further reduce the amount of mustard present; and using supertropical bleach, lime, and sodium hydroxide to destroy chemical agents. The ROD provides an interim remedy for contaminated ground water and its effect on surface water. The primary contaminants of concern affecting the ground water are VOCs including benzene, PCE, TCE, and toluene; and metals including arsenic. The selected remedial action for this interim remedy includes installing a downgradient extraction well network; and pumping and onsite treatment of contaminated ground water using chemical precipitation.

  9. Focused feasibility study for surface soil at the main pits and pushout area, J-field toxic burning pits area, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Patton, T.; Benioff, P.; Biang, C.; Butler, J.

    1996-06-01

    The Environmental Management Division of Aberdeen Proving Ground (APG), Maryland, is conducting a remedial investigation and feasibility study of the J-Field area at APG pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act, as amended (CERCLA). J-Field is located within the Edgewood Area of APG in Harford County, Maryland. Since World War II, activities in the Edgewood Area have included the development, manufacture, testing, and destruction of chemical agents and munitions. These materials were destroyed at J-Field by open burning/open detonation. Portions of J-Field continue to be used for the detonation and disposal of unexploded ordnance (UXO) by open burning/open detonation under authority of the Resource Conservation and Recovery Act.

  10. Chemical-Stockpile Disposal Program. Evaluation of multiple-incinerator air-quality impacts, Edgewood Area, Aberdeen Proving Ground. Final report, November 1986-May 1987

    SciTech Connect

    Not Available

    1987-05-01

    The purpose of this study was to examine the long-term additive ambient impact of certain toxic air pollutants that will potentially be emitted from the Chemical Agent Incinerator (AI) proposed for the Edgewood Area (EA) of Aberdeen Proving Ground (APG), Maryland and from three additional planned or existing incinerators also located on the EA. This impact was determined in consideration of the existence and operation of three additional planned or existing incinerators also located on EA. Based on air-dispersion modeling conducted as part of an original analysis, emissions were estimated of chlorinated organics from the U.S. Army Medical Research Institute for Chemical Research, Development and Engineering Center Decontamination/Detoxification Municipal Waste Incinerator (MWI), for downwind distances as great as the distance to the nearest boundary of the EA. Consequently, for this evaluation, only the MWI is considered to emit chlorinated organics.

  11. Preliminary assessment of microbial communities and biodegradation of chlorinated volatile organic compounds in wetlands at Cluster 13, Lauderick Creek area, Aberdeen Proving Ground, Maryland

    USGS Publications Warehouse

    Lorah, Michelle M.; Voytek, Mary A.; Spencer, Tracey A.

    2003-01-01

    A preliminary assessment of the microbial communities and biodegradation processes for chlorinated volatile organic compounds was con-ducted by the U.S. Geological Survey in wetlands at the Cluster 13, Lauderick Creek area at Aberdeen Proving Ground, Maryland. The U.S. Geological Survey collected wetland sediment samples from 11 sites in the Lauderick Creek area for microbial analyses, and used existing data to evaluate biodegradation processes and rates. The bacterial and methanogen communities in the Lauderick Creek wetland sediments were similar to those observed in a previous U.S. Geological Survey study at the West Branch Canal Creek wet-land area, Aberdeen Proving Ground. Evaluation of the degradation rate of 1,1,2,2-tetrachloroethane and the daughter compounds produced also showed similar results for the two wetlands. How-ever, a vertical profile of contaminant concentra-tions in the wetlands was available at only one site in the Lauderick Creek area, and flow velocities in the wetland sediment are unknown. To better evaluate natural attenuation processes and rates in the wetland sediments at Lauderick Creek, chemi-cal and hydrologic measurements are needed along ground-water flowpaths in the wetland at additional sites and during different seasons. Nat-ural attenuation in the wetlands, enhanced biore-mediation, and constructed wetlands could be feasible remediation methods for the chlorinated volatile organic compounds discharging in the Lauderick Creek area. The similarities in the microbial communities and biodegradation pro-cesses at the Lauderick Creek and West Branch Canal Creek areas indicate that enhanced bioreme-diation techniques currently being developed for the West Branch Canal Creek wetland area would be transferable to this area.

  12. Modeling exposure to depleted uranium in support of decommissioning at Jefferson Proving Ground, Indiana

    SciTech Connect

    Ebinger, M.H.; Oxenburg, T.P.

    1997-02-01

    Jefferson Proving Ground was used by the US Army Test and Evaluation Command for testing of depleted uranium munitions and closed in 1995 under the Base Realignment and Closure Act. As part of the closure of JPG, assessments of potential adverse health effects to humans and the ecosystem were conducted. This paper integrates recent information obtained from site characterization surveys at JPG with environmental monitoring data collected from 1983 through 1994 during DU testing. Three exposure scenarios were evaluated for potential adverse effects to human health: an occasional use scenario and two farming scenarios. Human exposure was minimal from occasional use, but significant risk were predicted from the farming scenarios when contaminated groundwater was used by site occupants. The human health risk assessments do not consider the significant risk posed by accidents with unexploded ordnance. Exposures of white-tailed deer to DU were also estimated in this study, and exposure rates result in no significant increase in either toxicological or radiological risks. The results of this study indicate that remediation of the DU impact area would not substantially reduce already low risks to humans and the ecosystem, and that managed access to JPG is a reasonable model for future land use options.

  13. New and improved methods for monitoring air quality and the terrestrial environment: Applications at Aberdeen Proving Ground-Edgewood area. Annual report, 1 April--14 November 1997

    SciTech Connect

    Bromenshenk, J.J.; Smith, G.C.

    1998-03-01

    Honey bees (Apis mellifera L.) have been shown to be multi-media monitors of chemical exposures and resultant effects. This five-year project has developed an automated system to assess in real-time colony behavioral responses to stressors, both anthropogenic and natural, including inclement weather. Field trials at the Aberdeen Proving Ground-Edgewood included the Old O Field and J field landfills, the Canal Creek and Bush River areas, and a Churchville, MD reference site. Preliminary results show varying concentrations of bioavailable inorganic elements and chlorinated hydrocarbons in bee colonies from all Maryland sites. Industrial solvents in the air inside beehives exhibited the greatest between site differences, with the highest levels occurring in hives near landfills at Old O Field, J Field, and at some sites in the Bush River and Canal Creek areas. Compared to 1996, the 1997 levels of solvents in Old O Field hives decreased by an order of magnitude, and colony performance significantly improved, probably as a consequence of capping the landfill. Recent chemical monitoring accomplishments include development of a new apparatus to quantitatively calibrate TD/GC/MS analysis, a QA/QC assessment of factors that limit the precision of these analyses, and confirmation of transport of aqueous contaminants into the hive. Real-time effects monitoring advances include development of an extensive array of software tools for automated data display, inspection, and numerical analysis and the ability to deliver data from remote locations in real time through Internet or Intranet connections.

  14. The use of innovative screening-level techniques for the bioassessment of estuarine sediments at U.S. Army Aberdeen Proving Ground, MD

    SciTech Connect

    Neubauer, R.J.; Thebeau, L.; Paul, J.

    1994-12-31

    The US Army Aberdeen Proving Ground (APG) is a primarily undeveloped installation on the upper Chesapeake bay in Maryland. The bush and Gunpowder Rivers are two sub-estuaries that run through the installation before emptying into the Chesapeake Bay. Past activities at EA APG include pilot-scale chemical agent manufacturing, munitions testing, smoke/incendiary manufacturing, domestic and rubble landfilling, and disposal of chemical warfare agents as well as other materials. It was determined that if contamination of the Gunpowder River exists from these previous activities on EA APG it was most likely to be found in the sediments. The initial phase was to conduct a sediment survey of the river to determine the spatial distribution of sediment types and the suitability of the benthos for the proposed methodologies. The second phase was to combine innovative screening-level investigative methodologies as well as sediment chemical and physical analyses into one survey of the benthos and sediments of the Gunpowder River. This phase used the Microtox luminescent bioassay and Daphnia magna IQ Toxicity Test, Surface and Profile Image (SPI) photography, analysis of sediment physical characteristics, and limited chemical analysis to identify locations that warrant a more focused investigation.

  15. Lithologic and ground-water-quality data collected using Hoverprobe drilling techniques at the West Branch Canal Creek wetland, Aberdeen Proving Ground, Maryland, April-May 2000

    USGS Publications Warehouse

    Phelan, Daniel J.; Senus, Michael P.; Olsen, Lisa D.

    2001-01-01

    This report presents lithologic and groundwater- quality data collected during April and May 2000 in the remote areas of the tidal wetland of West Branch Canal Creek, Aberdeen Proving Ground, Maryland. Contamination of the Canal Creek aquifer with volatile organic compounds has been documented in previous investigations of the area. This study was conducted to investigate areas that were previously inaccessible because of deep mud and shallow water, and to support ongoing investigations of the fate and transport of volatile organic compounds in the Canal Creek aquifer. A unique vibracore drill rig mounted on a hovercraft was used for drilling and groundwater sampling. Continuous cores of the wetland sediment and of the Canal Creek aquifer were collected at five sites. Attempts to sample ground water were made by use of a continuous profiler at 12 sites, without well installation, at a total of 81 depths within the aquifer. Of those 81 attempts, only 34 sampling depths produced enough water to collect samples. Ground-water samples from two sites had the highest concentrations of volatile organic compounds?with total volatile organic compound concentrations in the upper part of the aquifer ranging from about 15,000 to 50,000 micrograms per liter. Ground-water samples from five sites had much lower total volatile organic compound concentrations (95 to 2,100 micrograms per liter), whereas two sites were essentially not contaminated, with total volatile organic compound concentrations less than or equal to 5 micrograms per liter.

  16. Effect of Fe(III) on 1,1,2,2-Tetrachloroethane degradation and vinyl chloride accumulation in wetland sediments of the Aberdeen Proving Ground

    USGS Publications Warehouse

    Jones, Elizabeth; Voytek, Mary; Lorah, Michelle

    2004-01-01

    1,1,2,2-Tetrachloroethane (TeCA) contaminated groundwater at the Aberdeen Proving Ground discharges through an anaerobic wetland in West Branch Canal Creek (MD), where dechlorination occurs. Two microbially mediated pathways, dichloroelimination and hydrogenolysis, account for most of the TeCA degradation at this site. The dichloroelimination pathways lead to the formation of vinyl chloride (VC), a recalcitrant carcinogen of great concern. The goal of this investigation was to determine whether microbially-available Fe(III) in the wetland surface sediment influenced the fate of TeCA and its daughter products. Differences were identified in the TeCA degradation pathway between microcosms treated with amorphous ferric oxyhydroxide (AFO-treated) and untreated (no AFO) microcosms. TeCA degradation was accompanied by a lower accumulation of VC in AFO-treated microcosms than untreated microcosms. The microcosm incubations and subsequent experiments with the microcosm materials showed that AFO treatment resulted in lower production of VC by (1) shifting TeCA degradation from dichloroelimination pathways to production of a greater proportion of chlorinated ethane products, and (2) decreasing the microbial capability to produce VC from 1,2-dichloroethene (DCE). VC degradation was not stimulated in the presence of Fe(III). Rather, VC degradation occurred readily under methanogenic conditions and was inhibited under Fe(III)-reducing conditions.

  17. Effect of Fe(III) on 1,1,2,2-tetrachloroethane degradation and vinyl chloride accumulation in wetland sediments of the Aberdeen proving ground

    USGS Publications Warehouse

    Jones, E.J.P.; Voytek, M.A.; Lorah, M.M.

    2004-01-01

    1,1,2,2-Tetrachloroethane (TeCA) contaminated groundwater at the Aberdeen Proving Ground discharges through an anaerobic wetland in West Branch Canal Creek, MD, where dechlorination occurred. Two microbially mediated pathways, dichloroelimination and hydrogenolysis, account for most of the TeCA degradation at this site. The dichloroelimination pathways led to the formation of vinyl chloride (VC), a recalcitrant carcinogen of great concern. The effect of adding Fe(III) to TeCA-amended microcosms of wetland sediment was studied. Differences were identified in the TeCA degradation pathway between microcosms treated with amorphous ferric oxyhydroxide (AFO-treated) and untreated (no AFO) microcosms. TeCA degradation was accompanied by a lower accumulation of VC in AFO-treated microcosms than no AFO microcosms. The microcosm incubations and subsequent experiments with the microcosm materials showed that AFO treatment resulted in lower production of VC by shifting TeCA degradation from dichloroelimination pathways to production of a greater proportion of chlorinated ethane products, and decreasing the microbial capability to produce VC from 1,2-dichloroethylene. VC degradation was not stimulated in the presence of Fe(III). Rather, VC degradation occurred readily under methanogenic conditions and was inhibited under Fe(III)-reducing conditions.

  18. Contamination of ground water, surface water, and soil, and evaluation of selected ground-water pumping alternatives in the Canal Creek area of Aberdeen Proving Ground, Maryland

    USGS Publications Warehouse

    Lorah, Michelle M.; Clark, Jeffrey S.

    1996-01-01

    Chemical manufacturing, munitions filling, and other military-support activities have resulted in the contamination of ground water, surface water, and soil in the Canal Creek area of Aberdeen Proving Ground, Maryland. Chlorinated volatile organic compounds, including 1,1,2,2-tetrachloroethane and trichloroethylene, are widespread ground-water contaminants in two aquifers that are composed of unconsolidated sand and gravel. Distribution and fate of chlorinated organic compounds in the ground water has been affected by the movement and dissolution of solvents in their dense immiscible phase and by microbial degradation under anaerobic conditions. Detection of volatile organic contaminants in adjacent surface water indicates that shallow contaminated ground water discharges to surface water. Semivolatile organic compounds, especially polycyclic aromatic hydrocarbons, are the most prevalent organic contaminants in soils. Various trace elements, such as arsenic, cadmium, lead, and zinc, were found in elevated concentrations in ground water, surface water, and soil. Simulations with a ground-water-flow model and particle tracker postprocessor show that, without remedial pumpage, the contaminants will eventually migrate to Canal Creek and Gunpowder River. Simulations indicate that remedial pumpage of 2.0 million gallons per day from existing wells is needed to capture all particles originating in the contaminant plumes. Simulated pumpage from offsite wells screened in a lower confined aquifer does not affect the flow of contaminated ground water in the Canal Creek area.

  19. Long-term ground-water monitoring program and performance-evaluation plan for the extraction system at the former Nike Missile Battery Site, Aberdeen Proving Ground, Maryland

    USGS Publications Warehouse

    Senus, Michael P.; Tenbus, Frederick J.

    2000-01-01

    This report presents lithologic and ground-water-quality data collected during April and May 2000 in the remote areas of the tidal wetland of West Branch Canal Creek, Aberdeen Proving Ground, Maryland. Contamination of the Canal Creek aquifer with volatile organic compounds has been documented in previous investigations of the area. This study was conducted to investigate areas that were previously inaccessible because of deep mud and shallow water, and to support ongoing investigations of the fate and transport of volatile organic compounds in the Canal Creek aquifer. A unique vibracore drill rig mounted on a hovercraft was used for drilling and ground-water sampling. Continuous cores of the wetland sediment and of the Canal Creek aquifer were collected at five sites. Attempts to sample ground water were made by use of a continuous profiler at 12 sites, without well installation, at a total of 81 depths within the aquifer. Of those 81 attempts, only 34 sampling depths produced enough water to collect samples. Ground-water samples from two sites had the highest concentrations of volatile organic compounds?with total volatile organic compound concentrations in the upper part of the aquifer ranging from about 15,000 to 50,000 micrograms per liter. Ground-water samples from five sites had much lower total volatile organic compound concentrations (95 to 2,100 micrograms per liter), whereas two sites were essentially not contaminated, with total volatile organic compound concentrations less than or equal to 5 micrograms per liter.

  20. Characterization of Preferential Ground-Water Seepage From a Chlorinated Hydrocarbon-Contaminated Aquifer to West Branch Canal Creek, Aberdeen Proving Ground, Maryland, 2002-04

    USGS Publications Warehouse

    Majcher, Emily H.; Phelan, Daniel J.; Lorah, Michelle M.; McGinty, Angela L.

    2007-01-01

    Wetlands act as natural transition zones between ground water and surface water, characterized by the complex interdependency of hydrology, chemical and physical properties, and biotic effects. Although field and laboratory demonstrations have shown efficient natural attenuation processes in the non-seep wetland areas and stream bottom sediments of West Branch Canal Creek, chlorinated volatile organic compounds are present in a freshwater tidal creek at Aberdeen Proving Ground, Maryland. Volatile organic compound concentrations in surface water indicate that in some areas of the wetland, preferential flow paths or seeps allow transport of organic compounds from the contaminated sand aquifer to the overlying surface water without undergoing natural attenuation. From 2002 through 2004, the U.S. Geological Survey, in cooperation with the Environmental Conservation and Restoration Division of the U.S. Army Garrison, Aberdeen Proving Ground, characterized preferential ground-water seepage as part of an ongoing investigation of contaminant distribution and natural attenuation processes in wetlands at this site. Seep areas were discrete and spatially consistent during thermal infrared surveys in 2002, 2003, and 2004 throughout West Branch Canal Creek wetlands. In these seep areas, temperature measurements in shallow pore water and sediment more closely resembled those in ground water than those in nearby surface water. Generally, pore water in seep areas contaminated with chlorinated volatile organic compounds had lower methane and greater volatile organic compound concentrations than pore water in non-seep wetland sediments. The volatile organic compounds detected in shallow pore water in seeps were spatially similar to the dominant volatile organic compounds in the underlying Canal Creek aquifer, with both parent and anaerobic daughter compounds detected. Seep locations characterized as focused seeps contained the highest concentrations of chlorinated parent compounds

  1. Microbial Consortia Development and Microcosm and Column Experiments for Enhanced Bioremediation of Chlorinated Volatile Organic Compounds, West Branch Canal Creek Wetland Area, Aberdeen Proving Ground, Maryland

    USGS Publications Warehouse

    Lorah, Michelle M.; Majcher, Emily H.; Jones, Elizabeth J.; Voytek, Mary A.

    2008-01-01

    Chlorinated solvents, including 1,1,2,2-tetrachloroethane, tetrachloroethene, trichloroethene, carbon tetrachloride, and chloroform, are reaching land surface in localized areas of focused ground-water discharge (seeps) in a wetland and tidal creek in the West Branch Canal Creek area, Aberdeen Proving Ground, Maryland. In cooperation with the U.S. Army Garrison, Aberdeen Proving Ground, Maryland, the U.S. Geological Survey is developing enhanced bioremediation methods that simulate the natural anaerobic degradation that occurs without intervention in non-seep areas of the wetland. A combination of natural attenuation and enhanced bioremediation could provide a remedy for the discharging ground-water plumes that would minimize disturbance to the sensitive wetland ecosystem. Biostimulation (addition of organic substrate or nutrients) and bioaugmentation (addition of microbial consortium), applied either by direct injection at depth in the wetland sediments or by construction of a permeable reactive mat at the seep surface, were tested as possible methods to enhance anaerobic degradation in the seep areas. For the first phase of developing enhanced bioremediation methods for the contaminant mixtures in the seeps, laboratory studies were conducted to develop a microbial consortium to degrade 1,1,2,2-tetrachloroethane and its chlorinated daughter products under anaerobic conditions, and to test biostimulation and bioaugmentation of wetland sediment and reactive mat matrices in microcosms. The individual components required for the direct injection and reactive mat methods were then combined in column experiments to test them under groundwater- flow rates and contaminant concentrations observed in the field. Results showed that both direct injection and the reactive mat are promising remediation methods, although the success of direct injection likely would depend on adequately distributing and maintaining organic substrate throughout the wetland sediment in the seep

  2. Design and analysis of a natural-gradient ground-water tracer test in a freshwater tidal wetland, West Branch Canal Creek, Aberdeen Proving Ground, Maryland

    USGS Publications Warehouse

    Olsen, Lisa D.; Tenbus, Frederick J.

    2005-01-01

    A natural-gradient ground-water tracer test was designed and conducted in a tidal freshwater wetland at West Branch Canal Creek, Aberdeen Proving Ground, Maryland. The objectives of the test were to characterize solute transport at the site, obtain data to more accurately determine the ground-water velocity in the upper wetland sediments, and to compare a conservative, ionic tracer (bromide) to a volatile tracer (sulfur hexafluoride) to ascertain whether volatilization could be an important process in attenuating volatile organic compounds in the ground water. The tracer test was conducted within the upper peat unit of a layer of wetland sediments that also includes a lower clayey unit; the combined layer overlies an aquifer. The area selected for the test was thought to have an above-average rate of ground-water discharge based on ground-water head distributions and near-surface detections of volatile organic compounds measured in previous studies. Because ground-water velocities in the wetland sediments were expected to be slow compared to the underlying aquifer, the test was designed to be conducted on a small scale. Ninety-seven ?-inch-diameter inverted-screen stainless-steel piezometers were installed in a cylindrical array within approximately 25 cubic feet (2.3 cubic meters) of wetland sediments, in an area with a vertically upward hydraulic gradient. Fluorescein dye was used to qualitatively evaluate the hydrologic integrity of the tracer array before the start of the tracer test, including verifying the absence of hydraulic short-circuiting due to nonnatural vertical conduits potentially created during piezometer installation. Bromide and sulfur hexafluoride tracers (0.139 liter of solution containing 100,000 milligrams per liter of bromide ion and 23.3 milligrams per liter of sulfur hexafluoride) were co-injected and monitored to generate a dataset that could be used to evaluate solute transport in three dimensions. Piezometers were sampled 2 to 15 times

  3. Design and Performance of an Enhanced Bioremediation Pilot Test in a Tidal Wetland Seep, West Branch Canal Creek, Aberdeen Proving Ground, Maryland

    USGS Publications Warehouse

    Majcher, Emily H.; Lorah, Michelle M.; Phelan, Daniel J.; McGinty, Angela L.

    2009-01-01

    Because of a lack of available in situ remediation methods for sensitive wetland environments where contaminated groundwater discharges, the U.S. Geological Survey, in cooperation with the U.S. Army Garrison, Aberdeen Proving Ground, Maryland, conceived, designed, and pilot tested a permeable reactive mat that can be placed horizontally at the groundwater/surface-water interface. Development of the reactive mat was part of an enhanced bioremediation study in a tidal wetland area along West Branch Canal Creek at Aberdeen Proving Ground, where localized areas of preferential discharge (seeps) transport groundwater contaminated with carbon tetrachloride, chloroform, tetrachloroethene, trichloroethene, and 1,1,2,2-tetrachloroethane from the Canal Creek aquifer to land surface. The reactive mat consisted of a mixture of commercially available organic- and nutrient-rich peat and compost that was bioaugmented with a dechlorinating microbial consortium, WBC-2, developed for this study. Due to elevated chlorinated methane concentrations in the pilot test site, a layer of zero-valent iron mixed with the peat and compost was added at the base of the reactive mat to promote simultaneous abiotic and biotic degradation. The reactive mat for the pilot test area was designed to optimize chlorinated volatile organic compound degradation efficiency without altering the geotechnical and hydraulic characteristics, or creating undesirable water quality in the surrounding wetland area, which is referred to in this report as achieving geotechnical, hydraulic, and water-quality compatibility. Optimization of degradation efficiency was achieved through the selection of a sustainable organic reactive matrix, electron donor, and bioaugmentation method. Consideration of geotechnical compatibility through design calculations of bearing capacity, settlement, and geotextile selection showed that a 2- to 3-feet tolerable thickness of the mat was possible, with 0.17 feet settlement predicted for

  4. Changes in ground-water quality in the Canal Creek Aquifer between 1995 and 2000-2001, West Branch Canal Creek area, Aberdeen Proving Ground, Maryland

    USGS Publications Warehouse

    Phelan, Daniel J.; Fleck, William B.; Lorah, Michelle M.; Olsen, Lisa D.

    2002-01-01

    Since 1917, Aberdeen Proving Ground, Maryland has been the primary chemical-warfare research and development center for the U.S. Army. Ground-water contamination has been documented in the Canal Creek aquifer because of past disposal of chemical and ordnance manufacturing waste. Comprehensive sampling for volatile organic compounds in ground water by the U.S. Geological Survey in the West Branch Canal Creek area was done in June?October 1995 and June?August 2000. The purpose of this report is (1) to compare volatile organic compound concentrations and determine changes in the ground-water contaminant plumes along two cross sections between 1995 and 2000, and (2) to incorporate data from new piezometers sampled in spring 2001 into the plume descriptions. Along the southern cross section, total concentrations of volatile organic compounds in 1995 were determined to be highest in the landfill area east of the wetland (5,200 micrograms per liter), and concentrations were next highest deep in the aquifer near the center of the wetland (3,300 micrograms per liter at 35 feet below land surface). When new piezometers were sampled in 2001, higher carbon tetrachloride and chloroform concentrations (2,000 and 2,900 micrograms per liter) were detected deep in the aquifer 38 feet below land surface, west of the 1995 sampling. A deep area in the aquifer close to the eastern edge of the wetland and a shallow area just east of the creek channel showed declines in total volatile organic compound concentrations of more than 25 percent, whereas between those two areas, con-centrations generally showed an increase of greater than 25 percent between 1995 and 2000. Along the northern cross section, total concentrations of volatile organic compounds in ground water in both 1995 and 2000 were determined to be highest (greater than 2,000 micrograms per liter) in piezometers located on the east side of the section, farthest from the creek channel, and concentrations were progressively lower

  5. Ground-water, surface-water, and bottom-sediment contamination in the O-field area, Aberdeen Proving Ground, Maryland, and the possible effects of selected remedial actions on ground water

    USGS Publications Warehouse

    Vroblesky, Don A.; Lorah, Michelle M.; Oliveros, James P.

    1995-01-01

    Disposal of munitions and chemical-warfare substances has introduced inorganic and organic contaminants to the ground water, surface water, and bottom sediment at O-Field, in the Edgewood area of Aberdeen Proving Ground, Maryland. Contaminants include chloride, arsenic, transition metals, chlorinated aliphatic hydrocarbons, aromatic compounds, and organosulfur and organophosphorus compounds. The hydrologic effects of several remedial actions were estimated by use of a ground-water-flow model. The remedial actions examined were an impermeable covering, encapsulation, subsurface barriers, a ground-water drain, pumping of wells to manage water levels or to remove contaminated ground water for treatment, and no action.

  6. Evaluation of several biological monitoring techniques for hazard assessment of potentially contaminated wastewater and groundwater. Volume 2. Aberdeen Proving Ground Wastewater Treatment Plant. Final report, November 1988-December 1991

    SciTech Connect

    Burton, D.T.; Herriott, R.S.

    1992-07-01

    An evaluation of several biological monitoring techniques for hazard assessment of potentially contaminated effluent was conducted at the Aberdeen Proving Ground Wastewater Treatment Plant (APG-WWTP), Aberdeen Proving Ground, MD, from early May 1990 to February 13, 1991. An array of biomonitoring tests structured in a tiered hazard assessment framework was used in the evaluation of the effluent. Several levels of biological organization were included in the array of tests. Acute toxicity was evaluated on daily 24-h composite samples using a 5- and 15-min Microtox assay which employs microbial (Photobacterium phosphoreum) bioluminescent activity. Three 24-h LC50 rotifer (Brachionus rubens) toxicity tests were conducted using 24-h composite samples. The following chronic tests were all performed three times using 24-h composite samples: 96-h EC50 algal (Selenastrum capricornutum) growth test, 7-d daphnid (Ceriodaphnia dubia) survival and reproduction test, and 7-d fathead minnow (Pimephales promelas) survival and growth test. The acute rotifer tests and all chronic tests were conducted during the same periods in order to compare toxicological responses between biomonitoring systems.... Wastewater, Aquatic, Acute toxicity, Chronic toxicity, Mutagenicity, Ames, Teratogencity, FETAX, Carcinogenicity, Ventilatory biomonitoring system, Microtox, Photobacterium.

  7. Evaluation of several biological monitoring techniques for hazard assessment of potentially contaminated wastewater and groundwater. Volume 1. Aberdeen proving ground-edgewood area wastewater treatment plant. Final report, November 1988-December 1991

    SciTech Connect

    Burton, D.T.; Graves, W.C.

    1992-07-01

    An evaluation of several biological monitoring techniques for hazard assessment of potentially contaminated effluent was conducted at the Aberdeen Proving Ground-Edgewood Area Wastewater Treatment Plant (APG-EA WWTP), Aberdeen Proving Ground, MD, from January 1989 to December 13, 1989. An array of biomonitoring tests structured in a tiered hazard assessment framework was used in the evaluation of the effluent. Several levels of biological organization were included in the array of tests. Acute toxicity was evaluated on 24-h composite samples using a 15-min Microtox R assay which employs microbial (Photobacterium phosphoreum) bioluminescent activity. Two 24-h LC50 rotifer (Brachionus rubens) toxicity tests were conducted using 24-h composite samples The following chronic tests were all performed two times using 24-h composite samples: 96-h EC50 algal (Selenastrum capricornutum) growth test, 7-d daphnid (Ceriodaphnia dubia) survival and reproduction test, and 7-d fathead minnow (Pimephales promelas) survival and growth test. Generally, the acute rotifer tests and all chronic tests were conducted during the same periods in order to compare toxicological responses between biomonitoring systems.... Wastewater, Aquatic, Acute toxicity, Chronic toxicity, Mutagenicity, Ames, Teratogenicity, FETAX, Carcinogenicity, Ventilatory biomonitoring system, Microtox R, Photobacterium.

  8. Evaluation of several biological monitoring techniques for hazard assessment of potentially contaminated ground water at the Old O-Field site at the Edgewood area of Aberdeen Proving Ground. Interim report, Jul 90-Sep 91

    SciTech Connect

    Burton, D.T.; Turley, S.D.

    1991-11-01

    The toxicity of contaminated Old O-Field (Edgewood Area of Aberdeen Proving Ground) groundwater and the reduction and/or elimination of toxicity by various treatment processes were evaluated. The study was divided into a bench scale and pilot scale study. The bench scale studies consisted of 48-h definitive acute toxicity tests run with daphnid neonates (Daphnia magna) and juvenile fathead minnows (Pimephales promelas) exposed to untreated Old O-Field groundwater and groundwater treated by (1) metals precipitation, (2) UV oxidation (H2O ), (3) carbon adsorption, and (4) carbon adsorption/biological sludge. The pilot scale studies consisted of (1) several 96-h definitive acute toxicity tests run with two freshwater and two saltwater invertebrates and fish and (2) Ames mutagenicity assays. Acute toxicity tests were run on untreated Old 0-Field groundwater and groundwater treated by (1) metals precipitation, (2) UV oxidation (H2O2), (3) air stripping, and (4) carbon adsorption during the pilot scale study. The freshwater invertebrate and fish used in the study were daphnid neonates and juvenile fathead minnows, respectively.

  9. Aberdeen Area Fire Training Area Hydrologic Assessment, Aberdeen Proving Ground

    DTIC Science & Technology

    1992-12-01

    boring soil gas surveys were conducted for volatile organic compound (VOC) contamination at the FTA. Deeper borings were conducted for monitor wells and...high, on the ground surface. Fire training exercises at the AFTA were stopped in March 1989. Assessment During the RFA, a soil gas survey by the...71 Soil Gas Survey ............................................. 77 Soil Samples ...... ........................................ 81 Underground

  10. Historic Building Inventory, Aberdeen Proving Ground, Maryland

    DTIC Science & Technology

    1982-01-01

    official recorded meeting at the Court House was in 1692, at which Thomas Heath, innkeeper, filed suit for expenses incurreo by tne Justices at the 1687...sportsmen. GUN CLUBS AND HUNTING LODGES The well-off sportsmen of the 1880’s ana 1890’s pursued their sport from posn gun ana hunting clubs. Among these...ABERDEEL4 AREA WORLD WAR I MOBILIZATION America’s call to arms necessitated by ner involvement in the First Woria War causeu many changes in American

  11. Vehicle Test Facilities at Aberdeen Proving Ground

    DTIC Science & Technology

    1981-07-06

    which affects wheeled vehicles mainly be splash. Course 2 is laid out in a loop of moderately irregular terrain. The native soil includes Sassafras ...loamu, a silty loam with 17.3 percent clay content, and Sassafras silt loam, a silty loam with less than 15 percent clay. Surfaces range from smooth to

  12. 15. OLD ROAD BRIDGE MISSISSIPPI, MONROE CO., ABERDEEN (EAST ABERDEEN) ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    15. OLD ROAD BRIDGE MISSISSIPPI, MONROE CO., ABERDEEN (EAST ABERDEEN) One mile E of Aberdeen, 1000 ft. N of (1978) U.S. 45 bridge. Oblique view of bridge, in early 1900s. Credit: Evans Memorial Library, Aberdeen, MS. No date. Sarcone Photography, Columbus, Ms. Sep 1978. - Bridges of the Upper Tombigbee River Valley, Columbus, Lowndes County, MS

  13. Anaerobic degradation of 1,1,2,2-tetrachloroethane and association with microbial communities in a freshwater tidal wetland, Aberdeen Proving Ground, Maryland : laboratory experiments and comparisons to field data

    USGS Publications Warehouse

    Lorah, Michelle M.; Voytek, Mary A.; Kirshtein, Julie D.; Jones, Elizabeth J.

    2003-01-01

    Defining biodegradation rates and processes is a critical part of assessing the feasibility of monitored natural attenuation as a remediation method for ground water containing organic contaminants. During 1998?2001, the U.S. Geological Survey conducted a microbial study at a freshwater tidal wetland along the West Branch Canal Creek, Aberdeen Proving Ground, Maryland, as part of an investigation of natural attenuation of chlorinated volatile organic compounds (VOCs) in the wetland sediments. Geochemical analyses and molecular biology techniques were used to investigate factors controlling anaerobic degradation of 1,1,2,2-tetrachloroethane (TeCA), and to characterize the microbial communities that potentially are important in its degradation. Rapid TeCA and daughter product degradation observed in laboratory experiments and estimated with field data confirm that natural attenuation is a feasible remediation method at this site. The diverse microbial community that seems to be involved in TeCA degradation in the wetland sediments varies with changing spatial and seasonal conditions, allowing continued effective natural attenuation throughout the year. Rates of TeCA degradation in anaerobic microcosm experiments conducted with wetland sediment collected from two different sites (WB23 and WB30) and during three different seasons (March?April 1999, July?August 1999, and October?November 2000) showed little spatial variability but high seasonal variability. Initial first-order degradation rate constants for TeCA ranged from 0.10?0.01 to 0.16?0.05 per day (half-lives of 4.3 to 6.9 days) for March?April 1999 and October?November 2000 microcosms incubated at 19 degrees Celsius, whereas lower rate constants of 0 ? 0.03 and 0.06 ? 0.03 per day were obtained in July?August 1999 microcosms incubated at 19 degrees Celsius. Microbial community profiles showed that low microbial biomass and microbial diversity in the summer, possibly due to competition for nutrients by the

  14. Decommissioning Handbook

    SciTech Connect

    Not Available

    1994-03-01

    The Decommissioning Handbook is a technical guide for the decommissioning of nuclear facilities. The decommissioning of a nuclear facility involves the removal of the radioactive and, for practical reasons, hazardous materials to enable the facility to be released and not represent a further risk to human health and the environment. This handbook identifies and technologies and techniques that will accomplish these objectives. The emphasis in this handbook is on characterization; waste treatment; decontamination; dismantling, segmenting, demolition; and remote technologies. Other aspects that are discussed in some detail include the regulations governing decommissioning, worker and environmental protection, and packaging and transportation of the waste materials. The handbook describes in general terms the overall decommissioning project, including planning, cost estimating, and operating practices that would ease preparation of the Decommissioning Plan and the decommissioning itself. The reader is referred to other documents for more detailed information. This Decommissioning Handbook has been prepared by Enserch Environmental Corporation for the US Department of Energy and is a complete restructuring of the original handbook developed in 1980 by Nuclear Energy Services. The significant changes between the two documents are the addition of current and the deletion of obsolete technologies and the addition of chapters on project planning and the Decommissioning Plan, regulatory requirements, characterization, remote technology, and packaging and transportation of the waste materials.

  15. Decommissioning handbook

    SciTech Connect

    Manion, W.J.; LaGuardia, T.S.

    1980-11-01

    This document is a compilation of information pertinent to the decommissioning of surplus nuclear facilities. This handbook is intended to describe all stages of the decommissioning process including selection of the end product, estimation of the radioactive inventory, estimation of occupational exposures, description of the state-of-the-art in re decontamination, remote csposition of wastes, and estimation of program costs. Presentation of state-of-the-art technology and data related to decommissioning will aid in consistent and efficient program planning and performance. Particular attention is focused on available technology applicable to those decommissioning activities that have not been accomplished before, such as remote segmenting and handling of highly activated 1100 MW(e) light water reactor vessel internals and thick-walled reactor vessels. A summary of available information associated with the planning and estimating of a decommissioning program is also presented. Summarized in particular are the methodologies associated with the calculation and measurement of activated material inventory, distribution, and surface dose level, system contamination inventory and distribution, and work area dose levels. Cost estimating techniques are also presented and the manner in which to account for variations in labor costs as impacting labor-intensive work activities is explained.

  16. Edgewood Area - Aberdeen Proving Ground Five-Year Review

    DTIC Science & Technology

    2008-10-01

    PROJECT NUMBER 5e. TASK NUMBER 5f. WORK UNIT NUMBER 7. PERFORMING ORGANIZATION NAME(S) AND ADDRESS(ES) General Physics Corporation,500 Edgewood Road...Suite 110,Edgewood,MD,21040 8. PERFORMING ORGANIZATION REPORT NUMBER 9. SPONSORING/MONITORING AGENCY NAME(S) AND ADDRESS(ES) 10. SPONSOR/MONITOR’S... organic compounds TAL Target Analyte List TCL Target Compound List TDS total dissolved solids TOC total organic carbon TI technical impracticability

  17. Aerosol tests conducted at Aberdeen Proving Grounds MD.

    SciTech Connect

    Brockmann, John E.; Lucero, Daniel A.; Servantes, Brandon Lee; Hankins, Matthew Granholm

    2012-06-01

    Test data are reported that demonstrate the deposition from a spray dispersion system (Illinois Tool Works inductively charging rotary atomization nozzle) for application of decontamination solution to various surfaces in the passenger cabin of a Boeing 737 aircraft. The decontamination solution (EnviroTru) was tagged with a known concentration of fluorescein permitting determination of both airborne decontaminant concentration and surface deposited decontaminant solution so that the effective deposition rates and surface coverage could be determined and correlated with the amount of material sprayed. Six aerosol dispersion tests were conducted. In each test, aluminum foil deposition coupons were set out throughout the passenger area and the aerosol was dispersed. The aerosol concentration was measured with filter samplers as well as with optical techniques Average aerosol deposition ranged from 3 to 15 grams of decontamination solution per square meter. Some disagreement was observed between various instruments utilizing different measurement principles. These results demonstrate a potentially effective method to disperse decontaminant to interior surfaces of a passenger aircraft.

  18. 76 FR 35511 - Decommissioning Planning

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-06-17

    ... Regulatory Commission (NRC or the Commission) is amending its regulations to improve decommissioning planning... financial assurance requirements. The amended regulations require decommissioning power reactor licensees to... with respect to permanently shutdown reactor decommissioning fund status and spent fuel management...

  19. Decommissioning at AWE

    SciTech Connect

    Biles, K.; Hedges, M.; Campbell, C

    2008-07-01

    AWE (A) has been at the heart of the UK Nuclear deterrent since it was established in the early 1950's. It is a nuclear licensed site and is governed by the United Kingdoms Nuclear Installation Inspectorate (NII). AWE plc on behalf of the Ministry of Defence (MOD) manages the AWE (A) site and all undertakings including decommissioning. Therefore under NII license condition 35 'Decommissioning', AWE plc is accountable to make and implement adequate arrangements for the decommissioning of any plant or process, which may affect safety. The majority of decommissioning projects currently being undertaken are to do with Hazard category 3, 4 or 5 facilities, systems or plant that have reached the end of their operational span and have undergone Post-Operational Clean-Out (POCO). They were either built for the production of fissile components, for supporting the early reactor fuels programmes or for processing facility waste arisings. They either contain redundant contaminated gloveboxes associated process areas, process plant or systems or a combination of all. In parallel with decommissioning project AWE (A) are undertaking investigation into new technologies to aid decommissioning projects; to remove the operative from hands on operations; to develop and implement modifications to existing process and techniques used. AWE (A) is currently going thorough a sustained phase of upgrading its facilities to enhance its scientific capability, with older facilities, systems and plant being replaced, making decommissioning a growth area. It is therefore important to the company to reduce these hazards progressively and safety over the coming years, making decommissioning an important feature of the overall legacy management aspects of AWE PLC's business. This paper outlines the current undertakings and progress of Nuclear decommissioning on the AWE (A) site. (authors)

  20. Estimating decommissioning costs: The 1994 YNPS decommissioning cost study

    SciTech Connect

    Szymczak, W.J.

    1994-12-31

    Early this year, Yankee Atomic Electric Company began developing a revised decommissioning cost estimate for the Yankee Nuclear Power Station (YNPS) to provide a basis for detailed decommissioning planning and to reflect slow progress in siting low-level waste (LLW) and spent-nuclear-fuel disposal facilities. The revision also reflects the need to change from a cost estimate that focuses on overall costs to a cost estimate that is sufficiently detailed to implement decommissioning and identify the final cost of decommissioning.

  1. The Aberdeen Impedance Imaging System.

    PubMed

    Kulkarni, V; Hutchison, J M; Mallard, J R

    1989-01-01

    The Aberdeen Impedance Imaging System is designed to reconstruct 2 dimensional images of the average distribution of the amplitude and phase of the complex impedance within a 3 dimensional region. The system uses the four electrode technique in a 16 electrode split-array. The system hardware consists of task-orientated electronic modules for: driving a constant current, multiplexing the current drive, demultiplexing peripheral voltages, differential amplification, phase sensitive detection and low-pass filtration, digitisation with a 14 bit analog to digital converter (ADC), and -control logic for the ADC and multiplexors. A BBC microprocessor (Master series), initiates a controlled sequence for the collection of a number of data sets which are averaged and stored on disk. Image reconstruction is by a process of convolution-backprojection similar to the fan-beam reconstruction of computerised tomography and is also known as Equipotential Backprojection. In imaging impedance changes associated with fracture healing the changes may be large enough to allow retrieval of both the amplitude and phase of the complex impedance. Sequential imaging of these changes would necessitate monitoring electronic and electrode drift by imaging an equivalent region of the contralateral limb. Differential images could be retrieved when the image of the normal limb is the image template. Better characterisation of tissues would necessitate a cleaner retrieval of the quadrature signal.

  2. Factors Impacting Decommissioning Costs - 13576

    SciTech Connect

    Kim, Karen; McGrath, Richard

    2013-07-01

    The Electric Power Research Institute (EPRI) studied United States experience with decommissioning cost estimates and the factors that impact the actual cost of decommissioning projects. This study gathered available estimated and actual decommissioning costs from eight nuclear power plants in the United States to understand the major components of decommissioning costs. Major costs categories for decommissioning a nuclear power plant are removal costs, radioactive waste costs, staffing costs, and other costs. The technical factors that impact the costs were analyzed based on the plants' decommissioning experiences. Detailed cost breakdowns by major projects and other cost categories from actual power plant decommissioning experiences will be presented. Such information will be useful in planning future decommissioning and designing new plants. (authors)

  3. Site decommissioning management plan

    SciTech Connect

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

    1993-10-01

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

  4. Reading standards in Aberdeen, 1962-72

    ERIC Educational Resources Information Center

    Nisbet, J.; And Others

    1974-01-01

    The NFER findings on recent trends in reading standards are confirmed by this study. While in Aberdeen at the age of eight years, the standard of performance in reading comprehension is relatively unchanged, at age 11 there has been a slight decline in average standard. (Author)

  5. Employer-Student Workshops: The Aberdeen Experience.

    ERIC Educational Resources Information Center

    Heard, Sue; Farrington, John

    1998-01-01

    Outlines much of the work accomplished by the University of Aberdeen geography department and an employer-liaison group. The group, in conjunction with local businesses, prepared seminars on developing and connecting academic geographic skills to the employment market. Lists employers involved and summarizes students' responses to the seminars.…

  6. Superfund Record of Decision (EPA Region 3): USA Aberdeen, Operable Unit One, Michaelsville, MD. (Second remedial action), June 1992

    SciTech Connect

    Not Available

    1992-06-30

    The 20-acre USA Aberdeen Michaelsville Landfill is a municipal landfill located along the Chesapeake Bay in Harford County, Maryland. The site is in the northern portion of the Aberdeen Proving Ground (APG) in the Aberdeen Area (AA) between Michaelsville Road and Trench Warfare Road. The majority of materials reportedly disposed of at the site included domestic trash, trash from nonindustrial sources at APG, solvents, waste motor oils, PCB transformer oils, wastewater treatment sludges, pesticides containing thallium, insecticides containing selenium, and rodenticides containing antimony. The ROD addresses protection of the ground water by minimizing leachate flow and preventing current or future exposure to waste materials as the first of two OUs planned for the site. The primary contaminants of concern affecting the soil are organics, including pesticides; and metals, including chromium and lead.

  7. INTERNATIONAL DECOMMISSIONING SYMPOSIUM 2000

    SciTech Connect

    M.A. Ebadian, Ph.D.

    2001-01-01

    The purpose of IDS 2000 was to deliver a world-class conference on applicable global environmental issues. The objective of this conference was to publicize environmental progress of individual countries, to provide a forum for technology developer and problem-holder interaction, to facilitate environmental and technology discussions between the commercial and financial communities, and to accommodate information and education exchange between governments, industries, universities, and scientists. The scope of this project included the planning and execution of an international conference on the decommissioning of nuclear facilities, and the providing of a business forum for vendors and participants sufficient to attract service providers, technology developers, and the business and financial communities. These groups, when working together with attendees from regulatory organizations and government decision-maker groups, provide an opportunity to more effectively and efficiently expedite the decommissioning projects.

  8. ORNL decontamination and decommissioning program

    SciTech Connect

    Bell, J. P.

    1980-01-01

    A program has been initiated at ORNL to decontaminate and decommission surplus or abandoned nuclear facilities. Program planning and technical studies have been performed by UCC-ND Engineering. A feasibility study for decommissioning the Metal Recovery Facility, a fuel reprocessing pilot plant, has been completed.

  9. 14. RAILROAD BRIDGE MISSISSIPPI, MONROE CO., ABERDEEN Reach by foot ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    14. RAILROAD BRIDGE MISSISSIPPI, MONROE CO., ABERDEEN Reach by foot from E end of Vine St. St. Louis and San Francisco RR bridge. Bridge built 1887, replaced, 1969. Credit: Evans Memorial Library, Aberdeen, Ms. No date. Sarcone Photography, Columbus, Ms. Sep 1978. - Bridges of the Upper Tombigbee River Valley, Columbus, Lowndes County, MS

  10. A hierarchical approach to ecological assessment of contaminated soils at Aberdeen Proving Ground, USA

    SciTech Connect

    Kuperman, R.G.

    1995-12-31

    Despite the expansion of environmental toxicology studies over the past decade, soil ecosystems have largely been ignored in ecotoxicological studies in the United States. The objective of this project was to develop and test the efficacy of a comprehensive methodology for assessing ecological impacts of soil contamination. A hierarchical approach that integrates biotic parameters and ecosystem processes was used to give insight into the mechanisms that lead to alterations in the structure and function of soil ecosystems in contaminated areas. This approach involved (1) a thorough survey of the soil biota to determine community structure, (2) laboratory and field tests on critical ecosystem processes, (3) toxicity trials, and (4) the use of spatial analyses to provide input to the decision-making, process. This methodology appears to, offer an efficient and potentially cost-saving tool for remedial investigations of contaminated sites.

  11. Personnel Management for Executives, Army Regional Training Center, Central Atlantic Region, Aberdeen Proving Ground, Maryland,

    DTIC Science & Technology

    1986-01-01

    HAVE PATIENCE ..TO WATCH FOR NEW ESSENTIALS .TO KEEP TRACK OF ESSENTIAL DETAIL ..TO TACKLE DIFFICULTIES WITH ZEST ..TO FACE DIFFICULTIES WITH REALISM .TO...AD-RI69 63B PERSONNEL MANAGEMENT FOR EXECUTIVES RMY REGIONAL i/ I TRINING CENTER CENTRAL..(U) BAR AND BAR COMMUINICATION I CONSULTANS AUSTIN TX N...BARR 1996 DAADSS-B6-M-L254 IUNCLASSIFIED F/O 5/10 L i flfllfllfllfllmfofl 11111 __________ 1_ 113- 41 5 1.8. 1*25 012 PERSONNEL MANAGEMENT FOR

  12. 33 CFR 334.140 - Chesapeake Bay; U.S. Army Proving Ground Reservation, Aberdeen, Md.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... of Swan Creek, Harford County, Maryland, the most northerly point of the reservation known as Plum... the boundary of the reservation to Swan Creek; and thence in a straight line to Plum Point. (The...

  13. Assessment of Aberdeen Proving Ground - Army Contracting Command, Contract Management Processes

    DTIC Science & Technology

    2015-04-11

    official policy position of the Navy, the Department of Defense, or the federal government. iii THIS PAGE INTENTIONALLY LEFT BLANK iv v TABLE OF...Approvals Reverse Auctions Reverse Auctions Reverse Auctions Formal Source Selections in Progress Protest Management Protest Management CPARS CPARS UCAs...Human Capital 1. Percentage of 1102 workforce that are interns 2. Total Fill Rate of employees to positions 3. Percent of operating division

  14. Assessment of Aberdeen Proving Ground - Army Contracting Command, Contract Management Processes

    DTIC Science & Technology

    2014-12-01

    thesis are those of the author and do not reflect the official policy or position of the Department of Defense or the U.S. Government. IRB Protocol...Justification and Approvals # of Justification and Approvals Reverse Auctions Reverse Auctions Reverse Auctions Formal Source Selections in Progress Protest...to positions 3. Percent of operating division personnel that directly support the mission of awarding/ administrating contracts 4. Number of

  15. Remedial Investigation Work Plan for J-Field, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Benioff, P.; Biang, R.; Dolak, D.; Dunn, C.; Haffenden, R.; Martino, L.; Patton, T.; Wang, Y.; Yuen, C.

    1995-03-01

    The purpose of an RI/FS is to characterize the nature and extent of the risks posed by contaminants present at a site and to develop and evaluate options for remedial actions. The overall objective of the RI is to provide a comprehensive evaluation of site conditions, types and quantities of contaminants present, release mechanisms and migration pathways, target populations, and risks to human health and the environment. The information developed during the RI provides the basis for the design and implementation of remedial actions during the FS. The purpose of this RI Work Plan is to define the tasks that will direct the remedial investigation of the J-Field site at APG.

  16. Personnel and Vehicle Data Collection at Aberdeen Proving Ground (APG) and its Distribution for Research

    DTIC Science & Technology

    2015-10-01

    5 Fig. 5 Day 3 walker’s diamond pattern ............................................................6 Fig. 6 Day 3...walker’s double wedge pattern ....................................................8 Fig. 10 Day 3 walker’s diamond in front and 2 men behind pattern...8 Fig. 11 Day 3 walker’s point man slack man pattern .........................................9 Fig. 12 Day 3 walker’s diamond

  17. Preliminary Review of the 63W10 Course at Aberdeen Proving Ground

    DTIC Science & Technology

    1988-09-01

    the temporary clasroom used in Annex E, this is the worst of the Phase I classrooms. (2) The within course test was given at the end of Block G-4...concern for and pride in student accomplishment; and 4) better management of student group composition/activity to insure each student performs

  18. 33 CFR 334.140 - Chesapeake Bay; U.S. Army Proving Ground Reservation, Aberdeen, Md.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... which passes through monuments No. 124 and No. 125 on westerly part of Carroll Island; thence... except Landerick Creek; (iii) The water adjacent to Carroll Island which lies between Brier Point...

  19. Hydrogeology and chemical quality of water and soil at Carroll Island, Aberdeen Proving Ground, Maryland

    USGS Publications Warehouse

    Tenbus, F.J.; Phillips, S.W.

    1996-01-01

    Carroll Island was used for open-air testing of chemical warfare agents from the late 1940's until 1971. Testing and disposal activities weresuspected of causing environmental contamination at 16 sites on the island. The hydrogeology and chemical quality of ground water, surface water, and soil at these sites were investigated with borehole logs, environmental samples, water-level measurements, and hydrologic tests. A surficial aquifer, upper confining unit, and upper confined aquifer were defined. Ground water in the surficial aquifer generally flows from the east-central part of the island toward the surface-water bodies, butgradient reversals caused by evapotranspiration can occur during dry seasons. In the confined aquifer, hydraulic gradients are low, and hydraulic head is affected by tidal loading and by seasonal pumpage from the west. Inorganic chemistry in the aquifers is affected by brackish-water intrusion from gradient reversals and by dissolution ofcarboniferous shell material in the confining unit.The concentrations of most inorganic constituents probably resulted from natural processes, but some concentrations exceeded Federal water-quality regulations and criteria. Organic compounds were detected in water and soil samples at maximum concentrations of 138 micrograms per liter (thiodiglycol in surface water) and 12 micrograms per gram (octadecanoic acid in soil).Concentrations of organic compounds in ground water exceeded Federal drinking-water regulations at two sites. The organic compounds that weredetected in environmental samples were variously attributed to natural processes, laboratory or field- sampling contamination, fallout from industrial air pollution, and historical military activities.

  20. 33 CFR 334.140 - Chesapeake Bay; U.S. Army Proving Ground Reservation, Aberdeen, Md.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... Point; thence southeasterly along the low water mark on the shore of Chesapeake Bay to and across the north entrance of Spesutie Narrows to and thence along the low water mark on the north shore of Spesutie... approximately 1,400 yards; thence following a line parallel with and 1,000 yards from the low water mark on...

  1. Civilian Talent Management: A Proposed Approach for the Aberdeen Proving Ground Workforce

    DTIC Science & Technology

    2010-04-01

    covers the GS-13 and above grades and their equivalents. Data from the Science and Technology Demonstration (DB) pay system was not available for this...of pay systems currently in use at APG. Nonetheless, data is available and this research was able to obtain and analyze a sampling to provide focus...SUBJECT TERMS 16. SECURITY CLASSIFICATION OF: 17. LIMITATION OF ABSTRACT Same as Report (SAR) 18. NUMBER OF PAGES 118 19a. NAME OF RESPONSIBLE

  2. Information Management for Installation Restoration with Focus on Aberdeen Proving Ground, Maryland

    DTIC Science & Technology

    1993-08-01

    titled "Installation Restoration Data Manage- ment Information System" (IRDMIS). This program, begun in 1975, has undergone several updates as technology ...Aurora, Colorado, produces similar videos, and can use animation technology to fill gaps between successive computer generated views. The application of...anima- tion technology is intended to reduce the number of required computer gener- ated views and presumably lower production costs. Similar products

  3. 78 FR 60238 - Proposed Modification and Establishment of Restricted Areas; Aberdeen Proving Ground, MD

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-10-01

    ..., economic, environmental, and energy-related aspects of the proposal. Communications should identify both... winds exceed 60 knots. Lighting of the mooring cables is not practical due to technical design issues... aircraft and the efficient use of airspace. This regulation is within the scope of that authority as...

  4. Hydrogeology and water quality in the Graces Quarters area of Aberdeen Proving Ground, Maryland

    USGS Publications Warehouse

    Tenbus, Frederick J.; Blomquist, Joel D.

    1995-01-01

    Graces Quarters was used for open-air testing of chemical-warfare agents from the late 1940's until 1971. Testing and disposal activities have resulted in the contamination of ground water and surface water. The hydrogeology and water quality were examined at three test areas, four disposal sites, a bunker, and a service area on Graces Quarters. Methods of investigation included surface and borehole geophysics, water-quality sampling, water- level measurement, and hydrologic testing. The hydrogeologic framework is complex and consists of a discontinuous surficial aquifer, one or more upper confining units, and a confined aquifer system. Directions of ground-water flow vary spatially and temporally, and results of site investigations show that ground-water flow is controlled by the geology of the area. The ground water and surface water at Graces Quarters generally are unmineralized; the ground water is mildly acidic (median pH is 5.38) and poorly buffered. Inorganic constituents in excess of certain Federal drinking-water regulations and ambient water-quality criteria were detected at some sites, but they probably were present naturally. Volatile and semivolatile organic com- pounds were detected in the ground water and surface water at seven of the nine sites that were investi- gated. Concentrations of organic compounds at two of the nine sites exceeded Federal drinking-water regulations. Volatile compounds in concentrations as high as 6,000 m/L (micrograms per liter) were detected in the ground water at the site known as the primary test area. Concentrations of volatile compounds detected in the other areas ranged from 0.57 to 17 m/L.

  5. Drinking Water Treatment Optimization Using the Pipe-Loop System: Demonstration at Aberdeen Proving Ground, Maryland

    DTIC Science & Technology

    1990-06-01

    define their water quality and appropriate treatments. However, because the simulation conditions are critical to a realistic analysis, it would be...treatment process includes alum coagulation followed by rapid sand filtration, lime treatment for pH adjustment, sodium silicate treatment for...corrosion control by adding sodium silicate at a dosage of 0.5 mg/L. The significance of this treatment on reducing lead dissolution from piumbing materials

  6. Anthropomorphic Phantom Radiation Dosimetry at the NATO Standard Reference Point at Aberdeen Proving Ground,

    DTIC Science & Technology

    1987-04-01

    will have a non-isotropic angular dependance . Thus, for free-field dosimetry, while the bubble detector results could be directly transformed * into...these experiments was the bubble dosimeter temperature dependance . In all experiments, the phantom was surrounded by a tent arrangement (see figs) in

  7. Conference on Receptor-Based Biosensors (3rd) Held in Aberdeen Proving Ground, Maryland, September 1987

    DTIC Science & Technology

    1988-07-01

    variety of organic calcium chazwel blockire agents including nifedipine, whioh is a m r of the dihydropyridine clams, o--- W7, which is the only... dihydropyridine -insenaitive calcium channel and injected into the oocytes? Leonard: Yes, he had. The preliminary indioations are that Numa has succeeded in getting...term of expressing that dihydropyridine receptor. 37 Leonard: With the proviso that there are other rat brain sodium charnela, for instance, one of

  8. Decontamination & decommissioning focus area

    SciTech Connect

    1996-08-01

    In January 1994, the US Department of Energy Office of Environmental Management (DOE EM) formally introduced its new approach to managing DOE`s environmental research and technology development activities. The goal of the new approach is to conduct research and development in critical areas of interest to DOE, utilizing the best talent in the Department and in the national science community. To facilitate this solutions-oriented approach, the Office of Science and Technology (EM-50, formerly the Office of Technology Development) formed five Focus AReas to stimulate the required basic research, development, and demonstration efforts to seek new, innovative cleanup methods. In February 1995, EM-50 selected the DOE Morgantown Energy Technology Center (METC) to lead implementation of one of these Focus Areas: the Decontamination and Decommissioning (D & D) Focus Area.

  9. Asset Decommissioning Risk Metrics for Floating Structures in the Gulf of Mexico.

    PubMed

    Kaiser, Mark J

    2015-08-01

    Public companies in the United States are required to report standardized values of their proved reserves and asset retirement obligations on an annual basis. When compared, these two measures provide an aggregate indicator of corporate decommissioning risk but, because of their consolidated nature, cannot readily be decomposed at a more granular level. The purpose of this article is to introduce a decommissioning risk metric defined in terms of the ratio of the expected value of an asset's reserves to its expected cost of decommissioning. Asset decommissioning risk (ADR) is more difficult to compute than a consolidated corporate risk measure, but can be used to quantify the decommissioning risk of structures and to perform regional comparisons, and also provides market signals of future decommissioning activity. We formalize two risk metrics for decommissioning and apply the ADR metric to the deepwater Gulf of Mexico (GOM) floater inventory. Deepwater oil and gas structures are expensive to construct, and at the end of their useful life, will be expensive to decommission. The value of proved reserves for the 42 floating structures in the GOM circa January 2013 is estimated to range between $37 and $80 billion for future oil prices between 60 and 120 $/bbl, which is about 10 to 20 times greater than the estimated $4.3 billion to decommission the inventory. Eni's Allegheny and MC Offshore's Jolliet tension leg platforms have ADR metrics less than one and are approaching the end of their useful life. Application of the proposed metrics in the regulatory review of supplemental bonding requirements in the U.S. Outer Continental Shelf is suggested to complement the current suite of financial metrics employed.

  10. 77 FR 41107 - Decommissioning Planning During Operations

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-07-12

    ...; ] NUCLEAR REGULATORY COMMISSION 10 CFR Parts 20, 30, 40, 50, 70, and 72 Decommissioning Planning During... on revised draft regulatory guide (DG) 4014, ``Decommissioning Planning During Operations.'' This... Decommissioning Planning Rule. The NRC will hold a public meeting and concurrent Webinar to facilitate the...

  11. On Mathematical Proving

    NASA Astrophysics Data System (ADS)

    Stefaneas, Petros; Vandoulakis, Ioannis M.

    2015-12-01

    This paper outlines a logical representation of certain aspects of the process of mathematical proving that are important from the point of view of Artificial Intelligence. Our starting-point is the concept of proof-event or proving, introduced by Goguen, instead of the traditional concept of mathematical proof. The reason behind this choice is that in contrast to the traditional static concept of mathematical proof, proof-events are understood as processes, which enables their use in Artificial Intelligence in such contexts, in which problem-solving procedures and strategies are studied. We represent proof-events as problem-centered spatio-temporal processes by means of the language of the calculus of events, which captures adequately certain temporal aspects of proof-events (i.e. that they have history and form sequences of proof-events evolving in time). Further, we suggest a "loose" semantics for the proof-events, by means of Kolmogorov's calculus of problems. Finally, we expose the intented interpretations for our logical model from the fields of automated theorem-proving and Web-based collective proving.

  12. Assessment of foreign decommissioning technology with potential application to US decommissioning needs

    SciTech Connect

    Allen, R.P.; Konzek, G.J.; Schneider, K.J.; Smith, R.I.

    1987-09-01

    This study was conducted by the Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE) to identify and technically assess foreign decommissioning technology developments that may represent significant improvements over decommissioning technology currently available or under development in the United States. Technology need areas for nuclear power reactor decommissioning operations were identified and prioritized using the results of past light water reactor (LWR) decommissioning studies to quantitatively evaluate the potential for reducing cost and decommissioning worker radiation dose for each major decommissioning activity. Based on these identified needs, current foreign decommissioning technologies of potential interest to the US were identified through personal contacts and the collection and review of an extensive body of decommissioning literature. These technologies were then assessed qualitatively to evaluate their uniqueness, potential for a significant reduction in decommissioning costs and/or worker radiation dose, development status, and other factors affecting their value and applicability to US needs.

  13. 77 FR 67689 - Fidelity Aberdeen Street Trust, et al.;

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-11-13

    ... COMMISSION Fidelity Aberdeen Street Trust, et al.; Notice of Application November 6, 2012. AGENCY: Securities... certain joint arrangements (``Prior Order'').\\1\\ \\1\\ Colchester Street Trust, et al., Investment Company..., Colchester Street Trust, et al., Investment Company Act Release Nos. 23787 (Apr. 15, 1999) (notice) and...

  14. Symbiotic Situation. Brown County, Aberdeen, and Alexander Mitchell Public Library.

    ERIC Educational Resources Information Center

    Barton, David

    Utilizing 1970 census data and updates plus local data and library records, the study seeks to assess the current status of public library usage in and around Aberdeen, South Dakota. A demographic profile of the community as a whole was first constructed and then compared with similar data for known public library users. Information was also…

  15. 76 FR 3837 - Nuclear Decommissioning Funds; Correction

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-01-21

    ... Internal Revenue Service 26 CFR Part 1 RIN 1545-BF08 Nuclear Decommissioning Funds; Correction AGENCY... decommissioning nuclear power plants. DATES: This correction is effective on January 21, 2011, and is applicable... interest in a nuclear power plant. * * * * * (e) * * * (3) * * * Example 2. * * * Pursuant to paragraph...

  16. STANDARD OPERATING PROTOCOLS FOR DECOMMISSIONING

    SciTech Connect

    Foss, D. L.; Stevens, J. L.; Gerdeman, F. W.

    2002-02-25

    Decommissioning projects at Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) sites are conducted under project-specific decision documents, which involve extensive preparation time, public comment periods, and regulatory approvals. Often, the decision documents must be initiated at least one year before commencing the decommissioning project, and they are expensive and time consuming to prepare. The Rocky Flats Environmental Technology Site (RFETS) is a former nuclear weapons production plant at which hazardous substances and wastes were released or disposed during operations. As a result of the releases, RFETS was placed on the National Priorities List in 1989, and is conducting cleanup activities under a federal facilities compliance agreement. Working closely with interested stakeholders and state and federal regulatory agencies, RFETS has developed and implemented an improved process for obtaining the approvals. The key to streamlining the approval process has been the development of sitewide decision documents called Rocky Flats Cleanup Agreement Standard Operating Protocols or ''RSOPs.'' RSOPs have broad applicability, and could be used instead of project-specific documents. Although no two decommissioning projects are exactly the same and they may vary widely in contamination and other hazards, the basic steps taken for cleanup are usually similar. Because of this, using RSOPs is more efficient than preparing a separate project-specific decision documents for each cleanup action. Over the Rocky Flats cleanup life cycle, using RSOPs has the potential to: (1) Save over 5 million dollars and 6 months on the site closure schedule; (2) Eliminate preparing one hundred and twenty project-specific decision documents; and (3) Eliminate writing seventy-five closure description documents for hazardous waste unit closure and corrective actions.

  17. Rancho Seco--Decommissioning Update

    SciTech Connect

    Newey, J. M.; Ronningen, E. T.; Snyder, M. W.

    2003-02-26

    The Rancho Seco Nuclear Generating Station ceased operation in June of 1989 and entered an extended period of SAFSTOR to allow funds to accumulate for dismantlement. Incremental dismantlement was begun in 1997 of steam systems and based on the successful completion of work, the Sacramento Municipal Utility District (SMUD) board of directors approved full decommissioning in July 1999. A schedule has been developed for completion of decommissioning by 2008, allowing decommissioning funds to accumulate until they are needed. Systems removal began in the Auxiliary Building in October of 1999 and in the Reactor Building in January of 2000. Systems dismantlement continues in the Reactor Building and should be completed by the end of 2003. System removal is near completion in the Auxiliary Building with removal of the final liquid waste tanks in progress. The spent fuel has been moved to dry storage in an onsite ISFSI, with completion on August 21, 2002. The spent fuel racks are currently being removed from the pool, packaged and shipped, and then the pool will be cleaned. Also in the last year the reactor coolant pumps and primary piping were removed and shipped. Characterization and planning work for the reactor vessel and internals is also in progress with various cut-up and/or disposal options being evaluated. In the year ahead the remaining systems in the Reactor Building will be removed, packaged and sent for disposal, including the pressurizer. Work will be started on embedded and underground piping and the large outdoor tanks. Building survey and decontamination will begin. RFP's for removal of the vessel and internals and the steam generators are planned to fix the cost of those components. If the costs are consistent with current estimates the work will go forward. If they are not, hardened SAFSTOR/entombment may be considered.

  18. Pipeline Decommissioning Trial AWE Berkshire UK - 13619

    SciTech Connect

    Agnew, Kieran

    2013-07-01

    This Paper details the implementation of a 'Decommissioning Trial' to assess the feasibility of decommissioning the redundant pipeline operated by AWE located in Berkshire UK. The paper also presents the tool box of decommissioning techniques that were developed during the decommissioning trial. Constructed in the 1950's and operated until 2005, AWE used a pipeline for the authorised discharge of treated effluent. Now redundant, the pipeline is under a care and surveillance regime awaiting decommissioning. The pipeline is some 18.5 km in length and extends from AWE site to the River Thames. Along its route the pipeline passes along and under several major roads, railway lines and rivers as well as travelling through woodland, agricultural land and residential areas. Currently under care and surveillance AWE is considering a number of options for decommissioning the pipeline. One option is to remove the pipeline. In order to assist option evaluation and assess the feasibility of removing the pipeline a decommissioning trial was undertaken and sections of the pipeline were removed within the AWE site. The objectives of the decommissioning trial were to: - Demonstrate to stakeholders that the pipeline can be removed safely, securely and cleanly - Develop a 'tool box' of methods that could be deployed to remove the pipeline - Replicate the conditions and environments encountered along the route of the pipeline The onsite trial was also designed to replicate the physical prevailing conditions and constraints encountered along the remainder of its route i.e. working along a narrow corridor, working in close proximity to roads, working in proximity to above ground and underground services (e.g. Gas, Water, Electricity). By undertaking the decommissioning trial AWE have successfully demonstrated the pipeline can be decommissioned in a safe, secure and clean manor and have developed a tool box of decommissioning techniques. The tool box of includes; - Hot tapping - a method

  19. Modelling of nuclear power plant decommissioning financing.

    PubMed

    Bemš, J; Knápek, J; Králík, T; Hejhal, M; Kubančák, J; Vašíček, J

    2015-06-01

    Costs related to the decommissioning of nuclear power plants create a significant financial burden for nuclear power plant operators. This article discusses the various methodologies employed by selected European countries for financing of the liabilities related to the nuclear power plant decommissioning. The article also presents methodology of allocation of future decommissioning costs to the running costs of nuclear power plant in the form of fee imposed on each megawatt hour generated. The application of the methodology is presented in the form of a case study on a new nuclear power plant with installed capacity 1000 MW.

  20. Sellafield Decommissioning Programme - Update and Lessons Learned

    SciTech Connect

    Lutwyche, P. R.; Challinor, S. F.

    2003-02-24

    The Sellafield site in North West England has over 240 active facilities covering the full nuclear cycle from fuel manufacture through generation, reprocessing and waste treatment. The Sellafield decommissioning programme was formally initiated in the mid 1980s though several plants had been decommissioned prior to this primarily to create space for other plants. Since the initiation of the programme 7 plants have been completely decommissioned, significant progress has been made in a further 16 and a total of 56 major project phases have been completed. This programme update will explain the decommissioning arrangements and strategies and illustrate the progress made on a number of the plants including the Windscale Pile Chimneys, the first reprocessing plan and plutonium plants. These present a range of different challenges and requiring approaches from fully hands on to fully remote. Some of the key lessons learned will be highlighted.

  1. Russian nuclear-powered submarine decommissioning

    SciTech Connect

    Bukharin, O.; Handler, J.

    1995-11-01

    Russia is facing technical, economic and organizational difficulties in dismantling its oversized and unsafe fleet of nuclear powered submarines. The inability of Russia to deal effectively with the submarine decommissioning crisis increases the risk of environmental disaster and may hamper the implementation of the START I and START II treaties. This paper discusses the nuclear fleet support infrastructure, the problems of submarine decommissioning, and recommends international cooperation in addressing these problems.

  2. Evaluation of Unexploded Ordnance (UXO) Detection Technology at the Standardized UXO Test Sites Aberdeen and Yuma Proving Grounds

    DTIC Science & Technology

    2007-11-01

    so that they combine the advantages of both the EM and MAG sensors. (4) Ground-penetrating radar ( GPR ). GPR systems work by transmitting...buried in the ground or any dielectric discontinuity and then return to the surface. By analyzing the signal that returns from the ground, GPR ...EM EM61MKII sling Jan. 2006 VF Warner Blind Grid (764) EM AMOS towed Dec. 2002 Witten Blind Grid (45) GPR Cart cart Dec. 2002 Witten Mine Grid

  3. Electrothermal-Chemical Modeling Workshop, Held in Aberdeen Proving Ground, Maryland on 12-13 May 1993. Volume 1

    DTIC Science & Technology

    1994-05-01

    Used with limited success by Wicks and Dukler (1960), Magiros and Dukler (1961), Wailis (1962), Steen and Wallis (1964), Cousins et al. (1965), Gill and...CORRELATIONS * Purely Empirical Approach - Wicks and Dukler (1960) - Minh and Huyghe (1965) - Paleev and Filipovich (1966) - Wallis (1968) * Semi...shearing off of the roll waves. "* Studies of droplet sizes have been performed by Hinze (1955), Hass (1964), Wicks and Dukler (1966), Cousins and

  4. Canal Creek Study Area, Aberdeen Proving Ground, Edgewood Area, Maryland. Groundwater Monitoring Plan, Final Health and Safety Plan

    DTIC Science & Technology

    1993-10-01

    TLV) (Ev) Benzaldlehyde 50.00 ________ ______ Benzene 396.00 1 9.24 Benzoic Acid 6,190.00 Benzothiazole 51.50 ______ Benzyl Alcohol 7.08 bis-(2...allergic dermatitis; moderately toxic by ingestion and skin. Benzothiazole Poison by intraperitoneal, intravenous, and other routes. Benzyl alcohol ... alcohol and coffee are diuretics, the use of alcohol in non-working hours will be discouraged as will the intake of coffee during working hours

  5. Beach Point Test Site, Aberdeen Proving Ground, Edgewood Area, Maryland. Focused Feasibility Study, Final Project Work Plan

    DTIC Science & Technology

    1993-10-01

    water/sediments. Storm water runoff and dust/volatile emission release mechanisms transport contaminants present In the surface soil to either air or...Drinking Water Act (SDWA). 0 Clean Air Act (CAA). 0 Clean Water Act (CWA). * Marine Protection, Research and Sanctuaries Act (MPRSA). * Solid Waste...drinking water source; therefore the SDWA MCLs are probably neither applicable or relevant and appropriate. Clean Air Act National Primary/Secondary

  6. An Analysis of Multiple Award Indefinite Delivery Indefinite Quantity Contracts at the Army Contracting Command -- Aberdeen Proving Ground

    DTIC Science & Technology

    2012-09-01

    quantity of 100 horses/ burros was insufficient to form binding contract. GAO denied the protest on the grounds that historical data indicated that...100 horses/ burros was a number the government was fairly certain to order and that given the multiple award nature of the IDIQ contract there was no...certainty how many horses/ burros each individual contractor would handle over the life of the contract. (Gamboa, 2000) c. B-291185: ABF Freight System’s

  7. Work Plan for the Feasibility Study for Remedial Action at J-Field, Aberdeen Proving Ground, Maryland

    SciTech Connect

    Benioff, P.; Biang, C.; Haffenden, R.; Goyette, M.; Martino, L.; Patton, T.; Yuen, C.

    1995-05-01

    The purpose of the feasibility study is to gather sufficient information to develop and evaluate alternative remedial actions to address contamination at J-Field in compliance with the NCP, CERCLA, and SARA. This FS Work Plan summarizes existing environmental data for each AOC and outlines the tasks to be performed to evaluate and select remedial technologies. The tasks to be performed will include (1) developing remedial action objectives and identifying response actions to meet these objectives; (2) identifying and screening remedial action technologies on the basis of effectiveness, implementability, and cost; (3) assembling technologies into comprehensive alternatives for J-Field; (4) evaluating, in detail, each alternative against the nine EPA evaluation criteria and comparing the alternatives to identify their respective strengths and weaknesses; and (5) selecting the preferred alternative for each operable unit.

  8. Remedial investigation sampling and analysis plan for J-Field, Aberdeen Proving Ground, Maryland: Volume 2, Quality Assurance Project Plan

    SciTech Connect

    Prasad, S.; Martino, L.; Patton, T.

    1995-03-01

    J-Field encompasses about 460 acres at the southern end of the Gunpowder Neck Peninsula in the Edgewood Area of APG (Figure 2.1). Since World War II, the Edgewood Area of APG has been used to develop, manufacture, test, and destroy chemical agents and munitions. These materials were destroyed at J-Field by open burning and open detonation (OB/OD). For the purposes of this project, J-Field has been divided into eight geographic areas or facilities that are designated as areas of concern (AOCs): the Toxic Burning Pits (TBP), the White Phosphorus Burning Pits (WPP), the Riot Control Burning Pit (RCP), the Robins Point Demolition Ground (RPDG), the Robins Point Tower Site (RPTS), the South Beach Demolition Ground (SBDG), the South Beach Trench (SBT), and the Prototype Building (PB). The scope of this project is to conduct a remedial investigation/feasibility study (RI/FS) and ecological risk assessment to evaluate the impacts of past disposal activities at the J-Field site. Sampling for the RI will be carried out in three stages (I, II, and III) as detailed in the FSP. A phased approach will be used for the J-Field ecological risk assessment (ERA).

  9. Focused Feasibility Study Final Health and Safety Plan. Beach Point Test Site, Aberdeen Proving Ground, Edgewood Area, Maryland.

    DTIC Science & Technology

    1993-10-01

    nodes in the region of the bite will often be tender or painful . In severe cases, there is rigidity of the S abdominal muscles and pain in the lower ... male and female are venomous. They average 6 to 12 mm in body length. The bite of this spider produces about the same * * degree of pain as the sting...1-12 1.1.3.3 Department of the Army ................................... 1-12 1.1.4 References

  10. Defense Hotline Allegations Concerning the Fort Huachuca, Army Contracting Command- Aberdeen Proving Ground Contract Administration and Oversight Functions

    DTIC Science & Technology

    2014-04-14

    surveillance plan (QASP). Fmi Huachuca contracting officials stated in the contracting officer’s representative (COR) appointment letter that the COR...as quality assurance evaluators in the QASP, but they are acting as CORs or alternate CORs. Fmi Huachuca contracting officials should ensure all

  11. Health Risk Assessment of Consuming Deer from Aberdeen Proving Ground, Maryland. Report and Appendices A-D

    DTIC Science & Technology

    1995-05-01

    the less soluble compounds, which are more likely to cause chronic pulmonary effects if inhaled. One of the most toxic inorganic arsenic compounds...studies have shown lhat inorganic arsenic, by intralrachca! instillation, can cause pulmonary inflammation and hyperplasia (Webb el al., 1986, 1987...systemic effects, the less soluble compounds are more likely to cause chronic pulmonary effects if inhaled. One of the most toxic arsenic compounds is

  12. 77 FR 14047 - Guidance for Decommissioning Planning During Operations

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-03-08

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Guidance for Decommissioning Planning During Operations AGENCY: Nuclear Regulatory Commission... public comment period for Draft Regulatory Guide (DG)-4014, ``Decommissioning Planning During...

  13. Decommissioning and dismantling strategies in the Federal Republic of Germany

    SciTech Connect

    Brennecke, P.; Berg, H.P.; Weil, L.

    1993-12-31

    This report discusses the following aspects of decommissioning and dismantling strategies in the federal republic of germany: legal requirements, nuclear installations to be decommissioned, reactor dismantling techniques, and radioactive waste management.

  14. 26 CFR 1.88-1 - Nuclear decommissioning costs.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 26 Internal Revenue 2 2010-04-01 2010-04-01 false Nuclear decommissioning costs. 1.88-1 Section 1... (CONTINUED) INCOME TAXES (CONTINUED) Items Specifically Included in Gross Income § 1.88-1 Nuclear decommissioning costs. (a) In general. Section 88 provides that the amount of nuclear decommissioning...

  15. 78 FR 64028 - Decommissioning of Nuclear Power Reactors

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-10-25

    ... COMMISSION Decommissioning of Nuclear Power Reactors AGENCY: Nuclear Regulatory Commission. ACTION... regulatory guide (RG) 1.184 ``Decommissioning of Nuclear Power Reactors.'' This guide describes a method NRC... decommissioning process for nuclear power reactors. The revision takes advantage of the 13 years...

  16. 26 CFR 1.88-1 - Nuclear decommissioning costs.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 26 Internal Revenue 2 2014-04-01 2014-04-01 false Nuclear decommissioning costs. 1.88-1 Section 1... (CONTINUED) INCOME TAXES (CONTINUED) Items Specifically Included in Gross Income § 1.88-1 Nuclear decommissioning costs. (a) In general. Section 88 provides that the amount of nuclear decommissioning...

  17. 26 CFR 1.88-1 - Nuclear decommissioning costs.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 26 Internal Revenue 2 2011-04-01 2011-04-01 false Nuclear decommissioning costs. 1.88-1 Section 1... (CONTINUED) INCOME TAXES (CONTINUED) Items Specifically Included in Gross Income § 1.88-1 Nuclear decommissioning costs. (a) In general. Section 88 provides that the amount of nuclear decommissioning...

  18. 26 CFR 1.88-1 - Nuclear decommissioning costs.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 26 Internal Revenue 2 2012-04-01 2012-04-01 false Nuclear decommissioning costs. 1.88-1 Section 1... (CONTINUED) INCOME TAXES (CONTINUED) Items Specifically Included in Gross Income § 1.88-1 Nuclear decommissioning costs. (a) In general. Section 88 provides that the amount of nuclear decommissioning...

  19. 26 CFR 1.88-1 - Nuclear decommissioning costs.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 26 Internal Revenue 2 2013-04-01 2013-04-01 false Nuclear decommissioning costs. 1.88-1 Section 1... (CONTINUED) INCOME TAXES (CONTINUED) Items Specifically Included in Gross Income § 1.88-1 Nuclear decommissioning costs. (a) In general. Section 88 provides that the amount of nuclear decommissioning...

  20. Decision framework for platform decommissioning in California.

    PubMed

    Bernstein, Brock B

    2015-10-01

    This article describes the overall decision framework for eventual decisions about decommissioning the 27 operating oil and gas platforms offshore southern California. These platforms will eventually reach the end of their useful lifetimes (estimated between 2015 and 2030, although specific dates have not been determined). Current law and regulations allow for alternative uses in lieu of the complete removal required in existing leases. To prepare for eventual decommissioning, the California Natural Resources Agency initiated an in-depth process to identify and investigate issues surrounding possible decommissioning alternatives. The detailed evaluation of alternatives focused on 2-complete removal and artificial reefing that included partial removal to 85 feet below the waterline. These were selected after a comparison of the technical and economic feasibility of several potential alternatives, availability of a legal framework for implementation, degree of interest from proponents, and relative acceptance by state and federal decision makers. Despite California's history of offshore oil and gas production, only 7 decommissioning projects have been completed and these were all relatively small and close to shore. In contrast, nearly 30% of the California platforms are in water depths (as much as 1200 feet) that exceed any decommissioning project anywhere in the world. Most earlier projects considered an artificial reefing alternative but none were implemented and all platforms were completely removed. Future decisions about decommissioning must grapple with a more complex decision context involving greater technological and logistical challenges and cost, a wider range of viable options, tradeoffs among environmental impacts and benefits, and an intricate maze of laws, regulations, and authorities. The specific engineering differences between complete and partial removal provide an explicit basis for a thorough evaluation of their respective impacts.

  1. Decontamination, decommissioning, and vendor advertorial issue, 2006

    SciTech Connect

    Agnihotri, Newal

    2006-07-15

    The focus of the July-August issue is on Decontamination, decommissioning, and vendor advertorials. Major articles/reports in this issue include: NPP Krsko revised decommissioning program, by Vladimir Lokner and Ivica Levanat, APO d.o.o., Croatia, and Nadja Zeleznik and Irena Mele, ARAO, Slovenia; Supporting the renaissance, by Marilyn C. Kray, Exelon Nuclear; Outage world an engineer's delight, by Tom Chrisopher, Areva, NP Inc.; Optimizing refueling outages with R and D, by Ross Marcoot, GE Energy; and, A successful project, by Jim Lash, FirstEnergy.

  2. The environmental issues of platform decommissioning

    SciTech Connect

    Susani, L.

    1996-12-31

    This paper provides a review of the environmental impacts of offshore platform disposal, based on past activities and technical and research studies. Environmental impacts are considered in relation to four main decommissioning options. The most significant effects stem from explosive cutting, sediment resuspension and release of contamination during initial production shut-down, well purging and removal of the jacket structure from the seabed. Any decommissioning option that minimizes movement of structures and avoids explosive cutting must therefore be viewed as preferable from an ecological viewpoint. Complete removal is preferred on the grounds of energy conservation, fisheries and navigational safety, and controlled disposal of potential contaminants.

  3. The Windscale Advanced Gas Cooled Reactor (WAGR) Decommissioning Project A Close Out Report for WAGR Decommissioning Campaigns 1 to 10 - 12474

    SciTech Connect

    Halliwell, Chris

    2012-07-01

    The reactor core of the Windscale Advanced Gas-Cooled Reactor (WAGR) has been dismantled as part of an ongoing decommissioning project. The WAGR operated until 1981 as a development reactor for the British Commercial Advanced Gas cooled Reactor (CAGR) power programme. Decommissioning began in 1982 with the removal of fuel from the reactor core which was completed in 1983. Subsequently, a significant amount of engineering work was carried out, including removal of equipment external to the reactor and initial manual dismantling operations at the top of the reactor, in preparation for the removal of the reactor core itself. Modification of the facility structure and construction of the waste packaging plant served to provide a waste route for the reactor components. The reactor core was dismantled on a 'top-down' basis in a series of 'campaigns' related to discrete reactor components. This report describes the facility, the modifications undertaken to facilitate its decommissioning and the strategies employed to recognise the successful decommissioning of the reactor. Early decommissioning tasks at the top of the reactor were undertaken manually but the main of the decommissioning tasks were carried remotely, with deployment systems comprising of little more than crane like devices, intelligently interfaced into the existing structure. The tooling deployed from the 3 tonne capacity (3te) hoist consisted either purely mechanical devices or those being electrically controlled from a 'push-button' panel positioned at the operator control stations, there was no degree of autonomy in the 3te hoist or any of the tools deployed from it. Whilst the ATC was able to provide some tele-robotic capabilities these were very limited and required a good degree of driver input which due to the operating philosophy at WAGR was not utilised. The WAGR box proved a successful waste package, adaptable through the use of waste box furniture specific to the waste-forms generated throughout

  4. 75 FR 80697 - Nuclear Decommissioning Funds

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-23

    ...This document contains final regulations under section 468A of the Internal Revenue Code relating to deductions for contributions to trusts maintained for decommissioning nuclear power plants. These final regulations affect taxpayers that own an interest in a nuclear power plant and reflect recent statutory changes. The corresponding temporary regulations are...

  5. Decontamination and decommissioning of Shippingport commercial reactor

    SciTech Connect

    Schreiber, J.

    1989-11-01

    To a certain degree, the decontamination and decommissioning (D and D) of the Shippingport reactor was a joint venture with Duquesne Light Company. The structures that were to be decommissioned were to be removed to at least three feet below grade. Since the land had been leased from Duquesne Light, there was an agreement with them to return the land to them in a radiologically safe condition. The total enclosure volume for the steam and nuclear containment systems was about 1.3 million cubic feet, more than 80% of which was below ground. Engineering plans for the project were started in July of 1980 and the final environmental impact statement (EIS) was published in May of 1982. The plant itself was shut down in October of 1982 for end-of-life testing and defueling. The engineering services portion of the decommissioning plans was completed in September of 1983. DOE moved onto the site and took over from the Navy in September of 1984. Actual physical decommissioning began after about a year of preparation and was completed about 44 months later in July of 1989. This paper describes the main parts of D and D.

  6. Sodium Reactor Experiment decommissioning. Final report

    SciTech Connect

    Carroll, J.W.; Conners, C.C.; Harris, J.M.; Marzec, J.M.; Ureda, B.F.

    1983-08-15

    The Sodium Reactor Experiment (SRE) located at the Rockwell International Field Laboratories northwest of Los Angeles was developed to demonstrate a sodium-cooled, graphite-moderated reactor for civilian use. The reactor reached full power in May 1958 and provided 37 GWh to the Southern California Edison Company grid before it was shut down in 1967. Decommissioning of the SRE began in 1974 with the objective of removing all significant radioactivity from the site and releasing the facility for unrestricted use. Planning documentation was prepared to describe in detail the equipment and techniques development and the decommissioning work scope. A plasma-arc manipulator was developed for remotely dissecting the highly radioactive reactor vessels. Other important developments included techniques for using explosives to cut reactor vessel internal piping, clamps, and brackets; decontaminating porous concrete surfaces; and disposing of massive equipment and structures. The documentation defined the decommissioning in an SRE dismantling plan, in activity requirements for elements of the decommissioning work scope, and in detailed procedures for each major task.

  7. 76 FR 77431 - Decommissioning Planning During Operations

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-13

    ...; ] NUCLEAR REGULATORY COMMISSION 10 CFR Parts 20, 30, 40, 50, 70, and 72 RIN 3150-AI55 Decommissioning Planning During Operations AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide; request for comment. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment...

  8. 78 FR 663 - Decommissioning Planning During Operations

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-04

    ..., Regulatory Guide Development Branch, Division of Engineering, Office of Nuclear Regulatory Research. BILLING... / Friday, January 4, 2013 / Rules and Regulations#0;#0; ] NUCLEAR REGULATORY COMMISSION 10 CFR Parts 20, 30, 40, 50, 70, and 72 RIN 3150-AI55 Decommissioning Planning During Operations AGENCY:...

  9. Decontamination and decommissioning focus area. Technology summary

    SciTech Connect

    1995-06-01

    This report presents details of the facility deactivation, decommissioning, and material disposition research for development of new technologies sponsored by the Department of Energy. Topics discussed include; occupational safety, radiation protection, decontamination, remote operated equipment, mixed waste processing, recycling contaminated metals, and business opportunities.

  10. University of Virginia Reactor Facility Decommissioning Results

    SciTech Connect

    Ervin, P. F.; Lundberg, L. A.; Benneche, P. E.; Mulder, R. U.; Steva, D. P.

    2003-02-24

    The University of Virginia Reactor Facility started accelerated decommissioning in 2002. The facility consists of two licensed reactors, the CAVALIER and the UVAR. This paper will describe the progress in 2002, remaining efforts and the unique organizational structure of the project team.

  11. Is Proving a Visual Act?

    ERIC Educational Resources Information Center

    Mudaly, Vimolan

    2013-01-01

    This paper looks at the role of visualisation in the proving process. It considers the different functions of proof and then describes student responses when engaged in the process of discovering Viviani's Theorem. The findings show that learners can attain high levels of conviction when working in a dynamic geometry environment. In particular,…

  12. 75 FR 67775 - Washington Department of Transportation, Olympic Division, Aberdeen Maintenance Office, Chehalis...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-11-03

    ... Maintenance Office, Chehalis Drawbridge Tenders, Aberdeen, WA; Notice of Negative Determination Regarding..., requested administrative reconsideration of the negative determination regarding workers' ] eligibility to... justified reconsideration of the decision. The negative determination of the TAA petition filed on behalf...

  13. The Development in Scotland of a University Company Group: The Aberdeen Experience.

    ERIC Educational Resources Information Center

    Sellar, Keith

    1985-01-01

    The University of Aberdeen's development, with the petroleum industry, of a group of companies for research and development are discussed, including problems encountered and recommendations for other universities with similar interests. (MSE)

  14. Proving Program Correctness. Volume V.

    DTIC Science & Technology

    1981-11-01

    td&Ot’ ’i number) Programming Sy Stems S.. - nulation Pr~ogramming Languages Sche,!%L -g Algorithm Programming Grammars Logic Programming 9roving...able to prove that programs perform as they are specified than is currently possible. Task 3. Grammars of Programming (P.I.: E.F. Storm). This group is...is "An Algorithmic Solution for a Queueing Model of a Computer System with Interactive and Batch Jobs. Volume 4. Report from the Grammars of

  15. NMSS handbook for decommissioning fuel cycle and materials licensees

    SciTech Connect

    Orlando, D.A.; Hogg, R.C.; Ramsey, K.M.

    1997-03-01

    The US Nuclear Regulatory Commission amended its regulations to set forth the technical and financial criteria for decommissioning licensed nuclear facilities. These regulations were further amended to establish additional recordkeeping requirements for decommissioning; to establish timeframes and schedules for the decommissioning; and to clarify that financial assurance requirements must be in place during operations and updated when licensed operations cease. Reviews of the Site Decommissioning Management Plan (SDMP) program found that, while the NRC staff was overseeing the decommissioning program at nuclear facilities in a manner that was protective of public health and safety, progress in decommissioning many sites was slow. As a result NRC determined that formal written procedures should be developed to facilitate the timely decommissioning of licensed nuclear facilities. This handbook was developed to aid NRC staff in achieving this goal. It is intended to be used as a reference document to, and in conjunction with, NRC Inspection Manual Chapter (IMC) 2605, ``Decommissioning Inspection Program for Fuel Cycle and Materials Licensees.`` The policies and procedures discussed in this handbook should be used by NRC staff overseeing the decommissioning program at licensed fuel cycle and materials sites; formerly licensed sites for which the licenses were terminated; sites involving source, special nuclear, or byproduct material subject to NRC regulation for which a license was never issued; and sites in the NRC`s SDMP program. NRC staff overseeing the decommissioning program at nuclear reactor facilities subject to regulation under 10 CFR Part 50 are not required to use the procedures discussed in this handbook.

  16. 30 CFR 250.1753 - After I decommission a pipeline, what information must I submit?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 2 2012-07-01 2012-07-01 false After I decommission a pipeline, what... SHELF Decommissioning Activities Pipeline Decommissioning § 250.1753 After I decommission a pipeline, what information must I submit? Within 30 days after you decommission a pipeline, you must submit...

  17. 30 CFR 250.1754 - When must I remove a pipeline decommissioned in place?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 2 2013-07-01 2013-07-01 false When must I remove a pipeline decommissioned in... Decommissioning Activities Pipeline Decommissioning § 250.1754 When must I remove a pipeline decommissioned in place? You must remove a pipeline decommissioned in place if the Regional Supervisor determines that...

  18. 30 CFR 250.1750 - When may I decommission a pipeline in place?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 2 2012-07-01 2012-07-01 false When may I decommission a pipeline in place... Decommissioning Activities Pipeline Decommissioning § 250.1750 When may I decommission a pipeline in place? You may decommission a pipeline in place when the Regional Supervisor determines that the pipeline...

  19. 30 CFR 250.1754 - When must I remove a pipeline decommissioned in place?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 2 2012-07-01 2012-07-01 false When must I remove a pipeline decommissioned in... Decommissioning Activities Pipeline Decommissioning § 250.1754 When must I remove a pipeline decommissioned in place? You must remove a pipeline decommissioned in place if the Regional Supervisor determines that...

  20. 30 CFR 250.1754 - When must I remove a pipeline decommissioned in place?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 30 Mineral Resources 2 2011-07-01 2011-07-01 false When must I remove a pipeline decommissioned in... SHELF Decommissioning Activities Pipeline Decommissioning § 250.1754 When must I remove a pipeline decommissioned in place? You must remove a pipeline decommissioned in place if the Regional Supervisor...

  1. 30 CFR 250.1753 - After I decommission a pipeline, what information must I submit?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 2 2010-07-01 2010-07-01 false After I decommission a pipeline, what... Decommissioning Activities Pipeline Decommissioning § 250.1753 After I decommission a pipeline, what information must I submit? Within 30 days after you decommission a pipeline, you must submit a written report...

  2. 30 CFR 250.1754 - When must I remove a pipeline decommissioned in place?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 30 Mineral Resources 2 2014-07-01 2014-07-01 false When must I remove a pipeline decommissioned in... Decommissioning Activities Pipeline Decommissioning § 250.1754 When must I remove a pipeline decommissioned in place? You must remove a pipeline decommissioned in place if the Regional Supervisor determines that...

  3. 30 CFR 250.1753 - After I decommission a pipeline, what information must I submit?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 30 Mineral Resources 2 2014-07-01 2014-07-01 false After I decommission a pipeline, what... SHELF Decommissioning Activities Pipeline Decommissioning § 250.1753 After I decommission a pipeline, what information must I submit? Within 30 days after you decommission a pipeline, you must submit...

  4. 30 CFR 250.1750 - When may I decommission a pipeline in place?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 30 Mineral Resources 2 2011-07-01 2011-07-01 false When may I decommission a pipeline in place... SHELF Decommissioning Activities Pipeline Decommissioning § 250.1750 When may I decommission a pipeline in place? You may decommission a pipeline in place when the Regional Supervisor determines that...

  5. 30 CFR 250.1750 - When may I decommission a pipeline in place?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 30 Mineral Resources 2 2014-07-01 2014-07-01 false When may I decommission a pipeline in place... Decommissioning Activities Pipeline Decommissioning § 250.1750 When may I decommission a pipeline in place? You may decommission a pipeline in place when the Regional Supervisor determines that the pipeline...

  6. 30 CFR 250.1751 - How do I decommission a pipeline in place?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 2 2013-07-01 2013-07-01 false How do I decommission a pipeline in place? 250... Decommissioning Activities Pipeline Decommissioning § 250.1751 How do I decommission a pipeline in place? You must do the following to decommission a pipeline in place: (a) Submit a pipeline...

  7. 30 CFR 250.1750 - When may I decommission a pipeline in place?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 2 2013-07-01 2013-07-01 false When may I decommission a pipeline in place... Decommissioning Activities Pipeline Decommissioning § 250.1750 When may I decommission a pipeline in place? You may decommission a pipeline in place when the Regional Supervisor determines that the pipeline...

  8. 30 CFR 250.1753 - After I decommission a pipeline, what information must I submit?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 2 2013-07-01 2013-07-01 false After I decommission a pipeline, what... SHELF Decommissioning Activities Pipeline Decommissioning § 250.1753 After I decommission a pipeline, what information must I submit? Within 30 days after you decommission a pipeline, you must submit...

  9. 30 CFR 250.1753 - After I decommission a pipeline, what information must I submit?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 30 Mineral Resources 2 2011-07-01 2011-07-01 false After I decommission a pipeline, what... OUTER CONTINENTAL SHELF Decommissioning Activities Pipeline Decommissioning § 250.1753 After I decommission a pipeline, what information must I submit? Within 30 days after you decommission a pipeline,...

  10. In Situ Decommissioning (ISD) Concepts and Approaches for Excess Nuclear Facilities Decommissioning End State - 13367

    SciTech Connect

    Serrato, Michael G.; Musall, John C.; Bergren, Christopher L.

    2013-07-01

    The United States Department of Energy (DOE) currently has numerous radiologically contaminated excess nuclear facilities waiting decommissioning throughout the Complex. The traditional decommissioning end state is complete removal. This commonly involves demolishing the facility, often segregating various components and building materials and disposing of the highly contaminated, massive structures containing tons of highly contaminated equipment and piping in a (controlled and approved) landfill, at times hundreds of miles from the facility location. Traditional demolition is costly, and results in significant risks to workers, as well as risks and costs associated with transporting the materials to a disposal site. In situ decommissioning (ISD or entombment) is a viable alternative to demolition, offering comparable and potentially more protective protection of human health and the environment, but at a significantly reduced cost and worker risk. The Savannah River Site (SRS) has completed the initial ISD deployment for radiologically contaminated facilities. Two reactor (P and R Reactors) facilities were decommissioned in 2011 using the ISD approach through the American Recovery and Reinvestment Act. The SRS ISD approach resolved programmatic, regulatory and technical/engineering issues associated with avoiding the potential hazards and cost associated with generating and disposing of an estimated 124,300 metric tons (153,000 m{sup 3}) of contaminated debris per reactor. The DOE Environmental Management Office of Deactivation and Decommissioning and Facility Engineering, through the Savannah River National Laboratory, is currently investigating potential monitoring techniques and strategies to assess ISD effectiveness. As part of SRS's strategic planning, the site is seeking to leverage in situ decommissioning concepts, approaches and facilities to conduct research, design end states, and assist in regulatory interactions in broad national and international

  11. Proving Stabilization of Biological Systems

    NASA Astrophysics Data System (ADS)

    Cook, Byron; Fisher, Jasmin; Krepska, Elzbieta; Piterman, Nir

    We describe an efficient procedure for proving stabilization of biological systems modeled as qualitative networks or genetic regulatory networks. For scalability, our procedure uses modular proof techniques, where state-space exploration is applied only locally to small pieces of the system rather than the entire system as a whole. Our procedure exploits the observation that, in practice, the form of modular proofs can be restricted to a very limited set. For completeness, our technique falls back on a non-compositional counterexample search. Using our new procedure, we have solved a number of challenging published examples, including: a 3-D model of the mammalian epidermis; a model of metabolic networks operating in type-2 diabetes; a model of fate determination of vulval precursor cells in the C. elegans worm; and a model of pair-rule regulation during segmentation in the Drosophila embryo. Our results show many orders of magnitude speedup in cases where previous stabilization proving techniques were known to succeed, and new results in cases where tools had previously failed.

  12. Decommissioning of the Tokamak Fusion Test Reactor

    SciTech Connect

    E. Perry; J. Chrzanowski; C. Gentile; R. Parsells; K. Rule; R. Strykowsky; M. Viola

    2003-10-28

    The Tokamak Fusion Test Reactor (TFTR) at the Princeton Plasma Physics Laboratory was operated from 1982 until 1997. The last several years included operations with mixtures of deuterium and tritium. In September 2002, the three year Decontamination and Decommissioning (D&D) Project for TFTR was successfully completed. The need to deal with tritium contamination as well as activated materials led to the adaptation of many techniques from the maintenance work during TFTR operations to the D&D effort. In addition, techniques from the decommissioning of fission reactors were adapted to the D&D of TFTR and several new technologies, most notably the development of a diamond wire cutting process for complex metal structures, were developed. These techniques, along with a project management system that closely linked the field crews to the engineering staff who developed the techniques and procedures via a Work Control Center, resulted in a project that was completed safely, on time, and well below budget.

  13. Yankee Nuclear Power Station - analysis of decommissioning costs

    SciTech Connect

    Lessard, L.P.

    1996-12-31

    The preparation of decommissioning cost estimates for nuclear power generating stations has received a great deal of interest in the last few years. Owners are required by regulation to ensure that adequate funds are collected for the timely decommissioning of their facilities. The unexpected premature shutdown of several facilities and uncertainties associated with radioactive waste disposal and long-term spent-fuel storage, when viewed in the light of a deregulated electric utility industry, has caused many companies to reevaluate their decommissioning cost estimates. The decommissioning of the Yankee Nuclear Power Station represents the first large-scale project involving the complete decontamination and dismantlement of a commercial light water nuclear power generation facility in the United States. Since this pressurized water reactor operated for 32 yr at a respectable 74% lifetime capacity factor, the actual costs and resources required to decommission the plant, when compared with decommissioning estimates, will yield valuable benchmarking data.

  14. Decommissioning Cost Estimating -The ''Price'' Approach

    SciTech Connect

    Manning, R.; Gilmour, J.

    2002-02-26

    Over the past 9 years UKAEA has developed a formalized approach to decommissioning cost estimating. The estimating methodology and computer-based application are known collectively as the PRICE system. At the heart of the system is a database (the knowledge base) which holds resource demand data on a comprehensive range of decommissioning activities. This data is used in conjunction with project specific information (the quantities of specific components) to produce decommissioning cost estimates. PRICE is a dynamic cost-estimating tool, which can satisfy both strategic planning and project management needs. With a relatively limited analysis a basic PRICE estimate can be produced and used for the purposes of strategic planning. This same estimate can be enhanced and improved, primarily by the improvement of detail, to support sanction expenditure proposals, and also as a tender assessment and project management tool. The paper will: describe the principles of the PRICE estimating system; report on the experiences of applying the system to a wide range of projects from contaminated car parks to nuclear reactors; provide information on the performance of the system in relation to historic estimates, tender bids, and outturn costs.

  15. Aberdeen Area Indian Health Service Environmental Health Program Review Conducted by: Indian Health Committee of the National Environmental Health Association (Aberdeen, South Dakota, May 23-27, 1977).

    ERIC Educational Resources Information Center

    Bureau of Indian Affairs (Dept. of Interior), Aberdeen, SD. Aberdeen Area Office.

    The Indian Health Committee met in Aberdeen, South Dakota, during the week of May 23, 1977 to (1) review the environmental health services provided to the tribal units on the 15 Indian reservations located in North Dakota, South Dakota, Nebraska and Iowa, and (2) make recommendations for improvement or expansion of current programs, if needed. The…

  16. HEAVY WATER COMPONENTS TEST REACTOR DECOMMISSIONING

    SciTech Connect

    Austin, W.; Brinkley, D.

    2011-10-13

    The Heavy Water Components Test Reactor (HWCTR) Decommissioning Project was initiated in 2009 as a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) Removal Action with funding from the American Recovery and Reinvestment Act (ARRA). This paper summarizes the history prior to 2009, the major D&D activities, and final end state of the facility at completion of decommissioning in June 2011. The HWCTR facility was built in 1961, operated from 1962 to 1964, and is located in the northwest quadrant of the Savannah River Site (SRS) approximately three miles from the site boundary. The HWCTR was a pressurized heavy water test reactor used to develop candidate fuel designs for heavy water power reactors. In December of 1964, operations were terminated and the facility was placed in a standby condition as a result of the decision by the U.S. Atomic Energy Commission to redirect research and development work on heavy water power reactors to reactors cooled with organic materials. For about one year, site personnel maintained the facility in a standby status, and then retired the reactor in place. In the early 1990s, DOE began planning to decommission HWCTR. Yet, in the face of new budget constraints, DOE deferred dismantlement and placed HWCTR in an extended surveillance and maintenance mode. The doors of the reactor facility were welded shut to protect workers and discourage intruders. In 2009 the $1.6 billion allocation from the ARRA to SRS for site footprint reduction at SRS reopened the doors to HWCTR - this time for final decommissioning. Alternative studies concluded that the most environmentally safe, cost effective option for final decommissioning was to remove the reactor vessel, both steam generators, and all equipment above grade including the dome. The transfer coffin, originally above grade, was to be placed in the cavity vacated by the reactor vessel and the remaining below grade spaces would be grouted. Once all above equipment

  17. Decommissioning: Nuclear Power's Missing Link. Worldwatch Paper 69.

    ERIC Educational Resources Information Center

    Pollock, Cynthia

    The processes and associated dilemmas of nuclear power plant decommissioning are reviewed in this publication. Decommissioning involves the clearing up and disposal of a retired nuclear plant and its equipment of such a way as to safeguard the public from the dangers of radioactivity. Related problem areas are identified and include: (1) closure…

  18. Optimising waste management performance - The key to successful decommissioning

    SciTech Connect

    Keep, Matthew

    2007-07-01

    Available in abstract form only. Full text of publication follows: On the 1. of April 2005 the United Kingdom's Nuclear Decommissioning Authority became responsible for the enormous task of decommissioning the UK's civilian nuclear liabilities. The success of the NDA in delivering its key objectives of safer, cheaper and faster decommissioning depends on a wide range factors. It is self-evident, however, that the development of robust waste management practices by those charged with decommissioning liability will be at the heart of the NDA's business. In addition, the implementation of rigorous waste minimisation techniques throughout decommissioning will deliver tangible environmental benefits as well as better value for money and release funds to accelerate the decommissioning program. There are mixed views as to whether waste minimisation can be achieved during decommissioning. There are those that argue that the radioactive inventory already exists, that the amount of radioactivity cannot be minimised and that the focus of activities should be focused on waste management rather than waste minimisation. Others argue that the management and decommissioning of the UK's civilian nuclear liability will generate significant volumes of additional radioactive waste and it is in this area where the opportunities for waste minimisation can be realised. (author)

  19. Decommissioning considerations at a time of nuclear renaissance

    SciTech Connect

    Devgun, Jas S.

    2007-07-01

    At a time of renaissance in the nuclear power industry, when it is estimated that anywhere between 60 to 130 new power reactors may be built worldwide over the next 15 years, why should we focus on decommissioning? Yet it is precisely the time to examine what decommissioning considerations should be taken into account as the industry proceeds with developing final designs for new reactors and the construction on the new build begins. One of the lessons learned from decommissioning of existing reactors has been that decommissioning was not given much thought when these reactors were designed three or four decades ago. Even though decommissioning may be sixty years down the road from the time they go on line, eventually all reactors will be decommissioned. It is only prudent that new designs be optimized for eventual decommissioning, along with the other major considerations. The overall objective in this regard is that when the time comes for decommissioning, it can be completed in shorter time frames, with minimum generation of radioactive waste, and with better radiological safety. This will ensure that the tail end costs of the power reactors are manageable and that the public confidence in the nuclear power is sustained through the renaissance and beyond. (author)

  20. A review of decommissioning considerations for new reactors

    SciTech Connect

    Devgun, J.S.Ph.D.

    2008-07-01

    At a time of 'nuclear renaissance' when the focus is on advanced reactor designs and construction, it is easy to overlook the decommissioning considerations because such a stage in the life of the new reactors will be some sixty years down the road. Yet, one of the lessons learned from major decommissioning projects has been that decommissioning was not given much thought when these reactors were designed three or four decades ago. Hence, the time to examine what decommissioning considerations should be taken into account is right from the design stage with regular updates of the decommissioning strategy and plans throughout the life cycle of the reactor. Designing D and D into the new reactor designs is necessary to ensure that the tail end costs of the nuclear power are manageable. Such considerations during the design stage will facilitate a more cost-effective, safe and timely decommissioning of the facility when a reactor is eventually retired. This paper examines the current regulatory and industry design guidance for the new reactors with respect to the decommissioning issues and provides a review of the design considerations that can help optimize the reactor designs for the eventual decommissioning. (authors)

  1. Decontamination, decommissioning, and vendor advertorial issue, 2007

    SciTech Connect

    Agnihotri, Newal

    2007-07-15

    The focus of the July-August issue is on Decontamination, decommissioning, and vendor advertorials. Major articles/reports in this issue include: An interesting year ahead of us, by Tom Christopher, AREVA NP Inc.; U.S.-India Civil Nuclear Cooperation; Decontamination and recycling of retired components, by Sean P. Brushart, Electric Power Research Institute; and, ANO is 33 and going strong, by Tyler Lamberts, Entergy Nuclear Operations, Inc. The industry innovation article is: Continuous improvement process, by ReNae Kowalewski, Arkansas Nuclear One.

  2. Environmental Impact Assessment (EIA) Process of V1 NPP Decommissioning

    SciTech Connect

    Matejovic, Igor; Polak, Vincent

    2007-07-01

    Through the adoption of Governmental Resolution No. 801/99 the Slovak Republic undertook a commitment to shutdown units 1 and 2 of Jaslovske Bohunice V 1 NPP (WWER 230 reactor type) in 2006 and 2008 respectively. Therefore the more intensive preparation of a decommissioning documentation has been commenced. Namely, the VI NPP Conceptual Decommissioning Plan and subsequently the Environmental Impact Assessment Report of VI NPP Decommissioning were developed. Thus, the standard environmental impact assessment process was performed and the most suitable alternative of V1 NPP decommissioning was selected as a basis for development of further decommissioning documents. The status and main results of the environmental impact assessment process and EIA report are discussed in more detail in this paper. (authors)

  3. Pre-decommissioning radiological characterization of concrete

    SciTech Connect

    Boden, Sven; Cantrel, Eric

    2007-07-01

    The decommissioning of the BR3 (Belgian Reactor 3) approaches its final phase, in which the building structures are being decontaminated and either denuclearized for possible reuse or demolished. Apart from the presence of naturally occurring radionuclides in building materials, other radionuclides might be present due to contamination or activation. The overall process of the BR3 building structure D and D (Decontamination and Decommissioning) consists of the following steps: - make a complete inventory and preliminary categorize all elements based on historical data; characterize and determine the contamination or activation depth; - determine the decontamination method; - perform the decontamination and clean up; - a possible intermediate characterization followed by an additional decontamination step; and characterize for clearance. A good knowledge of the contamination and activation depth (second step) is fundamental in view of cost minimization. Currently, the method commonly used for the determination of the depth is based on core drilling and destructive analysis. Recently, we have introduced a complementary non destructive assay based on in-situ gamma spectroscopy. Field tests at BR3, both for contamination and activation, showed promising results. (authors)

  4. Nuclear facility decommissioning and site remedial actions

    SciTech Connect

    Owen, P.T.; Knox, N.P.; Ferguson, S.D.; Fielden, J.M.; Schumann, P.L.

    1989-09-01

    The 576 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the tenth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title work, publication description, geographic location, subject category, and keywords.

  5. Nuclear facility decommissioning and site remedial actions

    SciTech Connect

    Knox, N.P.; Webb, J.R.; Ferguson, S.D.; Goins, L.F.; Owen, P.T.

    1990-09-01

    The 394 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eleventh in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Programs, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Grand Junction Remedial Action Program, (7) Uranium Mill Tailings Management, (8) Technical Measurements Center, (9) Remedial Action Program, and (10) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies.

  6. Lessons learnt from Ignalina NPP decommissioning project

    SciTech Connect

    NAISSE, Jean-Claude

    2007-07-01

    The Ignalina Nuclear Power Plant (INPP) is located in Lithuania, 130 km north of Vilnius, and consists of two 1500 MWe RBMK type units, commissioned respectively in December 1983 and August 1987. On the 1. of May 2004, the Republic of Lithuania became a member of the European Union. With the protocol on the Ignalina Nuclear Power in Lithuania which is annexed to the Accession Treaty, the Contracting Parties have agreed: - On Lithuanian side, to commit closure of unit 1 of INPP before 2005 and of Unit 2 by 31 December 2009; - On European Union side, to provide adequate additional Community assistance to the efforts of Lithuania to decommission INPP. The paper is divided in two parts. The first part describes how, starting from this agreement, the project was launched and organized, what is its present status and which activities are planned to reach the final ambitious objective of a green field. To give a global picture, the content of the different projects that were defined and the licensing process will also be presented. In the second part, the paper will focus on the lessons learnt. It will explain the difficulties encountered to define the decommissioning strategy, considering both immediate or differed dismantling options and why the first option was finally selected. The paper will mention other challenges and problems that the different actors of the project faced and how they were managed and solved. The paper will be written by representatives of the Ignalina NPP and of the Project Management Unit. (author)

  7. 26 CFR 1.468A-4T - Treatment of nuclear decommissioning fund (temporary).

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 26 Internal Revenue 6 2010-04-01 2010-04-01 false Treatment of nuclear decommissioning fund...-4T Treatment of nuclear decommissioning fund (temporary). (a) In general. A nuclear decommissioning... income earned by the assets of the nuclear decommissioning fund. (b) Modified gross income. For...

  8. 26 CFR 1.468A-4 - Treatment of nuclear decommissioning fund.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 26 Internal Revenue 6 2011-04-01 2011-04-01 false Treatment of nuclear decommissioning fund. 1...-4 Treatment of nuclear decommissioning fund. (a) In general. A nuclear decommissioning fund is... by the assets of the nuclear decommissioning fund. (b) Modified gross income. For purposes of...

  9. 26 CFR 1.468A-4 - Treatment of nuclear decommissioning fund.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 26 Internal Revenue 6 2012-04-01 2012-04-01 false Treatment of nuclear decommissioning fund. 1...-4 Treatment of nuclear decommissioning fund. (a) In general. A nuclear decommissioning fund is... by the assets of the nuclear decommissioning fund. (b) Modified gross income. For purposes of...

  10. 26 CFR 1.468A-4 - Treatment of nuclear decommissioning fund.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 26 Internal Revenue 6 2014-04-01 2014-04-01 false Treatment of nuclear decommissioning fund. 1...-4 Treatment of nuclear decommissioning fund. (a) In general. A nuclear decommissioning fund is... by the assets of the nuclear decommissioning fund. (b) Modified gross income. For purposes of...

  11. 26 CFR 1.468A-4 - Treatment of nuclear decommissioning fund.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 26 Internal Revenue 6 2013-04-01 2013-04-01 false Treatment of nuclear decommissioning fund. 1...-4 Treatment of nuclear decommissioning fund. (a) In general. A nuclear decommissioning fund is... by the assets of the nuclear decommissioning fund. (b) Modified gross income. For purposes of...

  12. 30 CFR 250.1750 - When may I decommission a pipeline in place?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 2 2010-07-01 2010-07-01 false When may I decommission a pipeline in place... Pipeline Decommissioning § 250.1750 When may I decommission a pipeline in place? You may decommission a pipeline in place when the Regional Supervisor determines that the pipeline does not constitute a...

  13. 30 CFR 250.1754 - When must I remove a pipeline decommissioned in place?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 2 2010-07-01 2010-07-01 false When must I remove a pipeline decommissioned in... Activities Pipeline Decommissioning § 250.1754 When must I remove a pipeline decommissioned in place? You must remove a pipeline decommissioned in place if the Regional Supervisor determines that the...

  14. DECOMMISSIONING OF A CAESIUM-137 SEALED SOURCE PRODUCTION FACILITY

    SciTech Connect

    Murray, A.; Abbott, H.

    2003-02-27

    Amersham owns a former Caesium-137 sealed source production facility. They commissioned RWE NUKEM to carry out an Option Study to determine a strategy for the management of this facility and then the subsequent decommissioning of it. The decommissioning was carried out in two sequential phases. Firstly robotic decommissioning followed by a phase of manual decommissioning. This paper describes the remote equipment designed built and operated, the robotic and manual decommissioning operations performed, the Safety Management arrangements and summarizes the lessons learned. Using the equipment described the facility was dismantled and decontaminated robotically. Some 2300kg of Intermediate Level Waste containing in the order of 4000Ci were removed robotically from the facility. Ambient dose rates were reduced from 100's of R per hour {gamma} to 100's of mR per hour {gamma}. The Telerobotic System was then removed to allow man access to complete the decommissioning. Manual decommissioning reduced ambient dose rates further to less than 1mR per hour {gamma} and loose contamination levels to less than 0.25Bq/cm2. This allowed access to the facility without respiratory protection.

  15. Decommissioning planning for the Joint European Torus Fusion Reactor

    SciTech Connect

    Wilson, K.A.; Stevens, K.

    2007-07-01

    The Joint European Torus (JET) machine is an experimental nuclear fusion device built in the United Kingdom by a European consortium. Tritium was first introduced into the Torus as a fuel in 1991 and it is estimated that at the end of operations and following a period of tritium recovery there will be 2 grams of tritium in the vacuum circuit. All in-vessel items are also contaminated with beryllium and the structure of the machine is neutron activated. Decommissioning of the facility will commence immediately JET operations cease and the UKAEA's plan is to remove all the facilities and to landscape the site within 10 years. The decommissioning plan has been through a number of revisions since 1995 that have refined the detail, timescales and costs. The latest 2005 revision of the decommissioning plan highlighted the need to clarify the size reduction and packaging requirements for the ILW and LLW. Following a competitive tender exercise, a contract was placed by UKAEA with NUKEM Limited to undertake a review of the waste estimates and to produce a concept design for the planned size reduction and packaging facilities. The study demonstrated the benefit of refining decommissioning planning by increasing the detail as the decommissioning date approaches. It also showed how a review of decommissioning plans by independent personnel can explore alternative strategies and result in improved methodologies and estimates of cost and time. This paper aims to describe this part of the decommissioning planning process and draw technical and procedural conclusions. (authors)

  16. 13. RAILROAD BRIDGE MISSISSIPPI, MONROE CO., ABERDEEN 1.5 mi. NW ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    13. RAILROAD BRIDGE MISSISSIPPI, MONROE CO., ABERDEEN 1.5 mi. NW of Amory. St. Louis and San Francisco RR bridge. Steam locomotive and coal train cross bridge on 10 August 1921. Credit: Owned by Jack Donnell, Columbus, Ms., photographer. Copied by Sarcone Photography, Columbus, Ms. - Bridges of the Upper Tombigbee River Valley, Columbus, Lowndes County, MS

  17. Shivers Junior/Senior High School: Aberdeen School District in Mississippi. Case Study in Sustainable Design.

    ERIC Educational Resources Information Center

    Zimmerman, David

    Design information, floor plan, photos, and energy use data are presented of a combined 45,000 square foot junior/senior high school in Mississippi's Aberdeen School District, built in 1956, and retrofitted over time to improve its usability. Exterior and interior photos are presented showing classrooms, the cafeteria, and gymnasium. Data are…

  18. The Aberdeen Indian Health Service Infant Mortality Study: Design, Methodology, and Implementation

    ERIC Educational Resources Information Center

    Randall, Leslie L.; Krogh, Christopher; Welty, Thomas K.; Willinger, Marian; Iyasu, Solomon

    2001-01-01

    Of all Indian Health Service areas, the Aberdeen Area has consistently had the highest infant mortality rate. Among some tribes in this area the rate has exceeded 30/1000 live birth and half the infant deaths have been attributed to Sudden Infant Death Syndrome, a rate four to five times higher than the national average. The Indian Health Service,…

  19. School to Work: The Aberdeen Hearing-Impaired School-Leaver 1960-72

    ERIC Educational Resources Information Center

    Welsh, Jennifer

    1976-01-01

    A small scale survey of hearing-impaired graduates from Aberdeen schools was carried out in March 1973. It focused on the relation between types of schooling received, degree of hearing loss and levels of communication ability, employment satisfaction, training for work, promotion, and social attitudes. (Author/RK)

  20. The Nature of the Beast: Or, The Aberdeen Bestiary on the World Wide Web.

    ERIC Educational Resources Information Center

    Beavan, Iain; Arnott, Michael; McLaren, Colin

    1997-01-01

    Discusses the digitization of the Aberdeen Bestiary and describes plans by Kings College (England) to increase accessibility via the World Wide Web to its humanities collections. Factors influencing the choice of this manuscript for the Web site, the decision to use PhotoCD for digitization, and the potential for further development are discussed.…

  1. Aberdeen Area Final Evaluation Report, ESEA Title I Projects, Fiscal Year 1976.

    ERIC Educational Resources Information Center

    Bureau of Indian Affairs (Dept. of Interior), Aberdeen, SD. Aberdeen Area Office.

    The final evaluation report on the 37 Elementary Secondary Education Act (ESEA) Title I projects in the Bureau of Indian Affairs (BIA) Aberdeen Area, this report presents graphic and tabular descriptions for each of the 37 projects re: (1) Title I expenditures (graphic display of expenditures for reading, math, language, administration, area…

  2. When a plant shuts down: The psychology of decommissioning

    SciTech Connect

    Schulz, J.; Crawford, A.C. )

    1993-07-01

    Within the next decade, 10 to 25 nuclear plants in the United States may be taken off line. Many will have reached the end of their 40-year life cycles, but others will be retired because the cost of operating them has begun to outweigh their economic benefit. Such was the case at Fort St. Vrain, the first decommissioning of a US commercial plant under new Nuclear Regulatory Commission (NRC) regulations. Two major problems associated with decommissioning plants have been obvious: (1) the technical challenges and costs of decommissioning, and (2) the cost of maintaining and finally decommissioning a plant after a safe storage (SAFSTOR) period of approximately 60 years. What has received little attention is the challenge that affects not only the people who make a plant work, but the quality of the solutions to these problems: how to maintain effective organizational performance during the process of downsizing and decommissioning and/or SAFSTOR. The quality of technical solutions for closing a plant, as well as how successfully the decommissioning process is held within or below budget, will depend largely on how effectively the nuclear organization functions as a social unit. Technical and people issues are bound together. The difficulty is how to operate a plant effectively when plant personnel have no sense of long-term security. As the nuclear power industry matures and the pace for closing operating plants accelerates, the time has come to prepare for the widespread decommissioning of plants. The industry would be well served by conducting a selective, industry-wide evaluation of plants to assess its overall readiness for the decommissioning process. A decommissioning is not likely to be trouble free, but with a healthy appreciation for the human side of the process, it will undoubtedly go more smoothly than if approached as a matter of dismantling a machine.

  3. Safety Oversight of Decommissioning Activities at DOE Nuclear Sites

    SciTech Connect

    Zull, Lawrence M.; Yeniscavich, William

    2008-01-15

    The Defense Nuclear Facilities Safety Board (Board) is an independent federal agency established by Congress in 1988 to provide nuclear safety oversight of activities at U.S. Department of Energy (DOE) defense nuclear facilities. The activities under the Board's jurisdiction include the design, construction, startup, operation, and decommissioning of defense nuclear facilities at DOE sites. This paper reviews the Board's safety oversight of decommissioning activities at DOE sites, identifies the safety problems observed, and discusses Board initiatives to improve the safety of decommissioning activities at DOE sites. The decommissioning of former defense nuclear facilities has reduced the risk of radioactive material contamination and exposure to the public and site workers. In general, efforts to perform decommissioning work at DOE defense nuclear sites have been successful, and contractors performing decommissioning work have a good safety record. Decommissioning activities have recently been completed at sites identified for closure, including the Rocky Flats Environmental Technology Site, the Fernald Closure Project, and the Miamisburg Closure Project (the Mound site). The Rocky Flats and Fernald sites, which produced plutonium parts and uranium materials for defense needs (respectively), have been turned into wildlife refuges. The Mound site, which performed R and D activities on nuclear materials, has been converted into an industrial and technology park called the Mound Advanced Technology Center. The DOE Office of Legacy Management is responsible for the long term stewardship of these former EM sites. The Board has reviewed many decommissioning activities, and noted that there are valuable lessons learned that can benefit both DOE and the contractor. As part of its ongoing safety oversight responsibilities, the Board and its staff will continue to review the safety of DOE and contractor decommissioning activities at DOE defense nuclear sites.

  4. Constructing Predictive Estimates for Worker Exposure to Radioactivity During Decommissioning: Analysis of Completed Decommissioning Projects - Master Thesis

    SciTech Connect

    Dettmers, Dana Lee; Eide, Steven Arvid

    2002-10-01

    An analysis of completed decommissioning projects is used to construct predictive estimates for worker exposure to radioactivity during decommissioning activities. The preferred organizational method for the completed decommissioning project data is to divide the data by type of facility, whether decommissioning was performed on part of the facility or the complete facility, and the level of radiation within the facility prior to decommissioning (low, medium, or high). Additional data analysis shows that there is not a downward trend in worker exposure data over time. Also, the use of a standard estimate for worker exposure to radioactivity may be a best estimate for low complete storage, high partial storage, and medium reactor facilities; a conservative estimate for some low level of facility radiation facilities (reactor complete, research complete, pits/ponds, other), medium partial process facilities, and high complete research facilities; and an underestimate for the remaining facilities. Limited data are available to compare different decommissioning alternatives, so the available data are reported and no conclusions can been drawn. It is recommended that all DOE sites and the NRC use a similar method to document worker hours, worker exposure to radiation (person-rem), and standard industrial accidents, injuries, and deaths for all completed decommissioning activities.

  5. Proving allelopathy in crop-weed interactions

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Allelopathy (plant/plant chemical warfare) is difficult to prove, especially when competition for resources is the dominant component of plant/plant interference (interference = allelopathy +competition). This paper describes experimental approaches for proving allelopathy and points out common pit...

  6. Decontamination, decommissioning, and vendor advertorial issue, 2008

    SciTech Connect

    Agnihotri, Newal

    2008-07-15

    The focus of the July-August issue is on Decontamination, decommissioning, and vendor advertorials. Articles and reports in this issue include: D and D technical paper summaries; The role of nuclear power in turbulent times, by Tom Chrisopher, AREVA, NP, Inc.; Enthusiastic about new technologies, by Jack Fuller, GE Hitachi Nuclear Energy; It's important to be good citizens, by Steve Rus, Black and Veatch Corporation; Creating Jobs in the U.S., by Guy E. Chardon, ALSTOM Power; and, and, An enviroment and a community champion, by Tyler Lamberts, Entergy Nuclear Operations, Inc. The Industry Innovations article is titled Best of the best TIP achievement 2008, by Edward Conaway, STP Nuclear Operating Company.

  7. Uranium enrichment decontamination and decommissioning fund

    SciTech Connect

    1994-12-31

    One of the most challenging issues facing the Department of Energy`s Office of Environmental Management is the cleanup of the three gaseous diffusion plants. In October 1992, Congress passed the Energy Policy Act of 1992 and established the Uranium Enrichment Decontamination and Decommissioning Fund to accomplish this task. This mission is being undertaken in an environmentally and financially responsible way by: devising cost-effective technical solutions; producing realistic life-cycle cost estimates, based on practical assumptions and thorough analysis; generating coherent long-term plans which are based on risk assessments, land use, and input from stakeholders; and, showing near-term progress in the cleanup of the gaseous diffusion facilities at Oak Ridge.

  8. Lessons Learned from the NASA Plum Brook Reactor Facility Decommissioning

    NASA Technical Reports Server (NTRS)

    2010-01-01

    NASA has been conducting decommissioning activities at its PBRF for the last decade. As a result of all this work there have been several lessons learned both good and bad. This paper presents some of the more exportable lessons.

  9. Decommissioning the UHTREX Reactor Facility at Los Alamos, New Mexico

    SciTech Connect

    Salazar, M.; Elder, J.

    1992-08-01

    The Ultra-High Temperature Reactor Experiment (UHTREX) facility was constructed in the late 1960s to advance high-temperature and gas-cooled reactor technology. The 3-MW reactor was graphite moderated and helium cooled and used 93% enriched uranium as its fuel. The reactor was run for approximately one year and was shut down in February 1970. The decommissioning of the facility involved removing the reactor and its associated components. This document details planning for the decommissioning operations which included characterizing the facility, estimating the costs of decommissioning, preparing environmental documentation, establishing a system to track costs and work progress, and preplanning to correct health and safety concerns in the facility. Work to decommission the facility began in 1988 and was completed in September 1990 at a cost of $2.9 million. The facility was released to Department of Energy for other uses in its Los Alamos program.

  10. Progress in Decommissioning the Humboldt Bay Power Plant - 13604

    SciTech Connect

    Rod, Kerry; Shelanskey, Steven K.; Kristofzski, John

    2013-07-01

    Decommissioning of the Pacific Gas and Electric (PG and E) Company Humboldt Bay Power Plant (HBPP) Unit 3 nuclear facility has now, after more than three decades of SAFSTOR and initial decommissioning work, transitioned to full-scale decommissioning. Decommissioning activities to date have been well orchestrated and executed in spite of an extremely small work site with space constricted even more by other concurrent on-site major construction projects including the demolition of four fossil units, construction of a new generating station and 60 KV switchyard upgrade. Full-scale decommissioning activities - now transitioning from Plant Systems Removal (PG and E self-perform) to Civil Works Projects (contractor performed) - are proceeding in a safe, timely, and cost effective manner. As a result of the successful decommissioning work to date (approximately fifty percent completed) and the intense planning and preparations for the remaining work, there is a high level of confidence for completion of all HBPP Unit 3 decommissions activities in 2018. Strategic planning and preparations to transition into full-scale decommissioning was carried out in 2008 by a small, highly focused project team. This planning was conducted concurrent with other critical planning requirements such as the loading of spent nuclear fuel into dry storage at the Independent Spent Fuel Storage Installation (ISFSI) finishing December 2008. Over the past four years, 2009 through 2012, the majority of decommissioning work has been installation of site infrastructure and removal of systems and components, known as the Plant System Removal Phase, where work scope was dynamic with significant uncertainty, and it was self-performed by PG and E. As HBPP Decommissioning transitions from the Plant System Removal Phase to the Civil Works Projects Phase, where work scope is well defined, a contracting plan similar to that used for Fossil Decommissioning will be implemented. Award of five major work scopes

  11. Progress in Decommissioning of Ignalina NPP Unit 1

    SciTech Connect

    Ancius, Darius; Krenevicius, Rimantas; Kutas, Saulius; Chouha, Michel

    2002-07-01

    The aim of the paper is to present the Lithuanian legal framework regarding the nuclear safety in Decommissioning and Waste Management, and the progress in the Decommissioning Programme of the unit 1 of Ignalina Nuclear Power Plant (INPP). INPP is the only nuclear plant in Lithuania. It comprises two RBMK-1500 reactors. After Lithuania has restored its independence, responsibility for Ignalina NPP was transferred to the Republic of Lithuania. To ensure the control of the Nuclear Safety in Lithuania, The State Nuclear Power Safety Inspectorate (VATESI) was created on 18 October 1991, by a resolution of the Lithuanian Government. Significant work has been performed over the last decade, aiming at upgrading the safety level of the Ignalina NPP with reference to the International standards. On 5 October 1999 the Seimas (Parliament) adopted the National Energy Strategy: It has been decided that unit 1 of Ignalina NPP will be closed down before 2005, The conditions and precise final date of the decommissioning of Unit 2 will be stated in the updated National Energy strategy in 2004. On 20-21 June 2000, the International Donors' Conference for the Decommissioning of Ignalina NPP took place in Vilnius. More than 200 Millions Euro were pledged of which 165 M funded directly from the European Union's budget, as financial support to the Decommissioning projects. The Decommissioning Program encompasses legal, organizational, financial and technical means including the social and economical impacts in the region of Ignalina. The Program is financed from International Support Fund, State budget, National Decommissioning Fund of Ignalina NPP and other funds. Decommissioning of Ignalina NPP is subject to VATESI license according to the Law on Nuclear Energy. The Government established the licensing procedure in the so-called 'Procedure for licensing of Nuclear Activities'; and the document 'General Requirements for Decommissioning of the Ignalina NPP' has been issued by VATESI. A

  12. The Decommissioning of the Trino Nuclear Power Plant

    SciTech Connect

    Brusa, L.; DeSantis, R.; Nurden, P. L.; Walkden, P.; Watson, B.

    2002-02-27

    Following a referendum in Italy in 1987, the four Nuclear Power Plants (NPPs) owned and operated by the state utility ENEL were closed. After closing the NPPs, ENEL selected a ''safestore'' decommissioning strategy; anticipating a safestore period of some 40-50 years. This approach was consistent with the funds collected during plant operation, and was reinforced by the lack of both a waste repository and a set of national free release limits for contaminated materials in Italy. During 1999, twin decisions were made to privatize ENEL and to transform the nuclear division into a separate subsidiary of the ENEL group. This group was renamed Sogin and during the following year, ownership of the company was transferred to the Italian Treasury. On formation, Sogin was asked by the Italian government to review the national decommissioning strategy. The objective of the review was to move from a safestore strategy to a prompt decommissioning strategy, with the target of releasing all of the nuclear sites by 2020. It was recognized that this target was conditional upon the availability of a national LLW repository together with interim stores for both spent fuel and HLW by 2009. The government also agreed that additional costs caused by the acceleration of the decommissioning program would be considered as stranded costs. These costs will be recovered by a levy on the kWh price of electricity, a process established and controlled by the Regulator of the Italian energy sector. Building on the successful collaboration to develop a prompt decommissioning strategy for the Latina Magnox reactor (1), BNFL and Sogin agreed to collaborate on an in depth study for the prompt decommissioning of the Sogin PWR at Trino. BNFL is currently decommissioning six NPPs and is at an advanced stage of planning for two further units, having completed a full and rigorous exercise to develop Baseline Decommissioning Plans (BDP's) for these stations. The BDP exercise utilizes the full range of

  13. Radioactive waste management and decommissioning of accelerator facilities.

    PubMed

    Ulrici, Luisa; Magistris, Matteo

    2009-11-01

    During the operation of high-energy accelerators, the interaction of radiation with matter can lead to the activation of the machine components and of the surrounding infrastructures. As a result of maintenance operation and during decommissioning of the installation, considerable amounts of radioactive waste are evacuated and shall be managed according to the radiation-protection legislation. This paper gives an overview of the current practices in radioactive waste management and decommissioning of accelerators.

  14. Decontamination and Decommissioning Experience at a Sellafield Uranium Purification Plant

    SciTech Connect

    Prosser, J.L.

    2006-07-01

    Built in the 1950's, this plant was originally designed to purify depleted uranyl nitrate solution arising from reprocessing operations at the Primary Separation and Head End Plant (Fig. 1). The facility was used for various purposes throughout its life cycle such as research, development and trial based processes. Test rigs were operated in the building from the 1970's until 1984 to support development of the process and equipment now used at Sellafield's Thermal Oxide Reprocessing Plant (THORP). The extensive decommissioning program for this facility began over 15 years ago. Many challenges have been overcome throughout this program such as decommissioning the four main process cells, which were very highly alpha contaminated. The cells contained vessels and pipeline systems that were contaminated to such levels that workers had to use pressurized suits to enter the cells. Since decommissioning at Sellafield was in its infancy, this project has trialed various decontamination/decommissioning methods and techniques in order to progress the project, and this has provided valuable learning for other decommissioning projects. The project has included characterization, decontamination, dismantling, waste handling, and is now ready for demolition during late 2005, early 2006. This will be the first major facility within the historic Separation Area at Sellafield to be demolished down to base slab level. The lessons learnt from this project will directly benefit numerous decommissioning projects as the cleanup at Sellafield continues. (authors)

  15. The unit cost factors and calculation methods for decommissioning - Cost estimation of nuclear research facilities

    SciTech Connect

    Kwan-Seong Jeong; Dong-Gyu Lee; Chong-Hun Jung; Kune-Woo Lee

    2007-07-01

    Available in abstract form only. Full text of publication follows: The uncertainties of decommissioning costs increase high due to several conditions. Decommissioning cost estimation depends on the complexity of nuclear installations, its site-specific physical and radiological inventories. Therefore, the decommissioning costs of nuclear research facilities must be estimated in accordance with the detailed sub-tasks and resources by the tasks of decommissioning activities. By selecting the classified activities and resources, costs are calculated by the items and then the total costs of all decommissioning activities are reshuffled to match with its usage and objectives. And the decommissioning cost of nuclear research facilities is calculated by applying a unit cost factor method on which classification of decommissioning works fitted with the features and specifications of decommissioning objects and establishment of composition factors are based. Decommissioning costs of nuclear research facilities are composed of labor cost, equipment and materials cost. Of these three categorical costs, the calculation of labor costs are very important because decommissioning activities mainly depend on labor force. Labor costs in decommissioning activities are calculated on the basis of working time consumed in decommissioning objects and works. The working times are figured out of unit cost factors and work difficulty factors. Finally, labor costs are figured out by using these factors as parameters of calculation. The accuracy of decommissioning cost estimation results is much higher compared to the real decommissioning works. (authors)

  16. Revised Analyses of Decommissioning Reference Non-Fuel-Cycle Facilities

    SciTech Connect

    MC Bierschbach; DR Haffner; KJ Schneider; SM Short

    2002-12-01

    Cost information is developed for the conceptual decommissioning of non-fuel-cycle nuclear facilities that represent a significant decommissioning task in terms of decontamination and disposal activities. This study is a re-evaluation of the original study (NUREG/CR-1754 and NUREG/CR-1754, Addendum 1). The reference facilities examined in this study are the same as in the original study and include: a laboratory for the manufacture of {sup 3}H-labeled compounds; a laboratory for the manufacture of {sup 14}C-labeled compounds; a laboratory for the manufacture of {sup 123}I-labeled compounds; a laboratory for the manufacture of {sup 137}Cs sealed sources; a laboratory for the manufacture of {sup 241}Am sealed sources; and an institutional user laboratory. In addition to the laboratories, three reference sites that require some decommissioning effort were also examined. These sites are: (1) a site with a contaminated drain line and hold-up tank; (2) a site with a contaminated ground surface; and (3) a tailings pile containing uranium and thorium residues. Decommissioning of these reference facilities and sites can be accomplished using techniques and equipment that are in common industrial use. Essentially the same technology assumed in the original study is used in this study. For the reference laboratory-type facilities, the study approach is to first evaluate the decommissioning of individual components (e.g., fume hoods, glove boxes, and building surfaces) that are common to many laboratory facilities. The information obtained from analyzing the individual components of each facility are then used to determine the cost, manpower requirements and dose information for the decommissioning of the entire facility. DECON, the objective of the 1988 Rulemaking for materials facilities, is the decommissioning alternative evaluated for the reference laboratories because it results in the release of the facility for restricted or unrestricted use as soon as possible. For a

  17. Evaluation of nuclear facility decommissioning projects. Project summary report, Elk River Reactor

    SciTech Connect

    Miller, R.L.; Adams, J.A.

    1982-12-01

    This report summarizes information concerning the decommissioning of the Elk River Reactor. Decommissioning data from available documents were input into a computerized data-handling system in a manner that permits specific information to be readily retrieved. The information is in a form that assists the Nuclear Regulatory Commission in its assessment of decommissioning alternatives and ALARA methods for future decommissionings projects. Samples of computer reports are included in the report. Decommissioning of other reactors, including NRC reference decommissioning studies, will be described in similar reports.

  18. An overview of U.S. decommissioning experience -- A basic introduction

    SciTech Connect

    Boing, L.E.

    1998-03-09

    This paper presents an overview of the US experiences in the decommissioning technical area. Sections included are: (1) an overview of the magnitude of the problem, (2) a review of the US decommissioning process, (3) regulation of decommissioning, (4) regulatory and funding requirements for decommissioning, and (5) a general overview of all on-going and completed decommissioning projects to date in the US. The final section presents a review of some issues in the decommissioning area currently being debated in the technical specialists community.

  19. Mobile workstation for decontamination and decommissioning operations

    SciTech Connect

    Whittaker, W.L.; Osborn, J.F.; Thompson, B.R.

    1993-10-01

    This project is an interdisciplinary effort to develop effective mobile worksystems for decontamination and decommissioning (D&D) of facilities within the DOE Nuclear Weapons Complex. These mobile worksystems will be configured to operate within the environmental and logistical constraints of such facilities and to perform a number of work tasks. Our program is designed to produce a mobile worksystem with capabilities and features that are matched to the particular needs of D&D work by evolving the design through a series of technological developments, performance tests and evaluations. The project has three phases. In this the first phase, an existing teleoperated worksystem, the Remote Work Vehicle (developed for use in the Three Mile Island Unit 2 Reactor Building basement), was enhanced for telerobotic performance of several D&D operations. Its ability to perform these operations was then assessed through a series of tests in a mockup facility that contained generic structures and equipment similar to those that D&D work machines will encounter in DOE facilities. Building upon the knowledge gained through those tests and evaluations, a next generation mobile worksystem, the RWV II, and a more advanced controller will be designed, integrated and tested in the second phase, which is scheduled for completion in January 1995. The third phase of the project will involve testing of the RWV II in the real DOE facility.

  20. Successful decommissioning and demolition at Weldon Spring

    SciTech Connect

    Davis, M.L.

    1994-12-31

    B&W Nuclear Environmental Services, Inc. (B&W NESI) and OHM Corporation (OHM) formed a joint venture company, B&W/OHM Weldon Spring, Inc. (B&W/OHM WSI) to perform work at the U.S. Department of Energy`s (DOE`s) Weldon Spring Site Remedial Action Project (WSSRAP). This joint venture company combines the hazardous and toxic waste remediation experience of OHM with the radiological decontamination and decommissioning experience of B&W NESI. Together, the two companies have over 60 yr of relevant experience and a strong record of performance in resolving problems associated with nuclear and hazardous materials contamination. The B&W/OHM WSI is under contract to MK-Ferguson, DOE`s project management contractor (PMC), at WSSRAP to provide supervision, tools, labor, and equipment to decontaminate and dismantle 11 buildings at the chemical plant site. The Weldon Spring site, located in St. Charles, Missouri, was used by the U.S. Atomic Energy Commission from 1957 through 1966 as a feed material production site to process uranium and thorium ore concentrates. Since the cessation of production activity at this site, the buildings and structures contained in the chemical plant have badly deteriorated, posing an immediate potential threat to workers, the general public, and the environment, prompting the DOE to initiate an Expedited Response Action to decontaminate, empty, and dismantle all the buildings and structures.

  1. The Frustration of Lady Aberdeen in her Crusade against Tuberculosis in Ireland

    PubMed Central

    Breathnach, Caoimhghín S; Moynihan, John B

    2012-01-01

    When in his Annual Report for 1905 the Registrar General for Ireland pointed out to the lately arrived Lord Lieutenant, The Earl of Aberdeen, that annually in every 100 deaths in Ireland 16 were victims of tuberculosis, Lady Aberdeen took notice. In March 1907 she founded the WNHA with the clear duty of taking part in the fight against the appalling ravages of that disease, and organised a Tuberculosis Exhibition the following October. And so began a campaign that led to the building of Peamount Sanatorium in county Dublin, the Allan Ryan Hospital at Ringsend, and the Collier Dispensary in the city centre. However, the Irish parliamentarians at Westminster emasculated the Tuberculosis Prevention (Ireland) Act 1908 by ensuring that notification was not made compulsory. Passage of the National Health Insurance Act (1911) necessitated changes that resulted in the Tuberculosis Prevention (Ireland) Act (1913), but the crucial shortcomings of the earlier Act were not rectified: notification was necessary but still not compulsory. Lady Aberdeen recognised this serious flaw she was powerless to correct, and turned to propaganda, editing Sláinte, a monthly magazine founded in January 1909 by the WNHA, and editing a three-volume account of Ireland’s Crusade Against Tuberculosis (1908-1909). PMID:23536737

  2. The frustration of Lady Aberdeen in her crusade against tuberculosis in Ireland.

    PubMed

    Breathnach, Caoimhghín S; Moynihan, John B

    2012-01-01

    When in his Annual Report for 1905 the Registrar General for Ireland pointed out to the lately arrived Lord Lieutenant, The Earl of Aberdeen, that annually in every 100 deaths in Ireland 16 were victims of tuberculosis, Lady Aberdeen took notice. In March 1907 she founded the WNHA with the clear duty of taking part in the fight against the appalling ravages of that disease, and organised a Tuberculosis Exhibition the following October. And so began a campaign that led to the building of Peamount Sanatorium in county Dublin, the Allan Ryan Hospital at Ringsend, and the Collier Dispensary in the city centre. However, the Irish parliamentarians at Westminster emasculated the Tuberculosis Prevention (Ireland) Act 1908 by ensuring that notification was not made compulsory. Passage of the National Health Insurance Act (1911) necessitated changes that resulted in the Tuberculosis Prevention (Ireland) Act (1913), but the crucial shortcomings of the earlier Act were not rectified: notification was necessary but still not compulsory. Lady Aberdeen recognised this serious flaw she was powerless to correct, and turned to propaganda, editing Sláinte, a monthly magazine founded in January 1909 by the WNHA, and editing a three-volume account of Ireland's Crusade Against Tuberculosis (1908-1909).

  3. Proceedings of the Annual Chemical Defense Bioscience Review (4th) Held at Aberdeen Proving Ground, Maryland on 30 May-1 June 1984

    DTIC Science & Technology

    1984-06-01

    KCN can be absorbed in potentially lethal amounts by all possible routes of exposure. 484 I-! REFERENCES Ballantyne, B. (1973). The forensic ...diagnosis of acute cyanide poisoning. In, Forensic Toxicolngy, Ed. by B. Ballantyne. Wright, Bristol, p. 99. Ballantyne, B. (1976). Changes in blood cyanide...victims. J. Forensic Sci. 11, 167-173. Winek, C. L. and Prex, D. M. (1981). A comparative study of analytical methods to determine postmortem changes in

  4. Ideas from Future Technologies Workshop Held by ARL/TARDEC in Aberdeen Proving Ground, Maryland on 9-11 June, 1993

    DTIC Science & Technology

    1994-08-01

    martensitic phase transformations for dissipating C. Rogers large strain energy. Use stress -induced phase transformation materials in passive armor...itself is in a state of stress owing to the initial impact with the skin, it seems plausible that rod breakup could occur with the chunks deflected...prefer to trade off increased perfonnance in this case against a lower disk speed, thereby decreasing the stresses on the disks, bearings, and

  5. Evaluation of Several Biological Monitoring Techniques for Hazard Assessment of Potentially Contaminated Groundwater at the Old O-Field Site at the Edgewood Area of Aberdeen Proving Ground

    DTIC Science & Technology

    1991-11-01

    definitive acute toxicity tests run with daphnid neonates ( Daphnia magna ) and juvenile fathead minnows (Pimephales promelas) exposed to untreated Old O... Daphnia magna , fathead minnow, Pimephales promelas, mysid, Mysidopsis bahia, sheepshead minnow, Cyprinodon variegatus

  6. Feasibility of using plants to assist in the remediation of heavy metal contamination at J-Field, Aberdeen Proving Ground, Maryland. Final report

    SciTech Connect

    Jastrow, J.D.

    1995-11-03

    Most remedial technologies currently being used at hazardous waste sites (e.g., containment, excavation, soil washing, or incineration) are expensive. Further, in some locations technologies involving excavation could increase off-site releases of hazardous materials by destabilizing the site. Thus, interest in the development of in situ bioremediation technologies has grown substantially over the last decade. The idea of phytoremediation (i.e., using plants to clean up toxic wastes) is generating increasing attention from scientists, industry, and government agencies. The attractiveness of phytoremediation stems from its potential (1) to be less expensive than technologies involving the human engineering costs of soil manipulation, and (2) to initiate simultaneously both the clean up of hazardous materials and site restoration. The purpose of this project was to investigate the potential for using plants to remediate J-Field soils contaminated with heavy metals. Phragmites australis, one of the dominant species in the Toxic Burning Pits (TBP) area and other contaminated sites within J-Field, appears to be both tolerant of heavy metal contaminated soil conditions and capable of producing large amounts of biomass. Consequently, this project has concentrated on characterizing heavy metal accumulation by Phragmites australis growing in the TBP area relative to soil concentrations and availabilities. This type of information is necessary to determine the feasibility of using this species to assist in the remediation of metal contaminated soils at J-Field.

  7. Canal Creek Study Area, Aberdeen Proving Ground, Edgewood Area, Maryland. Groundwater Monitoring Plan, Final Quality Assurance Project Plan, Standard Operating Procedures (SOPs). Appendix A

    DTIC Science & Technology

    1993-10-01

    and sample collection for set up and general operation. 3.4.1.2 Collecting dense noni-aqueous phase liquids ( DNAPLs ) will be accomplished using a...controlled fashion. Sample for analysis as above. The same field check described above may be employed for DNAPL . Refer to following sections on purging and...sampling. hh. NAPL: Record the presence and thickness of any non aqueous phase liquids (LNAPL and DNAPL ) ii. COMMENTS: record any pertinent information

  8. Beach Point Test Site, Aberdeen Proving Ground, Edgewood Area, Maryland. Focused Feasibility Study, Final Quality Assurance Project Plan, Standard Operating Procedures (SOPs). Appendix A

    DTIC Science & Technology

    1993-10-01

    sections on purging and sample collection for set up and general operation. 3.4.1.2 Collecting dense non-aqueous phase liquids ( DNAPLs ) will be...the well in a controlled fashion. Sample for analysis as above. The same field check described above may be employed for DNAPL . Refer to following...aqueous phase liquids (LNAPL and DNAPL ) ii. COMMENTS: record any pertinent information not already covered in the form. jj. SIGNATURE: sign the form

  9. Metallurgical Data on Certain Cast Armor Test Plates Tested at Aberdeen Proving Ground as a Part of the Cast Armor Low Alloy Development Program

    DTIC Science & Technology

    1942-04-25

    lllHUI iJLiliiMrJWliimMWiWWHWP^WHip» 1 oC00LIN0oRATE,0eS. F PER SECOND AT I300 #F. o o o o g SOOOOQ o o o « o«^^ m iO ...1.62 — Physical Properties T.S. - ios .750 Y.P. - 57.550 ^ Slor.g. - 22.0 1» P.. A. - 50.5 Izod - Brir-ell - 252 .20 1.05 .79...o AT I300T 2 9fDKɘ» #. ffi-öxn iO «1 ¥1 III « SO i « 1 >0 * < u 40 c Jl 1 \\ 4 10 r t A\\ a o1 rr ;Trr rTn

  10. The Annual Conference on Han-Based Liquid Propellants (5th) Held in Aberdeen Proving Ground on 22-24 August 1989

    DTIC Science & Technology

    1990-06-01

    triggering process, and the resulting system of ordi- nary differential equations are integrated forward in time using a backwards differentiation ... EQUATION OF STATE DEVELOPED PREVIOUSLY. TO ACCOUNT FOR THE EFFECT OF SOLUBIUTY, THE DENSITY IS MODIFIED AS FOLLOWS: p’ (mol/cm 3) = 1( xi) (5) p...TO OBTAIN THE FOLLOWING EQUATION . k* = 254.40 expT - -348.75 - 142.24 - 0.00292 P" T* 1/1/2 2 WHERE k =k(M3) a , [k, S/cm] T =T/13 [T, K] P’= P a3 /13

  11. Evaluation of Several Biological Monitoring Techniques for Hazard Assessment of Potentially Contaminated Wastewater and Groundwater. Volume 2. Aberdeen Proving Ground Wastewater Treatment Plant

    DTIC Science & Technology

    1992-07-01

    daphnid ( Ceriodaphnia dubia) survival and reproduction test, and 7-d fathead minnow (Pimephales promelas) survival 20. OISTRIBUTION IAVALASlUTY OF...growth test, 7-d daphnid ( CeriodaPhnia dubia) survival and reproduction test, and 7-d fathead minnow (•P.imphils pRom1elas) survival and growth test...capricornutum, daphnid, Ceriodaphnia dubia, fathead minnow, Pimephales promelas, African clawed frog, Xenopus laevis, Japanese medaka, Oryzias latipes

  12. Metal Matrix Composites for Ordnance Applications. NDIA Firepower Symposium Held in U. S. Army Research Laboratory, Aberdeen Proving Ground, MD on 20 Jun 2001

    DTIC Science & Technology

    2007-11-02

    FY05 FY06 FY07 Cannon TRL=4 Sub- Scale Testing METRIC: Joining technology developed, non- destructive evaluation and fatigue tests...nε Effective Laminate Strain E ff ec ti ve L am in a te S tr es s a b -1000 -500 0 500 1000 -1000 -500 0 500 1000 (M P a) (MPa) σ x σ y final

  13. Proceedings of the Meeting of the Coordinating Group on Modern Control Theory (2nd) 10-11 December 1980, Aberdeen Proving Ground, Maryland. Part 1

    DTIC Science & Technology

    1981-04-01

    ki , k 2 and k3 are optimal gain constants, and K is the positive-definite sol - ution of the algebraic Riccati equation ATK + KA + Q - KBr-lBTK - 0. (9...parameters for these cases are given in Table, 3, ’note that the last three digits only of tho Identifier are used here). SoL - parapmeters are quite...response shown in Figure t0. For this case the same MMAC used in the previous examples was employed, but the vign of the radome boresight error model was

  14. Proceedings of the Scientific Conference on Obscuration and Aerosol Research Held in Aberdeen Proving Ground, Maryland on 21-24 June 1988

    DTIC Science & Technology

    1989-06-01

    dz’ exp IkLZ’(0-(cCOSO) (Z’/S-’ 2(z()I exp [i-EokL ds(Z’)/dZ’ / S(Z’)" fd2 p, (27T) !0(fEOkLp’slnO) exp-3p’ 2 /2po 2s(z’) 039) The Bessel function in...change the contents of the bacterium in a predictable way. Upon induction the lambda virus genes are transcribed and within a known time (about 30-50

  15. Proceedings of the Workshop on Acute Lung Injury and Pulmonary Edema Held in Aberdeen Proving Ground, Maryland on 4-5 May 1989

    DTIC Science & Technology

    1989-11-01

    RESTRICTIVE MARKINGS Unclassified N/A - 2a. SECURITY CLASSIFICATION AUTHORITY 3. DISTRIBUTION IAVAILABILITY OF REPORT N/A Approved for public release... pericarditis after inhalation of Teflon fumes.] Tidsskr. Nor. Laegeforen 109(5): 584-585. Karpov, B.D. (1975). Determination of the upper and lower toxicity

  16. Proceedings of the Scientific Conference on Obscuration and Aerosol Research Held in Aberdeen Proving Ground, Maryland on June 22-25, 1992

    DTIC Science & Technology

    1993-06-01

    b=0.025. 332 A THEORY OF HEATING OF VOIGT SOLIDS AND FLUIDS BY EXTERNAL ENERGY SOURCES AND FLAME THEORY D. K. Cohoon 43 Skyline Glen Mills , PA 19342...26] Eyring, Henry, and Mu Shik Jhon . Significant Liquid Structures New York: John Wiley and Sons (1969) [27] Fisher, I. Z. Statistical Theory of...Most Efficient Tests of Statistical Hypotheses," Philosophical Trans. A, 231, 289 (1933) 2M. G. Kendall and A. Stuart , The Advanced Theory of

  17. Proceedings of the 1990 Scientific Conference on Obscuration and Aerosol Research Held in Aberdeen Proving Ground, Maryland on 25 - 28 June 1990

    DTIC Science & Technology

    1991-06-01

    385 AEROSOL SIZE DISTRIBUTION INFERRED FROM LIDAR MULTIPLE SCATTERING MEASUREMENTS A. Ben-David, Y. Benayahu and S. Fastig, and A.Cohen...conditions for E. Coil bacteria led to changes in the size distribution of the bacteria as measured by electron microscopy. These changes correlated with...dimension is sampled many more times in a randomly oriented suspension. However, the electron microscope measurements indicated that the size changes

  18. Proceedings of the Scientific Conference on Obscuration and Aerosol Research Held in Aberdeen Proving Ground, Maryland on 17-21 June 1985.

    DTIC Science & Technology

    1986-07-01

    iii s will con3’st of development of continuous processes for prodi.r-:ion of linear chain S a, r os in the liq,uiit phase and means for li: p -rsal...tne ’!. S . Army Chemical Research and Development Center. White phosphorus (WP) was purchased from i cur’ercidl supplier because distribution of WP in...S1055, Prepared for U.S. Army Medical Research and Development Command by Pacific Northwest Laboratory, Richlana, Washington. Brazell, R. S ., R. W

  19. Proceedings of the 1993 Scientific Conference on Obscuration and Aerosol Research Held in Aberdeen Proving Ground on 22-24 Jun 1993

    DTIC Science & Technology

    1994-03-01

    SCIENTIFIC CONFERENCE ON OBSCURATION AND AEROSOL RESEARCH DTIC S EL.ECTE JU 0u 81994DU v F Janice E. Rhodes Sarah J. Wall BATTELLE EDGEWOOD OPERATIONS...Form ApprovedREPORT DOCUMENTATION PAGE OMB No. 0704-0188 Pubf reon burden f0, th ollection .) f tinfoirmation is eslimated to averaqe I hour per...34u" the collection of information. Send comments reqadun thsbud n esimt ori a .oth, 11oedý Of thiscolect~n f Ifomaton.uruI~ding sug estIons for

  20. Proceedings of the Scientific Conference on Obscuration and Aerosol Research Held in Aberdeen Proving Ground, Maryland on June 24 - 28, 1991

    DTIC Science & Technology

    1992-06-01

    gradient and the divergence of a curl vanish, curl( eurl (curlI(Q ))) = curl(- AP ) = + k2curl(&A) (2.64) Equation (2.64) is the basis of the Asano and...with small water droplets," Applied Optics, in press, 1991. M.) D.R. Alexander, S.A. Schaub, and J.P. Barton, "Modeling of a coherent imaging system: ap ...P=a (11b) R cc fo do"~s "’p (lic=a) D ,co do2 d4’[ K(A; 4i,)G(kI10 - A’I; n)R(k’ os)] (1ld) J0 Jo ]p#= ap =a Here K OC d / dplp=a TM (VI Ez) (12a) ]p

  1. Technology Description Sheets form the AMC 1990 Technology Expo Held in Aberdeen Proving Ground, Maryland on 1-4 October 1990

    DTIC Science & Technology

    1990-10-04

    launch Attn SLCHD-TAS, John Miler * Be completely contained in a volume of about 9.1 cubic inches (entire system2800 Powder Mill Road Adelphi. MD 20783...discerning size and weight of less DSN 584-3021 or (301) 671.3021 than 0.3 cubic feet and 20 pounds, respectively. This achievement represents an...include: " Ceramic Engine Components- zirconia and silicon nitride * Advanced Ceramic Armor-titanium diboride and silicon carbide " Ceramic Gun Tube Liners

  2. UNIQUE RADIOANALYTICAL PROTOCOLS FOR CHARACTERIZATION AND VERIFICATION DURING DECONTAMINATION AND DECOMMISSIONING

    SciTech Connect

    Diprete, C; David Diprete, D; Wooten Simpson, W

    2007-01-05

    In order to successfully decontaminate, deactivate and decommission surplus Department of Energy (DOE) facilities throughout the Savannah River Site (SRS), a variety of characterizations must be completed to sufficiently identify and quantify potential contaminants of concern. The ultimate goal is to rapidly and efficiently characterize, decontaminate (if necessary), and verify that the remnants meet specified limits established by either an industrial worker model or a groundwater model. To meet this end, the Savannah River National Laboratory (SRNL) developed a series of radioanalytical strategies and methodologies which can be used to characterize targeted facilities and prove that decontamination has been sufficient. To our knowledge, this is the first application of this novel methodology within the DOE complex. This methodology has been successfully utilized with nearly 1000 samples from over a dozen facilities. The application of this approach to just a single facility shortened the schedule by 30 days and resulted in non-labor dollar savings of over $60K. Cost savings for a second facility was determined to be $375K. Based on the success of this methodology at SRS, this approach will be valuable to other nuclear facilities in the USA and abroad involved with the decontamination and decommissioning process.

  3. Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron-Activated Shield Wall

    SciTech Connect

    Michael R. Kruzic

    2008-06-01

    Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility (Figure 1) was used in the early to mid-1960s for testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles. The TCA facility, known as Corrective Action Unit 115, was decontaminated and decommissioned (D&D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the Federal Facility Agreement and Consent Order. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously, provided technical decisions are made by an experienced decision maker within the site conceptual site model. Facility closure involved a seven-step decommissioning strategy. First, preliminary investigation activities were performed, including review of process knowledge documentation, targeted facility radiological and hazardous material surveys, concrete core drilling and analysis, shield wall radiological characterization, and discrete sampling, which proved to be very useful and cost-effective in subsequent decommissioning planning and execution and worker safety. Second, site setup and mobilization of equipment and personnel were completed. Third, early removal of hazardous materials, including asbestos, lead, cadmium, and oil, was performed ensuring worker safety during more invasive demolition activities. Process piping was to be verified void of contents. Electrical systems were de-energized and other systems were rendered free of residual energy. Fourth, areas of high radiological contamination were decontaminated using multiple methods. Contamination levels varied across the facility. Fixed beta/gamma contamination levels ranged up to 2 million disintegrations per minute (dpm)/100

  4. Windscale pile reactors - Decommissioning progress on a fifty year legacy

    SciTech Connect

    Sexton, Richard J.

    2007-07-01

    The decommissioning of the Windscale Pile 1 reactor, fifty years after the 1957 fire, is one of the most technically challenging decommissioning projects in the UK, if not the world. This paper presents a summary of the 1957 Windscale Pile 1 accident, its unique challenges and a new technical approach developed to safely and efficiently decommission the two Windscale Pile Reactors. The reactors will be decommissioned using a top down approach that employs an array of light weight, carbon fiber, high payload robotic arms to remove the damaged fuel, the graphite core, activated metals and concrete. This relatively conventional decommissioning approach has been made possible by a recently completed technical assessment of reactor core fire and criticality risk which concluded that these types of events are not credible if relatively simple controls are applied. This paper presents an overview of the design, manufacture and testing of equipment to remove the estimated 15 tons of fire damaged fuel and isotopes from the Pile 1 reactor. The paper also discusses recently conducted characterization activities which have allowed for a refined waste estimate and conditioning strategy. These data and an innovative approach have resulted in a significant reduction in the estimated project cost and schedule. (authors)

  5. The Chernobyl NPP decommissioning: Current status and alternatives

    SciTech Connect

    Mikolaitchouk, H.; Steinberg, N.

    1996-08-01

    After the Chernobyl accident of April 26, 1986, many contradictory decisions were taken concerning the Chernobyl nuclear power plant (NPP) future. The principal source of contradictions was a deadline for a final shutdown of the Chernobyl NPP units. Alterations in a political and socioeconomic environment resulted in the latest decision of the Ukrainian Authorities about 2000 as a deadline for a beginning of the Chernobyl NPP decommissioning. The date seems a sound compromise among the parties concerned. However, in order to meet the data a lot of work should be done. First of all, a decommissioning strategy has to be established. The problem is complicated due to both site-specific aspects and an absence of proven solutions for the RBMK-type reactor decommissioning. In the paper the problem of decommissioning option selection is considered taking into account an influence of the following factors: relevant legislative and regulatory requirements; resources required to carry out decommissioning (man-power, equipment, technologies, waste management infrastructure, etc.); radiological and physical status of the plant, including structural integrity and predictable age and weather effects; impact of planned activities at the destroyed unit 4 and within the 30-km exclusion zone of the Chernobyl NPP; planed use of the site; socio-economic considerations.

  6. Regulatory process for decommissioning nuclear power reactors. Final report

    SciTech Connect

    1998-03-01

    This report provides regulatory guidance for utilities consistent with the changes in the decommissioning rule, 10 CFR50.82 as revised in July 1996. The purpose of this report is to explain the new rule in the context of related industry experience and to provide practical guidance to licensees contemplating or implementing a shutdown. Because the regulatory process is still rapidly evolving, this report reflects only a current status of the acceptable methods and practices derived from a review of the current regulations, guidance documents and industry experience for decommissioning a nuclear power reactor. EPRI anticipates periodic updates of this document to incorporate various utility experiences with decommissioning, and also to reflect any regulatory changes. The report provides a summary of ongoing federal agency and industry activities and the regulatory requirements that are currently applicable, or no longer applicable, to nuclear power plants at the time of permanent shutdown through the early decommissioning stage. The report describes the major components of a typical decommissioning action plan, providing industry experience and guidance for licensees considering or implementing permanent shutdown.

  7. Batch Proving and Proof Scripting in PVS

    NASA Technical Reports Server (NTRS)

    Munoz, Cesar A.

    2007-01-01

    The batch execution modes of PVS are powerful, but highly technical, features of the system that are mostly accessible to expert users. This paper presents a PVS tool, called ProofLite, that extends the theorem prover interface with a batch proving utility and a proof scripting notation. ProofLite enables a semi-literate proving style where specification and proof scripts reside in the same file. The goal of ProofLite is to provide batch proving and proof scripting capabilities to regular, non-expert, users of PVS.

  8. Proving relations between modular graph functions

    NASA Astrophysics Data System (ADS)

    Basu, Anirban

    2016-12-01

    We consider modular graph functions that arise in the low energy expansion of the four graviton amplitude in type II string theory. The vertices of these graphs are the positions of insertions of vertex operators on the toroidal worldsheet, while the links are the scalar Green functions connecting the vertices. Graphs with four and five links satisfy several non-trivial relations, which have been proved recently. We prove these relations by using elementary properties of Green functions and the details of the graphs. We also prove a relation between modular graph functions with six links.

  9. Using probabilistic criteria in an assessment of the potential radiological consequences of the decommissioning of a nuclear research reactor

    SciTech Connect

    Wallner, Christian; Rall, Anna-Maria; Thummerer, Severin

    2013-07-01

    In order to assess the risk of radiological consequences of incidents and accidents in nuclear facilities it is important to contemplate their frequency of occurrence. It has to be shown that incidents and accidents occur sufficiently seldom according to their radiological consequences i. e. the occurrence frequency of radiological doses has to be limited. This is even demanded by the German radiation protection ordinance (StrlSchV), which says that in nuclear facilities other than nuclear power plants (NPP) in operation and for decommissioning, the occurrence frequency of incidents and accidents shall be contemplated in order to prove the design of safety measures and safety installations. Based on the ideas of the ICRP64, we developed a risk based assessment concept for nuclear facilities, which fulfils the requirements of the German regulations concerning dose limits in normal operation and design basis accidents. The general use of the concept is dedicated to nuclear facilities other than nuclear power plants (NPP) in operation and for decommissioning, where the regulation of risk assessment is less sophisticated. The concept specifies occurrence frequency limits for radiation exposure dose ranges, i. e. the occurrence frequency of incidents and accidents has to be limited according to their radiological effects. To apply this concept, scenarios of incidents and accidents are grouped in exposition classes according to their resulting potential effective dose to members of the general public. The occurrence frequencies of the incidents and accidents are summarized in each exposition class whereas the sum must not exceed the frequency limits mentioned above. In the following we introduce the application of this concept in the assessment of the potential radiological consequences of the decommissioning of a nuclear research reactor. We carried out this assessment for the licensing process of the decommissioning on behalf of German authorities. (authors)

  10. The shielding design process--new plants to decommissioning.

    PubMed

    Jeffries, Graham; Cooper, Andrew; Hobson, John

    2005-01-01

    BNFL have over 25 years experience of designing nuclear plant for the whole-fuel cycle. In the UK, a Nuclear Decommissioning Authority (NDA) is to be set up to ensure that Britain's nuclear legacy is cleaned up safely, securely and cost effectively. The resulting challenges and opportunities for shielding design will be substantial as the shielding design process was originally devised for the design of new plants. Although its underlying principles are equally applicable to decommissioning and remediation of old plants, there are many aspects of detailed application that need to adapt to this radically different operating environment. The paper describes both the common issues and the different challenges of shielding design at different operational phases. Sample applications will be presented of both new plant and decommissioning projects that illustrate not only the robust nature of the processes being used, but also how they lead to cost-effective solutions making a substantive and appropriate contribution to radiological protection goals.

  11. Management of the decommissioning of the Thetis reactor

    SciTech Connect

    Ooms, Luc; Maris, Patrick; Noynaert, Luc

    2013-07-01

    The Thetis research reactor on the site of the Nuclear Sciences Institute of the Ghent University has been in operation from 1967 until December 2003. This light-water moderated graphite-reflected low-enriched uranium pool-type reactor has been used for various purposes e.g. the production of radioisotopes and activation analyses. During the first years its core power was 15 kW. In the early '70, a core enlargement allowed for operation at typically 150 kW, while the maximum was allowed to be 250 kW In September 2007, Ghent University entrusted to SCK-CEN the management of the back-end of the spent fuel and the decommissioning of the reactor. In 2010, the spent fuel was removed from the reactor and transported to Belgoprocess for cementation in 400 l drums and interim storage awaiting final disposal. This activity allows tackling the decommissioning of the reactor. The objective is to complete its decommissioning by the end of 2014. In the framework of the decommissioning of the Thetis reactor, SCK-CEN set-up the final decommissioning plan and the decommissioning licensing file. These documents include among others a radiological inventory of the reactor. The graphite moderator blocks, the control and the safety pates, the liner of the pool were modeled to assess the activation products (isotopic vector and intensity). At the end of the unloading of the reactor in 2010 a brief mapping of the equipment's and internals of the reactor pool was performed. In 2012, we realized a more detailed mapping. These results confirmed those performed earlier and allowed to confirm the assumptions made in the final decommissioning plan. We set-up the terms of reference for the first decommissioning phase of the reactor namely the dismantling of the reactor i.e. reactor pool, circuits and rabbit system, equipment's and ventilation ducts. The removal of asbestos is also included into this phase. We conducted the selection process and the awarding of this decommissioning job. We

  12. DEACTIVATION AND DECOMMISSIONING PLANNING AND ANALYSIS WITH GEOGRAPHIC INFORMATION SYSTEMS

    SciTech Connect

    Bollinger, J; William Austin, W; Larry Koffman, L

    2007-09-17

    From the mid-1950's through the 1980's, the U.S. Department of Energy's Savannah River Site produced nuclear materials for the weapons stockpile, for medical and industrial applications, and for space exploration. Although SRS has a continuing defense-related mission, the overall site mission is now oriented toward environmental restoration and management of legacy chemical and nuclear waste. With the change in mission, SRS no longer has a need for much of the infrastructure developed to support the weapons program. This excess infrastructure, which includes over 1000 facilities, will be decommissioned and demolished over the forthcoming years. Dispositioning facilities for decommissioning and deactivation requires significant resources to determine hazards, structure type, and a rough-order-of-magnitude estimate for the decommissioning and demolition cost. Geographic information systems (GIS) technology was used to help manage the process of dispositioning infrastructure and for reporting the future status of impacted facilities.

  13. Beneficial Re-use of Decommissioned Former Nuclear Facilities

    SciTech Connect

    Boing, L.E.

    1997-06-01

    With the decision to decommission a nuclear facility, it is necessary to evaluate whether to fully demolish a facility or to re-use the facility in some capacity. This evaluation is often primarily driven by both the past mission of the site and the facility and the site's perceived future mission. In the case where the facility to be decommissioned is located within a large research or industrial complex and represents a significant resource to the site's future mission, it may be a perfect candidate to be re-used in some fashion. However, if the site is a rather remote older facility with little chance of being modified to today's standards for its re-use, the chances for its re-use will be substantially reduced. In this presentation, some specific cases of former nuclear facilities being decommissioned and re-used will be reviewed and some factors required to be considered in making this decision will be reviewed.

  14. Completion of decommissioning: Monitoring for site release and license termination

    SciTech Connect

    Boing, L.E.

    1997-08-01

    To request termination of a license upon completion of dismantling or decommissioning activities, documenting any residual radioactivity to show that the levels are environmentally acceptable will be necessary. When the regulators approve the decommissioning plan, they establish what the release criteria for the decommissioned site will be at the time of the site release and license termination. The criteria are numeric guidelines for direct radiation in soils and on surfaces. If the regulatory body finds that the measured on-site values are below the guidelines, the site will be acceptable for unrestricted release (no radiological controls or future use). If areas are found above those values, more decontamination or cleanup of these areas may be required unless the regulatory body grants an exemption.

  15. 26 CFR 1.468A-1T - Nuclear decommissioning costs; general rules (temporary).

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 26 Internal Revenue 6 2010-04-01 2010-04-01 false Nuclear decommissioning costs; general rules...-1T Nuclear decommissioning costs; general rules (temporary). (a) Introduction. Section 468A provides an elective method for taking into account nuclear decommissioning costs for Federal income...

  16. 30 CFR 585.1019 - What are the decommissioning requirements for an Alternate Use RUE?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... an Alternate Use RUE? 585.1019 Section 585.1019 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT... Facilities Decommissioning An Alternate Use Rue § 585.1019 What are the decommissioning requirements for an Alternate Use RUE? (a) Decommissioning requirements will be determined by BOEM on a case-by-case basis,...

  17. 30 CFR 285.1019 - What are the decommissioning requirements for an Alternate Use RUE?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... an Alternate Use RUE? 285.1019 Section 285.1019 Mineral Resources MINERALS MANAGEMENT SERVICE... Facilities Decommissioning An Alternate Use Rue § 285.1019 What are the decommissioning requirements for an Alternate Use RUE? (a) Decommissioning requirements will be determined by MMS on a case-by-case basis,...

  18. 30 CFR 585.1019 - What are the decommissioning requirements for an Alternate Use RUE?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... an Alternate Use RUE? 585.1019 Section 585.1019 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT... Facilities Decommissioning An Alternate Use Rue § 585.1019 What are the decommissioning requirements for an Alternate Use RUE? (a) Decommissioning requirements will be determined by BOEM on a case-by-case basis,...

  19. 30 CFR 285.1019 - What are the decommissioning requirements for an Alternate Use RUE?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... an Alternate Use RUE? 285.1019 Section 285.1019 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT... Activities Using Existing OCS Facilities Decommissioning An Alternate Use Rue § 285.1019 What are the decommissioning requirements for an Alternate Use RUE? (a) Decommissioning requirements will be determined by...

  20. 30 CFR 585.1019 - What are the decommissioning requirements for an Alternate Use RUE?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... an Alternate Use RUE? 585.1019 Section 585.1019 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT... Facilities Decommissioning An Alternate Use Rue § 585.1019 What are the decommissioning requirements for an Alternate Use RUE? (a) Decommissioning requirements will be determined by BOEM on a case-by-case basis,...

  1. 26 CFR 1.468A-1 - Nuclear decommissioning costs; general rules.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 26 Internal Revenue 6 2014-04-01 2014-04-01 false Nuclear decommissioning costs; general rules. 1...-1 Nuclear decommissioning costs; general rules. (a) Introduction. Section 468A provides an elective method for taking into account nuclear decommissioning costs for Federal income tax purposes. In...

  2. 26 CFR 1.468A-1 - Nuclear decommissioning costs; general rules.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 26 Internal Revenue 6 2012-04-01 2012-04-01 false Nuclear decommissioning costs; general rules. 1...-1 Nuclear decommissioning costs; general rules. (a) Introduction. Section 468A provides an elective method for taking into account nuclear decommissioning costs for Federal income tax purposes. In...

  3. 26 CFR 1.468A-1 - Nuclear decommissioning costs; general rules.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 26 Internal Revenue 6 2011-04-01 2011-04-01 false Nuclear decommissioning costs; general rules. 1...-1 Nuclear decommissioning costs; general rules. (a) Introduction. Section 468A provides an elective method for taking into account nuclear decommissioning costs for Federal income tax purposes. In...

  4. 26 CFR 1.468A-1 - Nuclear decommissioning costs; general rules.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 26 Internal Revenue 6 2013-04-01 2013-04-01 false Nuclear decommissioning costs; general rules. 1...-1 Nuclear decommissioning costs; general rules. (a) Introduction. Section 468A provides an elective method for taking into account nuclear decommissioning costs for Federal income tax purposes. In...

  5. 77 FR 8902 - Draft Regulatory Guide: Issuance, Availability Decommissioning of Nuclear Power Reactors

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-02-15

    ... COMMISSION Draft Regulatory Guide: Issuance, Availability Decommissioning of Nuclear Power Reactors AGENCY... ``Decommissioning of Nuclear Power Reactors.'' This guide describes a method NRC considers acceptable for use in decommissioning power reactors. DATES: Submit comments by April 16, 2012. Comments received after this date...

  6. 77 FR 75198 - Standard Format and Content for Post-Shutdown Decommissioning Activities Report

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-12-19

    ... COMMISSION Standard Format and Content for Post-Shutdown Decommissioning Activities Report AGENCY: Nuclear... Format and Content for Post-shutdown Decommissioning Activities Report.'' This guide describes a method...) 1.185, ``Standard Format and Content for Post-shutdown Decommissioning Activities Report,''...

  7. A costing model for offshore decommissioning in California.

    PubMed

    Bressler, Andrew; Bernstein, Brock B

    2015-10-01

    California's 27 offshore oil and gas platforms will reach the end of their useful lifetimes sometime in the near future and will require decommissioning. Although existing leases require complete removal of all platforms and associated infrastructure, the underlying laws and regulations have changed in recent years to allow a number of alternative uses after decommissioning. In particular, AB 2503, signed into law in September 2010, provides for a rigs-to-reefs program that allows the state to accept ownership of decommissioned platforms in federal waters. Decisions about whether to remove platforms completely or leave them in place as artificial reefs will depend in part on the relative cost of the 2 options. In this study, we describe the design and use of a mathematical decision model that provides detailed cost estimates of complete and partial removal (to 85 feet below the water line) for California's offshore platforms. The model, PLATFORM, is loaded with Bureau of Safety and Environmental Enforcement (BSEE) and Bureau of Ocean Energy Management (BOEM) costs for complete removal, along with costs for partial removal calculated for this study and estimates of the uncertainty associated with decommissioning cost estimates. PLATFORM allows users to define a wide range of decommissioning and costing scenarios (e.g., number of platforms, choice of heavy lift vessel, shell mound removal, reef enhancement). As a benchmark cost, complete removal of all 27 offshore platforms, grouped into the 7 decommissioning projects defined by the most recent federal cost estimates produced in 2010, would cost an estimated $1.09 billion, whereas partial removal of these platforms, grouped into the same set of projects, would cost $478 million, with avoided costs of $616 million (with minor rounding).

  8. The involvement of SCK-CEN in decommissioning projects

    SciTech Connect

    Noynaert, Luc; Cornelissen, Rene; Dadoumont, Jerome; Van den Dungen, Kurt

    2013-07-01

    SCK-CEN is the Belgian Nuclear Research Centre. Founded in the mid-fifties, it has accumulated experience and know-how in all fields of the nuclear power production: in the neutronics calculation, radiation protection, waste management, fuel performance and analysis, nuclear measurements, radiochemistry, reactor technology, etc. Since 1989, SCK-CEN has launched Decommissioning activities to deal with the Technical Liabilities created by 40 years of operation. The main projects started were: - the dismantling of the BR3 PWR reactor; - the dismantling of active laboratories and the decontamination of buildings for unrestricted reuse; - the management of the waste arising from the refurbishment activities of the BR2, especially the management of the high active beryllium matrix. In 1989, the BR3 reactor, a Pressurized Water Reactor, was selected by the European Commission as one of the four pilot dismantling projects in the framework of the EC five year RTD program on dismantling nuclear installations. Through this project, SCK-CEN has built up a broad know-how in dismantling and decommissioning operations. This know how concerns the decontamination for dose rate reduction and/or free release of materials, tele-operated techniques for cutting highly activated components of a reactor, concrete decontamination techniques, characterization techniques of radioactive waste or for free release of components and development of decommissioning management and record-keeping of material streams and of nuclear material accountancy. SCK-CEN is now actively involved in other decommissioning projects in Belgium and in expertise abroad. After giving an overview of the main achievements and the perspectives of the decommissioning of the BR3 reactor, the paper intends to present the involvement of SCK-CEN in the other decommissioning projects and to give an overview of our activities and capacities. (authors)

  9. Technology demonstrations in the Decontamination and Decommissioning Focus Area

    SciTech Connect

    Bossart, S.J.

    1996-02-01

    This paper describes three large-scale demonstration projects sponsored jointly by the Decontamination and Decommissioning Focus Area (DDFA), and the three US Department of Energy (DOE) Operations Offices that successfully offered to deactivate or decommission (D&D) one of its facilities using a combination of innovative and commercial D&D technologies. The paper also includes discussions on recent technology demonstrations for an Advanced Worker Protection System, an Electrohydraulic Scabbling System, and a Pipe Explorer{trademark}. The references at the conclusion of this paper should be consulted for more detailed information about the large-scale demonstration projects and recent technology demonstrations sponsored by the DDFA.

  10. Regulatory Reform and License Termination Planning in Decommissioning

    SciTech Connect

    Michael J. Meisner

    2000-06-04

    Decommissioning of commercial nuclear power plants (NPPs) must be safe and cost-effective and consider the needs of a wide range of stakeholders. The creative tension among these objectives has provided opportunities to reform the way these plants are regulated and managed in decommissioning. Enlightened and visionary leaders from the U.S. Nuclear Regulatory Commission (NRC) and industry are seizing these opportunities to create new paradigms for risk-informed regulation; creative stakeholder involvement; and effective, end-state focused, license termination planning.

  11. Jose Cabrera dismantling and decommissioning project

    SciTech Connect

    Ondaro, Manuel

    2013-07-01

    The Jose Cabrera Nuclear Power Plant (NPP) was the first commercial power reactor (Westinghouse 1 loop PWR 510 MWth, 160 MWe) commissioned in Spain and provided the base for future development and training. The reactor construction started in 1963 and it was officially on-line by 1969. The NPP operated from 1969 until 2006 when it became the first reactor to be shut down after completing its operational period. The containment is reinforced concrete with a stainless steel head. In 2010 responsibility for D and D was transferred to Enresa to achieve IAEA level 3 (a green field site available for unrestricted re-uses) by 2017. Of the total of more than 104,000 tons of materials that will be generated during dismantling, it is estimated that only ∼4,000 tons will be radioactive waste, some of which, 40 t are considered as intermediate level long-lived wastes and the rest (3,960 t) will be categorized as VLLW and ILLW. The Project is divided into five phases: Phase 0 - Removal of fuel and preliminary work.. Phase 1 - Preparatory Activities for D and D. complete. Phase 2 - Dismantling of Major Components. Phase 3 - Removal of Auxiliary Installations, Decontamination and Demolition. Phase 4 - Environmental Restoration. Phase 2, is currently ongoing (50% completed). To manage the diverse aspects of decommissioning operations, Enresa uses an internally developed computerized project management tool. The tool, based on knowledge gathered from other Enresa projects, can process operations management, maintenance operations, materials, waste, storage areas, procedures, work permits, operator dose management and records. Enresa considers that communication is important for both internal and external stakeholder relations and can be used to inform, to neutralize negative opinions and attitudes, to remove false expectations and for training. Enresa has created a new multi-purpose area (exhibition/visitor centre) and encourages visits from the public, local schools, local and

  12. Decommissioning Project of Bohunice A1 NPP

    SciTech Connect

    Stubna, M.; Pekar, A.; Moravek, J.; Spirko, M.

    2002-02-26

    1977 to terminate plant operation. The decision on the A1 plant decommissioning was issued in 1979.

  13. 26 CFR 1.468A-5 - Nuclear decommissioning fund qualification requirements; prohibitions against self-dealing...

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... taxpayer for decommissioning costs of the nuclear power plant to which the nuclear decommissioning fund... premiums on a policy to pay for the nuclear decommissioning costs of a nuclear power plant. Such term also... decommissioning costs of the nuclear power plant to which the nuclear......

  14. 26 CFR 1.468A-5 - Nuclear decommissioning fund qualification requirements; prohibitions against self-dealing...

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... taxpayer for decommissioning costs of the nuclear power plant to which the nuclear decommissioning fund... premiums on a policy to pay for the nuclear decommissioning costs of a nuclear power plant. Such term also... decommissioning costs of the nuclear power plant to which the nuclear......

  15. 26 CFR 1.468A-5 - Nuclear decommissioning fund qualification requirements; prohibitions against self-dealing...

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... taxpayer for decommissioning costs of the nuclear power plant to which the nuclear decommissioning fund... premiums on a policy to pay for the nuclear decommissioning costs of a nuclear power plant. Such term also... decommissioning costs of the nuclear power plant to which the nuclear......

  16. 26 CFR 1.468A-5 - Nuclear decommissioning fund qualification requirements; prohibitions against self-dealing...

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... taxpayer for decommissioning costs of the nuclear power plant to which the nuclear decommissioning fund... premiums on a policy to pay for the nuclear decommissioning costs of a nuclear power plant. Such term also... decommissioning costs of the nuclear power plant to which the nuclear......

  17. Integration of improved decontamination and characterization technologies in the decommissioning of the CP-5 research reactor

    SciTech Connect

    Bhattacharyya, S. K.; Boing, L. E.

    2000-02-17

    The aging of research reactors worldwide has resulted in a heightened awareness in the international technical decommissioning community of the timeliness to review and address the needs of these research institutes in planning for and eventually performing the decommissioning of these facilities. By using the reactors already undergoing decommissioning as test beds for evaluating enhanced or new/innovative technologies for decommissioning, it is possible that new techniques could be made available for those future research reactor decommissioning projects. Potentially, the new technologies will result in: reduced radiation doses to the work force, larger safety margins in performing decommissioning and cost and schedule savings to the research institutes in performing the decommissioning of these facilities. Testing of these enhanced technologies for decontamination, dismantling, characterization, remote operations and worker protection are critical to furthering advancements in the technical specialty of decommissioning. Furthermore, regulatory acceptance and routine utilization for future research reactor decommissioning will be assured by testing and developing these technologies in realistically contaminated environments prior to use in the research reactors. The decommissioning of the CP-5 Research Reactor is currently in the final phase of dismantlement. In this paper the authors present results of work performed at Argonne National Laboratory (ANL) in the development, testing and deployment of innovative and/or enhanced technologies for the decommissioning of research reactors.

  18. Generic Example Proving Criteria for All

    ERIC Educational Resources Information Center

    Yopp, David; Ely, Rob; Johnson­-Leung, Jennifer

    2015-01-01

    We review literature that discusses generic example proving and highlight ambiguities that pervade our research community's discourse about generic example arguments. We distinguish between pedagogical advice for choosing good examples that can serve as generic examples when teaching and advice for developing generic example arguments. We provide…

  19. Generic Proving: Reflections on Scope and Method

    ERIC Educational Resources Information Center

    Leron, Uri; Zaslavsky, Orit

    2013-01-01

    We analyze the role of generic proofs in helping students access difficult proofs more easily and naturally. We present three examples of generic proving--an elementary one on numbers, a more advanced one on permutations, and yet more advanced one on groups--and consider the affordances and pitfalls of the method by reflecting on these examples. A…

  20. Type Theory, Computation and Interactive Theorem Proving

    DTIC Science & Technology

    2015-09-01

    Springer, Heidelberg, 61-76, 2014. [9] Jeremy Avigad and John Harrison , “Formally verified mathematics,” Communications of the ACM, 57(4):66-75, 2014. [10...inequalities," in Gerwin Klein and Ruben Gamboa, eds., Interactive Theorem Proving 2014, Springer, Heidelberg, 61-76, 2014. 9) Jeremy Avigad and John Harrison

  1. The Role of Abduction in Proving Processes

    ERIC Educational Resources Information Center

    Pedemonte, Bettina; Reid, David

    2011-01-01

    This paper offers a typology of forms and uses of abduction that can be exploited to better analyze abduction in proving processes. Based on the work of Peirce and Eco, we describe different kinds of abductions that occur in students' mathematical activity and extend Toulmin's model of an argument as a methodological tool to describe students'…

  2. Affect, Behavioural Schemas and the Proving Process

    ERIC Educational Resources Information Center

    Selden, Annie; McKee, Kerry; Selden, John

    2010-01-01

    In this largely theoretical article, we discuss the relation between a kind of affect, behavioural schemas and aspects of the proving process. We begin with affect as described in the mathematics education literature, but soon narrow our focus to a particular kind of affect--nonemotional cognitive feelings. We then mention the position of feelings…

  3. Korea Research Reactor -1 & 2 Decommissioning Project in Korea

    SciTech Connect

    Park, S. K.; Chung, U. S.; Jung, K. J.; Park, J. H.

    2003-02-24

    Korea Research Reactor 1 (KRR-1), the first research reactor in Korea, has been operated since 1962, and the second one, Korea Research Reactor 2 (KRR-2) since 1972. The operation of both of them was phased out in 1995 due to their lifetime and operation of the new and more powerful research reactor, HANARO (High-flux Advanced Neutron Application Reactor; 30MW). Both are TRIGA Pool type reactors in which the cores are small self-contained units sitting in tanks filled with cooling water. The KRR-1 is a TRIGA Mark II, which could operate at a level of up to 250 kW. The second one, the KRR-2 is a TRIGA Mark III, which could operate at a level of up 2,000 kW. The decontamination and decommissioning (D & D) project of these two research reactors, the first D & D project in Korea, was started in January 1997 and will be completed to stage 3 by 2008. The aim of this decommissioning program is to decommission the KRR-1 & 2 reactors and to decontaminate the residual building structure s and the site to release them as unrestricted areas. KAERI (Korea Atomic Energy Research Institute) submitted the decommissioning plan and the environmental impact assessment reports to the Ministry of Science and Technology (MOST) for the license in December 1998, and was approved in November 2000.

  4. 10 CFR 72.130 - Criteria for decommissioning.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Criteria for decommissioning. 72.130 Section 72.130 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE General...

  5. 77 FR 8751 - Guidance for Decommissioning Planning During Operations

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-02-15

    ... Planning During Operations AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide; re... Commission (NRC) re-issued Draft Regulatory Guide, DG-4014, ``Decommissioning Planning During Operations'' in... Planning Rule. DATES: Submit comments by March 30, 2012. Comments received after this date will...

  6. 18 CFR 2.24 - Project decommissioning at relicensing.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 18 Conservation of Power and Water Resources 1 2012-04-01 2012-04-01 false Project decommissioning at relicensing. 2.24 Section 2.24 Conservation of Power and Water Resources FEDERAL ENERGY REGULATORY COMMISSION, DEPARTMENT OF ENERGY GENERAL RULES GENERAL POLICY AND INTERPRETATIONS Statements of...

  7. 18 CFR 2.24 - Project decommissioning at relicensing.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 18 Conservation of Power and Water Resources 1 2013-04-01 2013-04-01 false Project decommissioning at relicensing. 2.24 Section 2.24 Conservation of Power and Water Resources FEDERAL ENERGY REGULATORY COMMISSION, DEPARTMENT OF ENERGY GENERAL RULES GENERAL POLICY AND INTERPRETATIONS Statements of...

  8. 18 CFR 2.24 - Project decommissioning at relicensing.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 18 Conservation of Power and Water Resources 1 2010-04-01 2010-04-01 false Project decommissioning at relicensing. 2.24 Section 2.24 Conservation of Power and Water Resources FEDERAL ENERGY REGULATORY COMMISSION, DEPARTMENT OF ENERGY GENERAL RULES GENERAL POLICY AND INTERPRETATIONS Statements of...

  9. Technology, safety, and costs of decommissioning a reference large irradiator and reference sealed sources

    SciTech Connect

    Haffner, D.R.; Villelgas, A.J.

    1996-01-01

    This report contains the results of a study sponsored by the US Nuclear Regulatory Commission (NRC) to examine the decommissioning of large radioactive irradiators and their respective facilities, and a broad spectrum of sealed radioactive sources and their respective devices. Conceptual decommissioning activities are identified, and the technology, safety, and costs (in early 1993 dollars) associated with decommissioning the reference large irradiator and sealed source facilities are evaluated. The study provides bases and background data for possible future NRC rulemaking regarding decommissioning, for evaluation of the reasonableness of planned decommissioning actions, and for determining if adequate funds are reserved by the licensees for decommissioning of their large irradiator or sealed source facilities. Another purpose of this study is to provide background and information to assist licensees in planning and carrying out the decommissioning of their sealed radioactive sources and respective facilities.

  10. Decommissioning of the BR3 reactor: status and perspectives

    SciTech Connect

    Noynaert, L.; Verstraeten, I.

    2007-07-01

    The BR3 plant at Mol in Belgium built at the end of the fifties was the first PWR plant built outside the USA. The reactor had a small net power output (10 MWe) but comprised all the loops and features of a commercial PWR plant. The BR3 plant was operated with the main objective of testing advanced PWR fuels under irradiation conditions similar to those encountered in large commercial PWR plants. The reactor was started in 1962 and shut down in 1987 after 25 years of continuous operation. Since 1989, SCK.CEN is decommissioning the BR3 PWR research reactor. The dismantling of the metallic components including reactor pressure vessel and internals is completed and extensively reported in the literature. The dismantling of auxiliary components and the decontamination of parts of the infrastructure are now going on. The decommissioning progress is continuously monitored and costs and strategy are regularly reassessed. The first part of the paper describes the main results and lessons learned from the reassessment exercises performed in 1994, 1999, 2004 and 2007. Impacts of changes in legal framework on the decommissioning costs will be addressed. These changes concern e.g. licensing aspects, clearance levels, waste management... The middle part of the paper discusses the management of activated and/or contaminated concrete. The costing exercise performed in 1995 highlighted that the management of activated and contaminated concrete is the second main cost item after the dismantling of the reactor pressure vessel and internals. Different possible solutions were studied. These are evacuation as radioactive waste with or without supercompaction, recycling this 'radioactive' grout or concrete for conditioning of radioactive waste e.g. conditioning of metallic waste. The paper will give the results of the cost-benefit analysis made to select the solution retained. The last part of the paper will discuss the end goal of the decommissioning of the BR3. In the final

  11. Decommissioning of U.S. uranium production facilities

    SciTech Connect

    Not Available

    1995-02-01

    From 1980 to 1993, the domestic production of uranium declined from almost 44 million pounds U{sub 3}O{sub 8} to about 3 million pounds. This retrenchment of the U.S. uranium industry resulted in the permanent closing of many uranium-producing facilities. Current low uranium prices, excess world supply, and low expectations for future uranium demand indicate that it is unlikely existing plants will be reopened. Because of this situation, these facilities eventually will have to be decommissioned. The Uranium Mill Tailings and Radiation Control Act of 1978 (UMTRCA) vests the U.S. Environmental Protection Agency (EPA) with overall responsibility for establishing environmental standards for decommissioning of uranium production facilities. UMTRCA also gave the U.S. Nuclear Regulatory Commission (NRC) the responsibility for licensing and regulating uranium production and related activities, including decommissioning. Because there are many issues associated with decommissioning-environmental, political, and financial-this report will concentrate on the answers to three questions: (1) What is required? (2) How is the process implemented? (3) What are the costs? Regulatory control is exercised principally through the NRC licensing process. Before receiving a license to construct and operate an uranium producing facility, the applicant is required to present a decommissioning plan to the NRC. Once the plan is approved, the licensee must post a surety to guarantee that funds will be available to execute the plan and reclaim the site. This report by the Energy Information Administration (EIA) represents the most comprehensive study on this topic by analyzing data on 33 (out of 43) uranium production facilities located in Colorado, Nebraska, New Mexico, South Dakota, Texas, Utah, and Washington.

  12. Atmospheric discharges from nuclear facilities during decommissioning: German experiences

    SciTech Connect

    Braun, H.; Goertz, R.; Weil, L.

    1997-08-01

    In Germany, a substantial amount of experience is available with planning, licensing and realization of decommissioning projects. In total, a number of 18 nuclear power plants including prototype facilities as well as 6 research reactors and 3 fuel cycle facilities have been shut down finally and are at different stages of decommissioning. Only recently the final {open_quotes}green field{close_quotes} stage of the Niederaichbach Nuclear Power Plant total dismantlement project has been achieved. From the regulatory point of view, a survey of the decommissioning experience in Germany is presented highlighting the aspects of production and retention of airborne radioactivity. Nuclear air cleaning technology, discharge limits prescribed in licences and actual discharges are presented. As compared to operation, the composition of the discharged radioactivity is different as well as the off-gas discharge rate. In practically all cases, there is no significant amount of short-lived radionuclides. The discussion further includes lessons learned, for example inadvertent discharges of radionuclides expected not to be in the plants inventory. It is demonstrated that, as for operation of nuclear power plants, the limits prescribed in the Ordinance on Radiological Protection can be met using existing air cleaning technology, Optimization of protection results in public exposures substantially below the limits. In the frame of the regulatory investigation programme a study has been conducted to assess the airborne radioactivity created during certain decommissioning activities like decontamination, segmentation and handling of contaminated or activated parts. The essential results of this study are presented, which are supposed to support planning for decommissioning, for LWRs, Co-60 and Cs-137 are expected to be the dominant radionuclides in airborne discharges. 18 refs., 2 figs., 1 tab.

  13. Theorem Proving In Higher Order Logics

    NASA Technical Reports Server (NTRS)

    Carreno, Victor A. (Editor); Munoz, Cesar A.; Tahar, Sofiene

    2002-01-01

    The TPHOLs International Conference serves as a venue for the presentation of work in theorem proving in higher-order logics and related areas in deduction, formal specification, software and hardware verification, and other applications. Fourteen papers were submitted to Track B (Work in Progress), which are included in this volume. Authors of Track B papers gave short introductory talks that were followed by an open poster session. The FCM 2002 Workshop aimed to bring together researchers working on the formalisation of continuous mathematics in theorem proving systems with those needing such libraries for their applications. Many of the major higher order theorem proving systems now have a formalisation of the real numbers and various levels of real analysis support. This work is of interest in a number of application areas, such as formal methods development for hardware and software application and computer supported mathematics. The FCM 2002 consisted of three papers, presented by their authors at the workshop venue, and one invited talk.

  14. Dr. Auzoux's botanical teaching models and medical education at the universities of Glasgow and Aberdeen.

    PubMed

    Olszewski, Margaret Maria

    2011-09-01

    In the 1860s, Dr. Louis Thomas Jérôme Auzoux introduced a set of papier-mâché teaching models intended for use in the botanical classroom. These botanical models quickly made their way into the educational curricula of institutions around the world. Within these institutions, Auzoux's models were principally used to fulfil educational goals, but their incorporation into diverse curricula also suggests they were used to implement agendas beyond botanical instruction. This essay examines the various uses and meanings of Dr. Auzoux's botanical teaching models at the universities of Glasgow and Aberdeen in the nineteenth century. The two main conclusions of this analysis are: (1) investing in prestigious scientific collections was a way for these universities to attract fee-paying students so that better medical accommodation could be provided and (2) models were used to transmit different kinds of botanical knowledge at both universities. The style of botany at the University of Glasgow was offensive and the department there actively embraced and incorporated ideas of the emerging new botany. At Aberdeen, the style of botany was defensive and there was some hesitancy when confronting new botanical ideas.

  15. How utilities can achieve more accurate decommissioning cost estimates

    SciTech Connect

    Knight, R.

    1999-07-01

    The number of commercial nuclear power plants that are undergoing decommissioning coupled with the economic pressure of deregulation has increased the focus on adequate funding for decommissioning. The introduction of spent-fuel storage and disposal of low-level radioactive waste into the cost analysis places even greater concern as to the accuracy of the fund calculation basis. The size and adequacy of the decommissioning fund have also played a major part in the negotiations for transfer of plant ownership. For all of these reasons, it is important that the operating plant owner reduce the margin of error in the preparation of decommissioning cost estimates. To data, all of these estimates have been prepared via the building block method. That is, numerous individual calculations defining the planning, engineering, removal, and disposal of plant systems and structures are performed. These activity costs are supplemented by the period-dependent costs reflecting the administration, control, licensing, and permitting of the program. This method will continue to be used in the foreseeable future until adequate performance data are available. The accuracy of the activity cost calculation is directly related to the accuracy of the inventory of plant system component, piping and equipment, and plant structural composition. Typically, it is left up to the cost-estimating contractor to develop this plant inventory. The data are generated by searching and analyzing property asset records, plant databases, piping and instrumentation drawings, piping system isometric drawings, and component assembly drawings. However, experience has shown that these sources may not be up to date, discrepancies may exist, there may be missing data, and the level of detail may not be sufficient. Again, typically, the time constraints associated with the development of the cost estimate preclude perfect resolution of the inventory questions. Another problem area in achieving accurate cost

  16. Service Networks and Patterns of Utilization: Mental Health Programs, Indian Health Service (IHS). Volume 2: Aberdeen Area, 1965-1973.

    ERIC Educational Resources Information Center

    Attneave, Carolyn L.; Beiser, Morton

    The second volume in a 10-volume report on the historical development (1966-1973) of the 8 administrative Area Offices of the Indian Health Service (IHS) Mental Health Programs, this report presents information on the Aberdeen Area Office. Included in this document are: (1) Description of the Area (geography of the Area's Western Portion and…

  17. Proving refinement transformations using extended denotational semantics

    SciTech Connect

    Winter, V.L.; Boyle, J.M.

    1996-04-01

    TAMPR is a fully automatic transformation system based on syntactic rewrites. Our approach in a correctness proof is to map the transformation into an axiomatized mathematical domain where formal (and automated) reasoning can be performed. This mapping is accomplished via an extended denotational semantic paradigm. In this approach, the abstract notion of a program state is distributed between an environment function and a store function. Such a distribution introduces properties that go beyond the abstract state that is being modeled. The reasoning framework needs to be aware of these properties in order to successfully complete a correctness proof. This paper discusses some of our experiences in proving the correctness of TAMPR transformations.

  18. Carbon-14 bioassay for decommissioning of Hanford reactors.

    PubMed

    Carbaugh, Eugene H; Watson, David J

    2012-05-01

    The production reactors at the U.S. Department of Energy Hanford Site used large graphite piles as the moderator. As part of long-term decommissioning plans, the potential need for ¹⁴C radiobioassay of workers was identified. Technical issues associated with ¹⁴C bioassay and worker monitoring were investigated, including anticipated graphite characterization, potential intake scenarios, and the bioassay capabilities that may be required to support the decommissioning of the graphite piles. A combination of urine and feces sampling would likely be required for the absorption type S ¹⁴C anticipated to be encountered. However, the concentrations in the graphite piles appear to be sufficiently low that dosimetrically significant intakes of ¹⁴C are not credible, thus rendering moot the need for such bioassay.

  19. Decontamination and Decommissioning activities photobriefing book FY 1997

    SciTech Connect

    1998-04-01

    The Decontamination and Decommissioning (D and D) Program at Argonne National Laboratory-East (ANL-E) is dedicated to the safe and cost effective D{ampersand}D of surplus nuclear facilities. There is currently a backlog of more than 7,000 contaminated US Department of Energy facilities nationwide. Added to this are 110 licensed commercial nuclear power reactors operated by utilities learning to cope with deregulation and an aging infrastructure that supports the commercial nuclear power industry, as well as medical and other uses of radioactive materials. With this volume it becomes easy to understand the importance of addressing the unique issues and objectives associated with the D{ampersand}D of surplus nuclear facilities. This photobriefing book summarizes the decontamination and decommissioning projects and activities either completed or continuing at the ANL-E site during the year.

  20. Carbon-14 Bioassay for Decommissioning of Hanford Reactors

    SciTech Connect

    Carbaugh, Eugene H.; Watson, David J.

    2012-05-01

    The old production reactors at the US Department of Energy Hanford Site used large graphite piles as the moderator. As part of long-term decommissioning plans, the potential need for 14C radiobioassay of workers was identified. Technical issues associated with 14C bioassay and worker monitoring were investigated, including anticipated graphite characterization, potential intake scenarios, and the bioassay capabilities that may be required to support the decommissioning of the graphite piles. A combination of urine and feces sampling would likely be required for the absorption type S 14C anticipated to be encountered. However the concentrations in the graphite piles appear to be sufficiently low that dosimetrically significant intakes of 14C are not credible, thus rendering moot the need for such bioassay.

  1. Nuclear reactor decommissioning: an analysis of the regulatory environments

    SciTech Connect

    Cantor, R.

    1986-08-01

    In the next several decades, the electric utility industry will be faced withthe retirement of 50,000 megawatts (mW) of nuclear capacity. Responsibility for the financial and technical burdens this activity entails has been delegated to the utilities operating the reactors. However, the operators will have to perform the tasks of reactor decommissioning within the regulatory environment dictated by federal, state and local regulations. The purpose of this study was to highlight some of the current and likely trends in regulations and regulatory practices that will significantly affect the costs, technical alternatives and financing schemes encountered by the electric utilities and their customers. To identify significant trends and practices among regulatory bodies and utilities, a reviw of these factors was undertaken at various levels in the regulatory hierarchy. The technical policies were examined in reference to their treatment of allowed technical modes, restoration of the plant site including any specific recognition of the residual radioactivity levels, and planning requirements. The financial policies were examined for specification of acceptable financing arrangements, mechanisms which adjust for changes in the important parameters used to establish the fund, tax and rate-base treatments of the payments to and earnings on the fund, and whether or not escalation and/or discounting were considered in the estimates of decommissioning costs. The attitudes of regulators toward financial risk, the tax treatment of the decommissioning fund, and the time distribution of the technical mode were found to have the greatest effect on the discounted revenue requirements. Under plausible assumptions, the cost of a highly restricted environment is about seven times that of the minimum revenue requirement environment for the plants that must be decommissioned in the next three decades.

  2. Reducing environmental risk associated with laboratory decommissioning and property transfer.

    PubMed

    Dufault, R; Abelquist, E; Crooks, S; Demers, D; DiBerardinis, L; Franklin, T; Horowitz, M; Petullo, C; Sturchio, G

    2000-12-01

    The need for more or less space is a common laboratory problem. Solutions may include renovating existing space, leaving or demolishing old space, or acquiring new space or property for building. All of these options carry potential environmental risk. Such risk can be the result of activities related to the laboratory facility or property (e.g., asbestos, underground storage tanks, lead paint), or the research associated with it (e.g., radioactive, microbiological, and chemical contamination). Regardless of the option chosen to solve the space problem, the potential environmental risk must be mitigated and the laboratory space and/or property must be decommissioned or rendered safe prior to any renovation, demolition, or property transfer activities. Not mitigating the environmental risk through a decommissioning process can incur significant financial liability for any costs associated with future decommissioning cleanup activities. Out of necessity, a functioning system, environmental due diligence auditing, has evolved over time to assess environmental risk and reduce associated financial liability. This system involves a 4-phase approach to identify, document, manage, and clean up areas of environmental concern or liability, including contamination. Environmental due diligence auditing includes a) historical site assessment, b) characterization assessment, c) remedial effort and d) final status survey. General practice standards from the American Society for Testing and Materials are available for conducting the first two phases. However, standards have not yet been developed for conducting the third and final phases of the environmental due diligence auditing process. Individuals involved in laboratory decommissioning work in the biomedical research industry consider this a key weakness.

  3. TECHNOLOGY REQUIREMENTS FOR IN SITU DECOMMISSIONING WORKSHOP REPORT

    SciTech Connect

    Jannik, T.; Lee, P.; Gladden, J.; Langton, C.; Serrato, M.; Urland, C.; Reynolds, E.

    2009-06-30

    In recognition of the increasing attention being focused on In Situ Decommissioning (ISD or entombment) as an acceptable and beneficial decommissioning end state, the Department of Energy's (DOE) Office of Environmental Management (EM) is developing guidance for the implementation of ISD of excess facilities within the DOE complex. Consistent with the overarching DOE goals for increased personnel and environmental safety, reduced technical uncertainties and risks, and overall gains in efficiencies and effectiveness, EM's Office of Deactivation and Decommissioning and Facility Engineering (EM-23) initiated efforts to identify the technical barriers and technology development needs for the optimal implementation of ISD. Savannah River National Laboratory (SRNL), as the EM Corporate Laboratory, conducted an ISD Technology Needs Workshop to identify the technology needs at DOE sites. The overall goal of the workshop was to gain a full understanding of the specific ISD technical challenges, the technologies available, and those needing development. The ISD Workshop was held December 9-10, 2008 in Aiken, SC. Experienced decommissioning operations personnel from Richland Operations Office (RL), Idaho National Laboratory (INL) and Savannah River Site (SRS) along with scientists and engineers specific expertise were assembled to identify incremental and 'game changing' solutions to ISD technology challenges. The workshop and follow-up activities yielded 14 technology needs statements and the recommendation that EM-23 prioritize and pursue the following specific technology development and deployment actions. For each action, the recommended technology acquisition mechanisms (competitive solicitation (CS) or direct funding (TCR)) are provided. Activities that are time critical for ISD projects, or require unique capabilities that reside in the DOE Laboratory system will be funded directly to those institutions. Activities that have longer lead times and where the private

  4. Reducing environmental risk associated with laboratory decommissioning and property transfer.

    PubMed Central

    Dufault, R; Abelquist, E; Crooks, S; Demers, D; DiBerardinis, L; Franklin, T; Horowitz, M; Petullo, C; Sturchio, G

    2000-01-01

    The need for more or less space is a common laboratory problem. Solutions may include renovating existing space, leaving or demolishing old space, or acquiring new space or property for building. All of these options carry potential environmental risk. Such risk can be the result of activities related to the laboratory facility or property (e.g., asbestos, underground storage tanks, lead paint), or the research associated with it (e.g., radioactive, microbiological, and chemical contamination). Regardless of the option chosen to solve the space problem, the potential environmental risk must be mitigated and the laboratory space and/or property must be decommissioned or rendered safe prior to any renovation, demolition, or property transfer activities. Not mitigating the environmental risk through a decommissioning process can incur significant financial liability for any costs associated with future decommissioning cleanup activities. Out of necessity, a functioning system, environmental due diligence auditing, has evolved over time to assess environmental risk and reduce associated financial liability. This system involves a 4-phase approach to identify, document, manage, and clean up areas of environmental concern or liability, including contamination. Environmental due diligence auditing includes a) historical site assessment, b) characterization assessment, c) remedial effort and d) final status survey. General practice standards from the American Society for Testing and Materials are available for conducting the first two phases. However, standards have not yet been developed for conducting the third and final phases of the environmental due diligence auditing process. Individuals involved in laboratory decommissioning work in the biomedical research industry consider this a key weakness. PMID:11121365

  5. Decontamination and decommissioning of the Mayaguez (Puerto Rico) facility

    SciTech Connect

    Jackson, P.K.; Freemerman, R.L.

    1989-11-01

    On February 6, 1987 the US Department of Energy (DOE) awarded the final phase of the decontamination and decommissioning of the nuclear and reactor facilities at the Center for Energy and Environmental Research (CEER), in Mayaguez, Puerto Rico. Bechtel National, Inc., was made the decontamination and decommissioning (D and D) contractor. The goal of the project was to enable DOE to proceed with release of the CEER facility for use by the University of Puerto Rico, who was the operator. This presentation describes that project and lesson learned during its progress. The CEER facility was established in 1957 as the Puerto Rico Nuclear Center, a part of the Atoms for Peace Program. It was a nuclear training and research institution with emphasis on the needs of Latin America. It originally consisted of a 1-megawatt Materials Testing Reactor (MTR), support facilities and research laboratories. After eleven years of operation the MTR was shutdown and defueled. A 2-megawatt TRIGA reactor was installed in 1972 and operated until 1976, when it woo was shutdown. Other radioactive facilities at the center included a 10-watt homogeneous L-77 training reactor, a natural uranium graphite-moderated subcritical assembly, a 200KV particle accelerator, and a 15,000 Ci Co-60 irradiation facility. Support facilities included radiochemistry laboratories, counting rooms and two hot cells. As the emphasis shifted to non-nuclear energy technology a name change resulted in the CEER designation, and plans were started for the decontamination and decommissioning effort.

  6. A NOVEL APPROACH TO SPENT FUEL POOL DECOMMISSIONING

    SciTech Connect

    R. L. Demmer

    2011-04-01

    The Idaho National Laboratory (INL) has been at the forefront of developing methods to reduce the cost and schedule of deactivating spent fuel pools (SFP). Several pools have been deactivated at the INL using an underwater approach with divers. These projects provided a basis for the INL cooperation with the Dresden Nuclear Power Station Unit 1 SFP (Exelon Generation Company) deactivation. It represents the first time that a commercial nuclear power plant (NPP) SFP was decommissioned using this underwater coating process. This approach has advantages in many aspects, particularly in reducing airborne contamination and allowing safer, more cost effective deactivation. The INL pioneered underwater coating process was used to decommission three SFPs with a total combined pool volume of over 900,000 gallons. INL provided engineering support and shared project plans to successfully initiate the Dresden project. This report outlines the steps taken by INL and Exelon to decommission SFPs using the underwater coating process. The rationale used to select the underwater coating process and the advantages and disadvantages are described. Special circumstances are also discussed, such as the use of a remotely-operated underwater vehicle to visually and radiologically map the pool areas that were not readily accessible. A larger project, the INTEC-603 SFP in-situ (grouting) deactivation, is reviewed. Several specific areas where special equipment was employed are discussed and a Lessons Learned evaluation is included.

  7. Evaluating alternatives for decommissioning California's offshore oil and gas platforms.

    PubMed

    Bernstein, Brock B

    2015-10-01

    This paper introduces a series of 6 additional papers in this issue that describe an in-depth analysis of options for decommissioning oil and gas platforms offshore southern California. Although current leases require lessees in both state and federal waters to completely remove all production facilities and restore the seafloor to its pre-platform condition, other options have emerged since these leases were signed. Laws and regulations in other jurisdictions (particularly in federal waters) have evolved to allow a number of other uses such as aquaculture, alternative energy production, and artificial reefing. In response, the California Natural Resources Agency initiated an effort to investigate the issues associated with these and other decommissioning alternatives. The papers in this series are the result of the second phase in this process, a broad investigation of the engineering, economic, and environmental costs and benefits of the most feasible and likely options. In addition to the project's final report, the authors produced an interactive mathematical decision model, PLATFORM, that enables users to explore the implications of different decommissioning projects and options, as well as the effects of different approaches to valuing the associated costs and benefits.

  8. Aroma potential of oak battens prepared from decommissioned oak barrels.

    PubMed

    Li, Sijing; Crump, Anna M; Grbin, Paul R; Cozzolino, Daniel; Warren, Peter; Hayasaka, Yoji; Wilkinson, Kerry L

    2015-04-08

    During barrel maturation, volatile compounds are extracted from oak wood and impart aroma and flavor to wine, enhancing its character and complexity. However, barrels contain a finite pool of extractable material, which diminishes with time. As a consequence, most barrels are decommissioned after 5 or 6 years. This study investigated whether or not decommissioned barrels can be "reclaimed" and utilized as a previously untapped source of quality oak for wine maturation. Oak battens were prepared from staves of decommissioned French and American oak barrels, and their composition analyzed before and after toasting. The oak lactone glycoconjugate content of untoasted reclaimed oak was determined by liquid chromatography-tandem mass spectrometry, while the concentrations of cis- and trans-oak lactone, guaiacol, 4-methlyguaiacol, vanillin, eugenol, furfural, and 5-methylfurfural present in toasted reclaimed oak were determined by gas chromatography-mass spectrometry. Aroma potential was then evaluated by comparing the composition of reclaimed oak with that of new oak. Comparable levels of oak lactone glycoconjugates and oak volatiles were observed, demonstrating the aroma potential of reclaimed oak and therefore its suitability as a raw material for alternative oak products, i.e., chips or battens, for the maturation of wine. The temperature profiles achieved during toasting were also measured to evaluate the viability of any yeast or bacteria present in reclaimed oak.

  9. Decontamination and decommissioning surveillance and maintenance report for FY 1991

    SciTech Connect

    Gunter, David B.; Burwinkle, T. W.; Cannon, T. R.; Ford, M. K.; Holder, Jr., L.; Clotfelter, O. K.; Faulkner, R. L.; Smith, D. L.; Wooten, H. O.

    1991-12-01

    The Decontamination and Decommissioning (D D) Program has three distinct phases: (1) surveillance and maintenance (S M); (2) decontamination and removal of hazardous materials and equipment (which DOE Headquarters in Washington, D.C., calls Phase I of remediation); and (3) decommissioning and ultimate disposal, regulatory compliance monitoring, and property transfer (which DOE Headquarters calls Phase II of remediation). A large part of D D is devoted to S M at each of the sites. Our S M activities, which are performed on facilities awaiting decommissioning, are designed to minimize potential hazards to human health and the environment by: ensuring adequate containment of residual radioactive and hazardous materials; and, providing physical safety and security controls to minimize potential hazards to on-site personnel and the general public. Typically, we classify maintenance activities as either routine or special (major repairs). Routine maintenance includes such activities as painting, cleaning, vegetation control, minor structural repairs, filter changes, and building system(s) checks. Special maintenance includes Occupational Safety and Health Act facility upgrades, roof repairs, and equipment overhaul. Surveillance activities include inspections, radiological measurements, reporting, records maintenance, and security (as required) for controlling and monitoring access to facilities. This report summarizes out FY 1991 S M activities for the Tennessee plant sites, which include the K-25 Site, the Gas Centrifuge facilities, ORNL, and the Y-12 Plant.

  10. Radioactive waste from decommissioning of fast reactors (through the example of BN-800)

    NASA Astrophysics Data System (ADS)

    Rybin, A. A.; Momot, O. A.

    2017-01-01

    Estimation of volume of radioactive waste from operating and decommissioning of fast reactors is introduced. Preliminary estimation has shown that the volume of RW from decommissioning of BN-800 is amounted to 63,000 cu. m. Comparison of the amount of liquid radioactive waste derived from operation of different reactor types is performed. Approximate costs of all wastes disposal for complete decommissioning of BN-800 reactor are estimated amounting up to approx. 145 million.

  11. The Regulatory Challenges of Decommissioning Nuclear Power Plants in Korea - 13101

    SciTech Connect

    Lee, Jungjoon; Ahn, Sangmyeon; Choi, Kyungwoo; Kim, Juyoul; Kim, Juyub

    2013-07-01

    As of 2012, 23 units of nuclear power plants are in operation, but there is no experience of permanent shutdown and decommissioning of nuclear power plant in Korea. It is realized that, since late 1990's, improvement of the regulatory framework for decommissioning has been emphasized constantly from the point of view of International Atomic Energy Agency (IAEA)'s safety standards. And it is known that now IAEA prepare the safety requirement on decommissioning of facilities, its title is the Safe Decommissioning of Facilities, General Safety Requirement Part 6. According to the result of IAEA's Integrated Regulatory Review Service (IRRS) mission to Korea in 2011, it was recommended that the regulatory framework for decommissioning should require decommissioning plans for nuclear installations to be constructed and operated and these plans should be updated periodically. In addition, after the Fukushima nuclear disaster in Japan in March of 2011, preparedness for early decommissioning caused by an unexpected severe accident became also important issues and concerns. In this respect, it is acknowledged that the regulatory framework for decommissioning of nuclear facilities in Korea need to be improved. First of all, we identify the current status and relevant issues of regulatory framework for decommissioning of nuclear power plants compared to the IAEA's safety standards in order to achieve our goal. And then the plan is to be established for improvement of regulatory framework for decommissioning of nuclear power plants in Korea. After dealing with it, it is expected that the revised regulatory framework for decommissioning could enhance the safety regime on the decommissioning of nuclear power plants in Korea in light of international standards. (authors)

  12. The regulatory framework for safe decommissioning of nuclear power plants in Korea

    SciTech Connect

    Sangmyeon Ahn; Jungjoon Lee; Chanwoo Jeong; Kyungwoo Choi

    2013-07-01

    We are having 23 units of nuclear power plants in operation and 5 units of nuclear power plants under construction in Korea as of September 2012. However, we don't have any experience on shutdown permanently and decommissioning of nuclear power plants. There are only two research reactors being decommissioned since 1997. It is realized that improvement of the regulatory framework for decommissioning of nuclear facilities has been emphasized constantly from the point of view of IAEA's safety standards. It is also known that IAEA will prepare the safety requirement on decommissioning of facilities; its title is the Safe Decommissioning of Facilities, General Safety Requirement Part 6. According to the result of IAEA's Integrated Regulatory Review Service (IRRS) mission to Korea in 2011, it was recommended that the regulatory framework should require decommissioning plans for nuclear installations to be constructed and operated and these plans should be updated periodically. In addition, after the Fukushima nuclear disaster in Japan in March of 2011, preparedness for early decommissioning caused by an unexpected severe accident became important issues and concerns. In this respect, it is acknowledged that the regulatory framework for decommissioning of nuclear facilities in Korea need to be improved. First of all, we focus on identifying the current status and relevant issues of regulatory framework for decommissioning of nuclear power plants compared to the IAEA's safety standards in order to achieve our goal. And then the plan is established for improvement of regulatory framework for decommissioning of nuclear power plants in Korea. It is expected that if the things will go forward as planned, the revised regulatory framework for decommissioning could enhance the safety regime on the decommissioning of nuclear power plants in Korea in light of international standards. (authors)

  13. Technology, safety and costs of decommissioning a reference boiling water reactor power station. Appendices. Volume 2

    SciTech Connect

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Appendices are presented concerning the evaluations of decommissioning financing alternatives; reference site description; reference BWR facility description; radiation dose rate and concrete surface contamination data; radionuclide inventories; public radiation dose models and calculated maximum annual doses; decommissioning methods; generic decommissioning information; immediate dismantlement details; passive safe storage, continuing care, and deferred dismantlement details; entombment details; demolition and site restoration details; cost estimating bases; public radiological safety assessment details; and details of alternate study bases.

  14. A Plutonium Finishing Plant Model for the Cercla Removal Action and Decommissioning Construction Final Report

    SciTech Connect

    Hopkins, A.

    2008-07-01

    The joint policy between the U.S. Environmental Protection Agency (EPA) and the U.S. Department of Energy (DOE) for decommissioning buildings at DOE facilities documents an agreement between the agencies to perform decommissioning activities including demolition under the Comprehensive Environmental Response Compensation and Liability Act (CERCLA). The use of removal actions for decommissioning integrates EPA oversight authority, DOE lead agency responsibility, and state authority for decommissioning activities. Once removal actions have been performed under CERCLA, a construction completion report is required to document the completion of the required action. Additionally, a decommissioning report is required under DOE guidance. No direct guidance was found for documenting completion of decommissioning activities and preparing a final report that satisfies the CERCLA requirements and the DOE requirements for decommissioning. Additional guidance was needed for the documentation of construction completion under CERCLA for D and D projects undertaken under the joint policy that addresses the requirements of both agencies. A model for the construction completion report was developed to document construction completion for CERCLA D and D activities performed under the joint EPA/DOE policy at the Plutonium Finishing Plant (PFP). The model documentation report developed at PFP integrates the DOE requirements for establishing decommissioning end-points, documenting end-point completion and preparing a final decommissioning report with the CERCLA requirements to document completion of the action identified in the Action Memorandum (AM). The model includes the required information on health and safety, data management, cost and schedule and end-points completion. (authors)

  15. Evaluation of nuclear facility decommissioning projects: summary report. Plum Brook Reactor Facility

    SciTech Connect

    Doerge, D.H.; Miller, R.L.

    1984-02-01

    This document summarizes information concerning the decommissioning of the Plum Brook Reactor Facility, which was placed in a Nuclear Regulatory Commission (NRC) approved safe storage configuration. The data were placed in a computerized information retrieval/manipulation system which permits future utilization of this information in decommissioning of similar facilities. The information is presented both in computer output form and a manually assembled summarization. Complete cost data were not readily available and decommissioning activities did not in all cases conform with current criteria for the SAFSTOR decommissioning mode, therefore no cost comparisons were made.

  16. DECOMMISSIONING THE PHYSICS LABORATORY, BUILDING 777-10A, AT THE SAVANNAH RIVER SITE (SRS)

    SciTech Connect

    Musall, J; Cathy Sizemore, C

    2007-01-17

    SRS recently completed a four-year mission to decommission {approx}250 excess facilities. As part of that effort, SRS decommissioned a 48,000 ft{sup 2} laboratory that housed four low-power test reactors, formerly used by SRS to determine reactor physics. This paper describes and reviews the decommissioning, with a focus on component segmentation and handling (i.e. hazardous material removal, demolition, and waste handling). The paper is intended to be a resource for engineers, planners, and project managers who face similar decommissioning challenges.

  17. Technology, safety and costs of decommissioning a reference pressurized water reactor power station. Classification of decommissioning wastes. Addendum 3

    SciTech Connect

    Murphy, E.S.

    1984-09-01

    The radioactive wastes expected to result from decommissioning of the reference pressurized water reactor power station are reviewed and classified in accordance with 10 CFR 61. The 17,885 cubic meters of waste from DECON are classified as follows: Class A, 98.0%; Class B, 1.2%; Class C, 0.1%. About 0.7% (133 cubic meters) of the waste would be generally unacceptable for disposal using near-surface disposal methods.

  18. Technology, safety and costs of decommissioning a reference boiling water reactor power station. Classification of decommissioning wastes. Addendum 2

    SciTech Connect

    Murphy, E.S.

    1984-09-01

    The radioactive wastes expected to result from decommissioning of the reference boiling water reactor power station are reviewed and classified in accordance with 10 CFR 61. The 18,949 cubic meters of waste from DECON are classified as follows: Class A, 97.5%; Class B, 2.0%; Class C, 0.3%. About 0.2% (47 cubic meters) of the waste would be generally unacceptable for disposal using near-surface disposal methods.

  19. An outbreak of Vicia villosa (hairy vetch) poisoning in grazing Aberdeen Angus bulls in Argentina.

    PubMed

    Odriozola, E; Paloma, E; Lopez, T; Campero, C

    1991-06-01

    Vicia villosa (hairy vetch) is used as a forage source in some cattle-producing areas in Argentina. The plant had no previous reports of toxicity in this country. A herd of 33 Aberdeen Angus bulls grazed during 20 days in October on a pasture composed mainly of hairy vetch. Eight animals developed conjunctivitis, rinitis, dermatitis, loss of hair and fever. All of them died within 15 d after the development of signs with a marked loss of body condition. No more animals became sick 5 d after the removal of the herd from the pasture. Serum parameters tested (calcium, phosphorus, magnesium, GOT, alfa-GT and bilirubin) enlarged liver and spleen, generalized hemorrhage in the abomasum, dilated kidneys and multiple pale areas on the heart. Severe necrotizing granulomatous myocarditis, interstitial nephritis, and necrotizing cholangitis were the most striking microscopic changes. Close observation of animals feeding on pastures in which V villosa is dominant is the only prevention.

  20. a Test to Prove Cloud Whitening THEORY!

    NASA Astrophysics Data System (ADS)

    Buttram, J. W.

    2011-12-01

    Climate science researchers believe our planet can possibly tolerate twice the present carbon dioxide levels with no upwards temperature change, IF we could increase the amount of energy reflected back out into space by about 2.0%. (c)Cloudtec basically alters a blend of seawater and applies heat derived from magma to it at a temperature exceeding 2,000 degrees F. The interaction of seawater and magma displaces the oxygen, causing the volume of water to vaporize and expand over 4,000 times - transforming billions of tons of seawater into thousands of cubic miles of white, maritime, stratocumulus clouds to reflect the incident Sun's rays back out into space. A 6 month test to prove Cloud Whitening Theory will cost 6 million dollars. (No profit added.) This study will enable everyone on the planet with a computer the transparency to use satellite imagery and check out for themselves - if and when Cloud Whitening is occurring. If Cloud Whitening Theory is validated, (c)Cloudtec's innovation can strategically create the clouds we need to reflect the Sun's rays back out into space and help neutralize the projected 3.6 degrees F rise in temperature. Based on reasonable calculations of anthropogenic global warming: this one move alone would be comparable to slashing global carbon dioxide emissions by over 60% over the next 40 years.

  1. Proving Program Termination With Matrix Weighted Digraphs

    NASA Technical Reports Server (NTRS)

    Dutle, Aaron

    2015-01-01

    Program termination analysis is an important task in logic and computer science. While determining if a program terminates is known to be undecidable in general, there has been a significant amount of attention given to finding sufficient and computationally practical conditions to prove termination. One such method takes a program and builds from it a matrix weighted digraph. These are directed graphs whose edges are labeled by square matrices with entries in {-1,0,1}, equipped with a nonstandard matrix multiplication. Certain properties of this digraph are known to imply the termination of the related program. In particular, termination of the program can be determined from the weights of the circuits in the digraph. In this talk, the motivation for addressing termination and how matrix weighted digraphs arise will be briefly discussed. The remainder of the talk will describe an efficient method for bounding the weights of a finite set of the circuits in a matrix weighted digraph, which allows termination of the related program to be deduced.

  2. The Aberdeen Indian Health Service infant mortality study: design, methodology, and implementation.

    PubMed

    Randall, L L; Krogh, C; Welty, T K; Willinger, M; Iyasu, S

    2001-01-01

    Of all Indian Health Service areas, the Aberdeen Area has consistently had the highest infant mortality rate. Among some tribes in this area the rate has exceeded 30/ 1000 live birth and half the infant deaths have been attributed to Sudden Infant Death Syndrome,a rate four to five times higher than the national average. The Indian Health Service, Centers for Disease Control and Prevention, National Institute of Child Health and Human Development, and the Aberdeen Area Tribal Chairmen's Health Board collaborated to investigate these high rates with the goals of refining the ascertainment of the causes of death, improving cause-specific infant mortality rates and identifying factors contributing to the high rates. Ten of the 19 tribes or tribal communities, representing 66%of the area population, participated in a 4-year prospective case-control study of infants who died after discharge from the hospital. Infant care practices and socio-demographic, economic, medical, health care, and environmental factors were examined. The study included parental interviews, death scene investigations, autopsies, neuropathology studies, medical chart abstractions, blood cotinine assays, and a surveillance system for infant deaths. Controls were the previous and subsequent infants born on the case mother's reservation. From December 1,1992 until November 30,1996,72 infant deaths were investigated. This report describes the study methods and the model employed for involving the community and multiple agencies to study the problem of infant mortality among Northern Plains Indians. Data gathered during the investigations are being analyzed and will be published at a later date.

  3. Technology, safety, and costs of decommissioning reference nuclear research and test reactors: sensitivity of decommissioning radiation exposure and costs to selected parameters

    SciTech Connect

    Konzek, G.J.

    1983-07-01

    Additional analyses of decommissioning at the reference research and test (R and T) reactors and analyses of five recent reactor decommissionings are made that examine some parameters not covered in the initial study report (NUREG/CR-1756). The parameters examined for decommissioning are: (1) the effect on costs and radiation exposure of plant size and/or type; (2) the effects on costs of increasing disposal charges and of unavailability of waste disposal capacity at licensed waste disposal facilities; and (3) the costs of and the available alternatives for the disposal of nuclear R and T reactor fuel assemblies.

  4. A Strategy for Skills to meet the demands of Nuclear Decommissioning and Clean-up in the UK

    SciTech Connect

    Brownridge, M.; Ensor, B.

    2008-07-01

    The NDA remit as set out within the Energy Act includes - 'to ensure the availability of skills required to deliver the overall decommissioning and nuclear clean-up mission'. The NDA approach to meeting their statutory obligation is by: - finding the best ways of re-training, re-skilling or re-deploying people in a way that encourages a more flexible workforce; - identifying and communicating the skills and workforce requirements to deliver the mission; and - developing the infrastructure and capability initiatives in line with long term needs, for example, a National Skills Academy for Nuclear, Nuclear Institute, National Graduate Scheme, and - developing locally specific provision. Firstly, NDA has set the requirement for nuclear sites to write down within the Life Time Plans (LTP), at a high level, their Site Skills Strategies; furthermore, a National Skills Working Group has been established to develop tactical cross sector solutions to support the NDA's Skills Strategy. In support of the short, medium and long term needs to meet demands of the NDA sites and the nuclear decommissioning sector, as well as being aware of the broader nuclear sector, investments have been made in infrastructure and skills programmes such as: - A National Skills Academy for Nuclear - including UK wide representation of the whole nuclear sector; - A Nuclear Institute in partnership with the University of Manchester focussing on world class research and skills in Radiation Sciences and Decommissioning Engineering; - Post Graduate sponsorship for decommissioning related projects; - A National Graduate Scheme partnership with nuclear related employers; - Vocational qualifications and Apprenticeship Schemes - Engaging 14-19 year old students to encourage the take up of Science related subjects; and - A sector wide 'Skills Passport'. In conclusion: The skills challenge has many dimensions but requires addressing due to the clear link to improved business performance and the availability

  5. Heavy Water Components Test Reactor Decommissioning - Major Component Removal

    SciTech Connect

    Austin, W.; Brinkley, D.

    2010-05-05

    The Heavy Water Components Test Reactor (HWCTR) facility (Figure 1) was built in 1961, operated from 1962 to 1964, and is located in the northwest quadrant of the Savannah River Site (SRS) approximately three miles from the site boundary. The HWCTR facility is on high, well-drained ground, about 30 meters above the water table. The HWCTR was a pressurized heavy water test reactor used to develop candidate fuel designs for heavy water power reactors. It was not a defense-related facility like the materials production reactors at SRS. The reactor was moderated with heavy water and was rated at 50 megawatts thermal power. In December of 1964, operations were terminated and the facility was placed in a standby condition as a result of the decision by the U.S. Atomic Energy Commission to redirect research and development work on heavy water power reactors to reactors cooled with organic materials. For about one year, site personnel maintained the facility in a standby status, and then retired the reactor in place. In 1965, fuel assemblies were removed, systems that contained heavy water were drained, fluid piping systems were drained, deenergized and disconnected and the spent fuel basin was drained and dried. The doors of the reactor facility were shut and it wasn't until 10 years later that decommissioning plans were considered and ultimately postponed due to budget constraints. In the early 1990s, DOE began planning to decommission HWCTR again. Yet, in the face of new budget constraints, DOE deferred dismantlement and placed HWCTR in an extended surveillance and maintenance mode. The doors of the reactor facility were welded shut to protect workers and discourage intruders. The $1.6 billion allocation from the American Recovery and Reinvestment Act to SRS for site clean up at SRS has opened the doors to the HWCTR again - this time for final decommissioning. During the lifetime of HWCTR, 36 different fuel assemblies were tested in the facility. Ten of these

  6. 76 FR 3540 - Proposed Generic Communications Reporting for Decommissioning Funding Status Reports

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-01-20

    ... Funding Status Reports AGENCY: Nuclear Regulatory Commission. ACTION: Proposed generic communication... information that they should use and present to the NRC in the Decommissioning Funding Status reports to... . The Draft Regulatory Issue Summary 2010-XXX, ``10 CFR 50-75, Reporting for Decommissioning...

  7. 76 FR 65541 - Assuring the Availability of Funds for Decommissioning Nuclear Reactors

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-10-21

    ... COMMISSION Assuring the Availability of Funds for Decommissioning Nuclear Reactors AGENCY: Nuclear Regulatory... Decommissioning Nuclear Reactors.'' This guide provides guidance to applicants and licensees of nuclear power, research, and test reactors concerning methods acceptable to the staff of the U.S. Nuclear...

  8. 26 CFR 1.468A-0 - Nuclear decommissioning costs; table of contents.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 26 Internal Revenue 6 2013-04-01 2013-04-01 false Nuclear decommissioning costs; table of contents...-0 Nuclear decommissioning costs; table of contents. This section lists the paragraphs contained in.... (b) Definitions. (c) Special rules applicable to certain experimental nuclear facilities. §...

  9. 26 CFR 1.468A-0 - Nuclear decommissioning costs; table of contents.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 26 Internal Revenue 6 2014-04-01 2014-04-01 false Nuclear decommissioning costs; table of contents...-0 Nuclear decommissioning costs; table of contents. This section lists the paragraphs contained in.... (b) Definitions. (c) Special rules applicable to certain experimental nuclear facilities. §...

  10. 26 CFR 1.468A-0 - Nuclear decommissioning costs; table of contents.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 26 Internal Revenue 6 2011-04-01 2011-04-01 false Nuclear decommissioning costs; table of contents...-0 Nuclear decommissioning costs; table of contents. This section lists the paragraphs contained in.... (b) Definitions. (c) Special rules applicable to certain experimental nuclear facilities. §...

  11. 26 CFR 1.468A-0 - Nuclear decommissioning costs; table of contents.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 26 Internal Revenue 6 2012-04-01 2012-04-01 false Nuclear decommissioning costs; table of contents...-0 Nuclear decommissioning costs; table of contents. This section lists the paragraphs contained in.... (b) Definitions. (c) Special rules applicable to certain experimental nuclear facilities. §...

  12. 30 CFR 585.907 - How will BOEM process my decommissioning application?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... decommissioning application with the decommissioning general concept in your approved SAP, COP, or GAP to determine what technical and environmental reviews are needed. (b) You will likely have to revise your SAP... change in the impacts previously identified and evaluated in your SAP, COP, or GAP; (2) Require...

  13. 30 CFR 285.907 - How will MMS process my decommissioning application?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... compare your decommissioning application with the decommissioning general concept in your approved SAP... to revise your SAP, COP, or GAP, and MMS will begin the appropriate NEPA analysis and other... a significant change in the impacts previously identified and evaluated in your SAP, COP, or GAP;...

  14. 30 CFR 585.907 - How will BOEM process my decommissioning application?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... decommissioning application with the decommissioning general concept in your approved SAP, COP, or GAP to determine what technical and environmental reviews are needed. (b) You will likely have to revise your SAP... change in the impacts previously identified and evaluated in your SAP, COP, or GAP; (2) Require...

  15. 30 CFR 585.907 - How will BOEM process my decommissioning application?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... Environmental and Safety Management, Inspections, and Facility Assessments for Activities Conducted Under SAPs... your decommissioning application with the decommissioning general concept in your approved SAP, COP, or... revise your SAP, COP, or GAP, and BOEM will begin the appropriate NEPA analysis and other...

  16. Identification and evaluation of facilitation techniques for decommissioning light water power reactors

    SciTech Connect

    LaGuardia, T.S.; Risley, J.F.

    1986-06-01

    This report describes a study sponsored by the US Nuclear Regulatory Commission to identify practical techniques to facilitate the decommissioning of nuclear power generating facilities. The objective of these ''facilitation techniques'' is to reduce the radioactive exposures and/or volumes of waste generated during the decommissioning process. The report presents the possible facilitation techniques identified during the study and discusses the corresponding facilitation of the decommissioning process. Techniques are categorized by their applicability of being implemented during the three stages of power reactor life: design/construction, operation, or decommissioning. Detailed cost-benefit analyses were performed for each technique to determine the anticipated exposure and/or radioactive waste reduction; the estimated costs for implementing each technique were then calculated. Finally, these techniques were ranked by their effectiveness in facilitating the decommissioning process. This study is a part of the Nuclear Regulatory Commission's evaluation of decommissioning policy and its modification of regulations pertaining to the decommissioning process. The findings can be used by the utilities in the planning and establishment of activities to ensure that all objectives of decommissioning will be achieved.

  17. 10 CFR 72.30 - Financial assurance and recordkeeping for decommissioning.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... the decontamination and decommissioning of the ISFSI or MRS at the end of its useful life will provide... design features of the ISFSI or MRS that facilitate its decontamination and decommissioning at the end of... plan containing information on how reasonable assurance will be provided that funds will be...

  18. 10 CFR 50.75 - Reporting and recordkeeping for decommissioning planning.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... funds accumulated to the end of the calendar year preceding the date of the report; a schedule of the... of decommissioning funds accumulated to the end of the calendar year preceding the date of the report... provide reasonable assurance that funds will be available for the decommissioning process. For...

  19. 30 CFR 550.255 - What decommissioning information must accompany the DPP or DOCD?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 30 Mineral Resources 2 2014-07-01 2014-07-01 false What decommissioning information must accompany the DPP or DOCD? 550.255 Section 550.255 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT... brief description of how you intend to decommission your wells, platforms, pipelines, and...

  20. 30 CFR 550.255 - What decommissioning information must accompany the DPP or DOCD?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 2 2012-07-01 2012-07-01 false What decommissioning information must accompany the DPP or DOCD? 550.255 Section 550.255 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT... brief description of how you intend to decommission your wells, platforms, pipelines, and...

  1. 30 CFR 550.255 - What decommissioning information must accompany the DPP or DOCD?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 2 2013-07-01 2013-07-01 false What decommissioning information must accompany the DPP or DOCD? 550.255 Section 550.255 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT... brief description of how you intend to decommission your wells, platforms, pipelines, and...

  2. Superfund Record of Decision (EPA Region 4): Aberdeen Pesticide/Fairway Six, Inc. (First Remedial Action), June 1989

    SciTech Connect

    Not Available

    1989-06-30

    The Aberdeen Pesticide Dumps/Fairway Six site is a former disposal area in Moore County, North Carolina, approximately 1.6 miles west-northwest of Aberdeen. In August 1984, the State was alerted that pesticides had been disposed of at and around the site for a number of years. A State inspection revealed that soil and debris were contaminated with pesticides. In June 1985, EPA initiated an emergency response action to excavate and remove onsite contaminated surface soil and two buried trenches. The soil and debris were disposed of offsite. The predominant contaminants of concern affecting the soil and debris are chlorinated organo-pesticides. The selected remedial action for this site includes excavating and homogenizing stockpiled pesticide-contaminated wastes; treating homogenized wastes in an onsite, mobile thermal treatment facility and reinjecting process waste water or scrubber blowdown into the thermal treatment facility.

  3. SAVANNAH RIVER SITE R REACTOR DISASSEMBLY BASIN IN SITU DECOMMISSIONING

    SciTech Connect

    Langton, C.; Blankenship, J.; Griffin, W.; Serrato, M.

    2009-12-03

    The US DOE concept for facility in-situ decommissioning (ISD) is to physically stabilize and isolate in tact, structurally sound facilities that are no longer needed for their original purpose of, i.e., generating (reactor facilities), processing(isotope separation facilities) or storing radioactive materials. The 105-R Disassembly Basin is the first SRS reactor facility to undergo the in-situ decommissioning (ISD) process. This ISD process complies with the105-R Disassembly Basin project strategy as outlined in the Engineering Evaluation/Cost Analysis for the Grouting of the R-Reactor Disassembly Basin at the Savannah River Site and includes: (1) Managing residual water by solidification in-place or evaporation at another facility; (2) Filling the below grade portion of the basin with cementitious materials to physically stabilize the basin and prevent collapse of the final cap - Sludge and debris in the bottom few feet of the basin will be encapsulated between the basin floor and overlying fill material to isolate if from the environment; (3) Demolishing the above grade portion of the structure and relocating the resulting debris to another location or disposing of the debris in-place; and (4) Capping the basin area with a concrete slab which is part of an engineered cap to prevent inadvertent intrusion. The estimated total grout volume to fill the 105-R Reactor Disassembly Basin is 24,424 cubic meters or 31,945 cubic yards. Portland cement-based structural fill materials were design and tested for the reactor ISD project and a placement strategy for stabilizing the basin was developed. Based on structural engineering analyses and work flow considerations, the recommended maximum lift height is 5 feet with 24 hours between lifts. Pertinent data and information related to the SRS 105-R-Reactor Disassembly Basin in-situ decommissioning include: regulatory documentation, residual water management, area preparation activities, technology needs, fill material designs

  4. HLRW management during MR reactor decommissioning in NRC 'Kurchatov Institute'

    SciTech Connect

    Chesnokov, Alexander; Ivanov, Oleg; Kolyadin, Vyacheslav; Lemus, Alexey; Pavlenko, Vitaly; Semenov, Sergey; Stepanov, Vyacheslav; Smirnov, Sergey; Potapov, Victor; Fadin, Sergey; Volkov, Victor; Shisha, Anatoly

    2013-07-01

    A program of decommissioning of MR research reactor in the Kurchatov institute started in 2008. The decommissioning work presumed a preliminary stage, which included: removal of spent fuel from near reactor storage; removal of spent fuel assemble of metal liquid loop channel from a core; identification, sorting and disposal of radioactive objects from gateway of the reactor; identification, sorting and disposal of radioactive objects from cells of HLRW storage of the Kurchatov institute for radwaste creating form the decommissioning of MR. All these works were performed by a remote controlled means with use of a remote identification methods of high radioactive objects. A distribution of activity along high radiated objects was measured by a collimated radiometer installed on the robot Brokk-90, a gamma image of the object was registered by gamma-visor. Spectrum of gamma radiation was measured by a gamma locator and semiconductor detector system. For identification of a presence of uranium isotopes in the HLRW a technique, based on the registration of characteristic radiation of U, was developed. For fragmentation of high radiated objects was used a cold cutting technique and dust suppression system was applied for reduction of volume activity of aerosols in air. The management of HLRW was performed by remote controlled robots Brokk-180 and Brokk-330. They executed sorting, cutting and parking of high radiated part of contaminated equipment. The use of these techniques allowed to reduce individual and collective doses of personal performed the decommissioning. The average individual dose of the personnel was 1,9 mSv/year in 2011, and the collective dose is estimated by 0,0605 man x Sv/year. Use of the remote control machines enables reducing the number of working personal (20 men) and doses. X-ray spectrometric methods enable determination of a presence of the U in high radiated objects and special cans and separation of them for further spent fuel inspection. The

  5. Waste management for Shippingport Station Decommissioning Project: Extended summary

    SciTech Connect

    Mullee, G.R.; Schulmeister, A.R.

    1987-01-01

    The Shippingport Station (SSDP) is demonstrating that the techniques and methodologies of waste management, which are currently employed by the nuclear industry, provide adequate management and control of waste activities for the decommissioning of a large scale nuclear plant. The SSDP has some unique aspects in that as part of the objective to promote technology transfer, multiple subcontractors are being utilized in the project. The interfaces resulting from multiple subcontractors require additional controls. Effective control has been accomplished by the use of a process control and inventory system, coupled with personnel training in waste management activities. This report summarizes the waste management plan and provides a status of waste management activities for SSDP.

  6. Remote machine engineering applications for nuclear facilities decommissioning

    SciTech Connect

    Toto, G.; Wyle, H.R.

    1983-01-01

    Decontamination and decommissioning of a nuclear facility require the application of techniques that protect the worker and the enviroment from radiological contamination and radiation. Remotely operated portable robotic arms, machines, and devices can be applied. The use of advanced systems should enhance the productivity, safety, and cost facets of the efforts; remote automatic tooling and systems may be used on any job where job hazard and other factors justify application. Many problems based on costs, enviromental impact, health, waste generation, and political issues may be mitigated by use of remotely operated machines. The work that man can not do or should not do will have to be done by machines.

  7. ANSYS analyses on the Shippingport Station Decommissioning Project

    SciTech Connect

    DeSantis, P.V.; McNamee, H.G.

    1987-01-01

    The nuclear reactor vessel from the Shippingport Station, located in Shippingport, Pennsylvania, will be removed as part of the overall Decommissioning Project. The reactor vessel along with a specially designed lifting beam and skirt were modelled to examine the stresses and behavior of the combined structure. Both the PC/Linear Version of ANSYS and the Cray Version were used in the two phases of the analysis. This paper describes the modelling and analytical techniques used to evaluate the design of this one-of-a-kind structure. The combination of the two versions of ANSYS provided the design team with excellent results in a timely and cost effective manner.

  8. Shutdown plus 3 - a look at Yankee decommissioning experience

    SciTech Connect

    Szymczak, W.J.

    1995-12-31

    In three years, the Yankee Nuclear Power Station has not only made the transition from a facility with a full power operating license to a shut down facility but to a facility with a mature and experienced organization poised to effectively and efficiently decommission the remainder of the plant. Opportunities were acted upon to reduce the cost of running and dismantling a shut-down facility. This paper describes some of those opportunities and Yankee`s future strategy for dismantling in an environment with limited waste disposal availability.

  9. 30 CFR 585.902 - What are the general requirements for decommissioning for facilities authorized under my SAP, COP...

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... decommissioning for facilities authorized under my SAP, COP, or GAP? 585.902 Section 585.902 Mineral Resources... authorized under my SAP, COP, or GAP? (a) Except as otherwise authorized by BOEM under § 585.909, within 2... decommissioning the facilities under your SAP, COP, or GAP, you must submit a decommissioning application...

  10. 30 CFR 585.902 - What are the general requirements for decommissioning for facilities authorized under my SAP, COP...

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... decommissioning for facilities authorized under my SAP, COP, or GAP? 585.902 Section 585.902 Mineral Resources... authorized under my SAP, COP, or GAP? (a) Except as otherwise authorized by BOEM under § 585.909, within 2... decommissioning the facilities under your SAP, COP, or GAP, you must submit a decommissioning application...

  11. Resource book: Decommissioning of contaminated facilities at Hanford

    SciTech Connect

    Not Available

    1991-09-01

    In 1942 Hanford was commissioned as a site for the production of weapons-grade plutonium. The years since have seen the construction and operation of several generations of plutonium-producing reactors, plants for the chemical processing of irradiated fuel elements, plutonium and uranium processing and fabrication plants, and other facilities. There has also been a diversification of the Hanford site with the building of new laboratories, a fission product encapsulation plant, improved high-level waste management facilities, the Fast Flux test facility, commercial power reactors and commercial solid waste disposal facilities. Obsolescence and changing requirements will result in the deactivation or retirement of buildings, waste storage tanks, waste burial grounds and liquid waste disposal sites which have become contaminated with varying levels of radionuclides. This manual was established as a written repository of information pertinent to decommissioning planning and operations at Hanford. The Resource Book contains, in several volumes, descriptive information of the Hanford Site and general discussions of several classes of contaminated facilities found at Hanford. Supplementing these discussions are appendices containing data sheets on individual contaminated facilities and sites at Hanford. Twelve appendices are provided, corresponding to the twelve classes into which the contaminated facilities at Hanford have been organized. Within each appendix are individual data sheets containing administrative, geographical, physical, radiological, functional and decommissioning information on each facility within the class. 68 refs., 54 figs., 18 tabs.

  12. Characterisation of radioactive waste products associated with plant decommissioning.

    PubMed

    Sejvar, J; Fero, A H; Gil, C; Hagler, R J; Santiago, J L; Holgado, A; Swenson, R

    2005-01-01

    The inventory of radioactivity that must be considered in the decommissioning of a typical 1000 MWe Spanish pressurised water reactor (PWR) was investigated as part of a generic plant decommissioning study. Analyses based on DORT models (in both R-Z and R-theta geometries) were used with representative plant operating history and core power distribution data in defining the expected neutron environment in regions near the reactor core. The activation analyses were performed by multiplying the DORT scalar fluxes by energy-dependent reaction cross sections (based on ENDF/B-VI data) to generate reaction rates on a per atom basis. The results from the ORIGEN2 computer code were also used for determining the activities associated with certain nuclides where multi-group cross section data were not available. In addition to the bulk material activation of equipment and structures near the reactor, the activated corrosion-product (or 'crud') deposits on system and equipment surfaces were considered. The projected activities associated with these sources were primarily based on plant data and experience from operating PWR plants.

  13. Resource book: Decommissioning of contaminated facilities at Hanford

    SciTech Connect

    Not Available

    1991-09-01

    In 1942 Hanford was commissioned as a site for the production of weapons-grade plutonium. The years since have seen the construction and operation of several generations of plutonium-producing reactors, plants for the chemical processing of irradiated fuel elements, plutonium and uranium processing and fabrication plants, and other facilities. There has also been a diversification of the Hanford site with the building of new laboratories, a fission product encapsulation plant, improved high-level waste management facilities, the Fast Flux test facility, commercial power reactors and commercial solid waste disposal facilities. Obsolescence and changing requirements will result in the deactivation or retirement of buildings, waste storage tanks, waste burial grounds and liquid waste disposal sites which have become contaminated with varying levels of radionuclides. This manual was established as a written repository of information pertinent to decommissioning planning and operations at Hanford. The Resource Book contains, in several volumes, descriptive information of the Hanford Site and general discussions of several classes of contaminated facilities found at Hanford. Supplementing these discussions are appendices containing data sheets on individual contaminated facilities and sites at Hanford. Twelve appendices are provided, corresponding to the twelve classes into which the contaminated facilities at Hanford have been organized. Within each appendix are individual data sheets containing administrative, geographical, physical, radiological, functional and decommissioning information on each facility within the class. 49 refs., 44 figs., 14 tabs.

  14. Radiological characterization of a vitrification facility for decommissioning

    SciTech Connect

    Asou, M.

    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)

  15. The AVR (HTGR) decommissioning project with new strategy

    SciTech Connect

    Sterner, Hakan; Rittscher, Dieter

    2007-07-01

    The 15-MWel prototype pilot reactor AVR is a pebble bed HTGR. It was designed in the late 50's and was connected to the grid end of 1967. After 21 y of successful operation the reactor was shut down end of 1988. In 1994 the first decommissioning license was granted and work with defueling, dismantling and preparation of a Safe Enclosure started. The primary system is contaminated with the fission products Sr{sup 90} and Cs{sup 137} and the activation products are Co{sup 60}, C{sup 14} and H{sup 3}. Due to the large amounts of Sr and Cs bound to graphite dust, the dismantling of systems connected to the pressure vessel is very tedious. In 2003 the AVR company was restructured and the strategy of the decommissioning was changed from safe enclosure to green field, i.e. the complete direct dismantling of all facilities and clean up of the site. The highlight during the dismantling is the removal of the reactor vessel (diameter ca. 7.6 m and length ca. 26 m) in one piece. Before handling the reactor vessel it will be filled with low density cellular concrete. Subsequently the reactor building will be cut open and the reactor vessel (total weight ca. 2100 Mg) lifted out and transported to an interim store. (authors)

  16. Nuclear facility decommissioning and site remedial actions: a selected bibliography

    SciTech Connect

    Owen, P.T.; Knox, N.P.; Fielden, J.M.; Johnson, C.A.

    1982-09-01

    This bibliography contains 693 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. Foreign, as well as domestic, literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Uranium Mill Tailings Remedial Action Program, Grand Junction Remedial Action Program, and Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General Studies. The references within each chapter are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for (1) author; (2) corporate affiliation; (3) title; (4) publication description; (5) geographic location; and (6) keywords. An appendix of 202 bibliographic references without abstracts or indexes has been included in this bibliography. This appendix represents literature identified but not abstracted due to time constraints.

  17. DECOMMISSIONING THE BROOKHAVEN NATIONAL LABORATORY BUILDING 830 GAMMA IRRADIATION FACILITY.

    SciTech Connect

    BOWERMAN, B.S.; SULLIVAN, P.T.

    2001-08-13

    The Building 830 Gamma Irradiation Facility (GIF) at Brookhaven National Laboratory (BNL) was decommissioned because its design was not in compliance with current hazardous tank standards and its cobalt-60 sources were approaching the end of their useful life. The facility contained 354 stainless steel encapsulated cobalt-60 sources in a pool, which provided shielding. Total cobalt-60 inventory amounted to 24,000 Curies when the sources were shipped for disposal. The decommissioning project included packaging, transport, and disposal of the sources and dismantling and disposing of all other equipment associated with the facility. Worker exposure was a major concern in planning for the packaging and disposal of the sources. These activities were planned carefully according to ALARA (As Low As Reasonably Achievable) principles. As a result, the actual occupational exposures experienced during the work were within the planned levels. Disposal of the pool water required addressing environmental concerns, since the planned method was to discharge the slightly contaminated water to the BNL sewage treatment plant. After the BNL evaluation procedure for discharge to the sewage treatment plant was revised and reviewed by regulators and BNL's Community Advisory Council, the pool water was discharged to the Building 830 sanitary system. Because the sources were sealed and the pool water contamination levels were low, most of the remaining equipment was not contaminated; therefore disposal was straightforward, as scrap metal and construction debris.

  18. Decommissioning of the high flux beam reactor at Brookhaven Lab

    SciTech Connect

    Hu, J.P.; Reciniello, R.N.; Holden, N.E.

    2011-07-01

    The high-flux beam reactor (HFBR) at the Brookhaven National Laboratory was a heavy water cooled and moderated reactor that achieved criticality on Oct. 31, 1965. It operated at a power level of 40 megawatts. An equipment upgrade in 1982 allowed operations at 60 megawatts. After a 1989 reactor shutdown to reanalyze safety impact of a hypothetical loss of coolant accident, the reactor was restarted in 1991 at 30 megawatts. The HFBR was shut down in December 1996 for routine maintenance and refueling. At that time, a leak of tritiated water was identified by routine sampling of groundwater from wells located adjacent to the reactor's spent fuel pool. The reactor remained shut down for almost three years for safety and environmental reviews. In November 1999 the United States Dept. of Energy decided to permanently shut down the HFBR. The decontamination and decommissioning of the HFBR complex, consisting of multiple structures and systems to operate and maintain the reactor, were complete in 2009 after removing and shipping off all the control rod blades. The emptied and cleaned HFBR dome, which still contains the irradiated reactor vessel, is presently under 24/7 surveillance for safety. Detailed dosimetry performed for the HFBR decommissioning during 1996-2009 is described in the paper. (authors)

  19. Technology, Safety and Costs of Decommissioning Nuclear Reactors At Multiple-Reactor Stations

    SciTech Connect

    Wittenbrock, N. G.

    1982-01-01

    Safety and cost information is developed for the conceptual decommissioning of large (1175-MWe) pressurized water reactors (PWRs) and large (1155-MWe) boiling water reactors {BWRs) at multiple-reactor stations. Three decommissioning alternatives are studied: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). Safety and costs of decommissioning are estimated by determining the impact of probable features of multiple-reactor-station operation that are considered to be unavailable at a single-reactor station, and applying these estimated impacts to the decommissioning costs and radiation doses estimated in previous PWR and BWR decommissioning studies. The multiple-reactor-station features analyzed are: the use of interim onsite nuclear waste storage with later removal to an offsite nuclear waste disposal facility, the use of permanent onsite nuclear waste disposal, the dedication of the site to nuclear power generation, and the provision of centralized services. Five scenarios for decommissioning reactors at a multiple-reactor station are investigated. The number of reactors on a site is assumed to be either four or ten; nuclear waste disposal is varied between immediate offsite disposal, interim onsite storage, and immediate onsite disposal. It is assumed that the decommissioned reactors are not replaced in one scenario but are replaced in the other scenarios. Centralized service facilities are provided in two scenarios but are not provided in the other three. Decommissioning of a PWR or a BWR at a multiple-reactor station probably will be less costly and result in lower radiation doses than decommissioning an identical reactor at a single-reactor station. Regardless of whether the light water reactor being decommissioned is at a single- or multiple-reactor station: • the estimated occupational radiation dose for decommissioning an LWR is lowest for SAFSTOR and highest for DECON • the estimated

  20. Ecological and political issues surrounding decommissioning of offshore oil facilities in the Southern California Bight

    USGS Publications Warehouse

    Schroeder, Donna M.; Love, Milton S.

    2004-01-01

    To aid legislators, resource managers, and the general public, this paper summarizes and clarifies some of the issues and options that the federal government and the state of California face in decommissioning offshore oil and gas production platforms, particularly as these relate to platform ecology. Both local marine ecology and political climate play a role in decommissioning offshore oil production platforms. Compared to the relatively supportive political climate in the Gulf of Mexico for “rigs-to-reefs” programs, conflicting social values among stakeholders in Southern California increases the need for understanding ecological impacts of various decommissioning alternatives (which range from total removal to allowing some or all of platform structure to remain in the ocean). Additional scientific needs in the decommissioning process include further assessment of platform habitat quality, estimation of regional impacts of decommissioning alternatives to marine populations, and determination of biological effects of any residual contaminants. The principal management need is a ranking of environmental priorities (e.g. species-of-interest and marine habitats). Because considerable numbers of economically important species reside near oil platforms, National Oceanic and Atmospheric Administration Fisheries should consider the consequences of decommissioning alternatives in their overall management plans. Management strategies could include designating reefed platforms as marine protected areas. The overarching conclusion from both ecological and political perspectives is that decommissioning decisions should be made on a case-by-case basis.

  1. DASAO: software tool for the management of safeguards, waste and decommissioning

    SciTech Connect

    Noynaert, Luc; Verwaest, Isi; Libon, Henri; Cuchet, Jean-Marie

    2013-07-01

    Decommissioning of nuclear facilities is a complex process involving operations such as detailed surveys, decontamination and dismantling of equipment's, demolition of buildings and management of resulting waste and nuclear materials if any. This process takes place in a well-developed legal framework and is controlled and followed-up by stakeholders like the Safety Authority, the Radwaste management Agency and the Safeguards Organism. In the framework of its nuclear waste and decommissioning program and more specifically the decommissioning of the BR3 reactor, SCK-CEN has developed different software tools to secure the waste and material traceability, to support the sound management of the decommissioning project and to facilitate the control and the follow-up by the stakeholders. In the case of Belgium, it concerns the Federal Agency for Nuclear Control, the National Agency for radioactive waste management and fissile material and EURATOM and IAEA. In 2005, Belgonucleaire decided to shutdown her Dessel MOX fuel fabrication plant and the production stopped in 2006. According to the final decommissioning plan ('PDF') approved by NIRAS, the decommissioning works should start in 2008 at the earliest. In 2006, the management of Belgonucleaire identified the need for an integrated database and decided to entrust SCK-CEN with its development, because SCK-CEN relies on previous experience in comparable applications namely already approved by authorities such as NIRAS, FANC and EURATOM. The main objectives of this integrated software tool are: - simplified and updated safeguards; - waste and material traceability; - computerized documentation; - support to project management; - periodic and final reporting to waste and safety authorities. The software called DASAO (Database for Safeguards, Waste and Decommissioning) was successfully commissioned in 2008 and extensively used from 2009 to the satisfaction of Belgonucleaire and the stakeholders. SCK-CEN is now implementing

  2. Early life predictors of childhood intelligence: evidence from the Aberdeen children of the 1950s study

    PubMed Central

    Lawlor, D.; Batty, G; Morton, S.; Deary, I.; Macintyre, S.; Ronalds, G.; Leon, D.

    2005-01-01

    Objective: To identify the early life predictors of childhood intelligence. Design: Cohort study of 10 424 children who were born in Aberdeen (Scotland) between 1950 and 1956. Results: Social class of father around the time of birth, gravidity, maternal age, maternal physical condition, whether the child was born outside of marriage, prematurity, intrauterine growth, and childhood height were all independently associated with childhood intelligence at ages 7, 9, and 11. The effect of social class at birth was particularly pronounced, with a graded linear association across the distribution even with adjustment for all other covariates (p<0.001 for linear trend). Those from the lowest social class (V) had intelligence scores that were on average 0.9–1.0 of a standard deviation lower than those from the higher groups (I and II) at each of the three ages of intelligence testing. Collectively, the early life predictors that were examined explained 16% of the variation in intelligence at each age. Conclusions: Father's social class around the time of birth was an important predictor of childhood intelligence, even after adjustment for maternal characteristics and perinatal and childhood factors. Studies of the association of childhood intelligence with future adult disease need to ensure that the association is not fully explained by socioeconomic position. PMID:16020642

  3. TWRS privatization: Phase I monitoring well engineering study and decommissioning plan

    SciTech Connect

    Williams, B.A.

    1996-09-11

    This engineering study evaluates all well owners and users, the status or intended use of each well, regulatory programs, and any future well needs or special purpose use for wells within the TWRS Privatization Phase I demonstration area. Based on the evaluation, the study recommends retaining 11 of the 21 total wells within the demonstration area and decommissioning four wells prior to construction activities per the Well Decommissioning Plan (WHC-SD-EN-AP-161, Rev. 0, Appendix I). Six wells were previously decommissioned.

  4. How Does Decommissioning Forest Roads Effect Hydrologic and Geomorphic Risk?

    NASA Astrophysics Data System (ADS)

    Black, T.; Luce, C.; Cissel, R. M.; Nelson, N.; Staab, B.

    2010-12-01

    The US Forest Service is investigating road decommissioning projects to understand how treatments change hydrologic and geomorphic risks. Road treatment effect was measured using a before after control impact design (BACI), using the Geomorphic Road Analysis and Inventory Package (http://www.fs.fed.us/GRAIP). This suite of inventory and analysis tools evaluates: road-stream hydrologic connectivity, fine sediment production and delivery, shallow landslide risk, gully initiation risk, and risks associated with stream crossing failures. The Skokomish River study site is steep and wet and received a high intensity treatment including the removal of stream crossing pipes and fills, all ditch relief pipes and a full hillslope recontouring. Road to stream hydrologic connectivity was reduced by 70%. The treatments reduced fine sediment delivery by 21.8 tons or 81%. The removal of the stream crossing culverts and large associated road fills eliminated the risk of pipe plugging related failures and the eventual erosion of over 4,000 m3 of fill. The slope stability risk was assessed using a modified version of SINMAP (Pack et al, 2005). Risk below drain point locations on the original road was reduced as water was redistributed across the hillslope to waterbars and diffuse drainage. It is unclear; however, if landslide risk was reduced across the entire treated road length because treatments slightly increased risk in some areas where new concentrated drainage features were added above steep slopes. Similarly, values of a gully index ESI (Istanbulluoglu et al, 2003), were reduced at many of the original drainage points, however some new drainage was added. ESI values still exceed a predicted conservative initiation thresholds at some sites, therefore it is uncertain if gully risk will be changed. Mann Creek occupies a moderately steep mid-elevation site in Southern Idaho. The high intensity treatments removed all constructed road drainage features including stream crossing

  5. TA-2 water boiler reactor decommissioning (Phase 1)

    SciTech Connect

    Elder, J.C.; Knoell, C.L.

    1986-12-01

    Removal of external structures and underground piping associated with the gaseous effluent (stack) line from the TA-2 Water Boiler Reactor was performed as Phase I of reactor decommissioning. Six concrete structures were dismantled and 435 ft of contaminated underground piping was removed. Extensive soil contamination by /sup 137/Cs was encountered around structure TA-2-48 and in a suspected leach field near the stream flowing through Los Alamos Canyon. Efforts to remove all contaminated soil were hampered by infiltrating ground water and heavy rains. Methods, cleanup guidelines, and ALARA decisions used to successfully restore the area are described. The cost of the project was approximately $320K; 970 m/sup 3/ of low-level solid radioactive waste resulted from the cleanup operations.

  6. Decontamination and decommissioning experience at the Savannah River Site

    SciTech Connect

    Monson, R.W.

    1994-07-01

    A continuing concern within the DOE complex is how to address the retirement contains special of a facility which nuclear material (SNM). When the life expectancy of a facility has been reached, decisions must be made pertaining to (1) rial from the facility, removing the mate (2) accounting for the material and (3) final disposition of the material. This paper will discuss such a decontamination and decommissioning (D&D) process which we are presently dealing with at the Savannah River Site. The process must follow DOE Order 5633.3A as well as internal Company procedures regarding MC&A. In some D&D cases the material can be exempt from the DOE Order when all of the following criteria are met: (1) the material has been declared waste, (2) the material has been written off the MC&A books, and (3) the material is under the control of a waste management organization.

  7. Overcoming decommissioning challenges through client/laboratory co-operation

    SciTech Connect

    Wharton, Mike; Gray, Lesley

    2007-07-01

    Available in abstract form only. Full text of publication follows: Accelerated decommissioning projects of the type underway at the former gaseous diffusion plant at BNG Capenhurst, UK, involve characterisation and radiochemical fingerprinting of a variety of unusual materials derived from legacy wastes. The project management and technical challenges that can occur during such a program can be successfully surmounted if a close working relationship between the client and the analytical laboratory is achieved. The Capenhurst Integrated Decommissioning Program (IDP) is an example of how such co-operation can reduce costs and time scales by providing the analytical laboratory with key sample and technical information prior to the shipping of the samples to the lab. This ensures that challenges associated with unusual sample matrices can be anticipated and dealt with at an early stage in the project. Gamma spectrometry is the most common analytical technique when analysing samples for radioactive content as it is non-destructive, relatively inexpensive and fast. However, accurate measurement generally requires samples of a known density to be counted in calibrated geometries. This becomes a challenge as many legacy wastes comprise materials of uneven geometry and/or varying density, as has been the case during the Capenhurst IDP. Liaising with the client to ensure a representative sub-sample of the material is taken on-site, and a series of additional checks when analysing the sample ensure that accurate results are obtained even for non-routine materials. Often it is only one or two radionuclides that dominate the radioactive inventory for legacy wastes. (authors)

  8. Overcoming the Obstacle of Poor Knowledge in Proving Geometry Tasks

    ERIC Educational Resources Information Center

    Magajna, Zlatan

    2013-01-01

    Proving in school geometry is not just about validating the truth of a claim. In the school setting, the main function of the proof is to convince someone that a claim is true by providing an explanation. Students consider proving to be difficult; in fact, they find the very concept of proof demanding. Proving a claim in planar geometry involves…

  9. Sensor Network Demonstration for In Situ Decommissioning - 13332

    SciTech Connect

    Lagos, L.; Varona, J.; Awwad, A.; Rivera, J.; McGill, J.

    2013-07-01

    Florida International University's (FIU's) Applied Research Center is currently supporting the Department of Energy's (DOE) Environmental Management Office of D and D and Facility Engineering program. FIU is supporting DOE's initiative to improve safety, reduce technical risks, and limit uncertainty within D and D operations by identifying technologies suitable to meet specific facility D and D requirements, assessing the readiness of those technologies for field deployment, and conducting feasibility studies and large scale demonstrations of promising technologies. During FY11, FIU collaborated with Savannah River National Laboratory in the development of an experimental test site for the demonstration of multiple sensor systems for potential use in the in situ decommissioning process. In situ decommissioning is a process in which the above ground portion of a facility is dismantled and removed, and the underground portion is filled with a cementious material such as grout. In such a scenario, the question remains on how to effectively monitor the structural health of the grout (cracking, flexing, and sinking), as well as track possible migration of contaminants within and out of the grouted monolith. The right types of sensors can aid personnel in better understanding the conditions within the entombed structure. Without sensors embedded in and around the monolith, it will be very difficult to estimate structural integrity and contaminant transport. Yet, to fully utilize the appropriate sensors and the provided data, their performance and reliability must be evaluated outside a laboratory setting. To this end, a large scale experimental setup and demonstration was conducted at FIU. In order to evaluate a large suite of sensor systems, FIU personnel designed and purchased a pre-cast concrete open-top cube, which served as a mock-up of an in situ DOE decommissioned facility. The inside of the cube measures 10 ft x 10 ft x 8 ft. In order to ensure that the

  10. Waste minimization value engineering workshop for the Los Alamos National Laboratory Omega West Reactor Decommissioning Project

    SciTech Connect

    Hartnett, S.; Seguin, N.; Burns, M.

    1995-12-31

    The Los Alamos National Laboratory Pollution Prevention Program Office sponsored a Value Engineering (VE) Workshop to evaluate recycling options and other pollution prevention and waste minimization (PP/WMin) practices to incorporate into the decommissioning of the Omega West Reactor (OWR) at the laboratory. The VE process is an organized, systematic approach for evaluating a process or design to identify cost saving opportunities, or in this application, waste reduction opportunities. This VE Workshop was a facilitated process that included a team of specialists in the areas of decontamination, decommissioning, PP/WMin, cost estimating, construction, waste management, recycling, Department of Energy representatives, and others. The uniqueness of this VE Workshop was that it used an interdisciplinary approach to focus on PP/WMin practices that could be included in the OWR Decommissioning Project Plans and specifications to provide waste reduction. This report discusses the VE workshop objectives, summarizes the OWR decommissioning project, and describes the VE workshop activities, results, and lessons learned.

  11. 75 FR 13568 - MMS Information Collection Activity: 1010-0142, Decommissioning Activities, Extension of a...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-22

    ... Minerals Management Service MMS Information Collection Activity: 1010-0142, Decommissioning Activities, Extension of a Collection; Comment Request AGENCY: Minerals Management Service (MMS), Interior. ACTION... comments to the Department of the Interior; Minerals Management Service; Attention: Cheryl Blundon;...

  12. 76 FR 8785 - ABB Inc.; License Amendment Request for Decommissioning of the ABB Inc., Combustion Engineering...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-02-15

    ...--Resident Farmer Thorium and Radium. August 2010. ML102310548. 5. ABB, Inc. Decommissioning Plan Revision 2.... ABB, Inc. Derivation of the Site Specific Soil DCGLs, Addendum, Soil DCGLs for thorium and...

  13. 78 FR 49553 - Three Mile Island, Unit 2; Post Shutdown Decommissioning Activities Report

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-14

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Three Mile Island, Unit 2; Post Shutdown Decommissioning Activities Report AGENCY: Nuclear...) for Three Mile Island, Unit 2 (TMI-2). The PSDAR provides an overview of GPUN's...

  14. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 2, Indexes

    SciTech Connect

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This is part 2 of a bibliography on nuclear facility decommissioning and site remedial action. This report contains indexes on the following: authors, corporate affiliation, title words, publication description, geographic location, subject category, and key word.

  15. 75 FR 54363 - BOEMRE Information Collection Activity: 1010-0142, Decommissioning Activities, Extension of a...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-09-07

    ... information. SUPPLEMENTARY INFORMATION: Title: 30 CFR 250, subpart Q, Decommissioning Activities. OMB Control... prevent or minimize the likelihood of blowouts, loss of well control, fires, spillages, physical... equipment and subsea protective covering; or other departures. Subtotal 50 responses 150...

  16. 30 CFR 250.1751 - How do I decommission a pipeline in place?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... to be decommissioned; and (4) Length (feet) of segment remaining. (b) Pig the pipeline, unless the Regional Supervisor determines that pigging is not practical; (c) Flush the pipeline; (d) Fill the...

  17. An Analysis of Decommissioning Costs for the AFRRI TRIGA Reactor Facility

    DTIC Science & Technology

    1989-12-01

    Laboratory, as provided in U.S. Nuclear Regulatory Commission publication NUREG /CR-1756. The data in this study were adapted to reflect the decommissioning requirements of the AFRRI TRIGA reactor facility.

  18. Applying and adapting the Swedish regulatory system for decommissioning to nuclear power reactors - The regulator's perspective.

    PubMed

    Amft, Martin; Leisvik, Mathias; Carroll, Simon

    2017-03-16

    Half of the original 13 Swedish nuclear power reactors will be shut down by 2020. The decommissioning of these reactors is a challenge for all parties involved, including the licensees, the waste management system, the financing system, and the Swedish Radiation Safety Authority (SSM). This paper presents an overview of the Swedish regulations for decommissioning of nuclear facilities. It describes some of the experiences that SSM has gained from the application of these regulations. The focus of the present paper is on administrative aspects of decommissioning, such as SSM's guidelines, the definition of fundamental concepts in the regulatory framework, and a proposed revision of the licensing process according to the Environmental Act. These improvements will help to streamline the administration of the commercial nuclear power plant decommissioning projects that are anticipated to commence in Sweden in the near future.

  19. Radiochemistry Lab Decommissioning and Dismantlement. AECL, Chalk River Labs, Ontario, Canada

    SciTech Connect

    Kenny, Stephen

    2008-01-15

    Atomic Energy of Canada (AECL) was originally founded in the mid 1940's to perform research in radiation and nuclear areas under the Canadian Defense Department. In the mid 50's The Canadian government embarked on several research and development programs for the development of the Candu Reactor. AECL was initially built as a temporary site and is now faced with many redundant buildings. Prior to 2004 small amounts of Decommissioning work was in progress. Many reasons for deferring decommissioning activities were used with the predominant ones being: 1. Reduction in radiation doses to workers during the final dismantlement, 2. Development of a long-term solution for the management of radioactive wastes in Canada, 3. Financial constraints presented by the number of facilities shutdown that would require decommissioning funds and the absence of an approved funding strategy. This has led to the development of a comprehensive decommissioning plan that is all inclusive of AECL's current and legacy liabilities. Canada does not have a long-term disposal site; therefore waste minimization becomes the driving factor behind decontamination for decommissioning before and during dismantlement. This decommissioning job was a great learning experience for decommissioning and the associated contractors who worked on this project. Throughout the life of the project there was a constant focus on waste minimization. This focus was constantly in conflict with regulatory compliance primarily with respect to fire regulations and protecting the facility along with adjacent facilities during the decommissioning activities. Discrepancies in historical documents forced the project to treat every space as a contaminated space until proven differently. Decommissioning and dismantlement within an operating site adds to the complexity of the tasks especially when it is being conducted in the heart of the plant. This project was very successful with no lost time accidents in over one hundred

  20. Engineering Evaluation/Cost Analysis for Decommissioning of the Engineering Test Reactor Complex

    SciTech Connect

    A. B. Culp

    2006-10-01

    Preparation of this Engineering Evaluation/Cost Analysis is consistent with the joint U.S. Department of Energy and U.S. Environmental Protection Agency Policy on Decommissioning of Department of Energy Facilities Under the Comprehensive Environmental Response, Compensation, and Liability Act, which establishes the Comprehensive Environmental Response, Compensation, and Liability Act non-time-critical removal action (NTCRA) process as an approach for decommissioning.

  1. Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Main report

    SciTech Connect

    Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

    1982-03-01

    Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). The study results are presented in two volumes. Volume 1 (Main Report) contains the results in summary form.

  2. Molecular Characterization of Salmonella enterica Serovar Aberdeen Negative for H2S Production in China

    PubMed Central

    Yi, Shengjie; Wang, Jian; Yang, Xiaoxia; Yang, Chaojie; Liang, Beibei; Ma, Qiuxia; Li, Hao; Song, Hongbin; Qiu, Shaofu

    2016-01-01

    Salmonella enterica infections continue to be a significant burden on public health worldwide. The ability of S. enterica to produce hydrogen sulfide (H2S) is an important phenotypic characteristic used to screen and identify Salmonella with selective medium; however, H2S-negative Salmonella have recently emerged. In this study, the H2S phenotype of Salmonella isolates was confirmed, and the selected isolates were subjected to antimicrobial susceptibility testing and molecular identification by multilocus sequence typing, pulsed-field gel electrophoresis, and clustered regularly interspaced short palindromic repeat (CRISPR) analysis. The phs genetic operon was also analyzed. A total of 160 S. enterica serovar Aberdeen isolates were detected between 2005 and 2013 in China. Of them, seven non-H2S-producing isolates were detected. Notably, four samples yielded four pairs of isolates with different H2S phenotypes, simultaneously. The data demonstrated that H2S-negative isolates were genetically closely related to H2S-positive isolates. Three new spacers (Abe1, Abe2, and Abe3) were identified in CRISPR locus 1 in four pairs of isolates with different H2S phenotypes from the same samples. Sequence analysis revealed a new nonsense mutation at position 208 in the phsA gene of all non-H2S-producing isolates. Additionally, we describe a new screening procedure to avoid H2S-negative Salmonella, which would normally be overlooked during laboratory and hospital screening. The prevalence of this pathogen may be underestimated; therefore, it is important to focus on improving surveillance of this organism to control its spread. PMID:27552230

  3. Molecular Characterization of Salmonella enterica Serovar Aberdeen Negative for H2S Production in China.

    PubMed

    Wu, Fuli; Xu, Xuebin; Xie, Jing; Yi, Shengjie; Wang, Jian; Yang, Xiaoxia; Yang, Chaojie; Liang, Beibei; Ma, Qiuxia; Li, Hao; Song, Hongbin; Qiu, Shaofu

    2016-01-01

    Salmonella enterica infections continue to be a significant burden on public health worldwide. The ability of S. enterica to produce hydrogen sulfide (H2S) is an important phenotypic characteristic used to screen and identify Salmonella with selective medium; however, H2S-negative Salmonella have recently emerged. In this study, the H2S phenotype of Salmonella isolates was confirmed, and the selected isolates were subjected to antimicrobial susceptibility testing and molecular identification by multilocus sequence typing, pulsed-field gel electrophoresis, and clustered regularly interspaced short palindromic repeat (CRISPR) analysis. The phs genetic operon was also analyzed. A total of 160 S. enterica serovar Aberdeen isolates were detected between 2005 and 2013 in China. Of them, seven non-H2S-producing isolates were detected. Notably, four samples yielded four pairs of isolates with different H2S phenotypes, simultaneously. The data demonstrated that H2S-negative isolates were genetically closely related to H2S-positive isolates. Three new spacers (Abe1, Abe2, and Abe3) were identified in CRISPR locus 1 in four pairs of isolates with different H2S phenotypes from the same samples. Sequence analysis revealed a new nonsense mutation at position 208 in the phsA gene of all non-H2S-producing isolates. Additionally, we describe a new screening procedure to avoid H2S-negative Salmonella, which would normally be overlooked during laboratory and hospital screening. The prevalence of this pathogen may be underestimated; therefore, it is important to focus on improving surveillance of this organism to control its spread.

  4. Deactivation and Decommissioning Planning and Analysis with Geographic Information Systems

    SciTech Connect

    Bollinger, James S.; Koffman, Larry D.; Austin, William E.

    2008-01-15

    From the mid-1950's through the 1980's, the U.S. Department of Energy's Savannah River Site produced nuclear materials for the weapons stockpile, for medical and industrial applications, and for space exploration. Although SRS has a continuing defense-related mission, the overall site mission is now oriented toward environmental restoration and management of legacy chemical and nuclear waste. With the change in mission, SRS no longer has a need for much of the infrastructure developed to support the weapons program. This excess infrastructure, which includes over 1000 facilities, will be decommissioned and demolished over the forthcoming years. Dis-positioning facilities for decommissioning and deactivation requires significant resources to determine hazards, structure type, and a rough-order-of-magnitude estimate for the decommissioning and demolition cost. Geographic information systems (GIS) technology was used to help manage the process of dis-positioning infrastructure and for reporting the future status of impacted facilities. Several thousand facilities of various ages and conditions are present at SRS. Many of these facilities, built to support previous defense-related missions, now represent a potential hazard and cost for maintenance and surveillance. To reduce costs and the hazards associated with this excess infrastructure, SRS has developed an ambitious plan to decommission and demolish unneeded facilities in a systematic fashion. GIS technology was used to assist development of this plan by: providing locational information for remote facilities, identifying the location of known waste units adjacent to buildings slated for demolition, and for providing a powerful visual representation of the impact of the overall plan. Several steps were required for the development of the infrastructure GIS model. The first step involved creating an accurate and current GIS representation of the infrastructure data. This data is maintained in a Computer Aided Design

  5. Application of Robotics in Decommissioning and Decontamination - 12536

    SciTech Connect

    Banford, Anthony; Kuo, Jeffrey A.; Bowen, R.A.; Szilagyi, Andrew; Kirk, Paula

    2012-07-01

    Decommissioning and dismantling of nuclear facilities is a significant challenge worldwide and one which is growing in size as more plants reach the end of their operational lives. The strategy chosen for individual projects varies from the hands-on approach with significant manual intervention using traditional demolition equipment at one extreme to bespoke highly engineered robotic solutions at the other. The degree of manual intervention is limited by the hazards and risks involved, and in some plants are unacceptable. Robotic remote engineering is often viewed as more expensive and less reliable than manual approaches, with significant lead times and capital expenditure. However, advances in robotics and automation in other industries offer potential benefits for future decommissioning activities, with the high probability of reducing worker exposure and other safety risks as well as reducing the schedule and costs required to complete these activities. Some nuclear decommissioning tasks and facility environments are so hazardous that they can only be accomplished by exclusive use of robotic and remote intervention. Less hazardous tasks can be accomplished by manual intervention and the use of PPE. However, PPE greatly decreases worker productivity and still exposes the worker to both risk and dose making remote operation preferable to achieve ALARP. Before remote operations can be widely accepted and deployed, there are some economic and technological challenges that must be addressed. These challenges will require long term investment commitments in order for technology to be: - Specifically developed for nuclear applications; - At a sufficient TRL for practical deployment; - Readily available as a COTS. Tremendous opportunities exist to reduce cost and schedule and improve safety in D and D activities through the use of robotic and/or tele-operated systems. - Increasing the level of remote intervention reduces the risk and dose to an operator. Better

  6. Technology, safety and costs of decommissioning a Reference Boiling Water Reactor Power Station. Main report. Volume 1

    SciTech Connect

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWe.

  7. Waste management strategy for cost effective and environmentally friendly NPP decommissioning

    SciTech Connect

    Per Lidar; Arne Larsson; Niklas Bergh; Gunnar Hedin

    2013-07-01

    Decommissioning of nuclear power plants generates large volumes of radioactive or potentially radioactive waste. The proper management of the dismantling waste plays an important role for the time needed for the dismantling phase and thus is critical to the decommissioning cost. An efficient and thorough process for inventorying, characterization and categorization of the waste provides a sound basis for the planning process. As part of comprehensive decommissioning studies for Nordic NPPs, Westinghouse has developed the decommissioning inventories that have been used for estimations of the duration of specific work packages and the corresponding costs. As part of creating the design basis for a national repository for decommissioning waste, the total production of different categories of waste packages has also been predicted. Studsvik has developed a risk based concept for categorization and handling of the generated waste using six different categories with a span from extremely small risk for radiological contamination to high level waste. The two companies have recently joined their skills in the area of decommissioning on selected market in a consortium named ndcon to further strengthen the proposed process. Depending on the risk for radiological contamination or the radiological properties and other properties of importance for waste management, treatment routes are proposed with well-defined and proven methods for on-site or off-site treatment, activity determination and conditioning. The system is based on a graded approach philosophy aiming for high confidence and sustainability, aiming for re-use and recycling where found applicable. The objective is to establish a process where all dismantled material has a pre-determined treatment route. These routes should through measurements, categorization, treatment, conditioning, intermediate storage and final disposal be designed to provide a steady, un-disturbed flow of material to avoid interruptions. Bottle

  8. Waste Management Strategy for Dismantling Waste to Reduce Costs for Power Plant Decommissioning - 13543

    SciTech Connect

    Larsson, Arne; Lidar, Per; Bergh, Niklas; Hedin, Gunnar

    2013-07-01

    Decommissioning of nuclear power plants generates large volumes of radioactive or potentially radioactive waste. The proper management of the dismantling waste plays an important role for the time needed for the dismantling phase and thus is critical to the decommissioning cost. An efficient and thorough process for inventorying, characterization and categorization of the waste provides a sound basis for the planning process. As part of comprehensive decommissioning studies for Nordic NPPs, Westinghouse has developed the decommissioning inventories that have been used for estimations of the duration of specific work packages and the corresponding costs. As part of creating the design basis for a national repository for decommissioning waste, the total production of different categories of waste packages has also been predicted. Studsvik has developed a risk based concept for categorization and handling of the generated waste using six different categories with a span from extremely small risk for radiological contamination to high level waste. The two companies have recently joined their skills in the area of decommissioning on selected market in a consortium named 'ndcon' to further strengthen the proposed process. Depending on the risk for radiological contamination or the radiological properties and other properties of importance for waste management, treatment routes are proposed with well-defined and proven methods for on-site or off-site treatment, activity determination and conditioning. The system is based on a graded approach philosophy aiming for high confidence and sustainability, aiming for re-use and recycling where found applicable. The objective is to establish a process where all dismantled material has a pre-determined treatment route. These routes should through measurements, categorization, treatment, conditioning, intermediate storage and final disposal be designed to provide a steady, un-disturbed flow of material to avoid interruptions. Bottle

  9. Progress on the decommissioning of Zion nuclear generating station

    SciTech Connect

    Moloney, B. P.; Hess, J.

    2013-07-01

    The decommissioning of the twin 1040 MWe PWRs at Zion, near Chicago USA is a ground breaking programme. The original owner, Exelon Nuclear Corporation, transferred the full responsibility for reactor dismantling and site license termination to a subsidiary of EnergySolutions. The target end state of the Zion site for return to Exelon will be a green field with the exception of the dry fuel storage pad. In return, ZionSolutions has access to the full value of the decommissioning trust fund. There are two potential attractions of this model: lower overall cost and significant schedule acceleration. The Zion programme which commenced in September 2010 is designed to return the cleared site with an Independent Spent Fuel Storage Installation (ISFSI) pad in 2020, 12 years earlier than planned by Exelon. The overall cost, at $500 M per full size power reactor is significantly below the long run trend of $750 M+ per PWR. Implementation of the accelerated programme has been underway for nearly three years and is making good progress. The programme is characterised by numerous projects proceeding in parallel. The critical path is defined by the inspection and removal of fuel from the pond and transfer into dry fuel storage casks on the ISFSI pad and completion of RPV segmentation. Fuel loading is expected to commence in mid- 2013 with completion in late 2014. In parallel, ZionSolutions is proceeding with the segmentation of the Reactor Vessel (RV) and internals in both Units. Removal of large components from Unit 1 is underway. Numerous other projects are underway or have been completed to date. They include access openings into both containments, installation of heavy lift crane capacity, rail upgrades to support waste removal from the site, radiological characterization of facilities and equipment and numerous related tasks. As at February 2013, the programme is just ahead of schedule and within the latest budget. The paper will provide a fuller update. The first two

  10. Cost Savings through Innovation in Decontamination, Decommissioning, and Dismantlement

    SciTech Connect

    Neal A. Yancey

    2003-02-27

    The United States Department of Energy (DOE) continually seeks safer and more cost effective technologies for the decontamination and decommissioning (D&D) of nuclear facilities. The Deactivation and Decommissioning Focus Area (DDFA) of the DOE's Office of Science and Technology (OST) sponsored large-scale demonstration and deployment projects (LSDDPs) to help bring new technologies into the D&D programs. The Idaho National Engineering and Environmental Laboratory (INEEL) LSDDP generated a list of needs defining specific problems where improved technologies could be incorporated into ongoing D&D tasks. The needs fell into 5 major categories--characterization, dismantlement, safety, material dispositioning, and decontamination. Technologies were carefully selected that provide a large benefit for a small investment. The technologies must provide significant improvements in cost, safety, radiation exposure, waste volume reduction, or schedule savings and widely applicable throughout the DOE complex. The LSDDP project provided training for the new technologies and worked with technology suppliers to resolve any questions that arose. Since 1998, 26 technologies have been demonstrated or deployed through the LSDDP for the D&D program at the INEEL. Of the 26 demonstrated and deployed technologies, 14 were in characterization, 3 were in decontamination, 4 were in dismantlement, 3 were in safety, and 2 were in material dispositioning. To promote the use of these technologies at other sites within the DOE complex, the LSDDP team published fact sheets, videos, technology summary reports, articles in INEEL star newspaper, posters, and maintained an internet home page on the project. As a result, additional deployments have taken place at the Hanford, Mound, Fernald, Oak Ridge, Ashtabula, and West Valley. Eight of the 26 technologies evaluated were developed in foreign countries. The technologies demonstrated have been shown to be faster, less expensive, and/or safer. The

  11. Oak Ridge National Laboratory Technology Logic Diagram. Volume 2, Technology Logic Diagram: Part A, Decontamination and Decommissioning

    SciTech Connect

    Not Available

    1993-09-01

    This report documents activities of decontamination and decommissioning at ORNL. Topics discussed include general problems, waste types, containment, robotics automation and decontamination processes.

  12. Marital Status and Reproduction: Associations with Childhood Intelligence and Adult Social Class in the Aberdeen Children of the 1950s Study

    ERIC Educational Resources Information Center

    von Stumm, Sophie; Batty, G. David; Deary, Ian J.

    2011-01-01

    Childhood intelligence (age 11) and occupational social status at midlife (age 46 to 51) was associated with marital status and reproduction in a sample from the Aberdeen Children of the 1950s cohort study (N = 9614). Male and female divorcees had lower childhood intelligence test scores than their married counterparts, but no meaningful…

  13. Intelligence, Social Class of Origin, Childhood Behavior Disturbance and Education as Predictors of Status Attainment in Midlife in Men: The Aberdeen Children of the 1950s Study

    ERIC Educational Resources Information Center

    von Stumm, Sophie; Macintyre, Sally; Batty, David G.; Clark, Heather; Deary, Ian J.

    2010-01-01

    In a birth cohort of 6281 men from Aberdeen, Scotland, social class of origin, childhood intelligence, childhood behavior disturbance and education were examined as predictors of status attainment in midlife (46 to 51 years). Social class of origin, intelligence and behavior disturbance were conceptualized as correlated predictors, whose effects…

  14. The Potential of Live Teacher Supported Distance Learning: A Case-Study of the Use of Audio Conferencing at the University of Aberdeen.

    ERIC Educational Resources Information Center

    Newlands, David; McLean, Alasdair

    1996-01-01

    The experience of teaching a University of Aberdeen distance learning course to students in the Scottish Highlands and Islands using audio conferencing suggests that with new technologies the benefits of distance learning can be preserved while the problems of traditional distance courses can be mitigated. The results of a survey of 45 students…

  15. The Effect of Alternative Work Schedules (AWS) on Performance During Acquisition Based Testing at the U.S. Army Aberdeen Test Center

    DTIC Science & Technology

    2014-09-01

    Pickar Brad Naegle Melissa Steffen Approved for public release; distribution is unlimited THIS PAGE INTENTIONALLY LEFT BLANK i...Thomas Approved by: Charles Pickar Brad Naegle Melissa Steffen , U.S. Army Aberdeen Test Center William R...Melissa Steffen , for taking time out of their daily schedules to provide me with guidance, support and motivation during the execution of this project

  16. The Status of Proving among US Secondary Mathematics Teachers

    ERIC Educational Resources Information Center

    Kotelawala, Usha

    2016-01-01

    This report examines teachers' self-espoused attitudes and beliefs on proving in the secondary mathematics classroom. Conclusions were based on a questionnaire of 78 US mathematics teachers who had completed at least 2 years of teaching mathematics at the secondary level. While these teachers placed importance on proving as a general mathematical…

  17. Cabri as a "Shared Workspace" within the Proving Process

    ERIC Educational Resources Information Center

    Olivero, Federica

    2003-01-01

    This paper will discuss some findings from a study investigating the development of the proving process in a dynamic geometry environment. Through a detailed analysis of students' processes when working with open geometry problems involving conjecturing and proving in Cabri, an analytical and explanatory framework has been developed. This paper…

  18. 20 CFR 219.23 - Evidence to prove death.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 20 Employees' Benefits 1 2013-04-01 2012-04-01 true Evidence to prove death. 219.23 Section 219.23... REQUIRED FOR PAYMENT Evidence of Age and Death § 219.23 Evidence to prove death. (a) Preferred evidence of death. The best evidence of a person's death is— (1) A certified copy of or extract from the...

  19. 20 CFR 219.23 - Evidence to prove death.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 20 Employees' Benefits 1 2011-04-01 2011-04-01 false Evidence to prove death. 219.23 Section 219... EVIDENCE REQUIRED FOR PAYMENT Evidence of Age and Death § 219.23 Evidence to prove death. (a) Preferred evidence of death. The best evidence of a person's death is— (1) A certified copy of or extract from...

  20. 20 CFR 219.23 - Evidence to prove death.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 20 Employees' Benefits 1 2012-04-01 2012-04-01 false Evidence to prove death. 219.23 Section 219... EVIDENCE REQUIRED FOR PAYMENT Evidence of Age and Death § 219.23 Evidence to prove death. (a) Preferred evidence of death. The best evidence of a person's death is— (1) A certified copy of or extract from...

  1. 20 CFR 219.23 - Evidence to prove death.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 20 Employees' Benefits 1 2010-04-01 2010-04-01 false Evidence to prove death. 219.23 Section 219... EVIDENCE REQUIRED FOR PAYMENT Evidence of Age and Death § 219.23 Evidence to prove death. (a) Preferred evidence of death. The best evidence of a person's death is— (1) A certified copy of or extract from...

  2. 20 CFR 219.23 - Evidence to prove death.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 20 Employees' Benefits 1 2014-04-01 2012-04-01 true Evidence to prove death. 219.23 Section 219.23... REQUIRED FOR PAYMENT Evidence of Age and Death § 219.23 Evidence to prove death. (a) Preferred evidence of death. The best evidence of a person's death is— (1) A certified copy of or extract from the...

  3. Generating and Using Examples in the Proving Process

    ERIC Educational Resources Information Center

    Sandefur, J.; Mason, J.; Stylianides, G. J.; Watson, A.

    2013-01-01

    We report on our analysis of data from a dataset of 26 videotapes of university students working in groups of 2 and 3 on different proving problems. Our aim is to understand the role of example generation in the proving process, focusing on deliberate changes in representation and symbol manipulation. We suggest and illustrate four aspects of…

  4. The Earth is Flat, and I Can Prove It!

    ERIC Educational Resources Information Center

    Klinger, Art

    1998-01-01

    Describes an educational program that asks students to attempt to prove that the earth is spherical and that it rotates. Presents tips to pique student interest and charts related to sensing the spin, nonrotation notions, flat earth fallacies, evidence that the earth is spherical and rotates, and the role of watersheds in proving that the earth…

  5. Preservice Mathematics Teachers' Metaphorical Perceptions towards Proof and Proving

    ERIC Educational Resources Information Center

    Ersen, Zeynep Bahar

    2016-01-01

    Since mathematical proof and proving are in the center of mathematics; preservice mathematics teachers' perceptions against these concepts have a great importance. Therefore, the study aimed to determine preservice mathematics teachers' perceptions towards proof and proving through metaphors. The participants consisted of 192 preservice…

  6. 14 CFR 121.163 - Aircraft proving tests.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 14 Aeronautics and Space 3 2011-01-01 2011-01-01 false Aircraft proving tests. 121.163 Section 121... REQUIREMENTS: DOMESTIC, FLAG, AND SUPPLEMENTAL OPERATIONS Aircraft Requirements § 121.163 Aircraft proving...) Alterations to the aircraft or its components that materially affect flight characteristics. (e)...

  7. 14 CFR 121.163 - Aircraft proving tests.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Aircraft proving tests. 121.163 Section 121... REQUIREMENTS: DOMESTIC, FLAG, AND SUPPLEMENTAL OPERATIONS Aircraft Requirements § 121.163 Aircraft proving...) Alterations to the aircraft or its components that materially affect flight characteristics. (e)...

  8. 14 CFR 121.163 - Aircraft proving tests.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 14 Aeronautics and Space 3 2012-01-01 2012-01-01 false Aircraft proving tests. 121.163 Section 121... REQUIREMENTS: DOMESTIC, FLAG, AND SUPPLEMENTAL OPERATIONS Aircraft Requirements § 121.163 Aircraft proving...) Alterations to the aircraft or its components that materially affect flight characteristics. (e)...

  9. 14 CFR 91.1041 - Aircraft proving and validation tests.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 14 Aeronautics and Space 2 2011-01-01 2011-01-01 false Aircraft proving and validation tests. 91... Ownership Operations Program Management § 91.1041 Aircraft proving and validation tests. (a) No program manager may permit the operation of an aircraft, other than a turbojet aircraft, for which two pilots...

  10. 14 CFR 91.1041 - Aircraft proving and validation tests.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 14 Aeronautics and Space 2 2013-01-01 2013-01-01 false Aircraft proving and validation tests. 91... Ownership Operations Program Management § 91.1041 Aircraft proving and validation tests. (a) No program manager may permit the operation of an aircraft, other than a turbojet aircraft, for which two pilots...

  11. 14 CFR 121.163 - Aircraft proving tests.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 14 Aeronautics and Space 3 2013-01-01 2013-01-01 false Aircraft proving tests. 121.163 Section 121... REQUIREMENTS: DOMESTIC, FLAG, AND SUPPLEMENTAL OPERATIONS Aircraft Requirements § 121.163 Aircraft proving...) Alterations to the aircraft or its components that materially affect flight characteristics. (e)...

  12. 14 CFR 121.163 - Aircraft proving tests.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 14 Aeronautics and Space 3 2014-01-01 2014-01-01 false Aircraft proving tests. 121.163 Section 121... REQUIREMENTS: DOMESTIC, FLAG, AND SUPPLEMENTAL OPERATIONS Aircraft Requirements § 121.163 Aircraft proving...) Alterations to the aircraft or its components that materially affect flight characteristics. (e)...

  13. Reasoning-and-Proving in School Mathematics Textbooks

    ERIC Educational Resources Information Center

    Stylianides, Gabriel J.

    2009-01-01

    Despite widespread agreement that the activity of "reasoning-and-proving" should be central to all students' mathematical experiences, many students face serious difficulties with this activity. Mathematics textbooks can play an important role in students' opportunities to engage in reasoning-and-proving: research suggests that many decisions that…

  14. Assessment of strippable coatings for decontamination and decommissioning

    SciTech Connect

    Ebadian, M.A.

    1998-01-01

    Strippable or temporary coatings were developed to assist in the decontamination of the Three Mile Island (TMI-2) reactor. These coatings have become a viable option during the decontamination and decommissioning (D and D) of both US Department of Energy (DOE) and commercial nuclear facilities to remove or fix loose contamination on both vertical and horizontal surfaces. A variety of strippable coatings are available to D and D professionals. However, these products exhibit a wide range of performance criteria and uses. The Hemispheric Center for Environmental Technology (HCET) at Florida International University (FIU) was commissioned to perform a 2-year investigation into strippable coatings. This investigation was divided into four parts: (1) identification of commercially available strippable coating products; (2) survey of D and D professionals to determine current uses of these coatings and performance criteria; (3) design and implementation of a non-radiological testing program to evaluate the physical properties of these coatings; and (4) design and implementation of a radiological testing program to determine decontamination factors and effects of exposure to ionizing radiation. Activities during fiscal year 1997 are described.

  15. Ecological risk assessment of a decommissioned military base

    SciTech Connect

    Starodub, M.E.; Feniak, N.A.; Willes, R.F.; Moore, C.E.; Mucklow, L.; Marshall, L.

    1995-12-31

    The ecological health risks to selected terrestrial animals at a decommissioned military base in Atlantic Canada have been assessed. Areas of the base varied in terms of terrain, ground cover, as well as types and extent of contamination, dependent on former uses of the sites. Analysis of surficial soils, sediments, water and fish tissue at the base indicated contamination by metals, PCBs, and various petroleum products and their constituents. Identification of chemicals of concern was based on these analyses, in conjunction with detailed chemical selection procedures. Exposures to chemicals of concern for ecological receptors were assessed in one of two ways. The exposures of moose, snowshoe hare and meadow vole were estimated in areas with surficial contamination, based on expected exposures to environmental media via oral inhalation, and dermal routes of exposure. For two top predators (mink and bald-headed eagle), exposures to bioaccumulative chemicals (cadmium, lead, mercury and PCBs) via transport through the aquatic and/or terrestrial foodchain were estimated. A toxicological assessment was conducted for the chemicals of concern, to yield exposure limits derived from governmental regulations or developed based on no-observed-effect-levels (NOELs) reported in scientifically sound toxicological assays in relevant species. The risk evaluation of each chemical of concern was conducted as a comparison of the estimated total exposures to the exposure limits derived for the selected ecological receptors.

  16. Decommissioning of the High Flux Beam Reactor at Brookhaven Lab

    SciTech Connect

    Hu, J. P.; Reciniello, R. N.; Holden, N. E.

    2011-05-27

    The High Flux Beam Reactor at the Brookhaven National Laboratory was a heavy water cooled and moderated reactor that achieved criticality on October 31, 1965. It operated at a power level of 40 mega-watts. An equipment upgrade in 1982 allowed operations at 60 mega-watts. After a 1989 reactor shutdown to reanalyze safety impact of a hypothetical loss of coolant accident, the reactor was restarted in 1991 at 30 mega-watts. The HFBR was shutdown in December 1996 for routine maintenance and refueling. At that time, a leak of tritiated water was identified by routine sampling of ground water from wells located adjacent to the reactor’s spent fuel pool. The reactor remained shutdown for almost three years for safety and environmental reviews. In November 1999 the United States Department of Energy decided to permanently shutdown the HFBR. The decontamination and decommissioning of the HFBR complex, consisting of multiple structures and systems to operate and maintain the reactor, were complete in 2009 after removing and shipping off all the control rod blades. The emptied and cleaned HFBR dome which still contains the irradiated reactor vessel is presently under 24/7 surveillance for safety. Details of the HFBR cleanup conducted during 1999-2009 will be described in the paper.

  17. UK contractors' experience of management of tritium during decommissioning projects

    SciTech Connect

    Green, Tommy; Stevens, Keith; Heaney, John; Murray, Alan; Warwick, Phil; Croudace, Ian

    2007-07-01

    Available in abstract form only. Full text of publication follows: This paper provides an account of the tritium management experience of a UK decommissioning and remediation contracting organisation (NUKEM Limited), supported by a specialist radio-analysis organisation (GAU-Radioanalytical). This experience was gained during the execution of projects which involved the characterisation and remediation of facilities which had previously been used for tritium work and were contaminated with tritium. The emphasis of the paper is on the characterisation (sampling and analysis) of tritium. An account is given of the development of a methodology to improve the accuracy of tritium characterisation. The improved methodology evolved from recognition of the need to minimise tritium losses during sampling, storage, transport and preparation for analysis. These improvements were achieved in a variety of ways, including use of cold and dry sampling techniques in preference to hot or wet ones and freezing relevant samples during storage and transport. The major benefit was an improvement in the accuracy and reliability of the analyses results, essential for proper categorisation, sentencing and future management of tritiated waste. (authors)

  18. Lessons Learned in the Decommissioning of the Stardust Spacecraft

    NASA Technical Reports Server (NTRS)

    Larson, Timothy W.

    2012-01-01

    The Stardust spacecraft completed its prime mission in 2006, returning samples from the coma of comet Wild 2 to earth in the sample return capsule. Still healthy, and in a heliocentric orbit, the Stardust spacecraft was repurposed for a new mission - Stardust NExT. This new mission would take the veteran spacecraft to a 2011 encounter with comet Tempel 1, providing a new look at the comet visited in 2005 by the Deep Impact mission. This extended mission for Stardust would push it to the limits of its fuel reserves, prompting several studies aimed at determining the actual remaining fuel on board. The results were used to plan mission events within the constraints of this dwindling resource. The team tracked fuel consumption and adjusted the mission plans to stay within the fuel budget. This effort intensified toward the end of the mission, when a final assessment showed even less remaining fuel than previously predicted, triggering a delay in the start of comet imaging during the approach phase. The flyby of comet Tempel 1 produced spectacular up close views of this comet, imaging previously seen areas as well as new territory, and providing clear views of the location of the 2005 impact. The spacecraft was decommissioned about a month after the flyby, revealing that the fuel tank was now empty after having flown successfully for 12 years, returned comet dust samples to earth, and flown by an asteroid and two comets.

  19. Action Memorandum for Decommissioning of TAN-607 Hot Shop Area

    SciTech Connect

    M. A. Pinzel

    2007-05-01

    The Department of Energy is documenting the selection of an alternative for the TAN-607 Hot Shop Area using a Comprehensive Environmental Response, Compensation, and Liability Act non-time-critical removal action (NTCRA). The scope of the removal action is limited to TAN-607 Hot Shop Area. An engineering evaluation/cost analysis (EE/CA) has assisted the Department of Energy Idaho Operations Office in identifuomg the most effective method for performing the decommissioning of this structure whose mission has ended. TAN-607 Hot Shop Area is located at Test Area North Technical Support Facility within the Idaho National Laboratory Site. The selected alternative consists of demolishing the TAN-607 aboveground structures and components, removing belowground noninert components (e.g. wood products), and removing the radiologically contaminated debris that does not meet remedial action objectives (RAOs), as defined in the Record of Decision Amendment for the V-Tanks and Explanation of Significant Differences for the PM-2A Tanks at Test Area North, Operable Unit 1-10.

  20. Lessons learned from decommissioning projects at Los Alamos National Laboratory

    SciTech Connect

    Salazar, M.

    1995-09-01

    This paper describes lessons learned over the last 20 years from 12 decommissioning projects at Los Alamos National Laboratory. These lessons relate both to overall program management and to management of specific projects during the planning and operations phases. The issues include waste management; the National Environmental Policy Act (NEPA); the Resource Conservation and Recovery Act (RCRA); the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA); contracting; public involvement; client/customer interface; and funding. Key elements of our approach are to be proactive; follow the observation method; perform field activities concurrently; develop strategies to keep reportable incidents from delaying work; seek and use programs, methods, etc., in existence to shorten learning curves; network to help develop solutions; and avoid overstudying and overcharacterizing. This approach results in preliminary plans that require very little revision before implementation, reasonable costs and schedules, early acquisition of permits and NEPA documents, preliminary characterization reports, and contracting documents. Our track record is good -- the last four projects (uranium and plutonium-processing facility and three research reactors) have been on budget and on schedule.

  1. DECOMMISSIONING OF NUCLEAR FACILITIES IN GERMANY - STATUS AT BMBF SITES

    SciTech Connect

    Papp, R.; Komorowski, K.

    2002-02-25

    In a period of approximately 40 years prior to 1994, the German Federal Government had spent about {approx} 15 billion to promote nuclear technology. These funds were earmarked for R&D projects as well as demonstration facilities which took up operation between 1960 and 1980. These BMBF (Federal Ministry for Research) facilities were mainly located at the sites of the federal research centers at Juelich and Karlsruhe (the research reactors AVR, FR2, FRJ-1, KNK, and MZFR, the pilot reprocessing plant WAK) but included also the pilot plants SNR-300 and THTR-300 for fast breeder and high-temperature gas-cooled reactor development, respectively, and finally the salt mine Asse which had been used for waste emplacement prior to conversion into an underground research laboratory. In the meantime, almost all of these facilities were shut down and are now in a state of decommissioning and dismantling. This is mainly due to the facts that R&D needs are satisfied or do not exist any more and that, secondly, the lack of political consensus led to the cancellation of advanced nuclear technology.

  2. Decommissioning of the Molten Salt Reactor Experiment: A technical evaluation

    SciTech Connect

    Notz, K.J.

    1988-01-01

    This report completes a technical evaluation of decommissioning planning for the former Molten Salt Reactor Experiment, which was shut down in December, 1969. The key issues revolve around the treatment and disposal of some five tons of solid fuel salt which contains over 30 kg of fissionable uranium-233 plus fission products and higher actinides. The chemistry of this material is complicated by the formation of elemental fluorine via a radiolysis reaction under certain conditions. Supporting studies carried out as part of this evaluation include (a) a broad scope analysis of possible options for storage/disposal of the salts, (b) calculation of nuclide decay in future years, (c) technical evaluation of the containment facility and hot cell penetrations, (d) review and update of surveillance and maintenance procedures, (e) measurements of facility groundwater radioactivity and sump pump operation, (f) laboratory studies of the radiolysis reaction, and (g) laboratory studies which resulted in finding a suitable getter for elemental fluorine. In addition, geologic and hydrologic factors of the surrounding area were considered, and also the implications of entombment of the fuel in-place with concrete. The results of this evaluation show that the fuel salt cannot be left in its present form and location permanently. On the other hand, extended storage in its present form is quite acceptable for 20 to 30 years, or even longer. For continued storage in-place, some facility modifications are recommended. 30 refs., 5 figs., 9 tabs.

  3. Radioactive Waste Management and Nuclear Facility Decommissioning Progress in Iraq - 13216

    SciTech Connect

    Al-Musawi, Fouad; Shamsaldin, Emad S.; Jasim, Hadi; Cochran, John R.

    2013-07-01

    Management of Iraq's radioactive wastes and decommissioning of Iraq's former nuclear facilities are the responsibility of Iraq's Ministry of Science and Technology (MoST). The majority of Iraq's former nuclear facilities are in the Al-Tuwaitha Nuclear Research Center located a few kilometers from the edge of Baghdad. These facilities include bombed and partially destroyed research reactors, a fuel fabrication facility and radioisotope production facilities. Within these facilities are large numbers of silos, approximately 30 process or waste storage tanks and thousands of drums of uncharacterised radioactive waste. There are also former nuclear facilities/sites that are outside of Al-Tuwaitha and these include the former uranium processing and waste storage facility at Jesira, the dump site near Adaya, the former centrifuge facility at Rashdiya and the former enrichment plant at Tarmiya. In 2005, Iraq lacked the infrastructure needed to decommission its nuclear facilities and manage its radioactive wastes. The lack of infrastructure included: (1) the lack of an organization responsible for decommissioning and radioactive waste management, (2) the lack of a storage facility for radioactive wastes, (3) the lack of professionals with experience in decommissioning and modern waste management practices, (4) the lack of laws and regulations governing decommissioning or radioactive waste management, (5) ongoing security concerns, and (6) limited availability of electricity and internet. Since its creation eight years ago, the MoST has worked with the international community and developed an organizational structure, trained staff, and made great progress in managing radioactive wastes and decommissioning Iraq's former nuclear facilities. This progress has been made, despite the very difficult implementing conditions in Iraq. Within MoST, the Radioactive Waste Treatment and Management Directorate (RWTMD) is responsible for waste management and the Iraqi Decommissioning

  4. Activities ONDRAF/NIRAS related to the decommissioning of nuclear facilities

    SciTech Connect

    Cantarella, J.; Simenon, R.; Braeckeveldt, M.

    2013-07-01

    Since 1980, the Agency is responsible by law for the safe management of all radioactive waste produced in Belgium, including decommissioning wastes. By the law of 11 January 1991 and the implementing Royal Decree of 16/10/1991, ONDRAF/NIRAS has been entrusted with a mission concerning the decommissioning of nuclear facilities. This mission involves the collection and assessment of data concerning decommissioning forecasts for nuclear facilities, the approval of facilities' decommissioning programmes, the establishment - in consultation with operators - of financing conditions for decommissioning, as well as the implementation of these programmes on request by the operator, or in the case of its failure to do so. This is the case for the company Best Medical Belgium SA located at Fleurus (MDS Nordion SA, till April 2011), which produced radioisotopes for medical applications and went bankrupt in 2012. These installations have been entrusted to ONDRAF/NIRAS. A plan of action was developed for taking over the operations in the framework of remediation and decommissioning. Steps have been taken to integrate his new role as a nuclear operator. The installations of Best Medical Belgium SA are now referred to as the 'O/N - Site Fleurus.' Nuclear facility operators, or any person requesting to operate a nuclear facility, are obliged to provide ONDRAF/NIRAS, under their responsibility and in due time, with all the necessary information concerning these facilities' decommissioning forecasts, the nature, quantities and dates of transfer of the resulting waste, and the financing conditions for these facilities' decommissioning. In order to make the necessary funds available for decommissioning a nuclear facility when it will be shut down, operators are obliged to establish provisions during the facility's active life. These provisions are calculated in such a way that the total amount established at the time of the final shutdown covers all costs resulting from the facility

  5. Historical site assessments--they're not just for decommissioning anymore.

    PubMed

    Aker, Rock E

    2002-02-01

    At the conclusion of its mission, every nuclear facility eventually undergoes decommissioning. An early and essential part of decommissioning is the conduct of an extensive site characterization process. A Historical Site Assessment (HSA), a critical aspect of the site characterization process, sufficiently informs the facility owner and stakeholders of the radiological contaminants on the facility site. This allows for a safe and optimal decommissioning process. Although many nuclear facilities in the United States are permanently closed, many are entering a long-term storage condition typically known as safe storage (SAFSTOR). In these cases, only minimal characterization may be conducted initially. Full characterization may not occur for several decades. Additional delays in decommissioning will occur in operating facilities that successfully extend their operating licenses. In both of these cases, the conduct of a robust HSA can provide a valuable and cost-beneficial decommissioning step. This paper suggests that a substantial portion of the early site characterization process should be conducted prior to the conclusion of a facility's mission.

  6. DECOMMISSIONING OF THE NUCLEAR FACILITIES OF VKTA AT THE ROSSENDORF RESEARCH SITE

    SciTech Connect

    U. Helwig, W. Boessert

    2003-02-27

    VKTA decommissioned the old nuclear facilities of former GDR's (German Democratic Republic) Central Institute of Nuclear Research which was closed end of 1991. VKTA is responsible for fissile material and waste management, environmental and radiation protection and runs an accredited laboratory for environmental and radionuclide analytics. The Rossendorf research site is located east of the city of Dresden. The period from 1982 to about 1997 was mainly characterized by obtaining the necessary licenses for decommissioning and developing a new infrastructure (i.e. waste treatment facility, interim storages for fissile material and waste, clearance monitoring facility). The decommissioning work has been in progress since that time. The decommissioning projects are concentrated on three complexes: (1) the reactors and a fuel development and testing facility, (2) the radioisotope production facilities, and (3) the former liquid and solid waste storage facilities. The status of decommissioning progress and treatment of the residues will be demonstrated. Finally an outlook will be given on the future tasks of VKTA based on the ''Conception VKTA 2000 plus'', which was confirmed by the Saxonian government last year.

  7. Guide for radiological characterization and measurements for decommissioning of US Department of Energy surplus facilities

    SciTech Connect

    Denahm, D. H.; Barnes, M. G.; Jaquish, R. E.; Corley, J. P.; Gilbert, R. O.; Hoenes, G. R.; Jamison, J. D.; McMurray, B. J.; Watson, E. C.

    1983-08-01

    This Guide describes the elements of radiological characterization at DOE excess facilities in preparation for, during, and subsequent to decommissioning operations. It is the intent of this Guide and accompanying appendices to provide the reader (user) with sufficient information to carry out that task with a minimum of confusion and to provide a uniform basis for evaluating site conditions and verifying that decommissioning operations are conducted according to a specific plan. Some areas of particular interest in this Guide are: the need to involve appropriate staff from the affected states in the early planning stages of decommissioning; the need for and suggested methods of radiological site characterization to complete a decommissioning project, including: historical surveys, environmental pathway analyses, statistical sampling design, and choosing appropriate instrumentation and measurements; the need for and emphasis on quality assurance, documentation and records retention; the establishment of a Design Objective approach to applying site-specific contamination limits based on the ALARA philosophy; the establishment of a ''de minimis'' or minimum dose level of concern for decommissioning operations based on existing standards, experience and ALARA considerations.

  8. The conceptual solutions concerning decommissioning and dismantling of Russian civil nuclear powered ships

    SciTech Connect

    Kulikov, Konstantin N.; Nizamutdinov, Rinat A.; Abramov, Andrey N.

    2013-07-01

    From 1959 up to 1991 nine civil nuclear powered ships were built in Russia: eight ice-breakers and one lash lighter carrier (cargo ship). At the present time three of them were taking out of service: ice-breaker 'Lenin' is decommissioned as a museum and is set for storage in the port of Murmansk, nuclear ice-breakers 'Arktika' and 'Sibir' are berthing. The ice-breakers carrying rad-wastes appear to be a possible source of radiation contamination of Murmansk region and Kola Bay because the ship long-term storage afloat has the negative effect on hull's structures. As the result of this under the auspices of the Federal Targeted Program 'Nuclear and Radiation Safety of Russia for 2008 and the period until 2015' the conception and projects of decommissioning of nuclear-powered ships are developed by the State corporation Rosatom with the involvement of companies of United Shipbuilding Corporation. In developing the principal provisions of conception of decommissioning and dismantling of icebreakers the technical and economic assessment of dismantling options in ship-repairing enterprises of North-West of Russia was performed. The paper contains description of options, research procedure, analysis of options of decommissioning and dismantling of nuclear ice-breakers, taking into account the principle of optimization of potential radioactive effect to personnel, human population and environment. The report's conclusions contain the recommendations for selection of option for development of nuclear icebreaker decommissioning and dismantling projects. (authors)

  9. Conceptual and numerical models of the glacial aquifer system north of Aberdeen, South Dakota

    USGS Publications Warehouse

    Marini, Katrina A.; Hoogestraat, Galen K.; Aurand, Katherine R.; Putnam, Larry D.

    2012-01-01

    This U.S. Geological Survey report documents a conceptual and numerical model of the glacial aquifer system north of Aberdeen, South Dakota, that can be used to evaluate and manage the city of Aberdeen's water resources. The glacial aquifer system in the model area includes the Elm, Middle James, and Deep James aquifers, with intervening confining units composed of glacial till. The Elm aquifer ranged in thickness from less than 1 to about 95 feet (ft), with an average thickness of about 24 ft; the Middle James aquifer ranged in thickness from less than 1 to 91 ft, with an average thickness of 13 ft; and the Deep James aquifer ranged in thickness from less than 1 to 165 ft, with an average thickness of 23 ft. The confining units between the aquifers consisted of glacial till and ranged in thickness from 0 to 280 ft. The general direction of groundwater flow in the Elm aquifer in the model area was from northwest to southeast following the topography. Groundwater flow in the Middle James aquifer was to the southeast. Sparse data indicated a fairly flat potentiometric surface for the Deep James aquifer. Horizontal hydraulic conductivity for the Elm aquifer determined from aquifer tests ranged from 97 to 418 feet per day (ft/d), and a confined storage coefficient was determined to be 2.4x10-5. Estimates of the vertical hydraulic conductivity of the sediments separating the Elm River from the Elm aquifer, determined from the analysis of temperature gradients, ranged from 0.14 to 2.48 ft/d. Average annual precipitation in the model area was 19.6 inches per year (in/yr), and agriculture was the primary land use. Recharge to the Elm aquifer was by infiltration of precipitation through overlying outwash, lake sediments, and glacial till. The annual recharge for the model area, calculated by using a soil-water-balance method for water year (WY) 1975-2009, ranged from 0.028 inch in WY 1980 to 4.52 inches in WY 1986, with a mean of 1.56 inches. The annual potential

  10. U.S. Crude Oil and Natural Gas Proved Reserves

    EIA Publications

    2016-01-01

    U.S. oil and natural gas proved reserves declined in 2015 due to lower prices. U.S. crude oil and lease condensate proved reserves declined 4.7 billion barrels (11.8%) from their year-end 2014 level to 35.2 billion barrels at year-end 2015, according to U.S. Crude Oil and Natural Gas Proved Reserves, Year-end 2015, released today by the U.S. Energy Information Administration. U.S natural gas proved reserves decreased 64.5 trillion cubic feet, a 16.6% decline, reducing the U.S. total to 324.3 Tcf at year-end 2015.

  11. 29 CFR 18.405 - Methods of proving character.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... proving character. (a) Reputation of opinion. In all cases in which evidence of character or a trait of... conduct. (b) Specific instances of conduct. In cases in which character or a trait of character of...

  12. 29 CFR 18.405 - Methods of proving character.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... proving character. (a) Reputation of opinion. In all cases in which evidence of character or a trait of... conduct. (b) Specific instances of conduct. In cases in which character or a trait of character of...

  13. 29 CFR 18.405 - Methods of proving character.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... proving character. (a) Reputation of opinion. In all cases in which evidence of character or a trait of... conduct. (b) Specific instances of conduct. In cases in which character or a trait of character of...

  14. 29 CFR 18.405 - Methods of proving character.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... proving character. (a) Reputation of opinion. In all cases in which evidence of character or a trait of... conduct. (b) Specific instances of conduct. In cases in which character or a trait of character of...

  15. 29 CFR 18.405 - Methods of proving character.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... proving character. (a) Reputation of opinion. In all cases in which evidence of character or a trait of... conduct. (b) Specific instances of conduct. In cases in which character or a trait of character of...

  16. Mobile worksystems for decontamination and decommissioning operations. Final report

    SciTech Connect

    1997-02-01

    This project is an interdisciplinary effort to develop effective mobile worksystems for decontamination and decommissioning (D&D) of facilities within the DOE Nuclear Weapons Complex. These mobile worksystems will be configured to operate within the environmental and logistical constraints of such facilities and to perform a number of work tasks. Our program is designed to produce a mobile worksystem with capabilities and features that are matched to the particular needs of D&D work by evolving the design through a series of technological developments, performance tests and evaluations. The Phase I effort was based on a robot called the Remote Work Vehicle (RWV) that was previously developed by CMU for use in D&D operations at the Three Mile Island Unit 2 Reactor Building basement. During Phase I of this program, the RWV was rehabilitated and upgraded with contemporary control and user interface technologies and used as a testbed for remote D&D operations. We established a close working relationship with the DOE Robotics Technology Development Program (RTDP). In the second phase, we designed and developed a next generation mobile worksystem, called Rosie, and a semi-automatic task space scene analysis system, called Artisan, using guidance from RTDP. Both systems are designed to work with and complement other RTDP D&D technologies to execute selective equipment removal scenarios in which some part of an apparatus is extricated while minimally disturbing the surrounding objects. RTDP has identified selective equipment removal as a timely D&D mission, one that is particularly relevant during the de-activation and de-inventory stages of facility transitioning as a means to reduce the costs and risks associated with subsequent surveillance and monitoring. In the third phase, we tested and demonstrated core capabilities of Rosie and Artisan; we also implemented modifications and enhancements that improve their relevance to DOE`s facility transitioning mission.

  17. Decommissioning and PIE of the MEGAPIE spallation target

    SciTech Connect

    Latge, C.; Henry, J.; Wohlmuther, M.; Dai, Y.; Gavillet, D.; Hammer, B.; Heinitz, S.; Neuhausen, J.; Schumann, D.; Thomsen, K.; Tuerler, A.; Wagner, W.; Gessi, A.; Guertin, A.; Konstantinovic, M.; Lindau, R.; Maloy, S.; Saito, S.

    2013-07-01

    A key experiment in the Accelerated Driven Systems roadmap, the MEGAwatt PIlot Experiment (MEGAPIE) (1 MW) was initiated in 1999 in order to design and build a liquid lead-bismuth spallation target, then to operate it into the Swiss spallation neutron facility SINQ at Paul Scherrer Institute. The target has been designed, manufactured, and tested during integral tests, before irradiation carried out end of 2006. During irradiation, neutron and thermo hydraulic measurements were performed allowing deep interpretation of the experiment and validation of the models used during design phase. The decommissioning, Post Irradiation Examinations and waste management phases were defined properly. The phases dedicated to cutting, sampling, cleaning, waste management, samples preparation and shipping to various laboratories were performed by PSI teams: all these phases constitute a huge work, which allows now to perform post-irradiation examination (PIE) of structural material, irradiated in relevant conditions. Preliminary results are presented in the paper, they concern chemical characterization. The following radio-nuclides have been identified by γ-spectrometry: {sup 60}Co, {sup 101}Rh, {sup 102}Rh, {sup 108m}Ag, {sup 110m}Ag, {sup 133}Ba, {sup 172}Hf/Lu, {sup 173}Lu, {sup 194}Hg/Au, {sup 195}Au, {sup 207}Bi. For some of these nuclides the activities can be easily evaluated from γ-spectrometry results ({sup 207}Bi, {sup 194}Hg/Au), while other nuclides can only be determined after chemical separations ({sup 108m}Ag, {sup 110m}Ag, {sup 195}Au, {sup 129}I, {sup 36}Cl and α-emitting {sup 208-210}Po). The concentration of {sup 129}I is lower than expected. The chemical analysis already performed on spallation and corrosion products in the lead-bismuth eutectic (LBE) are very relevant for further applications of LBE as a spallation media and more generally as a coolant.

  18. Decontamination and decommissioning activities photobriefing book FY 1999

    SciTech Connect

    2000-03-08

    The Chicago Pile 5 (CP-5) Reactor, the first reactor built on the Argonne National Laboratory-East site, followed a rich history that had begun in 1942 with Enrico Fermi's original pile built under the west stands at the Stagg Field Stadium of The University of Chicago. CP-5 was a 5-megawatt, heavy water-moderated, enriched uranium-fueled reactor used to produce neutrons for scientific research from 1954--79. The reactor was shut down and defueled in 1979, and placed into a lay-up condition pending funding for decontamination and decommissioning (D and D). In 1990, work was initiated on the D and D of the facility in order to alleviate safety and environmental concerns associated with the site due to the deterioration of the building and its associated support systems. A decision was made in early Fiscal Year (FY) 1999 to direct focus and resources to the completion of the CP-5 Reactor D and D Project. An award of contract was made in December 1998 to Duke Engineering and Services (Marlborough, MA), and a D and D crew was on site in March 1999 to begin work, The project is scheduled to be completed in July 2000. The Laboratory has determined that the building housing the CP-5 facility is surplus to the Laboratory's needs and will be a candidate for demolition. In addition to a photographic chronology of FY 1999 activities at the CP-5 Reactor D and D Project, brief descriptions of other FY 1999 activities and of projects planned for the future are provided in this photobriefing book.

  19. DEACTIVATION AND DECOMMISSIONING (D AND D) TECHNOLOGY INTEGRATION

    SciTech Connect

    M.A. Ebadian, Ph.D.

    1999-01-01

    As part of the ongoing task of making Deactivation and Decommissioning (D&D) operations more efficient, this subtask has addressed the need to integrate existing characterization technologies with decontamination technologies in order to provide real-time data on the progress of contamination removal. Specifically, technologies associated with concrete decontamination and/or removal have been examined with the goal of integrating existing technologies and commercializing the resulting hybrid. The Department of Energy (DOE) has estimated that 23 million cubic meters of concrete will require disposition as 1200 buildings undergo the D&D process. All concrete removal to be performed will also necessitate extensive use of characterization techniques. The in-process characterization presents the most potential for improvement and cost-savings as compared to other types. Current methods for in-process characterization usually require cessation of work to allow for radiation surveys to assess the rate of decontamination. Combining together decontamination and characterization technologies would allow for in-process evaluation of decontamination efforts. Since the present methods do not use in-process evaluations for the progress of decontamination, they may allow for ''overremoval'' of materials (removal of contaminated along with non-contaminated materials). Overremoval increases the volume of waste and therefore the costs associated with disposal. Integrating technologies would facilitate the removal of only contaminated concrete and reduce the total volume of radioactive waste, which would be disposed of. This would eventually ensure better productivity and time savings. This project presents a general procedure to integrate the above-mentioned technologies in the form of the Technology Integration Module (TIM) along with combination lists of commercially available decontamination and characterization technologies. The scope of the project has also been expanded by FIU

  20. DEVELOPMENT OF PERSONAL PROTECTIVE EQUIPMENT FOR DECONTAMINATION AND DECOMMISSIONING

    SciTech Connect

    M.A. Ebadian, Ph.D.

    1999-01-01

    The purpose of this one-year investigation is to perform a technology integration/search, thereby ensuring that the safest and most cost-effective options are developed and subsequently used during the deactivation and decommissioning (D&D) of U.S. Department of Energy Environmental Management (DOE-EM) sites. Issues of worker health and safety are the main concern, followed by cost. Two lines of action were explored: innovative Personal Cooling Systems (PCS) and Personal Monitoring Equipment (PME). PME refers to sensors affixed to the worker that warn of an approaching heat stress condition, thereby preventing it. Three types of cooling systems were investigated: Pre-Chilled or Forced-Air System (PCFA), Umbilical Fluid-Chilled System (UFCS), and Passive Vest System (PVS). Of these, the UFCS leads the way. The PVS or Gel pack vest lagged due to a limited cooling duration. And the PCFA or chilled liquid air supply was cumbersome and required an expensive and complex recharge system. The UFCS in the form of the Personal Ice Cooling System (PICS) performed exceptionally. The technology uses a chilled liquid circulating undergarment and a Personal Protective Equipment (PPE) external pump and ice reservoir. The system is moderately expensive, but the recharge is low-tech and inexpensive enough to offset the cost. There are commercially available PME that can be augmented to meet the DOE's heat stress alleviation need. The technology is costly, in excess of $4,000 per unit. Workers easily ignore the alarm. The benefit to health & safety is indirect so can be overlooked. A PCS is a more justifiable expenditure.

  1. Technology, Safety and Costs of Decommissioning a Reference Uranium Hexafluoride Conversion Plant

    SciTech Connect

    Elder, H. K.

    1981-10-01

    Safety and cost information is developed for the conceptual decommissioning of a commercial uranium hexafluoride conversion (UF{sub 6}) plant. Two basic decommissioning alternatives are studied to obtain comparisons between cost and safety impacts: DECON, and passive SAFSTOR. A third alternative, DECON of the plant and equipment with stabilization and long-term care of lagoon wastes. is also examined. DECON includes the immediate removal (following plant shutdown) of all radioactivity in excess of unrestricted release levels, with subsequent release of the site for public use. Passive SAFSTOR requires decontamination, preparation, maintenance, and surveillance for a period of time after shutdown, followed by deferred decontamination and unrestricted release. DECON with stabilization and long-term care of lagoon wastes (process wastes generated at the reference plant and stored onsite during plant operation} is also considered as a decommissioning method, although its acceptability has not yet been determined by the NRC. The decommissioning methods assumed for use in each decommissioning alternative are based on state-of-the-art technology. The elapsed time following plant shutdown required to perform the decommissioning work in each alternative is estimated to be: for DECON, 8 months; for passive SAFSTOR, 3 months to prepare the plant for safe storage and 8 months to accomplish deferred decontamination. Planning and preparation for decommissioning prior to plant shutdown is estimated to require about 6 months for either DECON or passive SAFSTOR. Planning and preparation prior to starting deferred decontamination is estimated to require an additional 6 months. OECON with lagoon waste stabilization is estimated to take 6 months for planning and about 8 months to perform the decommissioning work. Decommissioning cost, in 1981 dollars, is estimated to be $5.91 million for OECON. For passive SAFSTOR, preparing the facility for safe storage is estimated to cost $0

  2. 30 CFR 250.1731 - Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... facility subject to an Alternate Use RUE? 250.1731 Section 250.1731 Mineral Resources BUREAU OF SAFETY AND... responsible for decommissioning an OCS facility subject to an Alternate Use RUE? (a) The holder of an Alternate Use RUE issued under 30 CFR part 585 is responsible for all decommissioning obligations...

  3. 30 CFR 285.1018 - Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... facility subject to an Alternate Use RUE? 285.1018 Section 285.1018 Mineral Resources BUREAU OF OCEAN...- and Marine-Related Activities Using Existing OCS Facilities Decommissioning An Alternate Use Rue § 285.1018 Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE? (a)...

  4. 30 CFR 285.1018 - Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... facility subject to an Alternate Use RUE? 285.1018 Section 285.1018 Mineral Resources MINERALS MANAGEMENT... Existing OCS Facilities Decommissioning An Alternate Use Rue § 285.1018 Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE? (a) The holder of an Alternate Use RUE...

  5. 30 CFR 250.1731 - Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... facility subject to an Alternate Use RUE? 250.1731 Section 250.1731 Mineral Resources MINERALS MANAGEMENT... for decommissioning an OCS facility subject to an Alternate Use RUE? (a) The holder of an Alternate Use RUE issued under part 285 of this subchapter is responsible for all decommissioning...

  6. 30 CFR 250.1731 - Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... facility subject to an Alternate Use RUE? 250.1731 Section 250.1731 Mineral Resources BUREAU OF SAFETY AND... responsible for decommissioning an OCS facility subject to an Alternate Use RUE? (a) The holder of an Alternate Use RUE issued under 30 CFR part 585 is responsible for all decommissioning obligations...

  7. 30 CFR 250.1731 - Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... facility subject to an Alternate Use RUE? 250.1731 Section 250.1731 Mineral Resources BUREAU OF SAFETY AND... responsible for decommissioning an OCS facility subject to an Alternate Use RUE? (a) The holder of an Alternate Use RUE issued under 30 CFR part 585 is responsible for all decommissioning obligations...

  8. 30 CFR 285.517 - How will MMS determine the amounts of the supplemental and decommissioning financial assurance...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... supplemental and decommissioning financial assurance requirements associated with commercial leases? 285.517... Assurance Requirements Financial Assurance Requirements for Commercial Leases § 285.517 How will MMS... decommissioning financial assurance requirements on estimates of the cost to meet all accrued lease...

  9. 75 FR 15423 - U.S. Nuclear Regulatory Commission Technical Evaluation Report for the Phase 1 Decommissioning...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-29

    .... Nuclear Regulatory Commission Technical Evaluation Report for the Phase 1 Decommissioning Plan for the... Regulatory Commission (NRC) Technical Evaluation Report (TER) for the Phase 1 Decommissioning Plan for the... Center (DOE/ EIS-0226). ADDRESSES: Copies of the U.S. Nuclear Regulatory Commission Technical...

  10. 30 CFR 285.902 - What are the general requirements for decommissioning for facilities authorized under my SAP, COP...

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... decommissioning for facilities authorized under my SAP, COP, or GAP? 285.902 Section 285.902 Mineral Resources... facilities authorized under my SAP, COP, or GAP? (a) Except as otherwise authorized by MMS under § 285.909...) Before decommissioning the facilities under your SAP, COP, or GAP, you must submit a...

  11. 30 CFR 585.902 - What are the general requirements for decommissioning for facilities authorized under my SAP, COP...

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... decommissioning for facilities authorized under my SAP, COP, or GAP? 585.902 Section 585.902 Mineral Resources..., Inspections, and Facility Assessments for Activities Conducted Under SAPs, COPs and GAPs Decommissioning... authorized under my SAP, COP, or GAP? (a) Except as otherwise authorized by BOEM under § 585.909, within...

  12. 30 CFR 285.902 - What are the general requirements for decommissioning for facilities authorized under my SAP, COP...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... decommissioning for facilities authorized under my SAP, COP, or GAP? 285.902 Section 285.902 Mineral Resources... SAP, COP, or GAP? (a) Except as otherwise authorized by MMS under § 285.909, within 2 years following... under your SAP, COP, or GAP, you must submit a decommissioning application and receive approval from...

  13. 77 FR 58591 - Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-09-21

    ... COMMISSION Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste... document entitled: NUREG-1307 Revision 15, ``Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities.'' DATES: Please submit comments by October...

  14. 77 FR 64361 - Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-10-19

    ... COMMISSION Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste... Commission (NRC or the Commission) issued Draft NUREG-1307, Revision 15, ``Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities,'' in the...

  15. Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Appendices

    SciTech Connect

    Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

    1982-03-01

    Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and EMTOMB (entombment). The study results are presented in two volumes. Volume 2 (Appendices) contains the detailed data that support the results given in Volume 1, including unit-component data.

  16. Environmental, health and safety assessment of decommissioning radioisotope thermoelectric generators (RTGs) in northwest Russia.

    PubMed

    Standring, W J F; Dowdall, M; Sneve, M; Selnaes, Ø G; Amundsen, I

    2007-09-01

    This paper presents findings from public health and environmental assessment work that has been conducted as part of a joint Norwegian-Russian project to decommission radioisotope thermoelectric generators (RTG) in northwest Russia. RTGs utilise heat energy from radioactive isotopes, in this case 90Sr and its daughter nuclide 90Y, to generate electricity as a power source. Different accident scenarios based on the decommissioning process for RTGs are assessed in terms of possible radiation effects to humans and the environment. Doses to humans and biota under the worst-case scenario were lower than threshold limits given in ICRP and IAEA literature.

  17. Environmental assessment of decommissioning radioisotope thermoelectric generators (RTG) in northwest Russia

    SciTech Connect

    Hosseini, A.; Standring, W.J.F.; Brown, J.E.; Dowdall, M.; Amundsen, I.B.

    2007-07-01

    This article presents some results from assessment work conducted as part of a joint Norwegian-Russian project to decommission radioisotope thermoelectric generators (RTG) in Northwest Russia. Potential worst case accident scenarios, based on the decommissioning procedures for RTGs, were assessed to study possible radiation effects to the environment. Close contact with exposed RTG sources will result in detrimental health effects. However, doses to marine biota from ingestion of radioactivity under the worst-case marine scenario studied were lower than threshold limits given in IAEA literature. (authors)

  18. Action Memorandum for General Decommissioning Activities under the Idaho Cleanup Project

    SciTech Connect

    S. L. Reno

    2006-10-26

    This Action Memorandum documents the selected alternative to perform general decommissioning activities at the Idaho National Laboratory (INL) under the Idaho Cleanup Project (ICP). Preparation of this Action Memorandum has been performed in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended by the "Superfund Amendments and Reauthorization Act of 1986", and in accordance with the "National Oil and Hazardous Substances Pollution Contingency Plan". An engineering evaluation/cost analysis (EE/CA) was prepared and released for public comment and evaluated alternatives to accomplish the decommissioning of excess buildings and structures whose missions havve been completed.

  19. Demonstration Report, Munitions Management Projects, ESTCP Project MR-200809, ALLTEM Multi-Axis Electromagnetic Induction System Demonstration and Validation, Aberdeen Proving Ground Standardized UXO Technology Demonstration Site, Version 1.0

    DTIC Science & Technology

    2011-11-17

    gradiometers to cancel the primary field. ALLTEM APG Demonstration Report November 2011 4 4 ALLTEM was tested at YPG in 2005 and 2006 (Figure 2) with...each Rx gradiometer loop pair has more than one “look” at even the smallest and shallowest target it may pass over. The names and receiver antenna...of 24 bit summation averaged sensor data per record. Records for 19 Tx-Rx gradiometer channels (x, y, z, or diagonal, component of the magnetic

  20. Proceedings of the U.S. Army Chemical Research, Development and Engineering Center Scientific Conference on Chemical Defense Research Held in Aberdeen Proving Ground, Maryland on 14-17 November 1989

    DTIC Science & Technology

    1990-08-01

    J. Richard Ward, Linda L . Szafranie4, William T. Beaudry, Sheldon E. Day, and Gintaras A. Dragunas Decontamination of Soman in Freon Mixtures...31 Barney L . Bales and Jack Deaton Syn’hesis of Organo-Ruthenium Complexes for Luminescence Probes in Microemulsion...Dimethyl Sulfoxide . . ,. .. -. . . ,. , . ,. .. . ,, . .e,. . . ... .... . 97 Yu-Chu Yang, Linda L . Szafraniec, William T. Beaudr,y and Fu-Lian Hsu