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Note: This page contains sample records for the topic "interim storage site" from the National Library of EnergyBeta (NLEBeta).
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1

Wayne Interim Storage Site annual environmental report for calendar year 1991, Wayne, New Jersey. [Wayne Interim Storage Site  

SciTech Connect

This document describes the envirormental monitoring program at the Wayne Interim Storage Site (WISS) and surrounding area, implementation of the program, and monitoring results for 1991. Environmental monitoring of WISS and surrounding area began in 1984 when Congress added the site to the US Department of Energy's (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP is a DOE program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. WISS is a National Priorities List site. The environmental monitoring program at WISS includes sampling networks for radon and thoron concentrations in air; external gamma radiation exposure; and radium-226, radium-228, thorium-232, and total uranium concentrations in surface water, sediment, and groundwater. Several nonradiological parameters are also measured in groundwater. Monitoring results are compared with applicable Environmental Protection Agency standards, DOE derived concentration guides, dose limits, and other requirements in DOE orders. Environmental standards are established to protect public health and the environment.

none,

1992-09-01T23:59:59.000Z

2

Finding of no significant impact. Consolidation and interim storage of special nuclear material at Rocky Flats Environmental Technology Site  

SciTech Connect

The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II special nuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage.

NONE

1995-06-01T23:59:59.000Z

3

Hazelwood Interim Storage Site annual site environmental report: Calendar year 1986  

SciTech Connect

During 1986, the environmental monitoring program was continued at the Hazelwood Interim Storage Site (HISS), a US Department of Energy (DOE) facility located in the City of Hazelwood, Missouri. Originally known as the Cotter Corporation site on Latty Avenue in Hazelwood, the HISS is presently used for the storage of soils contaminated with residual radioactive material. As part of the decontamination research and development project authorized by Congress under the 1984 Energy and Water Appropriations Act, remedial action and environmental monitoring program are being conducted at the site and at vicinity properties by Bechtel National, Inc., Project Management Contractor for FUSRAP. The monitoring program at the HISS measures radon gas concentrations in air; external gamma radiation levels; and uranium, radium, and thorium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard (100 mrem/yr) and assess its potential effect on public health, the radiation dose was calculated for the maximally exposed individual. Based on the scenario described in this report, the maximally exposed individual at the HISS would receive an annual external exposure approximately equivalent to 2% of the DOE radiation protection standard of 100 mrem/yr. This exposure is less than the exposure a person would receive during a round-trip flight from New York to Los Angeles. The cumulative dose to the population within an 80-km (50-mi) radius of the HISS that would result from radioactive materials present at the site would be indistinguishable from the dose that the same population would receive from naturally occurring radioactive sources. Results of the 1986 monitoring show that the HISS is in compliance with the DOE radiation protection standard. 11 refs., 6 figs., 10 tabs.

Not Available

1987-06-01T23:59:59.000Z

4

Maywood Interim Storage Site environmental report for calendar year 1989, Maywood, New Jersey  

SciTech Connect

The environmental monitoring program, which began in 1984, was continued in 1989 at the Maywood Interim Storage Site (MISS), a US Department of Energy (DOE) facility located in the Borough of Maywood and the Township of Rochelle Park, New Jersey. MISS is currently used for storage of soils contaminated with low-level radioactivity. MISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to identify and decontaminate or otherwise control sites where residual radioactive materials are present. The monitoring program at MISS measures thoron and radon concentrations in air; external gamma radiation levels; and thorium, uranium, and radium concentrations in surface water, groundwater, and sediment. Additionally, several nonradiological parameters are measured in groundwater. The radiation dose was calculated for a hypothetical maximally exposed individual to verify that the site is in compliance with the DOE radiation protection standard (100 mrem/yr) and to assess its potential effects on public health. This report presents the results of the environmental monitoring program conducted at the US Department of Energy's (DOE) Maywood Interim Storage Site (MISS) during calendar year 1989. Environmental monitoring began at MISS in 1984. 19 refs., 23 figs., 14 tabs.

Not Available

1990-05-01T23:59:59.000Z

5

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

SciTech Connect

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

Not Available

1985-07-01T23:59:59.000Z

6

Environmental surveillance results for 1994 for the Hazelwood Interim Storage Site. FUSRAP technical memorandum Number 140-95-011  

SciTech Connect

This report presents analytical results and an interpretation of the results for samples collected as part of the 1994 environmental surveillance program for the Hazelwood Interim Storage Site (HISS) for the interim storage of radiologically contaminated soils. The discussion provides a comparative analysis of local background conditions and applicable regulatory criteria to results reported for external gamma radiation and for samples from the media investigated (air, surface water, sediment, groundwater, and stormwater). Results from the 1994 environmental surveillance program at HISS indicate that Department of Energy (DOE) guidelines were not exceeded for the calculated airborne particulate dose or for the monitored constituents.

Szojka, S.

1995-06-01T23:59:59.000Z

7

Hazelwood Interim Storage Site environmental surveillance report for calendar year 1993  

SciTech Connect

This report summarizes the results of environmental surveillance activities conducted at the Hazelwood Interim Storage Site (HISS) during calendar year 1993. It includes an overview of site operations, the basis for monitoring for radioactive and non-radioactive parameters, summaries of environmental program at HISS, a summary of the results, and the calculated hypothetical radiation dose to the offsite population. Environmental surveillance activities were conducted in accordance with the site environmental monitoring plan, which describes the rationale and design criteria for the surveillance program, the frequency of sampling and analysis, specific sampling and analysis procedures, and quality assurance requirements. The US Department of Energy (DOE) began environmental monitoring of HISS in 1984, when the site was assigned to DOE by Congress through the energy and Water Development Appropriations Act and subsequent to DOE`s Formerly Utilized Sites Remediation Action Program (FUSRAP). Contamination at HISS originated from uranium processing work conducted at Mallinckrodt Chemical Works at the St. Louis Downtown Site (SLDS) from 1942 through 1957.

Not Available

1994-06-01T23:59:59.000Z

8

Hazelwood Interim Storage Site environmental report for calendar year 1992, 9200 Latty Avenue, Hazelwood, Missouri  

SciTech Connect

This report describes the environmental surveillance program at the Hazelwood Interim storage Site (HISS) and surrounding area, provides the results for 1992, and discusses applicable environmental standards and requirements with which the results were compared. HISS is located in eastern Missouri in the City of Hazelwood (St. Louis County) and occupies approximately 2.2 ha (5.5 acres). Environmental monitoring of HISS began in 1984 when the site was assigned to the US Department of Energy (DOE) as part of the decontamination research and development project authorized by Congress under the 1984 Energy and Water Development Appropriations Act. DOE placed responsibility for HISS under the Formerly Utilized Sites Remedial Action Program (FUSRAP), which was established to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation`s atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. In 1992 there were no environmental occurrences or unplanned contaminant releases as defined in DOE requirements and in the Superfund Amendment and Reauthorization Act (SARA) Title III of CERCLA.

Not Available

1993-05-01T23:59:59.000Z

9

Environmental surveillance results for 1995 for the Hazelwood Interim Storage Site  

SciTech Connect

This memorandum presents and interprets analytical results and measurements obtained as part of the 1995 environmental surveillance program for the Hazelwood Interim Storage Site (HISS) under the Formerly Utilized Sites Remedial Action Program (FUSRAP). The discussion provides a comparative analysis of average historical background conditions and applicable regulatory criteria to the 1995 results reported for external gamma radiation and for samples from the media investigated (air, surface water, sediment, groundwater, and stormwater). Results from the 1995 environmental surveillance program at HISS indicate that, with the exception of thorium-230 in streambed sediment, applicable US Department of Energy (DOE) guidelines were not exceeded for any measured parameter or for any dose calculated for potentially exposed members of the general public. In the absence of sediment guidelines, DOE soil guidelines serve as a standard of comparison for data obtained from stream bed sediment; two samples from downstream locations contained concentrations of thorium-230 that exceeded DOE soil guidelines. All stormwater sample results were in compliance with permit-specified limits. Other radioactive materials include radium 226 and natural uranium.

McCague, J.C.

1996-06-01T23:59:59.000Z

10

Interim Storage Facility decommissioning. Final report  

SciTech Connect

Decontamination and decommissioning of the Interim Storage Facility were completed. Activities included performing a detailed radiation survey of the facility, removing surface and imbedded contamination, excavating and removing the fuel storage cells, restoring the site to natural conditions, and shipping waste to Hanford, Washington, for burial. The project was accomplished on schedule and 30% under budget with no measurable exposure to decommissioning personnel.

Johnson, R.P.; Speed, D.L.

1985-03-15T23:59:59.000Z

11

Colonie Interim Storage Site annual site environmental report for calendar year 1989, Colonie, New York  

SciTech Connect

IN 1984, Congress assigned the cleanup of the National Lead (NL) Industries site in Colonie, New York, to the Department of Energy (DOE) as part of a decontamination research and development project under the 1984 Energy and Water Appropriations Act. DOE then included the site in the Formerly Utilized Sites Remedial Action Program (FUSRAP), an existing DOE program to decontaminate or otherwise control sites where residual radioactive materials remain for the early years of the nation's atomic energy program. DOE instituted an environmental monitoring program at the site in 1984. Results are presented annually in reports such as this. Under FUSRAP, the first environmental monitoring report for this site presented data for calendar year 1984. This report presents the findings of the environmental monitoring program conducted during calendar year 1989. 16 refs., 17 figs., 14 tabs.

Not Available

1990-05-01T23:59:59.000Z

12

Safe interim storage of Hanford tank wastes, draft environmental impact statement, Hanford Site, Richland, Washington  

SciTech Connect

This Draft EIS is prepared pursuant to the National Environmental Policy Act (NEPA) and the Washington State Environmental Policy Act (SEPA). DOE and Ecology have identified the need to resolve near-term tank safety issues associated with Watchlist tanks as identified pursuant to Public Law (P.L.) 101-510, Section 3137, ``Safety Measures for Waste Tanks at Hanford Nuclear Reservation,`` of the National Defense Authorization Act for Fiscal Year 1991, while continuing to provide safe storage for other Hanford wastes. This would be an interim action pending other actions that could be taken to convert waste to a more stable form based on decisions resulting from the Tank Waste Remediation System (TWRS) EIS. The purpose for this action is to resolve safety issues concerning the generation of unacceptable levels of hydrogen in two Watchlist tanks, 101-SY and 103-SY. Retrieving waste in dilute form from Tanks 101-SY and 103-SY, hydrogen-generating Watchlist double shell tanks (DSTs) in the 200 West Area, and storage in new tanks is the preferred alternative for resolution of the hydrogen safety issues.

Not Available

1994-07-01T23:59:59.000Z

13

EIS-0212: Safe Interim Storage of Hanford Tank Wastes, Hanford Site, Richland, WA  

Energy.gov (U.S. Department of Energy (DOE))

This environmental impact statement asseses Department of Energy and Washington State Department of Ecology maintanence of safe storage of high-level radioactive wastes currently stored in the older single-shell tanks, the Watchlist Tank 101-SY, and future waste volumes associated with tank farm and other Hanford facility operations, including a need to provide a modern safe, reliable, and regulatory-compliant replacement cross-site transfer capability. The purpose of this action is to prevent uncontrolled releases to the environment by maintaining safe storage of high-level tank wastes.

14

Colonie Interim Storage Site: Annual site environmental report, Colonie, New York, Calendar year 1986: Formerly Utilized Sites Remedial Action Program (FUSRAP)  

SciTech Connect

During 1986, the environmental monitoring program continued at the Colonie Interim Storage Site (CISS), a US Department of Energy (DOE) facility located in Colonie, New York. The CISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has mandated DOE to remedy. As part of the decontamination research and development project authorized by Congress under the 1984 Energy and Water Appropriations Act, remedial action is being conducted at the site and at vicinity properties by Bechtel National Inc. (BNI), Project Management Contractor for FUSRAP. The environmental monitoring program is also carried out by BNI. The monitoring program at the CISS measures external gamma radiation levels as well as uranium and radium-226 concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard and to assess the potential effect of the site on public health, the radiation dose was calculated for the maximally exposed individual. Based on the conservative scenario described in the report, the maximally exposed individual would receive an annual external exposure approximately equivalent to 5% of the DOE radiation protection standard of 100 mrem/y. Results of 1986 monitoring show that the CISS is in compliance with the DOE radiation protection standard. 14 refs., 9 figs., 9 tabs.

Not Available

1987-06-01T23:59:59.000Z

15

Fire Hazards Analysis for the 200 Area Interim Storage Area  

SciTech Connect

This documents the Fire Hazards Analysis (FHA) for the 200 Area Interim Storage Area. The Interim Storage Cask, Rad-Vault, and NAC-1 Cask are analyzed for fire hazards and the 200 Area Interim Storage Area is assessed according to HNF-PRO-350 and the objectives of DOE Order 5480 7A. This FHA addresses the potential fire hazards associated with the Interim Storage Area (ISA) facility in accordance with the requirements of DOE Order 5480 7A. It is intended to assess the risk from fire to ensure there are no undue fire hazards to site personnel and the public and to ensure property damage potential from fire is within acceptable limits. This FHA will be in the form of a graded approach commensurate with the complexity of the structure or area and the associated fire hazards.

JOHNSON, D.M.

2000-01-06T23:59:59.000Z

16

Maywood Interim Storage Site environmental report for calendar year 1992, 100 West Hunter Avenue, Maywood, New Jersey. Formerly Utilized Sites Remedial Action Program (FUSRAP)  

SciTech Connect

This report describes the environmental surveillance program at the Maywood Interim Storage Site (MISS) and provides the results for 1992. Environmental monitoring of MISS began in 1984, when the site was assigned to DOE by Congress through the Energy and Water Development Appropriations Act and was placed under DOE`s Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP was established to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation`s atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. MISS is part of a National Priorities List (NPL) site. The environmental surveillance program at MISS includes sampling networks for radon and thoron in air; external gamma radiation exposure; and radium-226, radium-228, thorium-232, and total uranium in surface water, sediment, and groundwater. Additionally, chemical analysis includes metals and organic compounds in surface water and groundwater and metals in sediments. This program assists in fulfilling the DOE objective of measuring and monitoring effluents from DOE activities and calculating hypothetical doses to members of the general public. Monitoring results are compared with applicable Environmental Protection Agency (EPA) and state standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements. Environmental standards are established to protect public health and the environment. The radiological data for all media sampled support the conclusion that doses to the public are not distinguishable from natural background radiation.

Not Available

1993-05-01T23:59:59.000Z

17

Wayne Interim Storage Site environmental report for calendar year 1992, 868 Black Oak Ridge Road, Wayne, New Jersey. Formerly Utilized Sites Remedial Action Program (FUSRAP)  

SciTech Connect

This report describes the environmental surveillance program at the Wayne Interim Storage Site (WISS) and provides the results for 1992. The fenced, site, 32 km (20 mi) northwest of Newark, New Jersey, was used between 1948 and 1971 for commercial processing of monazite sand to separate natural radioisotopes - predominantly thorium. Environmental surveillance of WISS began in 1984 in accordance with Department of Energy (DOE) Order 5400.1 when Congress added the site to DOE`s Formerly Utilized Sites Remedial Action Program (FUSRAP). The environmental surveillance program at WISS includes sampling networks for radon and thoron in air; external gamma radiation exposure; radium-226, radium-228, thorium-230, thorium-232, total uranium, and several chemicals in surface water and sediment; and total uranium, radium-226, radium-228, thorium-230, thorium-232, and organic and inorganic chemicals in groundwater. Monitoring results are compared with applicable Environmental Protection Agency (EPA) and state standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements. This monitoring program assists in fulfilling the DOE policy of measuring and monitoring effluents from DOE activities and calculating hypothetical doses. Results for environmental surveillance in 1992 show that the concentrations of all radioactive and most chemical contaminants were below applicable standards.

Not Available

1993-05-01T23:59:59.000Z

18

Design review report FFTF interim storage cask  

SciTech Connect

Final Design Review Report for the FFTF Interim Storage Cask. The Interim Storage Cask (ISC) will be used for long term above ground dry storage of FFTF irradiated fuel in Core Component Containers (CCC)s. The CCC has been designed and will house assemblies that have been sodium washed in the IEM Cell. The Solid Waste Cask (SWC) will transfer a full CCC from the IEM Cell to the RSB Cask Loading Station where the ISC will be located to receive it. Once the loaded ISC has been sealed at the RSB Cask Loading Station, it will be transferred by facility crane to the DSWC Transporter. After the ISC has been transferred to the Interim Storage Area (ISA), which is yet to be designed, a mobile crane will be used to place the ISC in its final storage location.

Scott, P.L.

1995-01-03T23:59:59.000Z

19

Permitting plan for the high-level waste interim storage  

SciTech Connect

This document addresses the environmental permitting requirements for the transportation and interim storage of solidified high-level waste (HLW) produced during Phase 1 of the Hanford Site privatization effort. Solidified HLW consists of canisters containing vitrified HLW (glass) and containers that hold cesium separated during low-level waste pretreatment. The glass canisters and cesium containers will be transported to the Canister Storage Building (CSB) in a U.S. Department of Energy (DOE)-provided transportation cask via diesel-powered tractor trailer. Tri-Party Agreement (TPA) Milestone M-90 establishes a new major milestone, and associated interim milestones and target dates, governing acquisition and/or modification of facilities necessary for: (1) interim storage of Tank Waste Remediation Systems (TWRS) immobilized HLW (IHLW) and other canistered high-level waste forms; and (2) interim storage and disposal of TWRS immobilized low-activity tank waste (ILAW). An environmental requirements checklist and narrative was developed to identify the permitting path forward for the HLW interim storage (HLWIS) project (See Appendix B). This permitting plan will follow the permitting logic developed in that checklist.

Deffenbaugh, M.L.

1997-04-23T23:59:59.000Z

20

Realization of the German Concept for Interim Storage of Spent Nuclear Fuel - Current Situation and Prospects  

SciTech Connect

The German government has determined a phase out of nuclear power. With respect to the management of spent fuel it was decided to terminate transports to reprocessing plants by 2005 and to set up interim storage facilities on power plant sites. This paper gives an overview of the German concept for spent fuel management focused on the new on-site interim storage concept and the applied interim storage facilities. Since the end of the year 1998, the utilities have applied for permission of on-site interim storage in 13 storage facilities and 5 storage areas; one application for the interim storage facility Stade was withdrawn due to the planned final shut down of Stade nuclear power plant in autumn 2003. In 2001 and 2002, 3 on-site storage areas and 2 on-site storage facilities for spent fuel were licensed by the Federal Office for Radiation Protection (BfS). A main task in 2002 and 2003 has been the examination of the safety and security of the planned interim storage facilities and the verification of the licensing prerequisites. In the aftermath of September 11, 2001, BfS has also examined the attack with a big passenger airplane. Up to now, these aircraft crash analyses have been performed for three on-site interim storage facilities; the fundamental results will be presented. It is the objective of BfS to conclude the licensing procedures for the applied on-site interim storage facilities in 2003. With an assumed construction period for the storage buildings of about two years, the on-site interim storage facilities could then be available in the year 2005.

Thomauske, B. R.

2003-02-25T23:59:59.000Z

Note: This page contains sample records for the topic "interim storage site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Burn site groundwater interim measures work plan.  

SciTech Connect

This Work Plan identifies and outlines interim measures to address nitrate contamination in groundwater at the Burn Site, Sandia National Laboratories/New Mexico. The New Mexico Environment Department has required implementation of interim measures for nitrate-contaminated groundwater at the Burn Site. The purpose of interim measures is to prevent human or environmental exposure to nitrate-contaminated groundwater originating from the Burn Site. This Work Plan details a summary of current information about the Burn Site, interim measures activities for stabilization, and project management responsibilities to accomplish this purpose.

Witt, Jonathan L. (North Wind, Inc., Idaho Falls, ID); Hall, Kevin A. (North Wind, Inc., Idaho Falls, ID)

2005-05-01T23:59:59.000Z

22

Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)  

SciTech Connect

The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis.

Burgard, K.C.

1998-04-09T23:59:59.000Z

23

Design report for the interim waste containment facility at the Niagara Falls Storage Site. [Surplus Facilities Management Program  

SciTech Connect

Low-level radioactive residues from pitchblende processing and thorium- and radium-contaminated sand, soil, and building rubble are presently stored at the Niagara Falls Storage Site (NFSS) in Lewiston, New York. These residues and wastes derive from past NFSS operations and from similar operations at other sites in the United States conducted during the 1940s by the Manhattan Engineer District (MED) and subsequently by the Atomic Energy Commission (AEC). The US Department of Energy (DOE), successor to MED/AEC, is conducting remedial action at the NFSS under two programs: on-site work under the Surplus Facilities Managemnt Program and off-site cleanup of vicinity properties under the Formerly Utilized Sites Remedial Action Program. On-site remedial action consists of consolidating the residues and wastes within a designated waste containment area and constructing a waste containment facility to prevent contaminant migration. The service life of the system is 25 to 50 years. Near-term remedial action construction activities will not jeopardize or preclude implementation of any other remedial action alternative at a later date. Should DOE decide to extend the service life of the system, the waste containment area would be upgraded to provide a minimum service life of 200 years. This report describes the design for the containment system. Pertinent information on site geology and hydrology and on regional seismicity and meteorology is also provided. Engineering calculations and validated computer modeling studies based on site-specific and conservative parameters confirm the adequacy of the design for its intended purposes of waste containment and environmental protection.

Not Available

1986-05-01T23:59:59.000Z

24

Interim Storage of Hanford Spent Fuel & Associated Sludge  

SciTech Connect

The Hanford site is currently dealing with a number of types of Spent Nuclear Fuel. The route to interim dry storage for the various fuel types branches along two different paths. Fuel types such as metallic N reactor fuel and Shippingport Core 2 Blanket assemblies are being placed in approximately 4 m long canisters which are then stored in tubes below grade in a new canister storage building. Other fuels such as TRIGA{trademark} and Light Water Reactor fuel will be relocated and stored in stand-alone casks on a concrete pad. Varying degrees of sophistication are being applied with respect to the drying and/or evacuation of the fuel interim storage canisters depending on the reactivity of the fuel, the degree of damaged fuel and the previous storage environment. The characterization of sludge from the Hanford K Basins is nearly complete and canisters are being designed to store the sludge (including uranium particles from fuel element cleaning) on an interim basis.

MAKENAS, B.J.

2002-07-01T23:59:59.000Z

25

US PRACTICE FOR INTERIM WET STORAGE OF RRSNF  

SciTech Connect

Aluminum research reactor spent nuclear fuel is currently being stored or is anticipated to be returned to the United States and stored at Department of Energy storage facilities at the Savannah River Site and the Idaho Nuclear Technology and Engineering Center. This paper summarizes the current practices to provide for continued safe interim wet storage in the U.S. Aluminum fuel stored in poor quality water is subject to aggressive corrosion attack and therefore water chemistry control systems are essential to maintain water quality. Fuel with minor breaches are safely stored directly in the basin. Fuel pieces and heavily damaged fuel is safely stored in isolation canisters.

Vinson, D.

2010-08-05T23:59:59.000Z

26

Report to Congress on Plan for Interim Storage of Spent Nuclear...  

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

Report to Congress on Plan for Interim Storage of Spent Nuclear Fuel from Decommissioned Reactors Report to Congress on Plan for Interim Storage of Spent Nuclear Fuel from...

27

Report to Congress on Plan for Interim Storage of Spent Nuclear Fuel from Decommissioned Reactors  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

6 6 Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel from Decommissioned Nuclear Power Reactor Sites December 2008 U.S. Department of Energy Office of Civilian Radioactive Waste Management Washington, D.C. Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel The picture on the cover is the Connecticut Yankee Independent Spent Fuel Storage Installation site in Haddam, Connecticut, with 43 dry storage NRC-licensed dual-purpose (storage and transport) casks. ii Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel EXECUTIVE SUMMARY The House Appropriations Committee Print that accompanied the Consolidated Appropriations Act, 2008, requests that the U.S. Department of Energy (the Department):

28

N Reactor Placed In Interim Safe Storage: Largest Hanford Reactor Cocooning  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

N Reactor Placed In Interim Safe Storage: Largest Hanford Reactor N Reactor Placed In Interim Safe Storage: Largest Hanford Reactor Cocooning Project Now Complete N Reactor Placed In Interim Safe Storage: Largest Hanford Reactor Cocooning Project Now Complete June 14, 2012 - 12:00pm Addthis Media Contacts Cameron Hardy Cameron.Hardy@rl.doe.gov 509-376-5365 Mark McKenna mmckenna@wch-rcc.com 509-372-9032 RICHLAND, WASH. - The U.S. Department of Energy's (DOE's) River Corridor contractor, Washington Closure Hanford, has completed placing N Reactor in interim safe storage, a process also known as "cocooning." N Reactor was the last of nine plutonium production reactors to be shut down at DOE's Hanford Site in southeastern Washington state. It was Hanford's longest-running reactor, operating from 1963 to 1987. "In the 1960's, N Reactor represented the future of energy in America.

29

Final Environmental Impact Statement Safe Interim Storage Of Hanford Tank Wastes  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

1995/01eis0212_cl.html[6/27/2011 1:02:59 PM] 1995/01eis0212_cl.html[6/27/2011 1:02:59 PM] Final Environmental Impact Statement Safe Interim Storage Of Hanford Tank Wastes DOE/EIS-0212 VOLUME 1 OF 2 VOLUME 1 FINAL ENVIRONMENTAL IMPACT STATEMENT SAFE INTERIM STORAGE OF HANFORD TANK WASTES Hanford Site Richland, Washington October, 1995 WASHINGTON STATE DEPARTMENT OF ECOLOGY NUCLEAR WASTE PROGRAM LACEY, WASHINGTON 98503 U.S. DEPARTMENT OF ENERGY RICHLAND OPERATIONS OFFICE

30

Safety of interim storage solutions of used nuclear fuel during extended term  

SciTech Connect

In 2013, the total amount of stored used nuclear fuel (UNF) in the world will reach 225,000 T HM. The UNF inventory in wet storage will take up over 80% of the available total spent fuel pool (SFP) capacity. Interim storage solutions are needed. They give flexibility to the nuclear operators and ensure that nuclear reactors continue to operate. However, we need to keep in mind that they are also an easy way to differ final decision and implementation of a UNF management approach (recycling or final disposal). In term of public perception, they can have a negative impact overtime as it may appear that nuclear industry may have significant issues to resolve. In countries lacking an integrated UNF management approach, the UNF are being discharged from the SFPs to interim storage (mostly to dry storage) at the same rate as UNF is being discharged from reactors, as the SFPs at the reactor sites are becoming full. This is now the case in USA, Taiwan, Switzerland, Spain, South Africa and Germany. For interim storage, AREVA has developed different solutions in order to allow the continued operation of reactors while meeting the current requirements of Safety Authorities: -) Dry storage canisters on pads, -) Dual-purpose casks (dry storage and transportation), -) Vault dry storage, and -) Centralized pool storage.

Shelton, C.; Bader, S.; Issard, H.; Arslan, M. [AREVA, 7135 Minstrel Way, Suite 300 Columbia, MD 21045 (United States)

2013-07-01T23:59:59.000Z

31

Engineering evaluation/cost analysis-environmental assessment for the proposed decontamination of properties in the vicinity of the Hazelwood Interim Storage Site, Hazelwood, Missouri. Revision 1  

SciTech Connect

The US Department of Energy (DOE), under its Formerly Utilized Sites Remedial Action Program (FUSRAP), is implementing a cleanup program for three groups of properties in the St. Louis, Missouri, area. None of the properties is owned by DOE, but each property contains radioactive residues from federal uranium-processing activities conducted at the SLDS during and after World War II. This engineering evaluation/cost analysis (EE/CA) report has been prepared to support the interim cleanup measures for the contaminated properties in the Hazelwood and Berkeley, Missouri area. The near-term cleanup measures that may be necessary at the vicinity properties are evaluated in the main body of this report. Because of the range of active land uses in the Hazelwood and Berkeley areas and because of the extent of contamination on public and private properties, the potential exists for disturbance and spreading of soil contamination. Specifically, implementation of the proposed action would allow DOE to remove, transport, and safely store contaminated soils from properties where other activities (not involving DOE) are likely to result in either spreading contamination or otherwise complicating ultimate cleanup measures.

Picel, M.H.; Peterson, J.M. [Argonne National Lab., IL (United States). Environmental Assessment and Information Sciences Div.; Williams, M.J. [Bechtel National, Inc., Oak Ridge, TN (United States)

1992-03-01T23:59:59.000Z

32

Engineering evaluation/cost analysis for the proposed decontamination of properties in the vicinity of the Hazelwood Interim Storage Site, Hazelwood, Missouri -- environment assessment  

SciTech Connect

The US Department of Energy (DOE), under its Formerly Utilized Sites Remedial Action Program (FUSRAP), is implementing a cleanup program for three groups of properties in the St. Louis, Missouri, area. None of the properties is owned by DOE, but each property contains radioactive residues from federal uranium-processing activities conducted at the SLDS during and after World War II. This engineering evaluation/cost analysis (EE/CA) report has been prepared to support the interim cleanup measures for the contaminated properties in the Hazelwood and Berkeley, Missouri area. The near-term cleanup measures that may be necessary at the vicinity properties are evaluated in the main body of this report. Because of the range of active land uses in the Hazelwood and Berkeley areas and because of the extent of contamination on public and private properties, the potential exists for disturbance and spreading of soil contamination. Specifically, implementation of the proposed action would allow DOE to remove, transport, and safely store contaminated soils from properties where other activities (not involving DOE) are likely to result in either spreading contamination or otherwise complicating ultimate cleanup measures. 25 refs., 4 figs., 6 tabs.

Picel, M.H.; Peterson, J.M. (Argonne National Lab., IL (USA). Environmental Assessment and Information Sciences Div.); Williams, M.J. (Bechtel National, Inc., Oak Ridge, TN (USA))

1991-05-01T23:59:59.000Z

33

Engineering evaluation/cost analysis-environmental assessment for the proposed decontamination of properties in the vicinity of the Hazelwood Interim Storage Site, Hazelwood, Missouri  

SciTech Connect

The US Department of Energy (DOE), under its Formerly Utilized Sites Remedial Action Program (FUSRAP), is implementing a cleanup program for three groups of properties in the St. Louis, Missouri, area. None of the properties is owned by DOE, but each property contains radioactive residues from federal uranium-processing activities conducted at the SLDS during and after World War II. This engineering evaluation/cost analysis (EE/CA) report has been prepared to support the interim cleanup measures for the contaminated properties in the Hazelwood and Berkeley, Missouri area. The near-term cleanup measures that may be necessary at the vicinity properties are evaluated in the main body of this report. Because of the range of active land uses in the Hazelwood and Berkeley areas and because of the extent of contamination on public and private properties, the potential exists for disturbance and spreading of soil contamination. Specifically, implementation of the proposed action would allow DOE to remove, transport, and safely store contaminated soils from properties where other activities (not involving DOE) are likely to result in either spreading contamination or otherwise complicating ultimate cleanup measures.

Picel, M.H.; Peterson, J.M. (Argonne National Lab., IL (United States). Environmental Assessment and Information Sciences Div.); Williams, M.J. (Bechtel National, Inc., Oak Ridge, TN (United States))

1992-03-01T23:59:59.000Z

34

Interim Storage of Plutonium in Existing Facilities  

SciTech Connect

'In this era of nuclear weapons disarmament and nonproliferation treaties, among many problems being faced by the Department of Energy is the safe disposal of plutonium. There is a large stockpile of plutonium at the Rocky Flats Environmental Technology Center and it remains politically and environmentally strategic to relocate the inventory closer to a processing facility. Savannah River Site has been chosen as the final storage location, and the Actinide Packaging and Storage Facility (APSF) is currently under construction for this purpose. With the ability of APSF to receive Rocky Flats material an estimated ten years away, DOE has decided to use the existing reactor building in K-Area of SRS as temporary storage to accelerate the removal of plutonium from Rocky Flats. There are enormous cost savings to the government that serve as incentive to start this removal as soon as possible, and the KAMS project is scheduled to receive the first shipment of plutonium in January 2000. The reactor building in K-Area was chosen for its hardened structure and upgraded seismic qualification, both resulting from an effort to restart the reactor in 1991. The KAMS project has faced unique challenges from Authorization Basis and Safety Analysis perspectives. Although modifying a reactor building from a production facility to a storage shelter is not technically difficult, the nature of plutonium has caused design and safety analysis engineers to make certain that the design of systems, structures and components included will protect the public, SRS workers, and the environment. A basic overview of the KAMS project follows. Plutonium will be measured and loaded into DOT Type-B shipping packages at Rocky Flats. The packages are 35-gallon stainless steel drums with multiple internal containment boundaries. DOE transportation vehicles will be used to ship the drums to the KAMS facility at SRS. They will then be unloaded, stacked and stored in specific locations throughout the reactor building. The storage life is projected to be ten years to allow the preparation of APSF. DOE has stipulated that there be no credible release during storage, since there are no design features in place to mitigate a release of plutonium (i.e. HEPA filters, facility containment boundaries, etc.). This mandate has presented most of the significant challenges to the safety analysis team. The shipping packages are designed to withstand certain accidents and conditions, but in order to take credit for these the storage environment must be strictly controlled. Damages to the packages from exposure to fire, dropping, crushing and other impact accidents have been analyzed, and appropriate preventative design features have been incorporated. Other efforts include the extension of the shipping life (roughly two years) to a suitable storage life of ten years. These issues include the effects of internal pressure increases, seal degradation and the presence of impurities. A process known as the Container Qualification Program has been conducted to address these issues. The KAMS project will be ready to receive the first shipment from Rocky Flats in January 2000. No credible design basis scenarios resulting in the release of plutonium exist. This work has been useful in the effort to provide a safer disposition of plutonium, but also the lessons learned and techniques established by the team will help with the analysis of future facility modifications.'

Woodsmall, T.D.

1999-05-10T23:59:59.000Z

35

The Time Needed to Implement the Blue Ribbon Commission Recommendation on Interim Storage - 13124  

SciTech Connect

The report of the Blue Ribbon Commission on America's Nuclear Future [1] makes a number of important recommendations to be considered if Congress elects to redirect U.S. high-level radioactive waste disposal policy. Setting aside for the purposes of this discussion any issues related to political forces leading to stopping progress on the Yucca Mountain project and driving the creation of the Commission, an important recommendation of the Commission was to institute prompt efforts to develop one or more consolidated storage facilities. The Blue Ribbon Commission noted that this recommended strategy for future storage and disposal facilities and operations should be implemented regardless of what happens with Yucca Mountain. It is too easy, however, to focus on interim storage as an alternative to geologic disposal. The Blue Ribbon Commission report does not go far enough in addressing the magnitude of the contentious problems associated with reopening the issues of relative authorities of the states and federal government with which Congress wrestled in crafting the Nuclear Waste Policy Act [2]. The Blue Ribbon Commission recommendation for prompt adoption of an interim storage program does not appear to be fully informed about the actions that must be taken, the relative cost of the effort, or the realistic time line that would be involved. In essence, the recommendation leaves to others the details of the systems engineering analyses needed to understand the nature and details of all the operations required to reach an operational interim storage facility without derailing forever the true end goal of geologic disposal. The material presented identifies a number of impediments that must be overcome before the country could develop a centralized federal interim storage facility. In summary, and in the order presented, they are: 1. Change the law, HJR 87, PL 107-200, designating Yucca Mountain for the development of a repository. 2. Bring new nuclear waste legislation to the floor of the Senate, overcoming existing House support for Yucca Mountain; 3. Change the longstanding focus of Congress from disposal to storage; 4. Change the funding concepts embodied in the Nuclear Waste Policy Act to allow the Nuclear Waste fund to be used to pay for interim storage; 5. Reverse the Congressional policy not to give states or tribes veto or consent authority, and to reserve to Congress the authority to override a state or tribal disapproval; 6. Promulgate interim storage facility siting regulations to reflect the new policies after such changes to policy and law; 7. Complete already underway changes to storage and transportation regulations, possibly incorporating changes to reflect changes to waste disposal law; 8. Promulgate new repository siting regulations if the interim storage facility is to support repository development; 9. Identify volunteer sites, negotiate agreements, and get Congressional approval for negotiated benefits packages; 10. Design, License and develop the interim storage facility. The time required to accomplish these ten items depends on many factors. The estimate developed assumes that certain of the items must be completed before other items are started; given past criticisms of the current program, such an assumption appears appropriate. Estimated times for completion of individual items are based on historical precedent. (authors)

Voegele, Michael D. [Consultant, Nye County Nuclear Waste Repository Project Office, 7404 Oak Grove Ave, Las Vegas, NV 89117 (United States)] [Consultant, Nye County Nuclear Waste Repository Project Office, 7404 Oak Grove Ave, Las Vegas, NV 89117 (United States); Vieth, Donald [1154 Chelttenham Place, Maineville, OH 45039 (United States)] [1154 Chelttenham Place, Maineville, OH 45039 (United States)

2013-07-01T23:59:59.000Z

36

Method of preparing nuclear wastes for tansportation and interim storage  

DOE Patents (OSTI)

Nuclear waste is formed into a substantially water-insoluble solid for temporary storage and transportation by mixing the calcined waste with at least 10 weight percent powdered anhydrous sodium silicate to form a mixture and subjecting the mixture to a high humidity environment for a period of time sufficient to form cementitious bonds by chemical reaction. The method is suitable for preparing an interim waste form from dried high level radioactive wastes.

Bandyopadhyay, Gautam (Naperville, IL); Galvin, Thomas M. (Darien, IL)

1984-01-01T23:59:59.000Z

37

Interim storage of recyclable materials. Final report  

SciTech Connect

The purpose of this study was to investigate long-term, economical, outdoor storage of a variety of postconsumer recyclable materials. Field investigations and laboratory analysis were performed to examine how protected and unprotected storage would affect marketability and product quality of baled plastics, papers, and other miscellaneous potentially recyclable materials. Baled materials were stored and evaluated over a period of approximately two years. Evaluation of the stored paper products was undertaken using handsheets to perform tests as published by the Technical Association of the Pulp and Paper Industry (TAPPI). A beater curve analysis of selected stored papers, a pilot-scale papermaking run on a Number 2 Fourdrinier Paper machine, and two microbial analysis of the paper materials were also undertaken. Plastic samples obtained from the field were evaluated for oxidation using an Infrared Spectrophotometer (IR), and a controlled `blackbox` IR study was completed. Liquid run-off from bales was analyzed on a quarterly basis. The authors` investigations show that inexpensive outdoor storage for some paper and plastic products is potentially viable as some postconsumer paper and plastic products can be stored outdoors for long periods of time, 300 days or more, without protection. Few potential negative environmental impacts of such storage were found.

NONE

1998-11-01T23:59:59.000Z

38

REACTOR REFUELING - INTERIM DECAY STORAGE (FFTF)  

SciTech Connect

The IDS facility is located between the CLEM rails and within the FFTF containment building. It is located in a rectangular steel-lined concrete cell which lies entirely below the 550 ft floor level with the top flush with the 550 ft floor level. The BLTC rails within containment traverse the IDS cover (H-4-38001). The facility consists of a rotatable storage basket submerged in liquid sodium which is contained in a stainless steel tank. The storage positions within the basket are arranged so that it is not physically possible to achieve a critical array. The primary vessel is enclosed in a secondary guard tank of such size and arrangement that, should a leak develop in the primary tank, the sodium level would not fall below the top of the fueled section of the stored core components or test assemblies. The atmosphere outside the primary vessel, but within the concrete cell, is nitrogen which also serves as a heat transfer medium to control the cell temperature. To provide space for the storage of test assemblies such as the OTA and CLIRA, 10 storage tubes (each approximately 43-1/4 ft long) are included near the center of the basket. This arrangement requires that the center of the primary vessel be quite deep. In this region, the primary vessel extends downward to elevation 501 ft 6 inches while the guard tank reaches 500 ft 4 inches. The floor of the cell is at 499 ft a inches which is 51 ft below the operating room floor. Storage positions are provided for 112 core components in the upper section of the storage basket. These positions are arranged in four circles, all of which are concentric with the test element array and the storage basket. The primary vessel and the guard tank are shaped to provide the necessary space with a minimum of excess volume. Both these vessels have a relatively small cylindrical lower section connected to a larger upper cylinder by a conical transition. The primary vessel is supported from a top flange by a vessel support structure. The guard tank is supported by a skirt which rests on a ledge at elevation 527 ft 2 inches. The skirt is an extension of the upper cylinder of the guard tank. The storage basket is supported by a gear-driven, mechanically indexed, ball bearing that rests on the bearing support, which in turn rests on the vessel support structure. The interior of the primary vessel above the sodium level is blanketed with argon at 6 inches of water gage pressure. The vessel is designed to allow the pressure to be increased to 3 psig to assist drainage of the sodium from the vessel. The structure which supports the primary vessel also serves as the cover to the IDS cell. The support structure rests on a shelf cast into the cell wall at the 544 ft 6 inch level. In addition to supporting the primary vessel and the storage basket bearing, this structure also provides support for the top shield which is a 16 inch thick by 15 ft 10 inch diameter laminated steel assembly, which in turn supports the impact absorber neutron shield, and the BLTC tracks where they cross the IDS. Storage position access ports are provided on the centerline of the IDS facility between the BLTC rails. Basket rotation and indexing allows any storage position to be located in alignment with its proper access port. Double buffered seals are provided for the removable plugs and removable lids for all components and access ports where necessary to seal between the vessel cover gas and the FFTF containment atmosphere. Buffering gas for these seals is argon. Capability of a 10 cfm argon purge rate is provided although normal argon flow into the cover gas cavity will be less than 1 cfm. Argon cover gas exits through a vapor trap located in the southwest corner of the support structure and then to the Cell Atmosphere Processing System. Vessel overpressure protection is provided by rupture discs on the inlet and outlet argon piping. Rupture discs vent to the IDS cell. Biological shielding is provided to maintain the radiation contribution in the operating area below 0.2 mrem/h. The primary gamma shield directly above

MCFADDEN NR; OMBERG RP

1990-06-18T23:59:59.000Z

39

Waste Encapsulation and Storage Facility (WESF) Interim Status Closure Plan  

SciTech Connect

This document describes the planned activities and performance standards for closing the Waste Encapsulation and Storage Facility (WESF). WESF is located within the 225B Facility in the 200 East Area on the Hanford Facility. Although this document is prepared based on Title 40 Code of Federal Regulations (CFR), Part 265, Subpart G requirements, closure of the storage unit will comply with Washington Administrative Code (WAC) 173-303-610 regulations pursuant to Section 5.3 of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Action Plan (Ecology et al. 1996). Because the intention is to clean close WESF, postclosure activities are not applicable to this interim status closure plan. To clean close the storage unit, it will be demonstrated that dangerous waste has not been left onsite at levels above the closure performance standard for removal and decontamination. If it is determined that clean closure is not possible or environmentally is impracticable, the interim status closure plan will be modified to address required postclosure activities. WESF stores cesium and strontium encapsulated salts. The encapsulated salts are stored in the pool cells or process cells located within 225B Facility. The dangerous waste is contained within a double containment system to preclude spills to the environment. In the unlikely event that a waste spill does occur outside the capsules, operating methods and administrative controls require that waste spills be cleaned up promptly and completely, and a notation made in the operating record. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge.

SIMMONS, F.M.

2000-12-01T23:59:59.000Z

40

Vermont Yankee experience with interim storage of low level radioactive waste in concrete modules  

SciTech Connect

This paper discusses the implementation of interim storage of low level radioactive waste using concrete modules at the Vermont Yankee Nuclear Power Station in Vernon, Vermont. Under the threat of possible loss of disposal capability in 1986, Vermont Yankee first considered the on-site storage option in 1985. prior to settling on a design, an investigation and economic analysis was performed of several designs. Modular concrete storage on a gravel pad was chosen as the most economical and the one providing the greatest flexibility. The engineering work, safety analysis, and pad construction were completed in 1985. Because of the passage of the Low Level Radioactive Waste Policy amendments Act in 1985, the loss of disposal capability did not occur in 1986. However, because the State of Vermont failed to meet the milestones of the Amendments Act, Vermont Yankee was restricted from the existing disposal sites on January 31, 1989. As a result, modules were purchased and waste was stored on site from 1989 until 1991. In 1991, the State of Vermont came back into compliance with the Amendments Act, and all waste stored on-site was shipped for burial. During the storage period 2 types of modules (1 box type and 1 cylinder type) were used. Lessons were learned, and changes were made to better control the off-site dose contribution of the waste. Recommendations are made to enhance the usability of the facility, such s lighting power, phones, etc. A shortcoming of the module storage concept is the inability to move waste during inclement weather. Despite this, the modules have provided an economical, technically sound, method of waste storage. The storage pad has not been used since 1991, but work is under way to review, and update as necessary, the safety analysis and procedures in preparation for reuse of the on-site storage facility after June 30, 1994.

Berger, S.; Weyman, D. [Vermont Yankee Nuclear Power Corporation, Vernon, VT (United States)

1995-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "interim storage site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Monticello Mill Tailings Site Operable Unit Ill Interim Remedial Action  

Office of Legacy Management (LM)

Site Site Operable Unit Ill Interim Remedial Action Mark Perfxmed Under DOE Contrici No. DE-AC13-96CJ873.35 for th3 U.S. De[:ar!menf of Energy app~oveJioi'ptiL#ic re1ease;dCinWlionis Unlimilra' This page intentionally left blank Monticello Mill Tailings Site Operable Unit I11 Interim Remedial Action Annual Status Report August 1999 Prepared for U.S. Department of Energy Albuquerque Operations Office Grand Junction Office Project Number MSG-035-0011-00-000 Document Number Q0017700 Work Performed Under DOE Contract Number DE-AC13-96GJ87335 Task Order Number MAC99-03 This page intentionally blank Document Number Q0017700 Acronyms Contents Page ACRONYMS .............................................................................................................................. V

42

Benchmarking of MCNP for calculating dose rates at an interim storage facility for nuclear waste  

Science Journals Connector (OSTI)

......an interim storage facility for nuclear waste Burkhard Heuel-Fabianek Ralf...Research Centre Julich, Germany, nuclear waste is stored in drums and other vessels...Research Centre Julich (FZJ) nuclear waste is generated, which has to be......

Burkhard Heuel-Fabianek; Ralf Hille

2005-12-20T23:59:59.000Z

43

NIAGARA FALLS STORAGE SITE  

Office of Legacy Management (LM)

:i" :i" _,, ' _~" ORISE 95/C-70 :E : i:; :' l,J : i.: RADIOLOGICAL SURVEY Op BUILDINGS 401, ' 403, AND ' m HITTMAN BUILDING $ <,' 2:. NIAGARA FALLS STORAGE SITE I .~~ ; " LEWISTON, ' NEW YORK : f? j:,:i I ,.J- ;b f" /: Li _e.*. ~,, I ,,~, ,:,,;:, Prepared by T. .I. Vitkus i,c Environmental Survey and Site Assessment Program Energy/Environment Systems Division ;>::; Oak Ridge Institute for Science and Education .,:, "Oak Ridge, Temressee 37831-0117 .F P ., ? :_ &,d ,,,, ;<:x,, Prepared for the 3 I. Office of Environmental Restoration I, U.S. Department of Energy i gy i. ~: ,,, "! ? ' :' : "' ,//, FINAL REPORT ".$ :,a ,,, MARCH 1995 ; m L ,, ,, ,,,. ., ,,. ' 1 jq ,Ij:,., .,~ _,I_ 1 This report is based on work performed under contract number DE-AC05-760R00033 with the

44

Interim storage of dismantled nuclear weapon components at the U.S. Department of Energy Pantex Plant  

SciTech Connect

Following the events of 1989 and the subsequent cessation of production of new nuclear weapons by the US, the mission of the Department of Energy (DOE) Nuclear Weapons Complex has shifted from production to dismantlement of retired weapons. The sole site in the US for accomplishing the dismantlement mission is the DOE Pantex Plant near Amarillo, Texas. Pending a national decision on the ultimate storage and disposition of nuclear components form the dismantled weapons, the storage magazines within the Pantex Plant are serving as the interim storage site for pits--the weapon plutonium-bearing component. The DOE has stipulated that Pantex will provide storage for up to 12,000 pits pending a Record of Decision on a comprehensive site-wide Environmental Impact Statement in November 1996.

Guidice, S.J.; Inlow, R.O. [USDOE Albuquerque Operations Office, NM (United States)

1995-12-31T23:59:59.000Z

45

Final Environmental Impact Statement Safe Interim Storage Of...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

transfer actions can contribute to the interim stabilization of older single-shell tanks to help reduce the risk of leaks from those tanks. Many of the single-shell tanks have...

46

1987 Federal interim storage fee study: A technical and economic analysis  

SciTech Connect

This document is the latest in a series of reports that are published annually by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE). This information in the report, which was prepared by E.R. Johnson Associates under subcontract to PNL, will be used by the DOE to establish a payment schedule for interim storage of spent nuclear fuel under the Federal Interim Storage (FIS) Program, which was mandated by the Nuclear Waste Policy Act of 1982. The information in this report will be used to establish the schedule of charges for FIS services for the year commencing January 1, 1988. 13 tabs.

Not Available

1987-09-01T23:59:59.000Z

47

1988 Federal Interim Storage Fee study: A technical and economic analysis  

SciTech Connect

This document is the latest in a series of reports that are published annually by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE). The information in this report, which was prepared by E.R. Johnson Associates, Inc., under subcontract to PNL, will be used by the DOE to establish a payment schedule for interim storage of spent nuclear fuel under the Federal Interim Storage (FIS) Program. The FIS Program was mandated by the Nuclear Waste Policy Act of 1982. The information will be used to establish the schedule of charges for FIS services for the year commencing January 1, 1989. 13 refs.

Not Available

1988-11-01T23:59:59.000Z

48

Interim UFD Storage and Transportation - Transportation Working Group Report  

SciTech Connect

The Used Fuel Disposition (UFD) Transportation Task commenced in October 2010. As its first task, Pacific Northwest National Laboratory (PNNL) compiled a draft list of structures, systems, and components (SSCs) of transportation systems and their possible degradation mechanisms during very long term storage (VLTS). The list of SSCs and the associated degradation mechanisms [known as features, events, and processes (FEPs)] were based on the list of SSCs and degradation mechanisms developed by the UFD Storage Task (Stockman et al. 2010)

Maheras, Steven J.; Ross, Steven B.

2011-03-30T23:59:59.000Z

49

ST. LOUIS AIRPORT/ HAZELWOOD INTERIM  

E-Print Network (OSTI)

International Airport County: St. Louis County Other Names: Hazelwood Interim Storage & Vicinity, Latty Avenue radioactively-contaminated sites are part of the Formerly Utilized Sites Remedial Action Program (FUSRAP the Formerly Utilized Site Remedial Action Program (FUSRAP). Site information and updates #12;can be found

50

RH-TRU Waste Shipments from Battelle Columbus Laboratories to the Hanford Nuclear Facility for Interim Storage  

SciTech Connect

Battelle Columbus Laboratories (BCL), located in Columbus, Ohio, must complete decontamination and decommissioning (D&D) activities for nuclear research buildings and grounds by 2006, as directed by Congress. Most of the resulting waste (approximately 27 cubic meters [m3]) is remote-handled (RH) transuranic (TRU) waste destined for disposal at the Waste Isolation Pilot Plant (WIPP). The BCL, under a contract to the U.S. Department of Energy (DOE) Ohio Field Office, has initiated a plan to ship the TRU waste to the DOE Hanford Nuclear Facility (Hanford) for interim storage pending the authorization of WIPP for the permanent disposal of RH-TRU waste. The first of the BCL RH-TRU waste shipments was successfully completed on December 18, 2002. This BCL shipment of one fully loaded 10-160B Cask was the first shipment of RH-TRU waste in several years. Its successful completion required a complex effort entailing coordination between different contractors and federal agencies to establish necessary supporting agreements. This paper discusses the agreements and funding mechanisms used in support of the BCL shipments of TRU waste to Hanford for interim storage. In addition, this paper presents a summary of the efforts completed to demonstrate the effectiveness of the 10-160B Cask system. Lessons learned during this process are discussed and may be applicable to other TRU waste site shipment plans.

Eide, J.; Baillieul, T. A.; Biedscheid, J.; Forrester, T,; McMillan, B.; Shrader, T.; Richterich, L.

2003-02-26T23:59:59.000Z

51

ADDENDUM TO ACTION DESCRIPTION MEMORANDUM NIAGARA FALLS STORAGE SITE  

Office of Legacy Management (LM)

ADDENDUM TO ADDENDUM TO ACTION DESCRIPTION MEMORANDUM NIAGARA FALLS STORAGE SITE PROPOSED INTERIM REMEDIAL ACTIONS FOR FY 1983-85 ACCELERATED PROGRAM (1984 VICINITY PROPERTIES CLEANUP) Prepared by Environmental Research Division Argonne National Laboratory Argonne, Illinois July 1984 Prepared for U.S. Department of Energy Oak Ridge Operations Technical Services Division Oak Ridge, Tennessee CONTENTS Page SUMMARY OF PROPOSED ACTION AND RELATED ACTIVITIES ........... 1 HISTORY AND ENVIRONMENTAL SETTING ........................ 4 RADIOLOGICAL CONTAMINATION AND NEED FOR PROPOSED ACTION ........ 4 Property A .. . . . . . . . . . . . . . . . .. . . . . . . 6 Property C' . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 Property H ...... ............. ... 7 Property H' . . . . . . . . . . . . . . . . . . .. . . . . . . . . 7 Property L ..... ...... .

52

The public response to Monitored Retrievable Storage: An interim report  

SciTech Connect

This report describes public opinion concerning the proposed monitored retrievable storage facility to be located in the vicinity of Oak Ridge, Tennessee. The majority of individuals who did express an opinion opposed the facility due to transport/safety concerns and environmental/health concerns. (CBS)

Not Available

1985-10-22T23:59:59.000Z

53

Interim Storage of RH-TRU 72B Canisters at the DOE Oak Ridge Reservation  

SciTech Connect

This paper describes an evaluation performed by the Department of Energy (DOE) Oak Ridge Operations (ORO) office for potential interim storage of remote-handled (RH) transuranic (TRU) 72B waste canisters at the Oak Ridge National Laboratory (ORNL). The evaluation included the conceptual design of a devoted canister storage facility and an assessment of the existing RHTRU waste storage facilities for storage of canisters. The concept for the devoted facility used modular concrete silos located on an above-grade storage pad. The assessment of the existing facilities considered the potential methods, facility modifications, and conceptual equipment that might be used for storage of 400 millisievert per hour (mSv/hr) canisters. The results of the evaluation indicated that the initial investment into a devoted facility was relatively high as compared to the certainty that significant storage capacity was necessary prior to the Waste Isolation Pilot Plant (WIPP) accepting RH-TRU waste for disposal. As an alternative, the use of individual concrete overpacks provided an incremental method that could be used with the existing storage facilities and outside storage pads. For the concrete overpack concepts considered, the cylindrical design stored in a vertical orientation was determined to be the most effective.

Forrester, T. W.; Hunt, R. A.; Riner, G. L.

2002-02-26T23:59:59.000Z

54

Northeast Site Non-Aqueous Phase Liquids Interim Measures Progress Report October through December 2002  

Office of Legacy Management (LM)

700 700 GJO-2003-411-TAC GJO-PIN 13.5.1-1 Pinellas Environmental Restoration Project Northeast Site Non-Aqueous Phase Liquids Interim Measures Progress Report October through December 2002 January 2003 Prepared by U.S. Department of Energy Grand Junction Office Grand Junction, Colorado Work Performed Under DOE Contract Number DE-AC13-02GJ79491 Task Order Number ST03-107 Document Number N0057700 Contents DOE/Grand Junction Office Northeast Site NAPL Interim Measures Progress Report January 2003 Page ii Contents Acronyms and Abbreviations ........................................................................................................ iii 1.0 Introduction ............................................................................................................................1

55

Technical Competencies for the Safe Interim Storage and Management of 233U at U.S. Department of Energy Facilities  

SciTech Connect

Uranium-233 (with concomitant {sup 232}U) is a man-made fissile isotope of uranium with unique nuclear characteristics which require high-integrity alpha containment biological shielding, and remote handling. The special handling considerations and the fact that much of the {sup 233}U processing and large-scale handling was performed over a decade ago underscore the importance of identifying the people within the DOE complex who are currently working with or have worked with {sup 233}U. The availability of these key personnel is important in ensuring safe interim storage, management and ultimate disposition of {sup 233}U at DOE facilities. Significant programs are ongoing at several DOE sites with actinides. The properties of these actinide materials require many of the same types of facilities and handling expertise as does {sup 233}U.

Campbell, D.O.; Krichinsky, A.M.; Laughlin, S.S.; Van Essen, D.C.; Yong, L.K.

1999-02-17T23:59:59.000Z

56

SPR Storage Sites | Department of Energy  

NLE Websites -- All DOE Office Websites (Extended Search)

SPR Storage Sites SPR Storage Sites SPR Storage Sites SPR Storage Sites graphic Emergency crude oil is stored in the Strategic Petroleum Reserve in salt caverns. Created deep within the massive salt deposits that underlie most of the Texas and Louisiana coastline, the caverns offer the best security and are the most affordable means of storage, costing up to 10 times less than aboveground tanks and 20 times less than hard rock mines. Storage locations along the Gulf Coast were selected because they provide the most flexible means for connecting to the Nation's commercial oil transport network. Strategic Reserve oil can be distributed through interstate pipelines to nearly half of the Nation's oil refineries or loaded into ships or barges for transport to other refineries.

57

Final environmental assessment and Finding-of-No-Significant-Impact - drum storage facility for interim storage of materials generated by environmental restoration operations  

SciTech Connect

The Department of Energy (DOE) has prepared an Environmental Assessment (EA), DOE/EA-0995, for the construction and operation of a drum storage facility at Rocky Flats Environmental Technology Site, Golden, Colorado. The proposal for construction of the facility was generated in response to current and anticipated future needs for interim storage of waste materials generated by environmental restoration operations. A public meeting was held on July 20, 1994, at which the scope and analyses of the EA were presented. The scope of the EA included evaluation of alternative methods of storage, including no action. A comment period from July 5, 1994 through August 4, 1994, was provided to the public and the State of Colorado to submit written comment on the EA. No written comments were received regarding this proposed action, therefore no comment response is included in the Final EA. Based on the analyses in the EA, DOE has determined that the proposed action would not significantly affect the quality of the human environment within the meaning of the National Environmental Policy Act of 1969 (NEPA). Therefore, preparation of an Environmental Impact Statement is not required and the Department is issuing this Finding of No Significant Impact.

Not Available

1994-09-01T23:59:59.000Z

58

EA-0995: Drum Storage Facility for Interim Storage of Materials Generated by Environmental Restoration Operations, Golden, Colorado  

Energy.gov (U.S. Department of Energy (DOE))

This EA evaluates the environmental impacts of the proposal to construct and operate a drum storage facility at the U.S. Department of Energy's Rocky Flats Environmental Technology Site in Golden,...

59

Northeast Site Non-Aqueous Phase Liquids Interim Measures Progress Report-January through March 2003  

Office of Legacy Management (LM)

4-TAC 4-TAC GJO-PIN 13.5.1-1 Pinellas Environmental Restoration Project January through March 2003 Northeast Site Non-Aqueous Phase Liquids Interim Measures Progress Report April 2003 Grand Junction Office U.S. Department of Energy Work Performed Under DOE Contract No. for the U.S. Department of Energy DE-AC13-02GJ79491 Approved for public release; distribution is unlimited. N0060900 GJO-2003-434-TAC GJO-PIN 13.5.1-1 Pinellas Environmental Restoration Project Northeast Site Non-Aqueous Phase Liquids Interim Measures Progress Report January through March 2003 April 2003 Prepared by U.S. Department of Energy Grand Junction Office Grand Junction, Colorado Work Performed Under DOE Contract Number DE-AC13-02GJ79491 Task Order Number ST03-107

60

Assessment of Stormflow and Water Quality from Undisturbed and Site Prepared Forest Land in East Texas (Interim Report)  

E-Print Network (OSTI)

TR- 117 1981 Assessment of Stormflow and Water Quality from Undisturbed and Site Prepared Forest Land in East Texas, Interim Report M.G. DeHaven W.H. Blackburn R.W. Knight A.T. Weichert...

DeHaven, M. G.; Blackburn, W. H.; Knight, R. W.; Weichert, A. T.

Note: This page contains sample records for the topic "interim storage site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

Interim reclamation report: Basalt Waste Isolation Project exploration shaft site  

SciTech Connect

In 1968, a program was started to assess the feasibility of storing Hanford Site defense waste in deep caverns constructed in basalt. This program was expanded in 1976 to include investigations of the Hanford Site as a potential location for a mined commercial nuclear waste repository. Extensive studies of the geotechnical aspects of the site were undertaken, including preparations for drilling a large diameter Exploratory Shaft. This report describes the development of the reclamation program for the Exploratory Shaft Facility, its implementation, and preliminary estimates of its success. The goal of the reclamation program is to return sites disturbed by the repository program as nearly as practicable to their original conditions using native plant species. 43 refs., 19 figs., 9 tabs.

Brandt, C.A.; Rickard, W.H. Jr.; Hefty, M.G.

1990-02-01T23:59:59.000Z

62

Department of Energy Plutonium ES&H Vulnerability Assessment Savannah River Site interim compensatory measures  

SciTech Connect

The Savannah River Site (SRS) has recently completed a self-assessment of potential vulnerabilities associated with plutonium and other transuranic materials stored at the site. An independent Working Group Assessment Team (WGAT) appointed by DOE/ES&H also performed an independent assessment, and reviewed and validated the site self-assessment. The purpose of this report is to provide a status of interim compensatory measures at SRS to address hazards in advance of any corrective actions. ES&H has requested this status for all vulnerabilities ranked medium or higher with respect to potential consequences to workers, environment, and the public.

Bickford, W.E.

1994-09-15T23:59:59.000Z

63

Site Visit Report, Hanford Waste Encapsulation Storage Facility...  

Energy Savers (EERE)

Site Visit Report, Hanford Waste Encapsulation Storage Facility - January 2011 Site Visit Report, Hanford Waste Encapsulation Storage Facility - January 2011 January 2011 Hanford...

64

EIS-0276: Rocky Flats Plutonium Storage, Golden, Colorado  

Energy.gov (U.S. Department of Energy (DOE))

This EIS analyzes DOE's proposed action to provide safe interim storage of approximately 10 metric tons of plutonium at the Rocky Flats Environmental Technology Site (RFETS).

65

DOE - Office of Legacy Management -- Niagara Falls Storage Site NY - NY 17  

Office of Legacy Management (LM)

Niagara Falls Storage Site NY - NY Niagara Falls Storage Site NY - NY 17 FUSRAP Considered Sites Niagara Falls Storage Site, NY Alternate Name(s): Lake Ontario Ordnance Works (LOOW) Niagara Falls Storage Site (NFSS) DOE-Niagara Falls Storage Site NY.17-1 NY.17-3 Location: Lewiston, New York NY.17-5 Historical Operations: Stored, shipped, and buried radioactive equipment and waste for MED and AEC containing uranium, radium, and thorium. Contains Interim Waste Containment Structure. NY.17-1 NY.17-2 NY.17-14 Eligibility Determination: Eligible NY.17-4 Radiological Survey(s): Assessment Surveys NY.17-3 NY.17-5 NY.17-6 NY.17-7 NY.17-8 NY.17-9 NY.17-10 NY.17-11 NY.17-12 NY.17-14 Site Status: Cleanup in progress by U.S. Army Corps of Engineers. NY.17-13 NY.17-14 NY.17-15 NY.17-16 USACE Website Long-term Care Requirements: To be determined upon completion.

66

INTERIM BARRIER AT HANFORDS TY FARM TO PROTECT GROUNDWATER AT THE HANFORD SITE WASHINGTON USA  

SciTech Connect

An innovative interim surface barrier was constructed as a demonstration project at the Hanford Site's TY Tank Farm. The purpose of the demonstration barrier is to stop rainwater and snowmelt from entering the soils within the tank farm and driving contamination from past leaks and spills toward the ground water. The interim barrier was constructed using a modified asphalt material with very low permeability developed by MatCon{reg_sign}. Approximately 2,400 cubic yards of fill material were added to the tank farm to create a sloped surface that will gravity drain precipitation to collection points where it will be routed through buried drain lines to an evapotranspiration basin adjacent to the farm. The evapotranspiration basin is a lined basin with a network of perforated drain lines covered with soil and planted with native grasses. The evapotranspiration concept was selected because it prevents the runoff from percolating into the soil column and also avoids potential monitoring and maintenance issues associated with standing water in a traditional evaporation pond. Because of issues associated with using standard excavation and earth moving equipment in the farm a number of alternate construction approaches were utilized to perform excavations and prepare the site for the modified asphalt.

PARKER DL; HOLM MJ; HENDERSON JC; LOBER RW

2011-01-13T23:59:59.000Z

67

Hanford Site  

NLE Websites -- All DOE Office Websites (Extended Search)

U Plant Equipment 183 KW Aerial 183 KW Aerial Interim Storage Building Demolition Interim Storage Building Demolition U Plant Condenser Relocation U Plant Condenser Relocation...

68

EIS-0283-S2: Interim Action Determination | Department of Energy  

NLE Websites -- All DOE Office Websites (Extended Search)

K-Area Materials Storage (KAMS) Area Expansion at the Savannah River Site) K-Area Materials Storage (KAMS) Area Expansion at the Savannah River Site) In order to meet the safe, secure storage demand for pit disassembly metals and non-pit plutonium that may be available soon after the SPD SEIS ROD, DOE has a need to initiate storage area construction preparations in advance of the SPD SEIS ROD. Specifically, beginning in May 2013, DOE plans to extend the KAMS Area into the current Final Storage Area and Presentation Room to store additional quantities of surplus plutonium, and, potentially, plutonium alloys. EIS-0283-S2-InterimActionDetermination_04_25_13.pdf More Documents & Publications EIS-0283-S2: Draft Supplemental Environmental Impact Statement EIS-0283-S2: Amended Interim Action Determination EIS-0283-S2: Interim Action Determination

69

Interim site characterization report and ground-water monitoring program for the Hanford site solid waste landfill  

SciTech Connect

Federal and state regulations governing the operation of landfills require utilization of ground-water monitoring systems to determine whether or not landfill operations impact ground water at the point of compliance (ground water beneath the perimeter of the facility). A detection-level ground-water monitoring system was designed, installed, and initiated at the Hanford Site Solid Waste Landfill (SWL). Chlorinated hydrocarbons were detected at the beginning of the ground-water monitoring program and continue to be detected more than 1 year later. The most probable source of the chlorinated hydrocarbons is washwater discharged to the SWL between 1985 and 1987. This is an interim report and includes data from the characterization work that was performed during well installation in 1987, such as field observations, sediment studies, and geophysical logging results, and data from analyses of ground-water samples collected in 1987 and 1988, such as field parameter measurements and chemical analyses. 38 refs., 27 figs., 8 tabs.

Fruland, R.M.; Hagan, R.A.; Cline, C.S.; Bates, D.J.; Evans, J.C.; Aaberg, R.L.

1989-07-01T23:59:59.000Z

70

Waste Encapsulation and Storage Facility (WESF) Basis for Interim Operation (BIO)  

SciTech Connect

The Waste Encapsulation and Storage Facility (WESF) is located in the 200 East Area adjacent to B Plant on the Hanford Site north of Richland, Washington. The current WESF mission is to receive and store the cesium and strontium capsules that were manufactured at WESF in a safe manner and in compliance with all applicable rules and regulations. The scope of WESF operations is currently limited to receipt, inspection, decontamination, storage, and surveillance of capsules in addition to facility maintenance activities. The capsules are expected to be stored at WESF until the year 2017, at which time they will have been transferred for ultimate disposition. The WESF facility was designed and constructed to process, encapsulate, and store the extracted long-lived radionuclides, {sup 90}Sr and {sup 137}Cs, from wastes generated during the chemical processing of defense fuel on the Hanford Site thus ensuring isolation of hazardous radioisotopes from the environment. The construction of WESF started in 1971 and was completed in 1973. Some of the {sup 137}Cs capsules were leased by private irradiators or transferred to other programs. All leased capsules have been returned to WESF. Capsules transferred to other programs will not be returned except for the seven powder and pellet Type W overpacks already stored at WESF.

COVEY, L.I.

2000-11-28T23:59:59.000Z

71

EIS-0220: Interim Management of Nuclear Materials at the Savannah River Site  

Energy.gov (U.S. Department of Energy (DOE))

This environmental impact statement assesses the potential environmental impacts of actions necessary to manage nuclear materials at the Savannah River Site (SRS) in Aiken, South Carolina, until decisions on their ultimate disposition are made and implemented. The Department of Energy has decided to initiate actions which will stabilize certain of the SRS materials that represent environment, safety and health vulnerabilities in their current storage condition or which may represent a vulnerability within the next 10 years.

72

DOE Issues Final Mercury Storage Environmental Impact Statement: Texas Site  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE Issues Final Mercury Storage Environmental Impact Statement: DOE Issues Final Mercury Storage Environmental Impact Statement: Texas Site Is Preferred for Long-Term Mercury Storage DOE Issues Final Mercury Storage Environmental Impact Statement: Texas Site Is Preferred for Long-Term Mercury Storage January 19, 2011 - 12:00pm Addthis Media Contact (202) 586-4940 WASHINGTON - The Department of Energy has prepared a Final Long-Term Management and Storage of Elemental Mercury Environmental Impact Statement to analyze the potential environmental, human health, and socioeconomic impacts of elemental mercury storage at seven locations. Based on these factors, DOE identified the Waste Control Specialists, LLC, site near Andrews, Texas, as the preferred alternative for long-term management and storage of mercury. DOE will consider the environmental impact information presented in this

73

DOE - Office of Legacy Management -- Niagara Falls Storage Site...  

Office of Legacy Management (LM)

of the Niagara Falls, New York, Storage Site NY.17-1 - AEC Memorandum; Malone to Smith; Subject: Monthly Progress Report for April; April 24, 1951. Attachment: Tonawanda...

74

Niagara Falls Storage Site, Annual site environmental report, Lewiston, New York, Calendar year 1986: Surplus Facilities Management Program (SFMP)  

SciTech Connect

During 1986, the environmental monitoring program was continued at the Niagara Falls Storage Site (NFSS), a US Department of Energy (DOE) surplus facility located in Niagara County, New York, presently used for the interim storage of radioactive residues and contaminated soils and rubble. The monitoring program is being conducted by Bechtel National, Inc. The monitoring program at the NFSS measures radon gas concentrations in air; external gamma radiation levels; and uranium and radium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard and to assess its potential effect on public health, the radiation dose was calculated for the maximally exposed individual. Based on the conservative scenario described in the report, this individual would receive an annual external exposure approximately equivalent to 6% of the DOE radiation protection standard of 100 mrem/yr. By comparison, the incremental dose received from living in a brick house versus a wooden house is 10 mrem/yr above background. The cumulative dose to the population within an 80-km (50-mi) radius of the NFSS that would result from radioactive materials present at the site would be indistinguishable from the dose that the same population would receive from naturally occurring radioactive sources. Results of the 1986 monitoring show that the NFSS is in compliance with the DOE radiation protection standard. 14 refs., 11 figs., 14 tabs.

Not Available

1987-06-01T23:59:59.000Z

75

Site Characterization of Promising Geologic Formations for CO2 Storage |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Site Characterization of Promising Geologic Formations for CO2 Site Characterization of Promising Geologic Formations for CO2 Storage Site Characterization of Promising Geologic Formations for CO2 Storage In September 2009, the U.S. Department of Energy announced the award of 11 projects with a total project value of $75.5 million* to conduct site characterization of promising geologic formations for CO2 storage. These Recovery Act projects will increase our understanding of the potential for these formations to safely and permanently store CO2. The information gained from these projects (detailed below) will further DOE's efforts to develop a national assessment of CO2 storage capacity in deep geologic formations. Site Characterization of Promising Geologic Formations for CO2 Storage * Subsequently, the Board of Public Works project in Holland, MI has been

76

Savannah River Site Interim Waste Management Program Plan FY 1991--1992  

SciTech Connect

The primary purpose of the Waste Management Program Plan is to provide an annual report of how Waste Management's operations are conducted, what facilities are being used to manage wastes, what forces are acting to change current waste management systems, and what plans are in store for the coming fiscal year. In addition, this document projects activities for several years beyond the coming fiscal year in order to adequately plan for safe handling, storage, and disposal of radioactive wastes generated at the Savannah River Site and for developing technology for improved management of wastes. In this document, work descriptions and milestone schedules are current as of December 1991.

Chavis, D.M.

1992-05-01T23:59:59.000Z

77

Savannah River Site Interim Waste Management Program Plan FY 1991--1992  

SciTech Connect

The primary purpose of the Waste Management Program Plan is to provide an annual report of how Waste Management`s operations are conducted, what facilities are being used to manage wastes, what forces are acting to change current waste management systems, and what plans are in store for the coming fiscal year. In addition, this document projects activities for several years beyond the coming fiscal year in order to adequately plan for safe handling, storage, and disposal of radioactive wastes generated at the Savannah River Site and for developing technology for improved management of wastes. In this document, work descriptions and milestone schedules are current as of December 1991.

Chavis, D.M.

1992-05-01T23:59:59.000Z

78

Environmental permits and approvals plan for high-level waste interim storage, Project W-464  

SciTech Connect

This report discusses the Permitting Plan regarding NEPA, SEPA, RCRA, and other regulatory standards and alternatives, for planning the environmental permitting of the Canister Storage Building, Project W-464.

Deffenbaugh, M.L.

1998-05-28T23:59:59.000Z

79

FutureGen Industrial Alliance Announces Carbon Storage Site Selection  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

FutureGen Industrial Alliance Announces Carbon Storage Site FutureGen Industrial Alliance Announces Carbon Storage Site Selection Process for FutureGen 2.0 FutureGen Industrial Alliance Announces Carbon Storage Site Selection Process for FutureGen 2.0 October 6, 2010 - 12:00am Addthis WASHINGTON -- The FutureGen Industrial Alliance today announced details of a process that will lead to the selection of an Illinois site for the storage of carbon dioxide (CO2) collected at FutureGen 2.0, a landmark project that will advance the deployment of carbon capture and storage technology at an Ameren Energy Resources power plant in Meredosia, Illinois. Last month the Department of Energy signed two agreements, one with the FutureGen Industrial Alliance and one with Ameren Energy Resources that committed $1 billion in Recovery Act funding to design, build and

80

Niagara Falls Storage Site environmental report for calendar year 1989, Lewiston, New York  

SciTech Connect

The environmental monitoring program, which began in 1981, was continued during 1989 at the Niagara Falls Storage Site (NFSS), a United States Department of Energy (DOE) surplus facility located in Niagara County, New York, that is currently used for interim storage of radioactive residues, contaminated soils, and rubble. The monitoring program is being conducted by Bechtel National, Inc. The monitoring program at NFSS measures radon concentrations in air; external gamma radiation levels; and uranium and radium concentrations in surface water, groundwater, and sediment. Additionally, several nonradiological parameters are measured in groundwater. To verify that the site is in compliance with the DOE radiation protection standard and to assess its potential effect on public health, the radiation dose was calculated for a hypothetical maximally exposed individual. Based on the conservative scenario described in this report, this hypothetical individual receives an annual external exposure equivalent to approximately 2 percent of the DOE radiation protection standard of 100 mrem/yr. This exposure is less than a person receives during a one-way flight from New York to Los Angeles (because of the greater amounts of cosmic radiation at higher altitudes). The cumulative dose to the population within an 80-km (50-mi) radius of NFSS that results from radioactive materials present at the site is indistinguishable from the dose that the same population receives from naturally occurring radioactive sources. Results of the 1989 monitoring show that NFSS is in compliance with applicable DOE radiation protection standards. 18 refs., 26 figs., 18 tabs.

Not Available

1990-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "interim storage site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Plutonium Finishing Plan (PFP) Treatment and Storage Unit Interim Status Closure Plan  

SciTech Connect

This document describes the planned activities and performance standards for closing the Plutonium Finishing Plant (PFP) Treatment and Storage Unit. The PFP Treatment and Storage Unit is located within the 234-52 Building in the 200 West Area of the Hanford Facility. Although this document is prepared based upon Title 40 Code of Federal Regulations (CFR), Part 265, Subpart G requirements, closure of the unit will comply with Washington Administrative Code (WAC) 173-303-610 regulations pursuant to Section 5.3 of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Action Plan (Ecology et al. 1996). Because the PFP Treatment and Storage Unit manages transuranic mixed (TRUM) waste, there are many controls placed on management of the waste. Based on the many controls placed on management of TRUM waste, releases of TRUM waste are not anticipated to occur in the PFP Treatment and Storage Unit. Because the intention is to clean close the PFP Treatment and Storage Unit, postclosure activities are not applicable to this closure plan. To clean close the unit, it will be demonstrated that dangerous waste has not been left onsite at levels above the closure performance standard for removal and decontamination. If it is determined that clean closure is not possible or is environmentally impractical, the closure plan will be modified to address required postclosure activities. The PFP Treatment and Storage Unit will be operated to immobilize and/or repackage plutonium-bearing waste in a glovebox process. The waste to be processed is in a solid physical state (chunks and coarse powder) and will be sealed into and out of the glovebox in closed containers. The containers of immobilized waste will be stored in the glovebox and in additional permitted storage locations at PFP. The waste will be managed to minimize the potential for spills outside the glovebox, and to preclude spills from reaching soil. Containment surfaces will be maintained to ensure integrity. In the unlikely event that a waste spill does occur outside the glovebox, operating methods and administrative controls will require that waste spills be cleaned up promptly and completely, and a notation will be made in the operating record. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge.

PRIGNANO, A.L.

2000-07-01T23:59:59.000Z

82

Appendix E: Underground Storage Annual Site Environmental Report  

E-Print Network (OSTI)

Appendix E: Underground Storage Tank Data #12;Annual Site Environmental Report Appendix E identification service Contents Status ( ) date to Corrective action Tank Out-of- assessment number date regulatory Installation Capacity Preliminary date (gallons) investigation Environmental agency Petroleum USTs

Pennycook, Steve

83

International Symposium on Site Characterization for CO2 Geological Storage  

E-Print Network (OSTI)

FEASIBILITY: TEAPOT DOME EOR PILOT L. Chiaramonte, M.TO IDENTIFY OPTIMAL CO 2 EOR STORAGE SITES V. Nez Lopez,from a carbon dioxide EOR/sequestration project. Energy

Tsang, Chin-Fu

2006-01-01T23:59:59.000Z

84

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

Office of Legacy Management (LM)

Designation Survey - Palmerton, Pa. Ore Storage Site Designation Survey - Palmerton, Pa. Ore Storage Site William Bibb Oak Ridge Operations Office Based on the information furnished in Aerospace's Review of the.subject site (Attachment 1) and the ORKL/RASA (Attachment 2), it Is requested that designation survey of the Palmerton Ore Storage Pennsylvania. The survey should be detailed to and subsurface data to make up for the lack of the previous AEC surveys and in keeping with ORNL/RASA group should furnish a draft survey approval prior to conducting any survey activities. If there are any questions, please call Edward DeLaney 04 FTS 253-4716. Arthur J. Whitman / '/ Division of Facility and Site ' Deconrnissioning P,rojects Office of Nuclear Energy : 2 Attachments I bee: I E. Keller, OR, w/attachs:

85

Remedial action work plan for the Colonie site. Revision 1  

SciTech Connect

The Colonie site is a DOE Formerly Utilized Sites Remedial Action Program (FUSRAP) site located in the Town of Colonie, New York, and consisting of an interim storage site and several vicinity properties. The Colonie Interim Storage Site (CISS) is the former National Lead (NL) Industries plant located at 1130 Central Avenue. There are 11 vicinity properties that received remedial action in 1984: 7 located south of the site on Yardboro and Palmer Avenues just across the Colonie-Albany town limits in Albany, and 4 located northwest of the site along Central Avenue in Colonie. Of these properties, nine are residences and two are commercial properties. This document describes the engineering design, construction, and associated plans for remedial action on the vicinity properties and the interim storage site. These plans include both radiological and chemical work. Radiological work includes: excavating the above-guideline radioactive wastes on the vicinity properties; designing required facilities for the interim storage site; preparing the interim storage site to receive these contaminated materials; transporting the contaminated materials to the interim waste storage stockpile; and preparing necessary schedules for accomplishing the remedial actions. Chemical work involves: developing the Resource Conservation and Recovery Act (RCRA) closure plans; neutralizing chemical hazards associated with plating solutions; inventorying on-site chemicals; and disposal of chemicals and/or residues. 17 refs., 5 figs., 1 tab.

Not Available

1985-08-01T23:59:59.000Z

86

Sandia National Laboratories: the NM Legislature's Interim Science...  

NLE Websites -- All DOE Office Websites (Extended Search)

the NM Legislature's Interim Science Technology and Telecommunications Committee New Mexico Renewable Energy Storage Task Force On January 28, 2014, in Energy, Energy Storage,...

87

Storage  

NLE Websites -- All DOE Office Websites (Extended Search)

Environmental Risks » Storage Environmental Risks » Storage Depleted UF6 Environmental Risks line line Storage Conversion Manufacturing Disposal Environmental Risks of Depleted UF6 Storage Discussion of the potential environmental impacts from storage of depleted UF6 at the three current storage sites, as well as potential impacts from the storage of depleted uranium after conversion to an oxide form. Impacts Analyzed in the PEIS The PEIS included an analysis of the potential environmental impacts from continuing to store depleted UF6 cylinders at the three current storage sites, as well as potential impacts from the storage of depleted uranium after conversion to an oxide form. Impacts from Continued Storage of UF6 Cylinders Continued storage of the UF6 cylinders would require extending the use of a

88

Interim Action Determination  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Interim Action Determination Interim Action Determination Processing of Plutonium Materials from the DOE Standard 3013 Surveillance Program in H-Canyon at the Savannah River Site The Department of Energy (DOE) is preparing the Surplus Plutonium Disposition Supplemental Environmental Impact Statement (SPD SEIS, DOE/EIS-0283-S2). DOE is evaluating alternatives for disposition of non-pit plutonium that is surplus to the national

89

Appendix C: Underground Storage Annual Site Environmental Report  

E-Print Network (OSTI)

Appendix C: Underground Storage Tank Data #12;#12;Annual Site Environmental Report Appendix C identification service Contents Status ( ) date to Corrective action Tank Out-of- assessment number date regulatory Installation Capacity Preliminary date (gallons) investigation Environmental agency Petroleum USTs

Pennycook, Steve

90

Engineering evaluation of alternatives for the disposition of Niagara Falls Storage Site, its residues and wastes  

SciTech Connect

The final disposition scenarios selected by DOE for assessment in this document are consistent with those stated in the Notice of Intent to prepare an Environmental Impact Statement (EIS) for the Niagara Falls Storage Site (NFSS) (DOE, 1983d) and the modifications to the alternatives resulting from the public scoping process. The scenarios are: take no action beyond interim remedial measures other than maintenance and surveillance of the NFSS; retain and manage the NFSS as a long-term waste management facility for the wastes and residues on the site; decontaminate, certify, and release the NFSS for other use, with long-term management of the wastes and residues at other DOE sites; and partially decontaminate the NFSS by removal and transport off site of only the more radioactive residues, and upgrade containment of the remaining wastes and residues on site. The objective of this document is to present to DOE the conceptual engineering, occupational radiation exposure, construction schedule, maintenance and surveillance requirements, and cost information relevant to design and implementation of each of the four scenarios. The specific alternatives within each scenario used as the basis for discussion in this document were evaluated on the bases of engineering considerations, technical feasibility, and regulatory requirements. Selected alternatives determined to be acceptable for each of the four final disposition scenarios for the NFSS were approved by DOE to be assessed and costed in this document. These alternatives are also the subject of the EIS for the NFSS currently being prepared by Argonne National Laboratory (ANL). 40 figures, 38 tables.

Not Available

1984-01-01T23:59:59.000Z

91

Interim Report: CHEMICAL SPECIES OF MIGRATING RADIONUCLIDES AT COMMERCIAL SHALLOW LAND BURIAL SITES  

SciTech Connect

This is the first quarterly report for .the project "Chemical Species of Migrating Radionuclides at Commercial Shallow Land Burial Site" under the new reporting schedule requested by the sponsor. Future reports will be issued following each fiscal quarter, with the next report scheduled in October, 1982. The primary purpose of this project is to develop an understanding of the processes responsible for radionuclide migration at low-level waste burial sites. Chemical measurements of waste trench leachate and identification of chemical changes in leachate during migration will provide a basis for geochemical waste transport models. This project will produce for the U.S. Nuclear Regulatory Commission information to support guidance for implementation of 10 CFR 61, particularly in the development of criteria for low level waste disposal site selection, management, permanent closure and monitoring. Topics covered include: Experimental Trench and Well Study; Chemical Species Characterization; Specific Radionuclide Mapping; Organic Complexing Compounds,

Kirby,, L. J.; Rickard,, W. H.; Toste,, A. P.

1982-08-01T23:59:59.000Z

92

Determination of ecologically vital groundwaters at selected sites in the Formerly Utilized Sites Remedial Action Program  

SciTech Connect

The US Department of Energy is classifying groundwaters at sites in its Formerly Utilized Sites Remedial Action Program (FUSRAP). Of particular concern is the potential presence of groundwaters that are highly vulnerable to contamination and that are either (1) irreplaceable sources of drinking water or (2) ecologically vital. Conditions at nine FUSRAP sites were evaluated to determine if ecologically vital groundwaters are present. The sites evaluated were Wayne Interim Storage Site, Maywood Interim Storage Site, and Middlesex Sampling Plant in New Jersey; Ashland 2 Site, Seaway Industrial Park, Colonie Interim storage Site, and Niagara Falls Storage Site in New York; and the St. Louis Airport Site and Hazelwood Interim Storage Site in Missouri. The analyses indicated that groundwaters are vulnerable to contamination at all but two of the sites -- the Ashland 2 and Seaway Industrial Park sites in New York. Groundwater discharge points were identified within a 2-mile radius (i.e., the classification review area) of all of the sites. No ecologically vital groundwater areas exist in the vicinities of any of the nine FUSRAP sites evaluated. 35 refs., 17 figs.

Vinikour, W.S.; Yin, S.C.L.

1989-08-01T23:59:59.000Z

93

Record of Decision; Safe Interim Storage of Hanford Tank Wastes, Hanford Site, Richland, WA  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

87 87 Federal Register / Vol. 60, No. 231 / Friday, December 1, 1995 / Notices the public will have access to the Committee's deliberations. These facilities will be provided in the location listed in the portion of this notice titles ''LOCATION.'' The public is being given less than fifteen days notice of this teleconference because there was no funding available to hold the previously announced Board Meeting in Seattle and plans have to be approved to hold another Board Meeting as soon as possible and to begin the Nominations process. Records are kept of all Board proceedings and are available for public inspection at the U.S. Department of Education, National Assessment Governing Board, Suite 825, 800 North Capitol Street NW., Washington, D.C., from 8:30 a.m. to 5:00 p.m.

94

Niagara Falls Storage Site Vicinity Properties in Lewiston, New York,  

Office of Legacy Management (LM)

Niagara Falls Storage Site Vicinity Niagara Falls Storage Site Vicinity Properties in Lewiston, New York, from 7983 through 7986 Depatfment of Energy Former Sites Restoration Division Oak Ridge Field Office July 7 992 I I I I I I I I I I I I I I I I I I I CONTENTS Figures .......................... Tables .......................... Abbreviations ....................... Acronyms ......................... 1.0 Introduction ..................... 2.0 Site History ..................... 3.0 Property Descriptions ................ 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 3.10 3.11 3.12 3.13 3.14 3.15 3.16 3.17 3.18 3.19 3.20 3.21 3.22 3.23 3.24 3.25 3.26 3.27 Property A ............ Property B ............ PropertyC' ........... Property D ............ Property F ........ .' ... PropertyH' ...........

95

Niagara Falls Storage Site environmental monitoring report. Calendar year 1983  

SciTech Connect

During 1983, an environmental monitoring program was continued at the Niagara Falls Storage Site, a United States Department of Energy (DOE) surplus facility located in Niagara County, New York presently used for the storage of radioactive residues, contaminated soils and rubble. The monitoring program at NFSS measures radon concentrations in air, uranium and radium concentrations in surface water, groundwater, and sediments, and external gamma exposure rates. Radiation doses to the public are also calculated. Environmental samples collected are analyzed to determine compliance with applicable standards. Comparison of 1983 monitoring results with 1982 results shows a significant decrease in radon levels at almost every monitoring location. External gamma exposure rates also showed a general decrease. 9 references, 10 figures, 11 tables

Not Available

1984-07-01T23:59:59.000Z

96

Interim Status of the Accelerated Site Technology Deployment Integrated Decontamination and Decommissioning Project  

SciTech Connect

The Idaho National Engineering and Environmental Laboratory (INEEL), Fernald Environmental Management Project (FEMP), and Argonne National Laboratory - East (ANL-E) teamed to establish the Accelerated Site Technology Deployment (ASTD) Integrated Decontamination and Decommissioning (ID&D) project to increase the use of improved technologies in D&D operations. The project is making the technologies more readily available, providing training, putting the technologies to use, and spreading information about improved performance. The improved technologies are expected to reduce cost, schedule, radiation exposure, or waste volume over currently used baseline methods. They include some of the most successful technologies proven in the large-scale demonstrations and in private industry. The selected technologies are the Pipe Explorer, the GammaCam, the Decontamination Decommissioning and Remediation Optimal Planning System (DDROPS), the BROKK Demolition Robot, the Personal Ice Cooling System (PICS), the Oxy-Gasoline Torch, the Track-Mounted Shear, and the Hand-Held Shear.

A. M Smith; G. E. Matthern; R. H. Meservey

1998-11-01T23:59:59.000Z

97

Underground storage tank compliance activities at the Hanford Site  

SciTech Connect

The Hanford Site covers 560 mi{sup 2} of semi-arid land that is owned by the US Government and managed by the US Department of Energy-Richland Operations Office (DOE-RL). It is located in the Columbia Basin and northwest of the City of Richland, Washington, which lies approximately 5 mi from the southernmost portion of the Hanford Site boundary and is the nearest population center. In early 1943, the US Army Corps of Engineers selected the Hanford Site for the production and purification of plutonium. The purpose of this report is fourfold: it describes the underground storage tanks (UST) at the Hanford Site regulated by title 40 Code of Federal Regulations (CFR) 280 (EPA 1988a); it defines the compliance programs completed, underway, or planned by the affected Hanford Site contractors; it provides costs of program compliance; and it defines long-range planning to comply with 40 CFR 280 after 1998. 5 refs., 1 fig., 2 tabs.

Morton, M.R.; Mihalic, M.A.

1990-08-01T23:59:59.000Z

98

DOE Interim Guidance on Mercury Management Procedures and Standards...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Services Waste Management Waste Disposition Long-Term Management and Storage of Elemental Mercury is in the Planning Stages DOE Interim Guidance on Mercury Management...

99

Niagara Falls Storage Site annual environmental report for calendar year 1991, Lewiston, New York. [Niagara Falls Storage Site  

SciTech Connect

This document describes the environmental monitoring program at the Niagara Falls Storage Site (NFSS) and surrounding area, implementation of the program, and monitoring results for 1991. Environmental monitoring at NFSS began in 1981. The site is owned by the US Department of Energy (DOE) and is assigned to the DOE Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP is a program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The environmental monitoring program at NFSS includes sampling networks for radon concentrations in air; external gamma radiation exposure; and total uranium and radium-226 concentrations in surface water, sediments, and groundwater. Additionally, several nonradiological parameters including seven metals are routinely measured in groundwater. Monitoring results are compared with applicable Environmental Protection Agency (EPA) standards, DOE derived concentration guides (DCGs), dose limits, and other requirements in DOE orders. Environmental standards are established to protect public health and the environment.

Not Available

1992-09-01T23:59:59.000Z

100

DOE Best Practices Manual Focuses on Site Selection for CO2 Storage |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Best Practices Manual Focuses on Site Selection for CO2 Storage Best Practices Manual Focuses on Site Selection for CO2 Storage DOE Best Practices Manual Focuses on Site Selection for CO2 Storage January 5, 2011 - 12:00pm Addthis Washington, DC - The most promising methods for assessing potential carbon dioxide (CO2) geologic storage sites - a crucial component of Carbon Capture and Storage (CCS) technology - is the focus of the latest in a series of U.S. Department of Energy (DOE) CCS "best practices" manuals. Developed by the Office of Fossil Energy's (FE) National Energy Technology Laboratory (NETL), the manual - Site Screening, Site Selection and Initial Characterization for Storage of CO2 in Deep Geologic Formations - is a resource for future project developers and CO2 producers and transporters. It can also be used to apprise government agencies of the

Note: This page contains sample records for the topic "interim storage site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

DOE Best Practices Manual Focuses on Site Selection for CO2 Storage |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Best Practices Manual Focuses on Site Selection for CO2 Storage Best Practices Manual Focuses on Site Selection for CO2 Storage DOE Best Practices Manual Focuses on Site Selection for CO2 Storage January 5, 2011 - 12:00pm Addthis Washington, DC - The most promising methods for assessing potential carbon dioxide (CO2) geologic storage sites - a crucial component of Carbon Capture and Storage (CCS) technology - is the focus of the latest in a series of U.S. Department of Energy (DOE) CCS "best practices" manuals. Developed by the Office of Fossil Energy's (FE) National Energy Technology Laboratory (NETL), the manual - Site Screening, Site Selection and Initial Characterization for Storage of CO2 in Deep Geologic Formations - is a resource for future project developers and CO2 producers and transporters. It can also be used to apprise government agencies of the

102

First-Generation Risk Profiles Help Predict CO2 Storage Site Obstacles |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

First-Generation Risk Profiles Help Predict CO2 Storage Site First-Generation Risk Profiles Help Predict CO2 Storage Site Obstacles First-Generation Risk Profiles Help Predict CO2 Storage Site Obstacles September 18, 2012 - 1:00pm Addthis Washington, DC - In support of large-scale carbon capture, utilization and storage (CCUS) projects, a collaboration of five U.S. Department of Energy (DOE) national laboratories has completed first-generation risk profiles that, for the first time, offer a means to predict the probability of complications that could arise from specific carbon dioxide (CO2) storage sites. With their detailed methodology for quantifying risk potential at underground carbon storage sites, the profiles will help support safe, large-scale CCUS projects, an important option in the effort to reduce human-generated CO2 emissions linked by many experts to global climate

103

Interim Activities at Corrective Action Unit 114: Area 25 EMAD Facility, Nevada National Security Site, Nevada, for Fiscal Years 2012 and 2013  

SciTech Connect

This letter report documents interim activities that have been completed at CAU 114 in fiscal years 2012 and 2013.

Silvas, A J

2013-10-24T23:59:59.000Z

104

Site-Dependent Activity of Atomic Ti Catalysts in Al-Based Hydrogen Storage Materials  

E-Print Network (OSTI)

Site-Dependent Activity of Atomic Ti Catalysts in Al-Based Hydrogen Storage Materials Abdullah Al storage processes. Here we analyze the role of atomic Ti catalysts in the hydrogenation of Al-based hydrogen storage materials. We show that Ti atoms near the Al surface activate gas-phase H2, a key step

Ciobanu, Cristian

105

RADIATION PROTECTION, RADIOACTIVE WASTE MANAGEMENT AND SITE MONITORING AT THE NUCLEAR SCIENTIFIC EXPERIMENTAL AND EDUCATIONAL CENTRE IRT-SOFIA AT INRNE-BAS  

Science Journals Connector (OSTI)

......related to radioactive waste treatments and interim...site to the temporary storage of radioactive waste operated by SE . Removal...The comprehensive long-term monitoring of the IRT...protection and radioactive waste management in the design......

Al. Mladenov; D. Stankov; Tz. Nonova; K. Krezhov

2014-07-01T23:59:59.000Z

106

Environmental Assessment and Finding of No Significant Impact: Interim Measures for the Mixed Waste Management Facility Groundwater at the Burial Ground Complex at the Savannah River Site  

SciTech Connect

The U. S. Department of Energy (DOE) prepared this environmental assessment (EA) to analyze the potential environmental impacts associated with the proposed interim measures for the Mixed Waste Management Facility (MW) groundwater at the Burial Ground Complex (BGC) at the Savannah River Site (SRS), located near Aiken, South Carolina. DOE proposes to install a small metal sheet pile dam to impound water around and over the BGC groundwater seepline. In addition, a drip irrigation system would be installed. Interim measures will also address the reduction of volatile organic compounds (VOCS) from ''hot-spot'' regions associated with the Southwest Plume Area (SWPA). This action is taken as an interim measure for the MWMF in cooperation with the South Carolina Department of Health and Environmental Control (SCDHEC) to reduce the amount of tritium seeping from the BGC southwest groundwater plume. The proposed action of this EA is being planned and would be implemented concurrent with a groundwater corrective action program under the Resource Conservation and Recovery Act (RCRA). On September 30, 1999, SCDHEC issued a modification to the SRS RCRA Part B permit that adds corrective action requirements for four plumes that are currently emanating from the BGC. One of those plumes is the southwest plume. The RCRA permit requires SRS to submit a corrective action plan (CAP) for the southwest plume by March 2000. The permit requires that the initial phase of the CAP prescribe a remedy that achieves a 70-percent reduction in the annual amount of tritium being released from the southwest plume area to Fourmile Branch, a nearby stream. Approval and actual implementation of the corrective measure in that CAP may take several years. As an interim measure, the actions described in this EA would manage the release of tritium from the southwest plume area until the final actions under the CAP can be implemented. This proposed action is expected to reduce the release of tritium from the southwest plume area to Fourmile Branch between 25 to 35 percent. If this proposed action is undertaken and its effectiveness is demonstrated, it may become a component of the final action in the CAP. This document was prepared in compliance with the National Environmental Policy Act (NEPA) of 1969, as amended; the requirements of the Council on Environmental Quality Regulations for Implementing NEPA (40 CFR 1500-1508); and the DOE Regulations for Implementing NEPA (10 CFR 1021). NEPA requires the assessment of environmental consequences of Federal actions that may affect the quality of the human environment. Based on the potential for impacts described herein, DOE will either publish a Finding of No Significant Impact (FONSI) or prepare an environmental impact statement (EM).

N /A

1999-12-08T23:59:59.000Z

107

Targeted Health Assessment for Wastes Contained at the Niagara Falls Storage Site to Guide Planning for Remedial Action Alternatives - 13428  

SciTech Connect

The U.S. Army Corps of Engineers (USACE) is evaluating potential remedial alternatives at the 191-acre Niagara Falls Storage Site (NFSS) in Lewiston, New York, under the Formerly Utilized Sites Remedial Action Program (FUSRAP). The Manhattan Engineer District (MED) and Atomic Energy Commission (AEC) brought radioactive wastes to the site during the 1940's and 1950's, and the U.S. Department of Energy (US DOE) consolidated these wastes into a 10-acre interim waste containment structure (IWCS) in the southwest portion of the site during the 1980's. The USACE is evaluating remedial alternatives for radioactive waste contained within the IWCS at the NFSS under the Feasibility Study phase of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) process. A preliminary evaluation of the IWCS has been conducted to assess potential airborne releases associated with uncovered wastes, particularly during waste excavation, as well as direct exposures to uncovered wastes. Key technical issues for this assessment include: (1) limitations in waste characterization data; (2) representative receptors and exposure routes; (3) estimates of contaminant emissions at an early stage of the evaluation process; (4) consideration of candidate meteorological data and air dispersion modeling approaches; and (5) estimates of health effects from potential exposures to both radionuclides and chemicals that account for recent updates of exposure and toxicity factors. Results of this preliminary health risk assessment indicate if the wastes were uncovered and someone stayed at the IWCS for a number of days to weeks, substantial doses and serious health effects could be incurred. Current controls prevent such exposures, and the controls that would be applied to protect onsite workers during remedial action at the IWCS would also effectively protect the public nearby. This evaluation provides framing context for the upcoming development and detailed evaluation of remedial alternatives for the IWCS. (authors)

Busse, John; Keil, Karen; Staten, Jane; Miller, Neil; Barker, Michelle [U.S. Army Corps of Engineers, Buffalo District, 1776 Niagara Street, Buffalo, NY (United States)] [U.S. Army Corps of Engineers, Buffalo District, 1776 Niagara Street, Buffalo, NY (United States); MacDonell, Margaret; Peterson, John; Chang, Young-Soo; Durham, Lisa [Argonne National Laboratory, Environmental Science Division, 9700 S. Cass Ave., Argonne, IL 60439 (United States)] [Argonne National Laboratory, Environmental Science Division, 9700 S. Cass Ave., Argonne, IL 60439 (United States)

2013-07-01T23:59:59.000Z

108

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

Energy.gov (U.S. Department of Energy (DOE))

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

109

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

Office of Legacy Management (LM)

COT"IPREITENS IVE RADIOLOGICAL COT"IPREITENS IVE RADIOLOGICAL SURVEY OFF-SITE PROPERTY P NIAGARA FALIS STORAGE SITE LEWISTON, NEW YORK Prepared for U.S. DePartment of EnergY as part of the Formerly Utilized Sites - Remedial ActLon Program J . D . B e r g e r P r o j e c t S t a f f J. Burden* w.L. Smlth* R.D. Condra T.J. Sowell J.S . Epler* G.M. S tePhens P.Iil. Frame L.B. Taus* W . 0 . H e l t o n C . F . W e a v e r R . C . G o s s l e e B . S . Z a c h a r e k d I I Prepared bY Radiological Slte Assessoent Progran Manpower Educailon Research, and Training Dlvision Oak Ridge Assoclated Universlties Oak Ridge, Tennessee 3783f-0117 I FINAL REPORT March 1984 Thts report ls based on work performed under contract number DE-AC05-760R00033 wiLh the DePartment of EnergY. *Evaluatlon Research Corporatlon, Oak Ridge, Tennessee TABLE OF CONTENTS L i s t o f F i g u

110

FutureGen Industrial Alliance Announces Carbon Storage Site Selection...  

Energy Savers (EERE)

(CO2) collected at FutureGen 2.0, a landmark project that will advance the deployment of carbon capture and storage technology at an Ameren Energy Resources power plant in...

111

Allegations of diversion and substitution of crude oil. Bayou Choctaw Storage Site, Strategic Petroleum Reserve  

SciTech Connect

Investigation did not substantiate allegations that crude oil destined for the Strategic Petroleum Reserve storage site at Bayou Choctaw was diverted to private use and some other material substituted in its place. However, recommendations are made for handling intermediate transport and storage systems for crude oil to tighten security aspects. (PSB)

Not Available

1984-03-30T23:59:59.000Z

112

Combining microseismic and geomechanical observations to interpret storage integrity at the In Salah CCS site  

Science Journals Connector (OSTI)

......of maximum energy radiation from...decay of the frequency-magnitude...instrument response, distance...production and CO2 storage project using...Geomechanical response to CO2 injection...intensity, energy and acceleration...In Salah CO2 storage site (Krechba...Analysis of High-Frequency Seismograms......

Bettina P. Goertz-Allmann; Daniela Khn; Volker Oye; Bahman Bohloli; Eyvind Aker

2014-01-01T23:59:59.000Z

113

EA-1211: Relocation and Storage of Isotopic Heat Sources, Hanford Site, Richland, Washington  

Energy.gov (U.S. Department of Energy (DOE))

This EA evaluates the environmental impacts for the proposal for relocation and storage of the isotopic heat sources at the U.S. Department of Energy Hanford Site in Richland, Washington.

114

Long-Term Storage of Cesium and Strontium at the Hanford Site  

Energy Savers (EERE)

From 1974 to 1985, cesium and strontium were recovered from high-level waste storage tanks at the Hanford Site, packed in corrosion-resistant capsules, and placed in underwater...

115

EIS-0283-S2: Amended Interim Action Determination  

Energy.gov (U.S. Department of Energy (DOE))

Disposition of Plutonium Materials from the Department of Energy Standard 3013 Surveillance Program at the Savannah River Site (Amending Interim Action Determination of 12/08/2008)

116

Environmental Site Characterization and Remediation at Former Grain Storage  

NLE Websites -- All DOE Office Websites (Extended Search)

Applied Geosciences and Environmental Management (AGEM) Program Applied Geosciences and Environmental Management (AGEM) Program The EVS Applied Geosciences and Environmental Management (AGEM) program improves methods for characterizing and restoring environmental sites contaminated with carbon tetrachloride. For decades, the EVS Applied Geosciences and Environmental Management program has been improving methods for characterizing and restoring environmental sites contaminated with carbon tetrachloride. A key to our streamlined site characterization process is extensive use of cone penetrometer technology, with customized sampling and drilling tools, to minimize intrusiveness and the amount of hazardous waste generated. We have also improved analytical methods so that we can rapidly detect lower concentrations of contaminants and have developed methods for integrating

117

Expedited approach to a carbon tetrachloride spill interim remedial action  

SciTech Connect

Monitored natural attenuation was selected as an interim measure for a carbon tetrachloride spill site where source removal or in situ treatment cannot currently be implemented due to the surrounding infrastructure. Rather than delay action until the site is more accessible to an interim action, this more expedited approach would support a final action. Individual Hazard Substance Site (IHSS) 118.1 is a former underground storage tank at Rocky Flats Environmental Technology Site (RFETS) that stored carbon tetrachloride for process use. Inadvertent releases associated with filling and failure of the tank system resulted in an accumulation of carbon tetrachloride in a bedrock depression around a group of former process waste tanks. Access to the source of contamination is obstructed by numerous utilities, the process waste tanks, and other components of the site infrastructure that limit the ability to conduct an effective remedial action. A preremedial field investigation was conducted in September 1997 to identify and delineate the extent of the dense nonaqueous phase liquid (DNAPL) in the subsurface. Data collected from the investigation revealed that natural processes might be limiting the migration of contaminants from the source area.

Cowdery, C.; Primrose, A. [Rocky Mountain Remediation Services, LLC, Golden, CO (United States). Rocky Flats Environmental Technology Site; Uhland, J. [Kaiser-Hill, LLC, Golden, CO (United States). Rocky Flats Environmental Technology Site; Castaneda, N. [Dept. of Energy, Golden, CO (United States). Rocky Flats Environmental Technology Site

1998-07-01T23:59:59.000Z

118

Criticality Safety Evaluation of Hanford Site High Level Waste Storage Tanks  

SciTech Connect

This criticality safety evaluation covers operations for waste in underground storage tanks at the high-level waste tank farms on the Hanford site. This evaluation provides the bases for criticality safety limits and controls to govern receipt, transfer, and long-term storage of tank waste. Justification is provided that a nuclear criticality accident cannot occur for tank farms operations, based on current fissile material and operating conditions.

ROGERS, C.A.

2000-02-17T23:59:59.000Z

119

Interim report  

SciTech Connect

This Interim Report summarizes the research and development activities of the Superconducting Super Collider project carried out from the completion of the Reference Designs Study (May 1984) to June 1985. It was prepared by the SSC Central Design Group in draft form on the occasion of the DOE Annual Review, June 19--21, 1985. Now largely organized by CDG Divisions, the bulk of each chapter documents the progress and accomplishments to date, while the final section(s) describe plans for future work. Chapter 1, Introduction, provides a basic brief description of the SSC, its physics justification, its origins, and the R&D organization set up to carry out the work. Chapter 2 gives a summary of the main results of the R&D program, the tasks assigned to the four magnet R&D centers, and an overview of the future plans. The reader wishing a quick look at the SSC Phase I effort can skim Chapter 1 and read Chapter 2. Subsequent chapters discuss in more detail the activities on accelerator physics, accelerator systems, magnets and cryostats, injector, detector R&D, conventional facilities, and project planning and management. The magnet chapter (5) documents in text and photographs the impressive progress in successful construction of many model magnets, the development of cryostats with low heat leaks, and the improvement in current-carrying capacity of superconducting strand. Chapter 9 contains the budgets and schedules of the COG Divisions, the overall R&D program, including the laboratories, and also preliminary projections for construction. Appendices provide information on the various panels, task forces and workshops held by the CDG in FY 1985, a bibliography of COG and Laboratory reports on SSC and SSC-related work, and on private industrial involvement in the project.

NONE

1985-06-01T23:59:59.000Z

120

Application to ship nonmixed transuranic waste to the Nevada Test Site for interim storage. Waste Cerification Program  

SciTech Connect

This report documents various regulations on radioactive waste processing and discusses how the Waste Isolation Pilot Plant will comply with and meet these requirements. Specific procedures are discussed concerning transuranic, metal scrap, salt block, solid, and glove box wastes.

Not Available

1993-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "interim storage site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Dedicated-site, interim storage of high-level nuclear waste as part of the management system  

Science Journals Connector (OSTI)

...develop permanent repositories. A systems approach...reprocessed nuclear wastes from fuel rods...In- teragency Review Group (1) and...high-level wastes, including both...mined geologic repositories for permanent...Under current plans for mined geologic...and performance standards of permanent...

E-an Zen

1980-01-01T23:59:59.000Z

122

Rigorous Screening Technology for Identifying Suitable CO2 Storage Sites II  

SciTech Connect

This report serves as the final technical report and users manual for the 'Rigorous Screening Technology for Identifying Suitable CO2 Storage Sites II SBIR project. Advanced Resources International has developed a screening tool by which users can technically screen, assess the storage capacity and quantify the costs of CO2 storage in four types of CO2 storage reservoirs. These include CO2-enhanced oil recovery reservoirs, depleted oil and gas fields (non-enhanced oil recovery candidates), deep coal seems that are amenable to CO2-enhanced methane recovery, and saline reservoirs. The screening function assessed whether the reservoir could likely serve as a safe, long-term CO2 storage reservoir. The storage capacity assessment uses rigorous reservoir simulation models to determine the timing, ultimate storage capacity, and potential for enhanced hydrocarbon recovery. Finally, the economic assessment function determines both the field-level and pipeline (transportation) costs for CO2 sequestration in a given reservoir. The screening tool has been peer reviewed at an Electrical Power Research Institute (EPRI) technical meeting in March 2009. A number of useful observations and recommendations emerged from the Workshop on the costs of CO2 transport and storage that could be readily incorporated into a commercial version of the Screening Tool in a Phase III SBIR.

George J. Koperna Jr.; Vello A. Kuuskraa; David E. Riestenberg; Aiysha Sultana; Tyler Van Leeuwen

2009-06-01T23:59:59.000Z

123

Preparing Class B and C Waste for Long Term Storage  

SciTech Connect

Commercial Nuclear Generating Stations outside of the Atlantic Compact will lose access to the Barnwell Disposal Facility in July of 2008. Many generators have constructed Interim On-Site Storage Buildings (IOSB) in which to store class B and C waste in the future as other permanent disposal options are developed. Until such time it is important for these generators to ensure class B and C waste generation is minimized and waste generated is packaged to facilitate long term storage. (authors)

Snyder, M.W. [Sacramento Municipal Utility District - Rancho Seco (United States)

2008-07-01T23:59:59.000Z

124

Measurement of Atmospheric Sea Salt Concentration in the Dry Storage Facility of the Spent Nuclear Fuel  

SciTech Connect

Spent nuclear fuel coming from a Japanese nuclear power plant is stored in the interim storage facility before reprocessing. There are two types of the storage methods which are wet and dry type. In Japan, it is anticipated that the dry storage facility will increase compared with the wet type facility. The dry interim storage facility using the metal cask has been operated in Japan. In another dry storage technology, there is a concrete overpack. Especially in USA, a lot of concrete overpacks are used for the dry interim storage. In Japan, for the concrete cask, the codes of the Japan Society of Mechanical Engineers and the governmental technical guidelines are prepared for the realization of the interim storage as well as the code for the metal cask. But the interim storage using the concrete overpack has not been in progress because the evaluation on the stress corrosion cracking (SCC) of the canister is not sufficient. Japanese interim storage facilities would be constructed near the seashore. The metal casks and concrete overpacks are stored in the storage building in Japan. On the other hand, in USA they are stored outside. It is necessary to remove the decay heat of the spent nuclear fuel in the cask from the storage building. Generally, the heat is removed by natural cooling in the dry storage facility. Air including the sea salt particles goes into the dry storage facility. Concerning the concrete overpack, air goes into the cask body and cools the canister. Air goes along the canister surface and is in contact with the surface directly. In this case, the sea salt in the air attaches to the surface and then there is the concern about the occurrence of the SCC. For the concrete overpack, the canister including the spent fuel is sealed by the welding. The loss of sealability caused by the SCC has to be avoided. To evaluate the SCC for the canister, it is necessary to make clear the amount of the sea salt particles coming into the storage building and the concentration on the canister. In present, the evaluation on that point is not sufficient. In this study, the concentration of the sea salt particles in the air and on the surface of the storage facility are measured inside and outside of the building. For the measurement, two sites of the dry storage facility using the metal cask are chosen. This data is applicable for the evaluation on the SCC of the canister to realize the interim storage using the concrete overpack. (authors)

Masumi Wataru; Hisashi Kato; Satoshi Kudo; Naoko Oshima; Koji Wada [Central Research Institute of Electric Power Industry - CRIEPI (Japan); Hirofumi Narutaki [Electric Power Engineering Systems Co. Ltd. (Japan)

2006-07-01T23:59:59.000Z

125

The final Record of Decision for the St. Louis North County Sites (ROD) presents the final remedy for cleanup of sites in North St. Louis County that  

E-Print Network (OSTI)

Properties (VPs), and Hazelwood Interim Storage Site (HISS)/Latty Avenue VPs. Contamination is being in St. Louis, Missouri and the FUSRAP Project Office at 8945 Latty Avenue in Berkeley, Missouri. The ROD addressed under the Formerly Utilized Sites Remedial Action Program (FUSRAP). The ROD was signed

US Army Corps of Engineers

126

EA-1146: Radioactive Waste Storage at Rocky Flats Environmental Technology  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

46: Radioactive Waste Storage at Rocky Flats Environmental 46: Radioactive Waste Storage at Rocky Flats Environmental Technology Site, Golden, Colorado EA-1146: Radioactive Waste Storage at Rocky Flats Environmental Technology Site, Golden, Colorado SUMMARY This EA evaluates the environmental impacts of the proposal to convert buildings at the U.S. Department of Energy Rocky Flats Environmental Technology Site from their former uses to interim waste storage facilities in order to increase storage capacity for low-level waste, low-level mixed waste, transuranic waste, and transuranic mixed waste. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD April 9, 1996 EA-1146: Finding of No Significant Impact Radioactive Waste Storage at Rocky Flats Environmental Technology Site, Golden, Colorado

127

DNFSB Recommendation 94-1 Hanford Site Integrated Stabilization Management Plan. Volume 1  

SciTech Connect

This document describes the plans of the Hanford Site for the safe interim storage of fissile materials. Currently, spent nuclear fuels reside in storage basins that have leaked in the past and are projected to leak in the future. Other problems in the basins include; sludge from decomposition, degraded cladding of fuel elements, and construction defects which make the basins seismically unsafe. This management plan describes the time and cost that it will take to implement a safe interim storage plan for the fissile materials.

McCormack, R.L.

1995-08-01T23:59:59.000Z

128

DOELEA-1211 Environmental Assessment Relocation and Storage of Isotopic Heat Sources, Hanford Site,  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOELEA-1211 DOELEA-1211 - Environmental Assessment Relocation and Storage of Isotopic Heat Sources, Hanford Site, Richland, Washington U.S. Department of Energy Richland, Washington June 1997 DOE/EA-1211 ENVIRONMENTAL ASSESSMENT FOR THE RELOCATION AND STORAGE OF ISOTOPIC HEAT SOURCES HANFORD SITE RICHLAND, WASHINGTON JUNE 1997 U.S. DEPARTMENT OF ENERGY NCHLAND, WASHINGTON Portions of this document may be iiIegiile in electronic image products. Images are produced from the best available original dornmeut DOWEA- 1 2 1 1 U.S. Department of Energy Preface PREFACE This environmental assessment (EA) has been prep- to assess potentia environmental impacts associated with the U.S. Department of Energy proposed action: Relocation and storage of the isotopic heat sources.

129

Teapot Dome: Characterization of a CO2-enhanced oil recovery and storage site in Eastern Wyoming  

Science Journals Connector (OSTI)

...storage, and underground coal gasification. Vicki Stamp has more than...unparalleled opportunity for industry and others to use the site...projects are intimately linked to industry-driven enhanced oil recovery...three-dimensional models United States waste disposal Wyoming GeoRef...

S. Julio Friedmann; Vicki W. Stamp

130

Interpretation of brine-permeability tests of the Salado Formation at the Waste Isolation Pilot Plant site: First interim report  

SciTech Connect

Pressure-pulse tests have been performed in bedded evaporites of the Salado Formation at the Waste Isolation Pilot Plant (WIPP) site to evaluate the hydraulic properties controlling brine flow through the Salado. Hydraulic conductivities ranging from about 10{sup {minus}14} to 10{sup {minus}11} m/s (permeabilities of about 10{sup {minus}21} to 10{sup {minus}18} m{sup 2}) have been interpreted from nine tests conducted on five stratigraphic intervals within eleven meters of the WIPP underground excavations. Tests of a pure halite layer showed no measurable permeability. Pore pressures in the stratigraphic intervals range from about 0.5 to 9.3 MPa. An anhydrite interbed (Marker Bed 139) appears to be one or more orders of magnitude more permeable than the surrounding halite. Hydraulic conductivities appear to increase, and pore pressures decrease, with increasing proximity to the excavations. These effects are particularly evident within two to three meters of the excavations. Two tests indicated the presence of apparent zero-flow boundaries about two to three meters from the boreholes. The other tests revealed no apparent boundaries within the radii of influence of the tests, which were calculated to range from about four to thirty-five meters from the test holes. The data are insufficient to determine if brine flow through evaporites results from Darcy-like flow driven by pressure gradients within naturally interconnected porosity or from shear deformation around excavations connecting previously isolated pores, thereby providing pathways for fluids at or near lithostatic pressure to be driven towards the low-pressure excavations. Future testing will be performed at greater distances from the excavations to evaluate hydraulic properties and processes beyond the range of excavation effects.

Beauheim, R.L. (Sandia National Labs., Albuquerque, NM (United States)); Saulnier, G.J. Jr.; Avis, J.D. (INTERA, Inc., Austin, TX (United States))

1991-08-01T23:59:59.000Z

131

Storage  

NLE Websites -- All DOE Office Websites (Extended Search)

Storage Storage DUF6 Health Risks line line Accidents Storage Conversion Manufacturing Disposal Transportation Storage A discussion of depleted UF6 cylinder storage activities and associated risks. Management Activities for Cylinders in Storage The long-term management of the existing DUF6 storage cylinders and the continual effort to remediate and maintain the safe condition of the DUF6 storage cylinders will remain a Departmental responsibility for many years into the future. The day to day management of the DUF6 cylinders includes actions designed to cost effectively maintain and improve their storage conditions, such as: General storage cylinder and storage yard maintenance; Performing regular inspections of cylinders; Restacking and respacing the cylinders to improve drainage and to

132

Fuel Cycle Technologies Near Term Planning for Storage and Transportation of Used Nuclear Fuel  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Fuels Storage Fuels Storage and Transportation Planning Project (NFST) Program Status Jeff Williams Project Director National Transportation Stakeholders Forum Buffalo, New York May 2013 2  "With the appropriate authorizations from Congress, the Administration currently plans to implement a program over the next 10 years that:  Sites, designs and licenses, constructs and begins operations of a pilot interim storage facility by 2021 with an initial focus on accepting used nuclear fuel from shut-down reactor sites;  Advances toward the siting and licensing of a larger interim storage facility to be available by 2025 that will have sufficient capacity to provide flexibility in the waste management system and allows for acceptance of enough used

133

Settlement Agreement on TRU Mixed Waste Storage at Nevada Test Site Summary  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Settlement Agreement for Transuranic (TRU) Mixed Settlement Agreement for Transuranic (TRU) Mixed Waste Storage Issues at the Nevada Test Site (NTS) State Nevada Agreement Type Settlement Agreement Legal Driver(s) RCRA Scope Summary Settle the Finding of Alleged Violation (FOAV) and Order of November 1, 1990, and the FOAV of June 24, 1991, related to the TRU waste storage pad at Area 5 of the NTS Parties DOE; Nevada Department of Environmental Protection Date 6/11/1992 SCOPE * Settle the Finding of Alleged Violation (FOAV) and Order of November 1, 1990, and the FOAV of June 24, 1991, related to the TRU waste storage pad at Area 5 of the NTS. ESTABLISHING MILESTONES * Within 90 days of the effective date of this Agreement, DOE will provide to NDEP documentation of why the current inventory of TRU mixed waste cannot be removed

134

Niagara Falls Storage Site environmental surveillance report for calendar year 1993  

SciTech Connect

This report summarizes the results of environmental surveillance activities conducted at the Niagara Falls Storage Site (NFSS) during calendar year 1993. It includes an overview of site operations, the basis for radiological and nonradiological monitoring, a summary of the results, and the estimated dose to the offsite population. Environmental surveillance activities were conducted in accordance with the site environmental monitoring plan, which describes the rationale and design criteria for the surveillance program, the frequency of sampling and analysis, specific sampling and analysis procedures, and quality assurance requirements. NFSS is in compliance with National Emission Standards for Hazardous Air Pollutants (NESHAPs) Subpart H of the Clean Air Act as well as the requirements of the National Pollutant Discharge Elimination System (NPDES) under the Clean Water Act. Located in northwestern New York, the site covers 191 acres. From 1944 to the present, the primary use of NFSS has been storage of radioactive residues that were by-products of uranium production. Most onsite areas of residual radioactivity above regulatory guidelines were remediated during the early 1980s. Additional isolated areas of onsite contamination were remediated in 1989, and the materials were consolidated into the waste containment structure in 1991. Remediation of the site has now been completed.

Not Available

1994-06-01T23:59:59.000Z

135

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

Energy.gov (U.S. Department of Energy (DOE))

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

136

Distributed Energy Resources On-Site Optimization for Commercial Buildings with Electric and Thermal Storage Technologies  

E-Print Network (OSTI)

and solar thermal collectors; electrical storage, flowis disallowed; 5. a low storage, PV, and solar thermal priceand heat storage; heat exchangers for application of solar

Stadler, Michael

2008-01-01T23:59:59.000Z

137

Savannah River Operations Office Interim Management of Nuclear  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

0 0 Federal Register / Vol. 62, No. 70 / Friday, April 11, 1997 / Notices 1 The term ''failed'' means that the cladding on the fuel has been breached. The ROD, 60 Fed. Reg. 65300 (December 19, 1995), stated that failed fuel is indicated by gas releases from a fuel storage canister or visible failure of the cladding or canisters. select samples for specialized surveys for example on children's services or on access for persons with disabilities. [FR Doc. 97-9341 Filed 4-10-97; 8:45 am] BILLING CODE 4000-01-P DEPARTMENT OF ENERGY Savannah River Operations Office Interim Management of Nuclear Materials at the Savannah River Site AGENCY: Department of Energy. ACTION: Supplemental record of decision and supplement analysis determination. SUMMARY: The U.S. Department of Energy (DOE) prepared a final

138

Record of Technical Change - Corrective Action Plan for Corrective Action Unit 204: Storage Bunkers, Nevada Test Site, Nevada, Revision 0  

SciTech Connect

Record of Technical Change, Technical Change No. CAP-1, dated April 13, 2005 for Corrective Action Plan for Corrective Action Unit 204: Storage Bunkers, Nevada Test Site, Nevada, Revision 0, September 2004, DOE/NV--1003.

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

2005-04-13T23:59:59.000Z

139

Niagara falls storage site: Annual site environmental report, Lewiston, New York, Calendar Year 1988: Surplus Facilities Management Program (SFMP)  

SciTech Connect

The monitoring program at the Niagara Falls Storage Site (NFSS) measures radon concentrations in air; external gamma radiation levels; and uranium and radium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard and to assess its potential effect on public health, the radiation dose was calculated for a hypothetical maximally exposed individual. Based on the conservative scenario described in this report, this hypothetical individual receives an annual external exposure approximately equivalent to 6 percent of the DOE radiation protection standard of 100 mrem/yr. This exposure is less than a person receives during two round-trip flights from New York to Los Angeles (because of the greater amounts of cosmic radiation at higher altitudes). The cumulative dose to the population within an 80-km (50-mi) radius of the NFSS that results from radioactive materials present at the site is indistinguishable from the dose that the same population receives from naturally occurring radioactive sources. Results of the 1988 monitoring show that the NFSS is in compliance with applicable DOE radiation protection standards. 17 refs., 31 figs., 20 tabs.

Not Available

1989-04-01T23:59:59.000Z

140

Environmental Assessment for the Ammunition Storage Facility at the Savannah River Site  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

t30. t30. U.S. DEPARTHEHT OF EMERCT , FXNIDIIG OF It0 SIONI~ICAMT. IMPACT -1TIOH STORAGE E'ACXLITX AT THE SAVAxmAa RI-R iIT@ " Afl[EN, 6OtfTE CAROLXNA AGEYCT: U.S. Department of Energy ACTIOR: Finding of No Significant Impact s-r: The Department of Energy (DOE1 hqe prepared an Environmental ~Asscssx~ent (EA), DOE/EA-0820, for the proposed construction and operation of ~rl Ammunition Storage Facility at the Savannah River Site (SRS), Aiken, South Carolina. Based on the analyses in the &A, DOE ha8 determined that the propoeed action ie aot a major Federal action significantly affecting the quality of the human environment, within the meaning of the Natioaal Eavironmcatal Policy Act (NEPA) of 1969. Therefore, the preparatioa of an environruents~,impaCt Statement iS not required

Note: This page contains sample records for the topic "interim storage site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Degradation of transuranic waste drums in underground storage at the Hanford Site  

SciTech Connect

In situ inspections were performed on tarp-covered 55-gallon drums of transuranic (TRU) waste stored underground at the Hanford Site. These inspections were part of a task to characterize TRU drums for extent of corrosion degradation and uncertainty in TRU designation (inaccuracy in earlier assay determinations may have led to drums that actually were low-level waste to be termed TRU), and to attempt to correlate accuracy of existing records with actual drum contents. Two separate storage trench sites were investigated; a total of 90 drums were inspected with ultrasonic techniques and 104 additional drums were visually inspected. A high-humidity environment in the underground storage trenches had been reported in earlier investigations and was expected to result in substantial corrosion degradation. However, corrosion was much less than expected. Only a small percentage of drums had significant corrosion (with one breach) and the maximum rate was estimated at 0.051 mm/yr (2 mils/yr). The corrosion time of underground exposure was 14 to 15 years. These inspection results should be applicable to other similar environments (this applicability should be restricted to arid climates such as the Hanford Site) where drums are stored underground but shielded from direct soil contact by a tarp or other means. Soil contact would lead to more rapid corrosion.

Duncan, D.R.

1996-05-07T23:59:59.000Z

142

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

SciTech Connect

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

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

1985-01-01T23:59:59.000Z

143

Closure Report for Corrective Action Unit 214: Bunkers and Storage Areas, Nevada Test Site, Nevada  

SciTech Connect

Corrective Action Unit (CAU) 214 is located in Areas 5, 11, and 25 of the Nevada Test Site (NTS). CAU 214 is listed in the Federal Facility Agreement and Consent Order (FFACO, 1996) as ''Corrective Action Unit 214: Bunkers and Storage Areas,'' and is comprised of nine Corrective Action Sites (CASs): {sm_bullet} CAS 05-99-01, Fallout Shelters {sm_bullet} CAS 11-22-03, Drum {sm_bullet} CAS 25-23-01, Contaminated Materials {sm_bullet} CAS 25-23-19, Radioactive Material Storage {sm_bullet} CAS 25-34-03, Motor Dr/Gr Assembly (Bunker) {sm_bullet} CAS 25-34-04, Motor Dr/Gr Assembly (Bunker) {sm_bullet} CAS 25-34-05, Motor Dr/Gr Assembly (Bunker) {sm_bullet} CAS 25-99-12, Fly Ash Storage {sm_bullet} CAS 25-99-18, Storage Area The Nevada Division of Environmental Protection (NDEP)-approved corrective action alternative for CASs 11-22-03, 25-34-03, 25-34-04, 25-34-05, 25-99-12, and 25-99-18 is No Further Action. Closure activities included: {sm_bullet} Removing and disposing of the fly ash and surrounding wooden structure at CAS 25-99-12 as a best management practice The NDEP-approved corrective action alternative for CAS 05-99-01 in CAU 214 is Clean Closure. Closure activities included: {sm_bullet} Removing and disposing of soil contaminated with the pesticide dieldrin The NDEP-approved corrective action alternative for CASs 25-23-01 and 25-23-19 is Closure in Place with Administrative Controls. Closure activities included: {sm_bullet} Removing and disposing of soil contaminated with chromium and soil impacted with the pesticides chlordane and heptachlor {sm_bullet} Implementing use restrictions (UR) at both CASs as detailed in the CAU 214 Corrective Action Plan (CAP) (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2005) {sm_bullet} Posting UR warning signs around CASs 25-23-01 and 25-23-19 on the existing chain link fence

NSTec Environmental Restoration

2006-09-01T23:59:59.000Z

144

Analysis of long-term impacts of TRU waste remaining at generator/storage sites for No Action Alternative 2  

SciTech Connect

This report is a supplement to the Waste Isolation Pilot Plant Disposal-Phase Final Supplemental Environmental Impact Statement (SEIS-II). Described herein are the underlying information, data, and assumptions used to estimate the long-term human-health impacts from exposure to radionuclides and hazardous chemicals in transuranic (TRU) waste remaining at major generator/storage sites after loss of institutional control under No Action Alternative 2. Under No Action Alternative 2, TRU wastes would not be emplaced at the Waste Isolation Pilot Plant (WIPP) but would remain at generator/storage sites in surface or near-surface storage. Waste generated at smaller sites would be consolidated at the major generator/storage sites. Current TRU waste management practices would continue, but newly generated waste would be treated to meet the WIPP waste acceptance criteria. For this alternative, institutional control was assumed to be lost 100 years after the end of the waste generation period, with exposure to radionuclides and hazardous chemicals in the TRU waste possible from direct intrusion and release to the surrounding environment. The potential human-health impacts from exposure to radionuclides and hazardous chemicals in TRU waste were analyzed for two different types of scenarios. Both analyses estimated site-specific, human-health impacts at seven major generator/storage sites: the Hanford Site (Hanford), Idaho National Engineering and Environmental Laboratory (INEEL), Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), Rocky Flats Environmental Technology Site (RFETS), and Savannah River Site (SRS). The analysis focused on these seven sites because 99 % of the estimated TRU waste volume and inventory would remain there under the assumptions of No Action Alternative 2.

Buck, J.W.; Bagaasen, L.M.; Bergeron, M.P.; Streile, G.P. [and others

1997-09-01T23:59:59.000Z

145

Amended Record of Decision for the Interim Management of Nuclear Materials (DOE/EIS-0220) (1/26/01)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

88 88 Federal Register / Vol. 66, No. 18 / Friday, January 26, 2001 / Notices 1 A ''pit'' is a nuclear weapon component. 2 A physical blend of uranium oxide and plutonium oxide. DEPARTMENT OF ENERGY Interim Management of Nuclear Materials AGENCY: Department of Energy ACTION: Amended record of decision. SUMMARY: On December 12, 1995, the U.S. Department of Energy (DOE) issued a Record of Decision (ROD) and Notice of Preferred Alternatives, 60 FR 65300 (December 19, 1995), for the final environmental impact statement, Interim Management of Nuclear Materials (IMNM EIS) (DOE/EIS-0220, October 20, 1995), at the Savannah River Site (SRS), Aiken, South Carolina. As part of its decision, DOE decided to construct a new facility, the Actinide Packaging and Storage Facility (APSF), to prepare, package, and store

146

INTERIM POLICY JANUARY 9, 2004  

E-Print Network (OSTI)

INTERIM POLICY JANUARY 9, 2004 CORNELL UNIVERSITY POLICY LIBRARY Health and Safety POLICY 2 _________________________________________________________________________________________________________________________________________________ POLICY STATEMENT. _________________________________________________________________________________________________________________________________________________ REASON FOR POLICY

Chen, Tsuhan

147

Distributed Energy Resources On-Site Optimization for Commercial Buildings with Electric and Thermal Storage Technologies  

E-Print Network (OSTI)

lead/acid battery, and thermal storage, capabilities, withhour electrical flow battery 8 thermal Not all constraintslifetime ( a) thermal storage 11 flow battery absorption

Stadler, Michael

2008-01-01T23:59:59.000Z

148

EA-1120: Solid Residues Treatment, Repackaging and Storage at the Rocky  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

0: Solid Residues Treatment, Repackaging and Storage at the 0: Solid Residues Treatment, Repackaging and Storage at the Rocky Flats Environmental Technology Site, Golden, Colorado EA-1120: Solid Residues Treatment, Repackaging and Storage at the Rocky Flats Environmental Technology Site, Golden, Colorado SUMMARY This EA evaluates the environmental impacts of the proposal to stabilize, if necessary, and/or repackage the residues for safe interim storage at the Site while awaiting the completion and opening of a suitable repository to which they would be shipped for disposal from the U.S. Department of Energy Rocky Flats Environmental Technology Site in Golden, Colorado. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD April 1, 1996 EA-1120: Finding of No Significant Impact Solid Residues Treatment, Repackaging and Storage at the Rocky Flats

149

Niagara Falls Storage Site, Lewiston, New York: Annual site environmental report, Calendar year 1987: Formerly Utilized Sites Remedial Action Program (FUSRAP)  

SciTech Connect

The monitoring program at the Niagara Falls Storage Site (NFSS) measures radon gas concentrations in air; external gamma radiation levels; and uranium and radium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard and to assess its potential effect on public health, the radiation dose was calculated for the maximally exposed individual. Based on the conservative scenario described in the report, this individual would receive an annual external exposure approximately equivalent to 6 percent of the DOE radiation protection standard of 100 mrem/yr. By comparison, the incremental dose received from living in a brick house versus a wooden house is 10 mrem/yr above background. The cumulative dose to the population within an 80-km (50-mi) radius of the NFSS that would result from radioactive materials present at the site would be indistinguishable from the dose that the same population would receive from naturally occurring radioactive sources. Results of the 1987 monitoring show that the NFSS is in compliance with the DOE radiation protection standard. 13 refs., 10 figs., 20 tabs.

Not Available

1988-04-01T23:59:59.000Z

150

Policy Statement and Interim  

E-Print Network (OSTI)

1 Policy Statement and Interim Procedures CORNELL UNIVERSITY POLICY LIBRARY POLICY 8.3 Volume: 8 Emergency Planning POLICY STATEMENT Cornell University organizes, coordinates, and directs available of this effort is dependent on the development of periodic review of comprehensive plans. This policy includes

Hemami, Sheila S.

151

Niagara Falls storage site annual environmental report for calendar year 1990, Lewiston, New York  

SciTech Connect

Environmental monitoring of the US DOE Niagara Falls Storage Site (NFSS) and surrounding area began in 1981. NFSS is part of a DOE program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial, operations causing conditions the Congress has authorized DOE to remedy. Environmental monitoring systems at NFSS include sampling networks for radon concentrations in air; external gamma radiation exposure; and total uranium and radium-226 concentrations in surface water sediments, and groundwater. Additionally, several nonradiological parameters are routinely measured in groundwater. During 1990, the average ambient air radon concentration (including background) at NFSS ranged from 0.3 to 0.7 pCi/L (0.01 to 0.03 Bq/L); the maximum at any location for any quarter was 1.6 pCi/L (0.06 Bq/L). The average on-site external gamma radiation exposure level was 69 mR/yr; the average at the property line was 68 mR/yr (including background). The average background radiation level in the area was 66 mR/yr. Average annual concentrations of radium-226 and total uranium in surface water ranged from 0.4E-9 to 0.9E-9 {mu}Ci/m1 (0.02 to 0.03 Bq/L) and from 5E-9 to 9E-9 {mu}Ci/m1 (0.2 to 0.3 Bq/L), respectively. Routine analyses of groundwater samples from NFSS included the indicator parameters total organic carbon, total organic halides, pH, and specific conductivity.

Not Available

1991-08-01T23:59:59.000Z

152

Availability of the St. Louis North County Site Feasibility Study and Proposed Plan (FS/PP) for Public Review and Comment  

E-Print Network (OSTI)

), SLAPS Vicinity Properties (VPs), and Hazelwood Interim Storage Site (HISS)/Latty Avenue VPs. While of Engineers, St. Louis District, FUSRAP Project Office at 8945 Latty Avenue in Berkeley, Missouri 63134; or 2 Cotner, FUSRAP Program Manager, U.S. Army Corps of Engineers, St. Louis District, 8945 Latty Avenue

US Army Corps of Engineers

153

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

Energy.gov (U.S. Department of Energy (DOE))

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

154

Sandboxing for a free-to-join grid with support for secure site-wide storage area  

E-Print Network (OSTI)

Sandboxing for a free-to-join grid with support for secure site-wide storage area Edjozane to provide security for OurGrid, an easy-to-use free-to-join grid that sup- ports Bag-of-Tasks applications. OurGrid poses in- teresting security challenges. It is free-to-join (which means one runs unknown

Cirne, Walfredo

155

Distributed Energy Resources On-Site Optimization for Commercial Buildings with Electric and Thermal Storage Technologies  

E-Print Network (OSTI)

efficiency requirements - Maximum emission limits Investment constraints: - Payback period is constrained Storage constraints: - Electricity stored is limited by battery

Stadler, Michael

2008-01-01T23:59:59.000Z

156

States want say in nuclear waste storage  

Science Journals Connector (OSTI)

The states have put Congress and the executive branch on notice that they want a very active role in deciding where and how the nation's nuclear wastes will be stored. ... The 19-member State Planning Council on Radioactive Waste Management, appointed by President Carter in February 1980, in its interim report says that it is seeking a middle ground between giving states or Indian tribes a veto over the siting of long-term nuclear waste storage facilities and pre-emptive imposition of federal will. ...

1981-04-06T23:59:59.000Z

157

EA-1120: Solid Residues Treatment, Repackaging and Storage at the Rocky  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

20: Solid Residues Treatment, Repackaging and Storage at the 20: Solid Residues Treatment, Repackaging and Storage at the Rocky Flats Environmental Technology Site, Golden, Colorado EA-1120: Solid Residues Treatment, Repackaging and Storage at the Rocky Flats Environmental Technology Site, Golden, Colorado SUMMARY This EA evaluates the environmental impacts of the proposal to stabilize, if necessary, and/or repackage the residues for safe interim storage at the Site while awaiting the completion and opening of a suitable repository to which they would be shipped for disposal from the U.S. Department of Energy Rocky Flats Environmental Technology Site in Golden, Colorado. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD April 1, 1996 EA-1120: Finding of No Significant Impact

158

Closure Report for Corrective Action Unit 124, Storage Tanks, Nevada Test Site, Nevada with Errata Sheet, Revision 0  

SciTech Connect

This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 124, Storage Tanks, Nevada Test Site (NTS), Nevada. This report complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996; as amended January 2007). This CR provides documentation and justification for the closure of CAU 124 without further corrective action. This justification is based on process knowledge and the results of the investigative activities conducted in accordance with the Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 124: Storage Tanks, Nevada Test Site, Nevada (NNSA/NSO, 2007). The SAFER Plan provides information relating to site history as well as the scope and planning of the investigation. Therefore, this information will not be repeated in this CR.

Alfred Wickline

2008-01-01T23:59:59.000Z

159

CHARACTERIZING DOE HANFORD SITE WASTE ENCAPSULATION STORAGE FACILITY CELLS USING RADBALL  

SciTech Connect

RadBall{trademark} is a novel technology that can locate and quantify unknown radioactive hazards within contaminated areas, hot cells, and gloveboxes. The device consists of a colander-like outer tungsten collimator that houses a radiation-sensitive polymer semi-sphere. The collimator has a number of small holes with tungsten inserts; as a result, specific areas of the polymer are exposed to radiation becoming increasingly more opaque in proportion to the absorbed dose. The polymer semi-sphere is imaged in an optical computed tomography scanner that produces a high resolution 3D map of optical attenuation coefficients. A subsequent analysis of the optical attenuation data using a reverse ray tracing or backprojection technique provides information on the spatial distribution of gamma-ray sources in a given area forming a 3D characterization of the area of interest. RadBall{trademark} was originally designed for dry deployments and several tests, completed at Savannah River National Laboratory and Oak Ridge National Laboratory, substantiate its modeled capabilities. This study involves the investigation of the RadBall{trademark} technology during four submerged deployments in two water filled cells at the DOE Hanford Site's Waste Encapsulation Storage Facility.

Farfan, E.; Coleman, R.

2011-03-31T23:59:59.000Z

160

Referenced-site environmental document for a Monitored Retrievable Storage facility: backup waste management option for handling 1800 MTU per year  

SciTech Connect

This environmental document includes a discussion of the purpose of a monitored retrievable storage facility, a description of two facility design concepts (sealed storage cask and field drywell), a description of three reference sites (arid, warm-wet, and cold-wet), and a discussion and comparison of the impacts associated with each of the six site/concept combinations. This analysis is based on a 15,000-MTU storage capacity and a throughput rate of up to 1800 MTU per year.

Silviera, D.J.; Aaberg, R.L.; Cushing, C.E.; Marshall, A.; Scott, M.J.; Sewart, G.H.; Strenge, D.L.

1985-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "interim storage site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Waste Panel Expected to Back Interim Storage  

Science Journals Connector (OSTI)

...a nuclear waste repository at Yucca Mountain, Nevada, last year, President...Then it would be shipped to Yucca Mountain, transferred into steel cylinders...licensed. One reason was that Yucca Mountain had to cool waste before permanently...

Eli Kintisch

2011-07-08T23:59:59.000Z

162

Feasibility study: Assess the feasibility of siting a monitored retrievable storage facility. Phase 1  

SciTech Connect

The purpose of phase one of this study are: To understand the waste management system and a monitored retrievable storage facility; and to determine whether the applicant has real interest in pursuing the feasibility assessment process. Contents of this report are: Generating electric power; facts about exposure to radiation; handling storage, and transportation techniques; description of a proposed monitored retrievable storage facility; and benefits to be received by host jurisdiction.

King, J.W.

1993-08-01T23:59:59.000Z

163

Stump Harvesting: Interim Guidance on  

E-Print Network (OSTI)

to supply biomass for heat and power generation in the UK and attention is now turning to the potential placed in adjacent `wind-rows', and then extracted by forwarder to road side for storage and subsequent, the benefits of increasing the use of biomass, as well as other potential advantages (such as easier site

164

Numerical simulation of ground-water flow in the Culebra dolomite at the Waste Isolation Pilot Plant (WIPP) site: Second interim report  

SciTech Connect

This hydrogeologic modeling study has been performed as part of the regional hydrologic characterization of the Waste Isolation Pilot Plant (WIPP) Site in southeastern New Mexico. The study resulted in an estimation of the transmissivity distrubution, hydraulic potentials, flow field, and fluid densities in the Culebra Dolomite Member of the Permian Rustler Formation at the WIPP site. The three-dimensional finite-difference code SWIFT-II was employed for the numerical modeling, using variable-fluid-density and a single-porosity formulation. The modeled area includes and extends beyond the WIPP controlled zone (Zone 3). The work performed consisted of modeling the hydrogeology of the Culebra using two approaches: (1) steady-state modeling to develop the best estimate of the undisturbed head distribution, i.e., of the situation before sinking if the WIPP shafts, which began in 1981; and (2) superimposed transient modeling of local hydrologic responses to excavation of the three WIPP shafts at the center of the WIPP site, as well as to various well tests. Boundary conditions (prescribed constant fluid pressures and densities) were estimated using hydraulic-head and fluid-density data obtained from about 40 wells at and near the WIPP site. The transient modeling used the calculated steady-state freshwater heads as initial conditions. 107 refs., 112 figs., 22 tabs.

LaVenue, A.M.; Haug, A.; Kelley, V.A.

1988-03-01T23:59:59.000Z

165

Amended Record of Decision for the Interim Management of Nuclear Materials: Savannah River Site Waste Management (DOE/EIS-0220) (07/28/03)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

29 29 Federal Register / Vol. 68, No. 144 / Monday, July 28, 2003 / Notices Electronic Access to This Document You may view this document, as well as all other Department of Education documents published in the Federal Register, in text or Adobe Portable Document Format (PDF) on the Internet at the following site: http://www.ed.gov/ legislation/FedRegister. To use PDF you must have Adobe Acrobat Reader, which is available free at this site. If you have questions about using the PDF, call the U.S. Government Printing Office (GPO), toll free, at 1- 888-293-6498; or in the Washington, DC, area at (202) 512-1530. Note: The official version of this document is the document published in the Federal Register. Free Internet access to the official edition of the Federal Register and the Code

166

Revised corrective action plan for underground storage tank 2331-U at the Building 9201-1 Site  

SciTech Connect

This document represents the Corrective Action Plan for underground storage tank (UST) 2331-U, previously located at Building 9201-1, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Tank 2331-U, a 560-gallon UST, was removed on December 14, 1988. This document presents a comprehensive summary of all environmental assessment investigations conducted at the Building 9201-1 Site and the corrective action measures proposed for remediation of subsurface petroleum product contamination identified at the site. This document is written in accordance with the regulatory requirements of the Tennessee Department of Environment and Conservation (TDEC) Rule 1200-1-15-.06(7).

Bohrman, D.E.; Ingram, E.M. [Oak Ridge Y-12 Plant, TN (United States)

1993-09-01T23:59:59.000Z

167

Corrective Action Investigation Plan for Corrective Action Unit 145: Wells and Storage Holes, Nevada Test Site, Nevada, Rev. No.: 0  

SciTech Connect

This Corrective Action Investigation Plan (CAIP) contains project-specific information for conducting site investigation activities at Corrective Action Unit (CAU) 145: Wells and Storage Holes. Information presented in this CAIP includes facility descriptions, environmental sample collection objectives, and criteria for the selection and evaluation of environmental samples. Corrective Action Unit 145 is located in Area 3 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 145 is comprised of the six Corrective Action Sites (CASs) listed below: (1) 03-20-01, Core Storage Holes; (2) 03-20-02, Decon Pad and Sump; (3) 03-20-04, Injection Wells; (4) 03-20-08, Injection Well; (5) 03-25-01, Oil Spills; and (6) 03-99-13, Drain and Injection Well. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation (CAI) prior to evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. One conceptual site model with three release scenario components was developed for the six CASs to address all releases associated with the site. The sites will be investigated based on data quality objectives (DQOs) developed on June 24, 2004, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQOs process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 145.

David A. Strand

2004-09-01T23:59:59.000Z

168

US Department of Energy interim mixed waste inventory report: Waste streams, treatment capacities and technologies: Volume 4, Site specific---Ohio through South Carolina  

SciTech Connect

The Department of Energy (DOE) has prepared this report to provide an inventory of its mixed wastes and treatment capacities and technologies in response to Section 105(a) of the Federal Facility Compliance Act (FFCAct) of 1992 (Pub. L. No. 102-386). As required by the FFCAct-1992, this report provides site-specific information on DOE`s mixed waste streams and a general review of available and planned treatment facilities for mixed wastes at the following five Ohio facilities: Battelle Columbus Laboratories; Fernald Environmental Management Project; Mound Plant; Portsmouth Gaseous Diffusion Plant; and RMI, Titanium Company.

Not Available

1993-04-01T23:59:59.000Z

169

A preliminary sub-basin scale evaluation framework of site suitability for onshore aquifer-based CO{sub 2} storage in China  

SciTech Connect

Development of a reliable, broadly applicable framework for the identification and suitability evaluation of potential CO{sub 2} storage sites is essential before large-scale deployment of carbon dioxide capture and geological storage (CCS) can commence. In this study, a sub-basin scale evaluation framework was developed to assess the suitability of potential onshore deep saline aquifers for CO{sub 2} storage in China. The methodology, developed in consultation with experts from the academia and the petroleum industry in China, is based on a multi-criteria analysis (MCA) framework that considers four objectives: (1) storage optimization, in terms of storage capacity and injectivity; (2) risk minimization and storage security; (3) environmental restrictions regarding surface and subsurface use; and (4) economic considerations. The framework is designed to provide insights into both the suitability of potential aquifer storage sites as well as the priority for early deployment of CCS with existing CO{sub 2} sources. Preliminary application of the framework, conducted using GIS-based evaluation tools revealed that 18% of onshore aquifer sites with a combined CO{sub 2} storage capacity of 746 gigatons are considered to exhibit very high suitability, and 11% of onshore aquifer sites with a total capacity of 290 gigatons exhibit very high priority opportunities for implementation. These onshore aquifer sites may provide promising opportunities for early large-scale CCS deployment and contribute to CO{sub 2} mitigation in China for many decades.

Wei, Ning; Li, Xiaochun; Wang, Ying; Dahowski, Robert T.; Davidson, Casie L.; Bromhal Grant S.

2013-01-01T23:59:59.000Z

170

Siting Is a Constraint to Realize Environmental Benefits from Carbon Capture and Storage  

Science Journals Connector (OSTI)

Carbon capture and storage (CCS) for coal power plants reduces onsite carbon dioxide emissions, but affects other air emissions on and offsite. This research assesses the net societal benefits and costs of Monoethanolamine (MEA) CCS, valuing changes in ...

Ashok Sekar; Eric Williams; Mikhail Chester

2014-09-03T23:59:59.000Z

171

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

SciTech Connect

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

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

2011-01-12T23:59:59.000Z

172

US Air Force installation restoration program: Remedial investigation of former herbicide storage site at Johnston Island, Pacific Ocean  

SciTech Connect

This report represents a synthesis and reformatting of six primary documents and other related materials on soils, ocean sediments, air, and biota investigations conducted at Johnston Island (JI), Pacific Ocean, to characterize contamination resulting from storage of 1.37 million gallons of Herbicide Orange (HO) from 1972 through 1977. The individual study components comprise the Remedial Investigation (RI) of the former HO storage site at JI. This report describes the procedures, results, and conclusions of the sampling and analysis programs conducted at JI. Samples of site soils, ocean sediments, airborne particulates, dust, sweepings, and aquatic organisms were collected and analyzed for HO-derived 2,4-dichlorophenoxyacetic acid (2,4-D), 2,4,5-trichlorophenoxyacetic acid (2,4,5-T), and 2,3,7,8- tetrachlorodibenzo-p-dioxin (TCDD). Environmental media other than soils at the storage facility itself were found to be free of contamination or to contain very low contaminant concentrations. No contamination was found in ocean sediments, indicating possible dispersion of contaminants due to erosion. A few of the biological specimens collected were found to contain TCDD levels below the guidelines of 25 to 50 parts per trillion established by the US Food and Drug Administration; TCDD in all other biota samples was nondetectable. Analysis of samples of airborne particulates and of soils, dust, and sweepings from high-use and residential areas outside the boundaries of the former storage site indicated that there is little or no concern of adverse impacts from airborne transport and deposition of TCDD.

Not Available

1988-09-01T23:59:59.000Z

173

Supplement Analysis for the Storage of Surplus Plutonium Materials at the Savannah River Site (DOE/EIS-0229-SA-4)(09/05/07)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

9-SA-4 9-SA-4 SUPPLEMENT ANALYSIS STORAGE OF SURPLUS PLUTONIUM MATERIALS AT THE SAVANNAH RIVER SITE INTRODUCTION AND PURPOSE In April 2002, DOE decided to immediately consolidate long-term storage at the Savannah River Site (SRS) of surplus, non-pit weapons-usable plutonium then stored at the Rocky Flats Environmental Technology Site (RFETS) (DOE, 2002a). That 2002 decision did not affect an earlier DOE decision made in the January 21, 1997, Record of Decision (ROD, DOE, 1997) for the Storage and Disposition of Weapons-Usable Fissile Materials Programmatic Environmental Impact Statement (Storage and Disposition PEIS, DOE, 1996) to continue storage of non-pit surplus plutonium at Hanford, the Idaho National Laboratory (INL), and the Los Alamos

174

Report on technical feasibility of underground pumped hydroelectric storage in a marble quarry site in the Northeast United States  

SciTech Connect

The technical and economic aspects of constructing a very high head underground hydroelectric pumped storage were examined at a prefeasibility level. Excavation of existing caverns in the West Rutland Vermont marble quarry would be used to construct the underground space. A plant capacity of 1200 MW and 12 h of continuous capacity were chosen as plant operating conditions. The site geology, plant design, and electrical and mechanical equipment required were considered. The study concluded that the cost of the 1200 MW underground pumped storage hydro electric project at this site even with the proposed savings from marketable material amounts to between $581 and $595 per kilowatt of installed capacity on a January 1982 pricing level. System studies performed by the planning group of the New England Power System indicate that the system could economically justify up to about $442 per kilowatt on an energy basis with no credit for capacity. To accommodate the plant with the least expensive pumping energy, a coal and nuclear generation mix of approximately 65% would have to be available before the project becomes feasible. It is not expected that this condition can be met before the year 2000 or beyond. It is therefore concluded that the West Rutland underground pumped storage facility is uneconomic at this time. Several variables however could have marked influence on future planning and should be examined on periodic basis.

Chas. T. Main, Inc.

1982-03-01T23:59:59.000Z

175

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

SciTech Connect

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

Clayton, Christopher [U.S Department of Energy Office of Legacy Management, Washington, DC; Kothari, Vijendra [U.S Department of Energy Office of Legacy Management, Morgantown, West Virginia; Starr, Ken [U.S Department of Energy Office of Legacy Management, Westminster, Colorado; Widdop, Michael; Gillespie, Joey [SM Stoller Corporation, Grand Junction, Colorado

2012-02-26T23:59:59.000Z

176

Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 130: Storage Tanks, Nevada Test Site, Nevada, Revision 0  

SciTech Connect

This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the actions needed to achieve closure for Corrective Action Unit (CAU) 130, Storage Tanks, identified in the Federal Facility Agreement and Consent Order (FFACO) (1996, as amended February 2008). Corrective Action Unit 130 consists of the seven following corrective action sites (CASs) located in Areas 1, 7, 10, 20, 22, and 23 of the Nevada Test Site: 01-02-01, Underground Storage Tank 07-02-01, Underground Storage Tanks 10-02-01, Underground Storage Tank 20-02-03, Underground Storage Tank 20-99-05, Tar Residue 22-02-02, Buried UST Piping 23-02-07, Underground Storage Tank This plan provides the methodology for field activities needed to gather the necessary information for closing each CAS. There is sufficient information and process knowledge from historical documentation and investigations of similar sites regarding the expected nature and extent of potential contaminants to recommend closure of CAU 130 using the SAFER process. Additional information will be obtained by conducting a field investigation before selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible recommendation that no further corrective action is necessary. This will be presented in a Closure Report that will be prepared and submitted to the Nevada Division of Environmental Protection (NDEP) for review and approval. The sites will be investigated based on the data quality objectives (DQOs) finalized on April 3, 2008, by representatives of NDEP; U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and National Security Technologies, LLC. The DQO process was used to identify and define the type, amount, and quality of data needed to determine and implement appropriate corrective actions for each CAS in CAU 130. The DQO process developed for this CAU identified the following expected closure options: (1) investigation and confirmation that no contamination exists above the final action levels, leading to a no further action declaration; (2) characterization of the nature and extent of contamination, leading to closure in place with use restrictions; or (3) clean closure by remediation and verification. The following text summarizes the SAFER activities that will support the closure of CAU 130: Perform site preparation activities (e.g., utilities clearances, geophysical surveys). Move or remove and dispose of debris at various CASs, as required. Collect environmental samples from designated target populations (e.g., stained soil) to confirm or disprove the presence of contaminants of concern (COCs) as necessary to supplement existing information. If no COCs are present at a CAS, establish no further action as the corrective action. If COCs exist, collect environmental samples from designated target populations (e.g., clean soil adjacent to contaminated soil) and submit for laboratory analyses to define the extent of COC contamination. If a COC is present at a CAS, either: - Establish clean closure as the corrective action. The material to be remediated will be removed, disposed of as waste, and verification samples will be collected from remaining soil, or - Establish closure in place as the corrective action and implement the appropriate use restrictions. Obtain consensus from NDEP that the preferred closure option is sufficient to protect human health and the environment. Close the underground storage tank(s) and their contents, if any, in accordance with Nevada Administrative Code regulations. Remove the lead brick(s) found at any CAS in accordance with the Resource Conservation and Recovery Act.

Alfred Wickline

2008-07-01T23:59:59.000Z

177

Assessing health impacts of CO2 leakage from a geological storage site into buildings: role of attenuation in the unsaturated zone and building foundation  

E-Print Network (OSTI)

a) Title Assessing health impacts of CO2 leakage from a geological storage site into buildings of the greenhouse gas CO2 has the potential to be a widespread and effective option to mitigate climate change. As any industrial activity, CO2 storage may lead to adverse impact on human health and the environment

Paris-Sud XI, Université de

178

Record of Technical Change for Corrective Action Plan for Corrective Action Unit 140: Waste Dumps, burn Pits, and Storage Area, Nevada Test Site, Nevada  

SciTech Connect

Record of Technical Change for Corrective Action Plan for Corrective Action Unit 140: Waste Dumps, Burn Pits, and Storage Area, Nevada Test Site, Nevada (DOE/NV--963-Rev 2, dated November 2004).

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

2005-01-05T23:59:59.000Z

179

INTERIM RESULTS FROM A STUDY OF THE IMPACTS OF TIN(II) BASED MERCURY TREATMENT IN A SMALL STREAM ECOSYSTEM: TIMS BRANCH, SAVANNAH RIVER SITE  

SciTech Connect

Mercury (Hg) has been identified as a 'persistent, bioaccumulative and toxic' pollutant with widespread impacts throughout North America and the world (EPA. 1997a, 1997b, 1998a, 1998b, 2000). Although most of the mercury in the environment is inorganic Hg, a small proportion of total Hg is transformed through the actions of aquatic microbes into methylmercury (MeHg). In contrast to virtually all other metals, MeHg biomagnifies or becomes increasingly concentrated as it is transferred through aquatic food chains so that the consumption of mercury contaminated fish is the primary route of this toxin to humans. For this reason, the ambient water quality criterion (AWQC) for mercury is based on a fish tissue endpoint rather than an aqueous Hg concentration, as the tissue concentration (e.g., < 0.3 {mu}g/g fillet) is considered to be a more consistent indicator of exposure and risk (EPA, 2001). Effective mercury remediation at point-source contaminated sites requires an understanding of the nature and magnitude of mercury inputs, and also knowledge of how these inputs must be controlled in order to achieve the desired reduction of mercury contamination in biota necessary for compliance with AWQC targets. One of the challenges to remediation is that mercury body burdens in fish are more closely linked to aqueous MeHg than to inorganic Hg concentrations (Sveinsdottir and Mason 2005), but MeHg production is not easily predicted or controlled. At point-source contaminated sites, mercury methylation is not only affected by the absolute mercury load, but also by the form of mercury loaded. In addition, once MeHg is formed, the hydrology, trophic structure, and water chemistry of a given system affect how it is transformed and transferred through the food chain to fish. Decreasing inorganic Hg concentrations and loading may often therefore be a more achievable remediation goal, but has led to mixed results in terms of responses in fish bioaccumulation. A number of source control measures have resulted in rapid responses in lake or reservoir fisheries (Joslin 1994, Turner and Southworth 1999; Orihel et al., 2007), but examples of similar responses in Hg-contaminated stream ecosystems are less common. Recent work suggests that stream systems may actually be more susceptible to mercury bioaccumulation than lakes, highlighting the need to better understand the ecological drivers of mercury bioaccumulation in stream-dwelling fish (Chasar et al. 2009, Ward et al. 2010). In the present study we examine the response of fish to remedial actions in Tims Branch, a point-source contaminated stream on the Department of Energy's (DOE) Savannah River Site in Aiken, South Carolina. This second order stream received inorganic mercury inputs at its headwaters from the 1950s-2000s which contaminated the water, sediments, and biota downstream. In 2007, an innovative mercury removal system using tin (II) chloride (stannous chloride, SnCl{sub 2}) was implemented at a pre-existing air stripper. Tin(II) reduces dissolved Hg (II) to Hg (0), which is removed by the air stripper. During this process, tin(II) is oxidized to tin (IV) which is expected to precipitate as colloidal tin(IV) oxides and hydroxides, particulate materials with relatively low toxicity (Hallas and Cooney, 1981, EPA 2002, ATSDR, 2005). The objectives of the present research are to provide an initial assessment of the net impacts of the tin(II) based mercury treatment on key biota and to document the distribution and fate of inorganic tin in this small stream ecosystem after the first several years of operating a full scale system. To support these objectives, we collected fish, sediment, water, invertebrates, and biofilm samples from Tims Branch to quantify the general behavior and accumulation patterns for mercury and tin in the ecosystem and to determine if the treatment process has resulted in: (1) a measurable beneficial impact on (i.e., decrease of) mercury concentration in upper trophic level fish and other biota; this is a key environmental endpoint since reducing mercury concen

Looney, B.; Bryan, L.; Mathews, T.

2012-03-30T23:59:59.000Z

180

Management of Hanford Site non-defense production reactor spent nuclear fuel, Hanford Site, Richland, Washington  

SciTech Connect

The US Department of Energy (DOE) needs to provide radiologically, and industrially safe and cost-effective management of the non-defense production reactor spent nuclear fuel (SNF) at the Hanford Site. The proposed action would place the Hanford Site`s non-defense production reactor SNF in a radiologically- and industrially-safe, and passive storage condition pending final disposition. The proposed action would also reduce operational costs associated with storage of the non-defense production reactor SNF through consolidation of the SNF and through use of passive rather than active storage systems. Environmental, safety and health vulnerabilities associated with existing non-defense production reactor SNF storage facilities have been identified. DOE has determined that additional activities are required to consolidate non-defense production reactor SNF management activities at the Hanford Site, including cost-effective and safe interim storage, prior to final disposition, to enable deactivation of facilities where the SNF is now stored. Cost-effectiveness would be realized: through reduced operational costs associated with passive rather than active storage systems; removal of SNF from areas undergoing deactivation as part of the Hanford Site remediation effort; and eliminating the need to duplicate future transloading facilities at the 200 and 400 Areas. Radiologically- and industrially-safe storage would be enhanced through: (1) removal from aging facilities requiring substantial upgrades to continue safe storage; (2) utilization of passive rather than active storage systems for SNF; and (3) removal of SNF from some storage containers which have a limited remaining design life. No substantial increase in Hanford Site environmental impacts would be expected from the proposed action. Environmental impacts from postulated accident scenarios also were evaluated, and indicated that the risks associated with the proposed action would be small.

NONE

1997-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "interim storage site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Niagara Falls Storage Site environmental report for calendar year 1992, 1397 Pletcher Road, Lewiston, New York. Formerly Utilized Sites Remedial Action Program (FUSRAP)  

SciTech Connect

This report describes the environmental surveillance program at the Niagara Falls Storage Site (NFSS) and provides the results for 1992. From 1944 to the present, the primary use of NFSS has been storage of radioactive residues produced as a by-product of uranium production. All onsite areas of residual radioactivity above guidelines have been remediated. Materials generated during remediation are stored onsite in the 4-ha (10-acre) waste containment structure (WCS). The WCS is a clay-lined, clay-capped, and grass-covered storage pile. The environmental surveillance program at NFSS includes sampling networks for radon concentrations in air; external gamma radiation exposure; and total uranium and radium-226 concentrations in surface water, sediments, and groundwater. Several chemical parameters, including seven metals, are also routinely measured in groundwater. This surveillance program assists in fulfilling the DOE policy of measuring and monitoring effluents from DOE activities and calculating hypothetical doses. Monitoring results are compared with applicable Environmental Protection Agency (EPA) and New York State Department of Environmental Conservation (NYSDEC) standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements. Results of environmental monitoring during 1992 indicate that levels of the parameters measured were in compliance with all but one requirement: Concentrations of iron and manganese in groundwater were above NYSDEC groundwater quality standards. However, these elements occur naturally in the soils and groundwater associated with this region. In 1992 there were no environmental occurrences or reportable quantity releases.

Not Available

1993-05-01T23:59:59.000Z

182

DOE - Office of Legacy Management -- Wayne Site - NJ 16  

Office of Legacy Management (LM)

Wayne Site - NJ 16 Wayne Site - NJ 16 FUSRAP Considered Sites Wayne, NJ Alternate Name(s): Wayne Interim Storage Site (WISS) W.R. Grace and Company W.R. Grace Site Rare Earths, Inc. Davison Chemical Division NJ.16-1 NJ.16-2 NJ.16-3 Location: 868 Black Oak Road, Wayne, New Jersey NJ.16-5 Historical Operations: Produced crude thorium hydroxide and rare earth elements from monazite sands. Site was also used for interim storage of contaminated material removed from vicinity properties under FUSRAP. NJ.16-5 Eligibility Determination: Eligible NJ.16-1 NJ.16-11 Radiological Survey(s): Assessment Surveys NJ.16-3 NJ.16-6 NJ.16-7 NJ.16-8 NJ.16-9 Site Status: USACE cleanup complete, not yet delisted from the National Priorities List. USACE Website EPA Website Long-term Care Requirements: Long-Term Surveillance and Maintenance Requirements for Remediated FUSRAP Sites S07566_FUSRAP

183

Faculty of Science Interim Dean  

E-Print Network (OSTI)

Faculty of Science Interim Dean: Prof DE Rawlings BScHons, PhD (Rhodes) CALENDAR 2013 PART 5 #12;Science 1 Table of Contents General Information........................................................................................................... 3 The Faculty of Science

Geldenhuys, Jaco

184

Spent-fuel dry-storage testing at E-MAD (March 1978-March 1982)  

SciTech Connect

From March 1978 through March 1982, spent fuel dry storage tests were conducted at the Engine Maintenance, Assembly and Disassembly (E-MAD) facility on the Nevada Test Site to confirm that commercial reactor spent fuel could be encapsulated and passively stored in one or more interim dry storage cell concepts. These tests were: electrically heated drywell, isolated and adjacent drywell, concrete silo, fuel assembly internal temperature measurement, and air-cooled vault. This document presents the test data and results as well as results from supporting test operations (spent fuel calorimetry and canister gas sampling).

Unterzuber, R.; Milnes, R.D.; Marinkovich, B.A.; Kubancsek, G.M.

1982-09-01T23:59:59.000Z

185

Combining microseismic and geomechanical observations to interpret storage integrity at the In Salah CCS site  

Science Journals Connector (OSTI)

......several gas fields is separated from the production stream and...producing gas field at Krechba...operations in the oil and gas industry...shows the cumulative number of...H. A full field simulation...Salah gas production and CO2 storage......

Bettina P. Goertz-Allmann; Daniela Khn; Volker Oye; Bahman Bohloli; Eyvind Aker

2014-01-01T23:59:59.000Z

186

EIS-0283-S2: Amended Interim Action Determination | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

EIS-0283-S2: Amended Interim Action Determination EIS-0283-S2: Amended Interim Action Determination EIS-0283-S2: Amended Interim Action Determination Disposition of Certain Plutonium Materials at the K-Area Complex, Savannah River Site DOE has reviewed the environmental analysis relevant to preparation for disposition in the HB-Line and K-Area at SRS, and disposal at WIPP, approximately 500 kg of surplus, non-pit plutonium. DOE finds that the analysis in the Interim Management of Nuclear Material EIS and the SRS Waste Management EIS are still representative of the impacts of disposal of these materials. Therefore, no adverse environmental impacts would result from disposal of these materials as TRU waste to WIPP and this action is clearly an allowable interim action in accordance with DOE regulations

187

Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks Nevada Test Site, Nevada  

SciTech Connect

This Corrective Action Investigation Plan (CAIP) has been developed in accordance with the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the US Department of Energy, Nevada Operations Office (DOE/NV); the State of Nevada Division of Environmental Protection (NDEP); and the US Department of Defense (FFACO, 1996). The CAIP is a document that provides or references all of the specific information for investigation activities associated with Corrective Action Units (CAUs) or Corrective Action Sites (CASs). According to the FFACO, CASs are sites potentially requiring corrective action(s) and may include solid waste management units or individual disposal or release sites (FFACO, 1996). Corrective Action Units consist of one or more CASs grouped together based on geography, technical similarity, or agency responsibility for the purpose of determining corrective actions. This CAIP contains the environmental sample collection objectives and the criteria for conducting site investigation activities at CAU 135, Area 25 Underground Storage Tanks (USTs), which is located on the Nevada Test Site (NTS). The NTS is approximately 105 kilometers (km) (65 miles [mi]) northwest of Las Vegas, Nevada.

U.S. Department of Energy, Nevada Operations Office

1999-05-05T23:59:59.000Z

188

Addendum to the Streamlined Approach for Environmental Restoration Closure Report for Corrective Action Unit 452: Historical Underground Storage Tank Release Sites, Nevada Test Site, Nevada, Revision 0  

SciTech Connect

This document constitutes an addendum to the Streamlined Approach for Environmental Restoration Closure Report for Corrective Action Unit 452: Historical Underground Storage Tank Release Sites, Nevada Test Site, Nevada, April 1998 as described in the document Supplemental Investigation Report for FFACO Use Restrictions, Nevada Test Site, Nevada (SIR) dated November 2008. The SIR document was approved by NDEP on December 5, 2008. The approval of the SIR document constituted approval of each of the recommended UR removals. In conformance with the SIR document, this addendum consists of: This page that refers the reader to the SIR document for additional information The cover, title, and signature pages of the SIR document The NDEP approval letter The corresponding section of the SIR document This addendum provides the documentation justifying the cancellation of the URs for CASs: 25-25-09, Spill H940825C (from UST 25-3101-1) 25-25-14, Spill H940314E (from UST 25-3102-3) 25-25-15, Spill H941020E (from UST 25-3152-1) These URs were established as part of Federal Facility Agreement and Consent Order (FFACO) corrective actions and were based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996). Since these URs were established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, these URs were re-evaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006). This re-evaluation consisted of comparing the original data (used to define the need for the URs) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove these URs because contamination is not present at these sites above the risk-based FALs. Requirements for inspecting and maintaining these URs will be canceled, and the postings and signage at each site will be removed. Fencing and posting may be present at these sites that are unrelated to the FFACO URs such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at these sites.

Grant Evenson

2009-05-01T23:59:59.000Z

189

Addendum 2 to the Streamlined Approach for Environmental Restoration Closure Report for Corrective Action Unit 454: Historical Underground Storage Tank Release Sites, Nevada Test Site, Nevada, Revision 0  

SciTech Connect

This document constitutes an addendum to the Streamlined Approach for Environmental Restoration Closure Report for Corrective Action Unit 454: Historical Underground Storage Tank Release Sites, Nevada Test Site, Nevada, April 1998 as described in the document Supplemental Investigation Report for FFACO Use Restrictions, Nevada Test Site, Nevada (SIR) dated November 2008. The SIR document was approved by NDEP on December 5, 2008. The approval of the SIR document constituted approval of each of the recommended UR removals. In conformance with the SIR document, this addendum consists of: This page that refers the reader to the SIR document for additional information The cover, title, and signature pages of the SIR document The NDEP approval letter The corresponding section of the SIR document This addendum provides the documentation justifying the cancellation of the URs for CASs: 12-25-08, Spill H950524F (from UST 12-B-1) 12-25-10, Spill H950919A (from UST 12-COMM-1) These URs were established as part of Federal Facility Agreement and Consent Order (FFACO) corrective actions and were based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996). Since these URs were established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, these URs were re-evaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006). This re-evaluation consisted of comparing the original data (used to define the need for the URs) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove these URs because contamination is not present at these sites above the risk-based FALs. Requirements for inspecting and maintaining these URs will be canceled, and the postings and signage at each site will be removed. Fencing and posting may be present at these sites that are unrelated to the FFACO URs such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at these sites.

Grant Evenson

2009-05-01T23:59:59.000Z

190

Thermal Analysis of the SAFKEG Package for Long Term Storage  

SciTech Connect

Interim plutonium storage for up to 10 years in the K-reactor building is currently being planned at Savannah River Site (SRS). SAFKEG package could be used to store Pu metal and oxide (PuO2) in the K-reactor complex with other packagings like 9975. The SAFKEG is designed for carrying Type-B materials across the DOE complex and meets the 10CFR71 requirements. Thermal analyses were performed to ensure that the temperatures of the SAFKEG components will not exceed their temperature limits under the K-reactor storage conditions. Thermal analyses of the SAFKEG packaging with three content configurations using BNFL 3013 outer container (Rocky Flats, SRS bagless transfer cans, and BNFL inner containers) were performed for storage of PuO2 and plutonium metal

NARENDRA, GUPTA

2005-01-10T23:59:59.000Z

191

Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 134: Aboveground Storage Tanks, Nevada Test Site, Nevada  

SciTech Connect

This Streamlined Approach for Environmental Restoration (SAFER) Plan identifies the activities required for the closure of Corrective Action Unit (CAU) 134, Aboveground Storage Tanks. CAU 134 is currently listed in Appendix III of the Federal Facility Agreement and Consent Order (FFACO) (FFACO, 1996; as amended February 2008) and consists of four Corrective Action Sites (CASs) located in Areas 3, 15, and 29 of the Nevada Test Site (NTS) (Figure 1): (1) CAS 03-01-03, Aboveground Storage Tank; (2) CAS 03-01-04, Tank; (3) CAS 15-01-05, Aboveground Storage Tank; and (4) CAS 29-01-01, Hydrocarbon Stain. CAS 03-01-03 consists of a mud tank that is located at the intersection of the 3-07 and the 3-12 Roads in Area 3 of the NTS. The tank and its contents are uncontaminated and will be dispositioned in accordance with applicable federal, state, and local regulations. This CAS will be closed by taking no further action. CAS 03-01-04 consists of a potable water tank that is located at the Core Complex in Area 3 of the NTS. The tank will be closed by taking no further action. CAS 15-01-05 consists of an aboveground storage tank (AST) and associated impacted soil, if any. This CAS is located on a steep slope near the Climax Mine in Area 15 of the NTS. The AST is empty and will be dispositioned in accordance with applicable federal, state, and local regulations. Soil below the AST will be sampled to identify whether it has been impacted by chemicals at concentrations exceeding the action levels. It appears that the tank is not at its original location. Soil will also be sampled at the original tank location, if it can be found. If soil at either location has been impacted at concentrations that exceed the action levels, then the extent of contamination will be identified and a use restriction (UR) will be implemented. The site may be clean closed if contamination is less than one cubic yard in extent and can be readily excavated. If action levels are not exceeded, then no further action is required. CAS 29-01-01 consists of soil that has been impacted by a release or operations from an active diesel AST that fuels the generator at the Shoshone Receiver Site in Area 29 of the NTS. Soil below the AST will be sampled to identify whether it has been impacted at concentrations exceeding the action levels. If it is, then the extent of contamination will be identified and a UR will be implemented. The site may be clean closed if contamination is less than one cubic yard in extent, can be readily excavated, and it is determined that clean closure is feasible based upon site conditions. If action levels are not exceeded, then no further action is required. Based on review of the preliminary assessment information for CAU 134 and recent site inspections, there is sufficient process knowledge to close CAU 134 using the SAFER process.

NSTec Environmental Restoration

2008-05-31T23:59:59.000Z

192

Corrective Action Decision Document for Corrective Action Unit 204: Storage Bunkers, Nevada Test Site, Nevada: Revision 0, Including Errata Sheet  

SciTech Connect

This Corrective Action Decision Document identifies the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's corrective action alternative recommendation for each of the corrective action sites (CASs) within Corrective Action Unit (CAU) 204: Storage Bunkers, Nevada Test Site (NTS), Nevada, under the Federal Facility Agreement and Consent Order. An evaluation of analytical data from the corrective action investigation, review of current and future operations at each CAS, and a detailed comparative analysis of potential corrective action alternatives were used to determine the appropriate corrective action for each CAS. There are six CASs in CAU 204, which are all located between Areas 1, 2, 3, and 5 on the NTS. The No Further Action alternative was recommended for CASs 01-34-01, 02-34-01, 03-34-01, and 05-99-02; and a Closure in Place with Administrative Controls recommendation was the preferred corrective action for CASs 05-18-02 and 05-33-01. These alternatives were judged to meet all requirements for the technical components evaluated as well as applicable state and federal regulations for closure of the sites and will eliminate potential future exposure pathways to the contaminated media at CAU 204.

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

2004-04-01T23:59:59.000Z

193

DOE/EA-1538; Environmental Assessment for the Safeguards and Security Upgrades for the Storage of Plutonium Materials at the Savannah River Site  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

8 8 December 2005 U. S. DEPARTMENT OF ENERGY SAVANNAH RIVER OPERATIONS OFFICE SAVANNAH RIVER SITE ENVIRONMENTAL ASSESSMENT FOR THE SAFEGUARDS AND SECURITY UPGRADES FOR STORAGE OF PLUTONIUM MATERIALS AT THE SAVANNAH RIVER SITE DOE/EA-1538 ENVIRONMENTAL ASSESSMENT FOR THE SAFEGUARDS AND SECURITY UPGRADES FOR STORAGE OF PLUTONIUM MATERIALS AT THE SAVANNAH RIVER SITE December 2005 U. S. DEPARTMENT OF ENERGY SAVANNAH RIVER OPERATIONS OFFICE SAVANNAH RIVER SITE ii This page is intentionally left blank iii TABLE OF CONTENTS Page 1.0 INTRODUCTION 1 1.1 Background 1 1.2 Purpose and Need for Action 3 2.0 PROPOSED ACTION AND ALTERNATIVES 3 2.1 Proposed Action 3 2.1.1 Modified Storage Capability within K Area for

194

Spent Nuclear Fuel (SNF) Project Acceptance Criteria for Light Water Reactor Spent Fuel Storage System [OCRWM PER REV2  

SciTech Connect

As part of the decommissioning of the 324 Building Radiochemical Engineering Cells there is a need to remove commercial Light Water Reactor (LWR) spent nuclear fuel (SNF) presently stored in these hot cells. To enable fuel removal from the hot cells, the commercial LWR SNF will be packaged and shipped to the 200 Area Interim Storage Area (ISA) in a manner that satisfies site requirements for SNF interim storage. This document identifies the criteria that the 324 Building Radiochemical Engineering Cell Clean-out Project must satisfy for acceptance of the LWR SNF by the SNF Project at the 200 Area ISA. In addition to the acceptance criteria identified herein, acceptance is contingent on adherence to applicable Project Hanford Management Contract requirements and procedures in place at the time of work execution.

JOHNSON, D.M.

2000-12-20T23:59:59.000Z

195

Characterization of interim reference shales  

SciTech Connect

Measurements have been made on the chemical and physical properties of two oil shales designated as interim reference oil shales by the Department of Energy. One oil shale is a Green River Formation, Parachute Creek Member, Mahogany Zone Colorado oil shale from the Anvil Points mine and the other is a Clegg Creek Member, New Albany shale from Kentucky. Material balance Fischer assays, kerogen concentrates, carbon aromaticities, thermal properties, and bulk mineralogic properties have been determined for the oil shales. The measured properties of the interim reference shales are comparable to results obtained from previous studies on similar shales. The western interim reference shale has a low carbon aromaticity, high Fischer assay conversion to oil, and a dominant carbonate mineralogy. The eastern interim reference shale has a high carbon aromaticity, low Fischer assay conversion to oil, and a dominant silicate mineralogy. Chemical and physical properties, including ASTM distillations, have been determined for shale oils produced from the interim reference shales. The distillation data were used in conjunction with API correlations to calculate a large number of shale oil properties that are required for computer models such as ASPEN. The experimental determination of many of the shale oil properties was beyond the scope of this study. Therefore, direct comparison between calculated and measured values of many properties could not be made. However, molecular weights of the shale oils were measured. In this case, there was poor agreement between measured molecular weights and those calculated from API and other published correlations. 23 refs., 12 figs., 15 tabs.

Miknis, F.P.; Sullivan, S.; Mason, G.

1986-03-01T23:59:59.000Z

196

Single-shell tank interim stabilization project plan  

SciTech Connect

Solid and liquid radioactive waste continues to be stored in 149 single-shell tanks at the Hanford Site. To date, 119 tanks have had most of the pumpable liquid removed by interim stabilization. Thirty tanks remain to be stabilized. One of these tanks (C-106) will be stabilized by retrieval of the tank contents. The remaining 29 tanks will be interim stabilized by saltwell pumping. In the summer of 1997, the US Department of Energy (DOE) placed a moratorium on the startup of additional saltwell pumping systems because of funding constraints and proposed modifications to the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) milestones to the Washington State Department of Ecology (Ecology). In a letter dated February 10, 1998, Final Determination Pursuant to Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) in the Matter of the Disapproval of the DOE`s Change Control Form M-41-97-01 (Fitzsimmons 1998), Ecology disapproved the DOE Change Control Form M-41-97-01. In response, Fluor Daniel Hanford, Inc. (FDH) directed Lockheed Martin Hanford Corporation (LNMC) to initiate development of a project plan in a letter dated February 25, 1998, Direction for Development of an Aggressive Single-Shell Tank (SST) Interim Stabilization Completion Project Plan in Support of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement). In a letter dated March 2, 1998, Request for an Aggressive Single-Shell Tank (SST) Interim Stabilization Completion Project Plan, the DOE reaffirmed the need for an aggressive SST interim stabilization completion project plan to support a finalized Tri-Party Agreement Milestone M-41 recovery plan. This project plan establishes the management framework for conduct of the TWRS Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organizational structure, roles, responsibilities, and interfaces; and operational methods. The plan is based on realistic assumptions and addresses three separate funding scenarios.

Ross, W.E.

1998-03-27T23:59:59.000Z

197

Public Preferences Related to Consent-Based Siting of Radioactive Waste  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Public Preferences Related to Consent-Based Siting of Radioactive Public Preferences Related to Consent-Based Siting of Radioactive Waste Management Facilities for Storage and Disposal Public Preferences Related to Consent-Based Siting of Radioactive Waste Management Facilities for Storage and Disposal This report provides findings from a set of social science studies undertaken by the Center for Risk and Crisis Management (CRCM) and Sandia National Laboratories (SNL), which focus on public attitudes and preferences concerning the siting of nuclear repositories and interim storage facilities. Overall these studies are intended to be responsive to the recommendation of the Blue Ribbon Commission on America's Nuclear Future (BRC) that US Department of Energy (DOE) learn as much as possible from prior experience. As stated by the BRC (BRC 2012: 118): "To ensure

198

EFFECTS OF CO2 LEAKAGES FROM STORAGE SITES ON THE QUALITY OF POTABLE GROUNDWATER  

E-Print Network (OSTI)

of SiO2 or as free/hydrated cations. The metal concentration #12;6 in sand, before and after sites. The mineralogy of a well-sorted silica sand is modified by the controlled precipitation of heavy metals (Cr, Mn, Fe, Co, Ni, Cu, Zn, Cd), and flow-through experiments are performed on two sand

199

Combining microseismic and geomechanical observations to interpret storage integrity at the In Salah CCS site  

Science Journals Connector (OSTI)

......site at the In Salah gas development project in...dioxide from several gas fields is separated from the production stream and then compressed...aquifer of a producing gas field at Krechba. Injection...monitoring technology and to cost-effectively verify......

Bettina P. Goertz-Allmann; Daniela Khn; Volker Oye; Bahman Bohloli; Eyvind Aker

2014-01-01T23:59:59.000Z

200

Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 124: Storage Tanks, Nevada Test Site, Nevada (Draft), Revision 0  

SciTech Connect

This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses closure for Corrective Action Unit (CAU) 124, Areas 8, 15, and 16 Storage Tanks, identified in the Federal Facility Agreement and Consent Order. Corrective Action Unit 124 consists of five Corrective Action Sites (CASs) located in Areas 8, 15, and 16 of the Nevada Test Site as follows: 08-02-01, Underground Storage Tank 15-02-01, Irrigation Piping 16-02-03, Underground Storage Tank 16-02-04, Fuel Oil Piping 16-99-04, Fuel Line (Buried) and UST This plan provides the methodology of field activities necessary to gather information to close each CAS. There is sufficient information and process knowledge from historical documentation and investigations of similar sites regarding the expected nature and extent of potential contaminants to recommend closure of CAU 124 using the SAFER process.

Alfred Wickline

2007-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "interim storage site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Site characterization plan: Conceptual design report: Volume 6, Drawing portfolio: Nevada Nuclear Waste Storage Investigations Project  

SciTech Connect

This document presents a description of a prospective geologic repository for high-level radioactive waste to support the development of the Site Characterization Plan for the Yucca Mountain site. The site for the prospective repository is located at Yucca Mountain in southwestern Nevada, and the waste emplacement area will be constructed in the underlying volcanic tuffs. The target horizon for waste emplacement is a sloping bed of densely welded tuff more than 650 ft below the surface and typically more than 600 ft above the water table. The conceptual design described in this report is unique among repository designs in that it uses ramps in addition to shafts to gain access to the underground facility, the emplacement horizon is located above the water table, and it is possible that 300- to 400-ft-long horizontal waste emplacement boreholes will be used. This report summarizes the design bases, design and performance criteria, and the design analyses performed. The current status of meeting the preclosure performance objectives for licensing and of resolving the repository design and preclosure issues is presented. The repository design presented in this report will be expanded and refined during the advanced conceptual design, the license application design, and the final procurement and construction design phases. Volume 6 contains drawings. 114 figs.

MacDougall, H.R.; Scully, L.W.; Tillerson, J.R. (comps.)

1987-09-01T23:59:59.000Z

202

Site Characterization for CO2 Geologic Storage and Vice Versa -The Frio Brine Pilot as a Case Study  

SciTech Connect

Careful site characterization is critical for successfulgeologic sequestration of CO2, especially for sequestration inbrine-bearing formations that have not been previously used for otherpurposes. Traditional site characterization techniques such asgeophysical imaging, well logging, core analyses, interference welltesting, and tracer testing are all valuable. However, the injection andmonitoring of CO2 itself provides a wealth of additional information.Rather than considering a rigid chronology in which CO2 sequestrationoccurs only after site characterization is complete, we recommend thatCO2 injection and monitoring be an integral part of thesite-characterization process. The advantages of this approach arenumerous. The obvious benefit of CO2 injection is to provide informationon multi-phase flow properties, which cannot be obtained from traditionalsitecharacterization techniques that examine single-phase conditions.Additionally, the low density and viscosity of CO2 compared to brinecauses the two components to flow through the subsurface differently,potentially revealing distinct features of the geology. Finally, tounderstand sequestered CO2 behavior in the subsurface, there is nosubstitute for studying the movement of CO2 directly. Making CO2injection part of site characterization has practical benefits as well.The infrastructure for surface handling of CO2 (compression, heating,local storage) can be developed, the CO2 injection process can bedebugged, and monitoring techniques can be field-tested. Prior to actualsequestration, small amounts of CO2 may be trucked in. Later, monitoringaccompanying the actual sequestration operations may be used tocontinually refine and improve understanding of CO2 behavior in thesubsurface.

Doughty, Christine

2006-02-14T23:59:59.000Z

203

DOE - Office of Legacy Management -- Maywood Site - NJ 10  

Office of Legacy Management (LM)

Maywood Site - NJ 10 Maywood Site - NJ 10 FUSRAP Considered Sites Maywood, NJ Alternate Name(s): Maywood Chemical Works Maywood Chemical Company Maywood Interim Storage Site (MISS) Stepan Chemical Company NJ.10-2 NJ.10-3 NJ.10-7 NJ.10-11 Location: 100 West Hunter Avenue, Maywood/Rochelle Park, New Jersey NJ.10-4 Historical Operations: Processed monazite sands for extraction of rare earth compounds and mantle-grade thorium nitrates. NJ.10-2 NJ.10-3 NJ.10-4 NJ.10-5 Eligibility Determination: Eligible NJ.10-1 NJ.10-10 Radiological Survey(s): Assessment Surveys NJ.10-6 NJ.10-7 NJ.10-8 Site Status: Cleanup in progress by U.S. Army Corps of Engineers. NJ.10-9 NJ.10-13 USACE FUSRAP Long-term Care Requirements: To be determined upon completion. Also see FUSRAP Maywood Superfund Site

204

LSPE Interim Stowage Thermal Constraints  

E-Print Network (OSTI)

-arm and thermal battery timers require operating temperatures at or above +40°F for reliable starting when·, ' LSPE Interim Stowage Thermal Constraints· Nl,;. ATM1080 PAGE 1 OF 13 DATE 15 December l97l constraints required for thermal integrity are defined. Prepared by:.:Z4·:..=..-~31!::..--.::..·~-:·::....-c

Rathbun, Julie A.

205

Final environmental assessment for the U.S. Department of Energy, Oak Ridge Operations receipt and storage of uranium materials from the Fernald Environmental Management Project site  

SciTech Connect

Through a series of material transfers and sales agreements over the past 6 to 8 years, the Fernald Environmental Management Project (FEMP) has reduced its nuclear material inventory from 14,500 to approximately 6,800 metric tons of uranium (MTU). This effort is part of the US Department of energy`s (DOE`s) decision to change the mission of the FEMP site; it is currently shut down and the site is being remediated. This EA focuses on the receipt and storage of uranium materials at various DOE-ORO sites. The packaging and transportation of FEMP uranium material has been evaluated in previous NEPA and other environmental evaluations. A summary of these evaluation efforts is included as Appendix A. The material would be packaged in US Department of Transportation-approved shipping containers and removed from the FEMP site and transported to another site for storage. The Ohio Field Office will assume responsibility for environmental analyses and documentation for packaging and transport of the material as part of the remediation of the site, and ORO is preparing this EA for receipt and storage at one or more sites.

NONE

1999-06-01T23:59:59.000Z

206

Interim Action Determination  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Processing of Plutonium Materials from the DOE Standard 3013 Surveillance Processing of Plutonium Materials from the DOE Standard 3013 Surveillance Program in H-Canyon at the Savannah River Site The Department of Energy (DOE) is preparing the Surplus Plutonium Disposition Supplemental Environmental Impact Statement (SPD SEIS, DOE/EIS-0283-S2). DOE is evaluating alternatives for disposition of non-pit plutonium that is surplus to the national security needs of the United States. Although the Deputy Secretary of Energy approved

207

The united kingdom's changing requirements for spent fuel storage  

SciTech Connect

The UK is adopting an open fuel cycle, and is necessarily moving to a regime of long term storage of spent fuel, followed by geological disposal once a geological disposal facility (GDF) is available. The earliest GDF receipt date for legacy spent fuel is assumed to be 2075. The UK is set to embark on a programme of new nuclear build to maintain a nuclear energy contribution of 16 GW. Additionally, the UK are considering a significant expansion of nuclear energy in order to meet carbon reduction targets and it is plausible to foresee a scenario where up to 75 GW from nuclear power production could be deployed in the UK by the mid 21. century. Such an expansion, could lead to spent fuel storage and its disposal being a dominant issue for the UK Government, the utilities and the public. If the UK were to transition a closed fuel cycle, then spent fuel storage should become less onerous depending on the timescales. The UK has demonstrated a preference for wet storage of spent fuel on an interim basis. The UK has adopted an approach of centralised storage, but a 16 GW new build programme and any significant expansion of this may push the UK towards distributed spent fuel storage at a number of reactors station sites across the UK.

Hodgson, Z.; Hambley, D.I.; Gregg, R.; Ross, D.N. [National Nuclear Laboratory, Chadwick House, Birchwood Park, Warrington, Cheshire WA3 6AE (United Kingdom)

2013-07-01T23:59:59.000Z

208

Optimized Energy Management for Large Organizations Utilizing an On-Site PHEV fleet, Storage Devices and Renewable Electricity Generation  

SciTech Connect

Abstract This paper focuses on the daily electricity management problem for organizations with a large number of employees working within a relatively small geographic location. The organization manages its electric grid including limited on-site energy generation facilities, energy storage facilities, and plug-in hybrid electric vehicle (PHEV) charging stations installed in the parking lots. A mixed integer linear program (MILP) is modeled and implemented to assist the organization in determining the temporal allocation of available resources that will minimize energy costs. We consider two cost compensation strategies for PHEV owners: (1) cost equivalent battery replacement reimbursement for utilizing vehicle to grid (V2G) services from PHEVs; (2) gasoline equivalent cost for undercharging of PHEV batteries. Our case study, based on the Oak Ridge National Laboratory (ORNL) campus, produced encouraging results and substantiates the importance of controlled PHEV fleet charging as opposed to uncontrolled charging methods. We further established the importance of realizing V2G capabilities provided by PHEVs in terms of significantly reducing energy costs for the organization.

Dashora, Yogesh [University of Texas, Austin; Barnes, J. Wesley [University of Texas, Austin; Pillai, Rekha S [ORNL; Combs, Todd E [ORNL; Hilliard, Michael R [ORNL

2012-01-01T23:59:59.000Z

209

Polymers for subterranean containment barriers for underground storage tanks (USTs). Letter report on FY 1992 activities  

SciTech Connect

The US Department of Energy (DOE) set up the Underground Storage Tank Integrated Demonstration Program (USTID) to demonstrate technologies for the retrieval and treatment of tank waste, and closure of underground storage tanks (USTs). There are more than 250 underground storage tanks throughout the DOE complex. These tanks contain a wide variety of wastes including high level, low level, transuranic, mixed and hazardous wastes. Many of the tanks have performed beyond the designed lifetime resulting in leakage and contamination of the local geologic media and groundwater. To mitigate this problem it has been proposed that an interim subterranean containment barrier be placed around the tanks. This would minimize or prevent future contamination of soil and groundwater in the event that further tank leakages occur before or during remediation. Use of interim subterranean barriers can also provide sufficient time to evaluate and select appropriate remediation alternatives. The DOE Hanford site was chosen as the demonstration site for containment barrier technologies. A panel of experts for the USTID was convened in February, 1992, to identify technologies for placement of subterranean barriers. The selection was based on the ability of candidate grouts to withstand high radiation doses, high temperatures and aggressive tank waste leachates. The group identified and ranked nine grouting technologies that have potential to place vertical barriers and five for horizontal barriers around the tank. The panel also endorsed placement technologies that require minimal excavation of soil surrounding the tanks.

Heiser, J.H.; Colombo, P.; Clinton, J.

1992-12-01T23:59:59.000Z

210

DNFSB Recommendation 94-1 Hanford Site Integrated Stabilization Management Plan. Volume 1  

SciTech Connect

The US Department of Energy (DOE) has developed an Integrated Program Plan (IPP) to address concerns identified in Defense Nuclear Facilities Safety Board Recommendation 94-1. The IPP describes the actions that DOE plans to implement at its various sites to convert excess fissile materials to forms or conditions suitable for safe interim storage. The baseline IPP was issued as DOE`s Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1 Implementation Plan (IP), which was transmitted to the DNFSB on February 28, 1995. The IPP is being further developed to include complex-wide requirements for research and development and a long-range facility requirements section. The planned additions to the baseline IPP are being developed based on a systems engineering approach that integrates facilities and capabilities at the various DOE sites and focuses on attaining safe interim storage with minimum safety risks and environmental impacts. Each affected DOE site has developed a Site Integrated Stabilization Management Plan (SISMP) to identify individual site plans to implement the DNFSB Recommendation 94-1 and to provide a basis for formulating planned additions to the IPP. The SISMPs were developed based on the objectives, requirements, and commitments identified in the baseline DNFSB Recommendation 94-1 IPP. The SISMPs will be periodically updated to reflect improved integration between DOE sites as identified during the IPP systems engineering evaluations.

Gerber, E.W.

1995-10-01T23:59:59.000Z

211

EMAB Risk Subcommittee Interim Report  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

FIRST INTERIM REPORT TO THE ENVIRONMENTAL MANAGEMENT ADVISORY BOARD Incorporating Risk and Sustainability into Decision Making Submitted by the EMAB Risk Subcommittee December 3, 2012 Background: In December 2011, then Acting Assistant Secretary for Environmental Management David Huizenga, asked the Environmental Management Advisory Board (EMAB or Board) to establish a Risk Subcommittee. In February 2012, the Subcommittee's Work Plan was approved. Under the Work Plan, the purpose of the Subcommittee is to evaluate "risk-informed decision making," specifically whether the prioritization tool developed by the Consortium for Risk Evaluation with Stakeholder Participation (CRESP) for use at the Oak Ridge Reservation (Oak Ridge) is one that

212

UC SANTA BARBARA POLICY AND PROCEDURE Interim Food Service Policy  

E-Print Network (OSTI)

UC SANTA BARBARA POLICY AND PROCEDURE Interim Food Service Policy Contact: Environmental Health & Safety or Housing and Auxiliary Services Supersedes: Food Services Interim Policy 6005, February 2001 Technical Update: June 2010 Pages: 2 Interim Food Service Policy I. Scope The Interim Food Service Policy

Bigelow, Stephen

213

METHODOLOGY AND CALCULATIONS FOR THE ASSIGNMENT OF WASTE GROUPS FOR THE LARGE UNDERGROUND WASTE STORAGE TANKS AT THE HANFORD SITE  

SciTech Connect

This document categorizes each of the large waste storage tanks into one of several categories based on each tank's waste characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement event. Revision 7 is the annual update of the calculations of the flammable gas Waste Groups for DSTs and SSTs. The Hanford Site contains 177 large underground radioactive waste storage tanks (28 double-shell tanks and 149 single-shell tanks). These tanks are categorized into one of three waste groups (A, B, and C) based on their waste and tank characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement gas release event. Assignments of waste groups to the 177 double-shell tanks and single-shell tanks, as reported in this document, are based on a Monte Carlo analysis of three criteria. The first criterion is the headspace flammable gas concentration following release of retained gas. This criterion determines whether the tank contains sufficient retained gas such that the well-mixed headspace flammable gas concentration would reach 100% of the lower flammability limit if the entire tank's retained gas were released. If the volume of retained gas is not sufficient to reach 100% of the lower flammability limit, then flammable conditions cannot be reached and the tank is classified as a waste group C tank independent of the method the gas is released. The second criterion is the energy ratio and considers whether there is sufficient supernatant on top of the saturated solids such that gas-bearing solids have the potential energy required to break up the material and release gas. Tanks that are not waste group C tanks and that have an energy ratio < 3.0 do not have sufficient potential energy to break up material and release gas and are assigned to waste group B. These tanks are considered to represent a potential induced flammable gas release hazard, but no spontaneous buoyant displacement flammable gas release hazard. Tanks that are not waste group C tanks and have an energy ratio {ge} 3.0, but that pass the third criterion (buoyancy ratio < 1.0, see below) are also assigned to waste group B. Even though the designation as a waste group B (or A) tank identifies the potential for an induced flammable gas release hazard, the hazard only exists for specific operations that can release the retained gas in the tank at a rate and quantity that results in reaching 100% of the lower flammability limit in the tank headspace. The identification and evaluation of tank farm operations that could cause an induced flammable gas release hazard in a waste group B (or A) tank are included in other documents. The third criterion is the buoyancy ratio. This criterion addresses tanks that are not waste group C double-shell tanks and have an energy ratio {ge} 3.0. For these double-shell tanks, the buoyancy ratio considers whether the saturated solids can retain sufficient gas to exceed neutral buoyancy relative to the supernatant layer and therefore have buoyant displacement gas release events. If the buoyancy ratio is {ge} 1.0, that double-shell tank is assigned to waste group A. These tanks are considered to have a potential spontaneous buoyant displacement flammable gas release hazard in addition to a potential induced flammable gas release hazard.

FOWLER KD

2007-12-27T23:59:59.000Z

214

METHODOLOGY AND CALCULATIONS FOR THE ASSIGNMENT OF WASTE GROUPS FOR THE LARGE UNDERGROUND WASTE STORAGE TANKS AT THE HANFORD SITE  

SciTech Connect

The Hanford Site contains 177 large underground radioactive waste storage tanks (28 double-shell tanks and 149 single-shell tanks). These tanks are categorized into one of three waste groups (A, B, and C) based on their waste and tank characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement gas release event. Assignments of waste groups to the 177 double-shell tanks and single-shell tanks, as reported in this document, are based on a Monte Carlo analysis of three criteria. The first criterion is the headspace flammable gas concentration following release of retained gas. This criterion determines whether the tank contains sufficient retained gas such that the well-mixed headspace flammable gas concentration would reach 100% of the lower flammability limit if the entire tank's retained gas were released. If the volume of retained gas is not sufficient to reach 100% of the lower flammability limit, then flammable conditions cannot be reached and the tank is classified as a waste group C tank independent of the method the gas is released. The second criterion is the energy ratio and considers whether there is sufficient supernatant on top of the saturated solids such that gas-bearing solids have the potential energy required to break up the material and release gas. Tanks that are not waste group C tanks and that have an energy ratio < 3.0 do not have sufficient potential energy to break up material and release gas and are assigned to waste group B. These tanks are considered to represent a potential induced flammable gas release hazard, but no spontaneous buoyant displacement flammable gas release hazard. Tanks that are not waste group C tanks and have an energy ratio {ge} 3.0, but that pass the third criterion (buoyancy ratio < 1.0, see below) are also assigned to waste group B. Even though the designation as a waste group B (or A) tank identifies the potential for an induced flammable gas release hazard, the hazard only exists for specific operations that can release the retained gas in the tank at a rate and quantity that results in reaching 100% of the lower flammability limit in the tank headspace. The identification and evaluation of tank farm operations that could cause an induced flammable gas release hazard in a waste group B (or A) tank are included in other documents. The third criterion is the buoyancy ratio. This criterion addresses tanks that are not waste group C double-shell tanks and have an energy ratio {ge} 3.0. For these double-shell tanks, the buoyancy ratio considers whether the saturated solids can retain sufficient gas to exceed neutral buoyancy relative to the supernatant layer and therefore have buoyant displacement gas release events. If the buoyancy ratio is {ge} 1.0, that double-shell tank is assigned to waste group A. These tanks are considered to have a potential spontaneous buoyant displacement flammable gas release hazard in addition to a potential induced flammable gas release hazard. This document categorizes each of the large waste storage tanks into one of several categories based on each tank's waste characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement event. Revision 8 is the annual update of the calculations of the flammable gas Waste Groups for DSTs and SSTs.

WEBER RA

2009-01-16T23:59:59.000Z

215

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

SciTech Connect

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

David Strand

2006-06-01T23:59:59.000Z

216

SITE  

Office of Legacy Management (LM)

-@-Y? ALTERNATE -@-Y? ALTERNATE NfiME: --___---------------___________________N~ME:---------------------- CITY- - .---------------^---------- STATE: wz ------ OWNER(S) -------- Past: Current: ------------------------ _~~--___~~-----_~~----~~-- Owner contacted [3 yes 0 no; if yes, date contacted ------------- TYPE OF ' OPERATION ____-------~----- q Research & Development !zl Facility Type 0 Production scale testing 0 Manufactuiinq 0 Pilot Scale [7 University 0 Bench Scale Process 0 Research Organization 0 Theoretical Studies 0 Government Sponsored Faci 1 i ty 0 Sample & Analysis Cl Other ---_-~~----_~~---~-~ 0 Production 0 Disposal/Storage TYPE OF CONTRACT -_---------~~~~~ q Prime q Subcontract& 0 Purchase Order 0 Other information (i.e., c&t

217

Hanford low-level tank waste interim performance assessment  

SciTech Connect

The Hanford Low-Level Tank Waste Interim Performance Assessment examines the long-term environmental and human health effects associated with the disposal of the low-level fraction of the Hanford single- and double-shell tank waste in the Hanford Site 200 East Area. This report was prepared as a good management practice to provide needed information about the relationship between the disposal system design and its performance as early as possible in the project cycle. The calculations in this performance assessment show that the disposal of the low-level fraction can meet environmental and health performance objectives.

Mann, F.M.

1996-09-16T23:59:59.000Z

218

Hanford low-level tank waste interim performance assessment  

SciTech Connect

The Hanford Low-Level Tank Waste Interim Performance Assessment examines the long-term environmental and human health effects associated with the disposal of the low-level fraction of the Hanford single and double-shell tank waste in the Hanford Site 200 East Area. This report was prepared as a good management practice to provide needed information about the relationship between the disposal system design and performance early in the disposal system project cycle. The calculations in this performance assessment show that the disposal of the low-level fraction can meet environmental and health performance objectives.

Mann, F.M.

1997-09-12T23:59:59.000Z

219

Engineering evaluation/cost analysis for decontamination at the St. Louis Downtown Site, St. Louis, Missouri  

SciTech Connect

The US Department of Energy (DOE) is implementing a cleanup program for three groups of properties in the St. Louis, Missouri, area: the St. Louis Downtown Site (SLDS), the St. Louis Airport Site (SLAPS) and vicinity properties, and the Latty Avenue Properties, including the Hazelwood Interim Storage Site (HISS). The general location of these properties is shown in Figure 1; the properties are referred to collectively as the St. Louis Site. None of the properties are owned by DOE, but each property contains radioactive residues from federal uranium processing activities conducted at the SLDS during and after World War 2. The activities addressed in this environmental evaluation/cost analysis (EE/CA) report are being proposed as interim components of a comprehensive cleanup strategy for the St. Louis Site. As part of the Department's Formerly Utilized Sites Remedial Action Program (FUSRAP), DOE is proposing to conduct limited decontamination in support of proprietor-initiated activities at the SLDS, commonly referred to as the Mallinckrodt Chemical Works. The primary goal of FUSRAP activity at the SLDS is to eliminate potential environmental hazards associated with residual contamination resulting from the site's use for government-funded uranium processing activities. 17 refs., 3 figs., 5 tabs.

Picel, M.H.; Hartmann, H.M.; Nimmagadda, M.R. (Argonne National Lab., IL (USA)); Williams, M.J. (Bechtel National, Inc., Oak Ridge, TN (USA))

1991-05-01T23:59:59.000Z

220

EIS-0283-S2: Amended Interim Action Determination | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Certain Plutonium Materials at the K-Area Complex, Savannah Certain Plutonium Materials at the K-Area Complex, Savannah River Site DOE has reviewed the environmental analysis relevant to preparation for disposition in the HB-Line and K-Area at SRS, and disposal at WIPP, approximately 500 kg of surplus, non-pit plutonium. DOE finds that the analysis in the Interim Management of Nuclear Material EIS and the SRS Waste Management EIS are still representative of the impacts of disposal of these materials. Therefore, no adverse environmental impacts would result from disposal of these materials as TRU waste to WIPP and this action is clearly an allowable interim action in accordance with DOE regulations for implementing NEPA. EIS-0283-S2-Amended_IAD-2013.pdf More Documents & Publications EIS-0283-S2: Interim Action Determination

Note: This page contains sample records for the topic "interim storage site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

DOE - Office of Legacy Management -- Latty Avenue Site - MO 04  

NLE Websites -- All DOE Office Websites (Extended Search)

Latty Avenue Site - MO 04 Latty Avenue Site - MO 04 FUSRAP Considered Sites Latty Avenue Site, MO Alternate Name(s): Futura Coatings Futura Chemical Company Facility Hazelwood Interim Storage Site (HISS) Former Cotter Site, Latty Avenue Properties Contemporary Metals Corp. Continental Mining and Milling MO.04-1 MO.04-2 MO.04-5 MO.04-6 MO.06-8 MO.06-11 Location: 9200 Latty Avenue, Hazelwood, Missouri MO.04-1 Historical Operations: Received, stored, and processed uranium residues for the AEC. Storage and processing were licensed by the AEC and NRC and resulted in contamination of uranium and thorium. MO.04-5 MO.04-6 Eligibility Determination: Eligible MO.04-3 MO.04-4 Radiological Survey(s): Assessment Surveys MO.04-2 MO.04-7 MO.04-8 MO.04-9 MO.04-10 MO.04-11 Site Status: Cleanup in progress by U.S. Army Corps of Engineers. MO.04-12

222

Natural Gas Storage in Basalt Aquifers of the Columbia Basin, Pacific Northwest USA: A Guide to Site Characterization  

SciTech Connect

This report provides the technical background and a guide to characterizing a site for storing natural gas in the Columbia River Basalt

Reidel, Steve P.; Spane, Frank A.; Johnson, Vernon G.

2002-08-08T23:59:59.000Z

223

Environmental assessment, finding of no significant impact, and response to comments. Sold residue treatment, repackaging, and storage  

SciTech Connect

From its founding in 1952 through the cessation of production in 1989, the United States Department of Energy`s (DOE) Rocky Flats Plant (now the Rocky Flats Environmental Technology Site [the Site]) produced components for nuclear weapons. Some of those components were made of plutonium. As a result of the processes used to recover and purify plutonium and manufacture the components, a variety of materials became contaminated with plutonium. If the level of contamination were low, the material was considered waste. However, if the concentration of plutonium in the material exceeded the {open_quotes}economic discard limit,{close_quotes} the materials were classified as {open_quotes}residue{close_quotes} rather than{open_quotes}Waste{close_quotes} and were stored for later recovery of the plutonium. While large quantities of residues were processed, others, primarily those more difficult to process, accumulated at the Site in storage. Two important events regarding residues have occurred at the Site since production activities ceased. One event was the end of the Cold War in 1991, which made the return to production of nuclear weapons, with their Rocky Flats-made components, unnecessary. This event led to DOE`s decision to permanently cease production at the Site, clean up and remove radioactive and chemical contamination at the Site, and find alternative uses for the Site. This document describes methods for processing of the wastes for safe interim storage. Environmental impacts from the processing and storage are discussed.

NONE

1996-04-01T23:59:59.000Z

224

Analysis in support of storage of residues in the pipe overpack container  

SciTech Connect

The disposition of the large backlog of plutonium residues at the Rocky Flats Environmental Technology Site (Rocky Flats) will require interim storage and subsequent shipment to a waste repository. Current plans call for disposal at the Waste Isolation Pilot Plant (WIPP) and the transportation to WIPP in the TRUPACT-II. The transportation phase will require the residues to be packaged in a container that is more robust than a standard 55 gallon waste drum. Rocky Flats has designed the Pipe Overpack Container to meet this need. The potential for damage to this container during onsite storage in unhardened structures for several hypothetical accident scenarios has been addressed using finite element calculations. This report will describe the initial conditions and assumptions for these analyses and the predicted response of the container.

Ludwigsen, J.S.; Ammerman, D.J.; Radloff, H.D.

1998-04-01T23:59:59.000Z

225

EIS-0062: Double-Shell Tanks for Defense High Level Waste Storage, Savannah River Site, Aiken, SC  

Energy.gov (U.S. Department of Energy (DOE))

This EIS analyzes the impacts of the various design alternatives for the construction of fourteen 1.3 million gallon high-activity radioactive waste tanks. The EIS further evaluates the effects of these alternative designs on tank durability, on the ease of waste retrieval from such tanks, and the choice of technology and timing for long-term storage or disposal of the wastes.

226

Corrective Action Decision Document for Corrective Action Unit 140: Waste Dumps, Burn Pits, and Storage Area, Nevada Test Site, Nevada: Revision No. 0  

SciTech Connect

This Corrective Action Decision Document identifies and rationalizes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's selection of a recommended corrective action alternative appropriate to facilitate the closure of Corrective Action Unit (CAU) 140: Waste Dumps, Burn Pits, and Storage Area, Nevada Test Site (NTS), Nevada, under the Federal Facility Agreement and Consent Order. Located in Areas 5, 22, and 23 of the NTS, CAU 140 consists of nine corrective action sites (CASs). Investigation activities were performed from November 13 through December 11, 2002, with additional sampling to delineate the extent of contaminants of concern (COCs) conducted on February 4 and March 18 and 19, 2003. Results obtained from the investigation activities and sampling indicated that only 3 of the 9 CASs at CAU 140 had COCs identified. Following a review of existing data, future land use, and current operations at the NTS, the following preferred alternatives were developed for consideration: (1) No Further Action - six CASs (05-08-02, 05-17-01, 05-19-01, 05-35-01, 05-99-04, and 22-99-04); (2) Clean Closure - one CAS (05-08-01), and (3) Closure-in-Place - two CASs (05-23-01 and 23-17-01). These alternatives were judged to meet all requirements for the technical components evaluated. Additionally, the alternatives meet all applicable state and federal regulations for closure of the site and will eliminate potential future exposure pathways to the contaminated media at CAU 140.

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

2003-10-17T23:59:59.000Z

227

Corrective Action Investigation Plan for Corrective Action Unit 140: Waste Dumps, Burn Pits, and Storage Area, Nevada Test Site, Nevada, July 2002, Rev. No. 0  

SciTech Connect

This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 140 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 140 consists of nine Corrective Action Sites (CASs): 05-08-01, Detonation Pits; 05-08-02, Debris Pits; 05-17-01, Hazardous Waste Accumulation Site (Buried); 05-19-01, Waste Disposal Site; 05-23-01, Gravel Gertie; 05-35-01, Burn Pit; 05-99-04, Burn Pit; 22-99-04, Radioactive Waste Dump; 23-17-01, Hazardous Waste Storage Area. All nine of these CASs are located within Areas 5, 22, and 23 of the Nevada Test Site (NTS) in Nevada, approximately 65 miles northwest of Las Vegas. This CAU is being investigated because disposed waste may be present without appropriate controls (i.e., use restrictions, adequate cover) and hazardous and/or radioactive constituents may be present or migrating at concentrations and locations that could potentially pose a threat to human health and the environment. The NTS has been used for various research and development projects including nuclear weapons testing. The CASs in CAU 140 were used for testing, material storage, waste storage, and waste disposal. A two-phase approach has been selected to collect information and generate data to satisfy needed resolution criteria and resolve the decision statements. Phase I will determine if contaminants of potential concern (COPCs) are present in concentrations exceeding preliminary action levels. This data will be evaluated at all CASs. Phase II will determine the extent of the contaminant(s) of concern (COCs). This data will only be evaluated for CASs with a COC identified during Phase I. Based on process knowledge, the COPCs for CAU 140 include volatile organics, semivolatile organics, petroleum hydrocarbons, explosive residues, herbicides, pesticides, polychlorinated biphenyls, metals, and radionuclides. The results of this field investigation will support a defensible evaluation of corrective action alternatives in the corrective action decision document.

NNSA /NV

2002-07-18T23:59:59.000Z

228

Hanford Site waste management and environmental restoration integration plan  

SciTech Connect

The Hanford Site Waste Management and Environmental Restoration Integration Plan'' describes major actions leading to waste disposal and site remediation. The primary purpose of this document is to provide a management tool for use by executives who need to quickly comprehend the waste management and environmental restoration programs. The Waste Management and Environmental Restoration Programs have been divided into missions. Waste Management consists of five missions: double-shell tank (DST) wastes; single-shell tank (SST) wastes (surveillance and interim storage, stabilization, and isolation); encapsulated cesium and strontium; solid wastes; and liquid effluents. Environmental Restoration consists of two missions: past practice units (PPU) (including characterization and assessment of SST wastes) and surplus facilities. For convenience, both aspects of SST wastes are discussed in one place. A general category of supporting activities is also included. 20 refs., 14 figs., 7 tabs.

Merrick, D.L.

1990-04-30T23:59:59.000Z

229

INTERIM SEXUAL AND GENDER-BASED HARASSMENT POLICY AND PROCEDURES  

E-Print Network (OSTI)

8/7/14 INTERIM SEXUAL AND GENDER-BASED HARASSMENT POLICY AND PROCEDURES FOR THE FACULTY OF ARTS Relationships Between Staff IV. Interim Procedures for Implementing Interim Sexual and Gender-Based Harassment Policy Including for Discipline A. Introduction B. Requests for Information and Advice C. Procedures

Paulsson, Johan

230

Corrective Action Investigation Plan for Corrective Action Unit 204: Storage Bunkers, Nevada Test Site, Nevada (December 2002, Revision No.: 0), Including Record of Technical Change No. 1  

SciTech Connect

The Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 204 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 204 is located on the Nevada Test Site approximately 65 miles northwest of Las Vegas, Nevada. This CAU is comprised of six Corrective Action Sites (CASs) which include: 01-34-01, Underground Instrument House Bunker; 02-34-01, Instrument Bunker; 03-34-01, Underground Bunker; 05-18-02, Chemical Explosives Storage; 05-33-01, Kay Blockhouse; 05-99-02, Explosive Storage Bunker. Based on site history, process knowledge, and previous field efforts, contaminants of potential concern for Corrective Action Unit 204 collectively include radionuclides, beryllium, high explosives, lead, polychlorinated biphenyls, total petroleum hydrocarbons, silver, warfarin, and zinc phosphide. The primary question for the investigation is: ''Are existing data sufficient to evaluate appropriate corrective actions?'' To address this question, resolution of two decision statements is required. Decision I is to ''Define the nature of contamination'' by identifying any contamination above preliminary action levels (PALs); Decision II is to ''Determine the extent of contamination identified above PALs. If PALs are not exceeded, the investigation is completed. If PALs are exceeded, then Decision II must be resolved. In addition, data will be obtained to support waste management decisions. Field activities will include radiological land area surveys, geophysical surveys to identify any subsurface metallic and nonmetallic debris, field screening for applicable contaminants of potential concern, collection and analysis of surface and subsurface soil samples from biased locations, and step-out sampling to define the extent of contamination, as necessary. The results of this field investigation will support a defensible evaluation of corrective action alternatives in the corrective action decision document.

NNSA /NSO

2002-12-12T23:59:59.000Z

231

CHARACTERIZATION THROUGH DATA QUALITY OBJECTIVES AND CERTIFICATION OF REMOTE-HANDLED TRANSURANIC WASTE GENERATOR/STORAGE SITES FOR SHIPMENT TO THE WIPP  

SciTech Connect

The Waste Isolation Pilot Plant (WIPP) is operating to receive and dispose of contact-handled (CH) transuranic (TRU) waste. The Department of Energy (DOE) Carlsbad Field Office (CBFO) is seeking approval from the Environmental Protection Agency (EPA) and the New Mexico Environment Department (NMED) of the remote-handled (RH) TRU characterization plan to allow disposal of RH TRU waste in the WIPP repository. In addition, the DOE-CBFO has received approval from the Nuclear Regulatory Commission (NRC) to use two shipping casks for transporting RH TRU waste. Each regulatory agency (i.e., EPA, NMED, and NRC) has different requirements that will have to be met through the use of information collected by characterizing the RH TRU waste. Therefore, the DOE-CBFO has developed a proposed characterization program for obtaining the RH TRU waste information necessary to demonstrate that the waste meets the applicable regulatory requirements. This process involved the development of a comprehensive set of Data Quality Objectives (DQOs) comprising the various regulatory requirements. The DOE-CBFO has identified seven DQOs for use in the RH TRU waste characterization program. These DQOs are defense waste determination, TRU waste determination, RH TRU determination, activity determination, RCRA physical and chemical properties, prohibited item determination, and EPA physical and chemical properties. The selection of the DQOs were based on technical, legal and regulatory drivers that assure the health and safety of the workers, the public, to protect the environment, and to comply with the requirements of the regulatory agencies. The DOE-CBFO also has the responsibility for the certification of generator/storage sites to ship RH TRU mixed waste to the WIPP for disposal. Currently, thirteen sites across the DOE complex are generators of RH TRU waste or store the waste at their location for other generators. Generator/storage site certification involves review and approval of site-specific programmatic documents that demonstrate compliance with the WIPP waste characterization and transportation requirements. Additionally, procedures must be developed to implement programmatic requirements and adequacy of those procedures determined. Finally, on-site audits evaluate the technical and administrative implementation and effectiveness of the operating procedures.

Spangler, L.R.; Most, Wm.A.; Kehrman, R.F.; Gist, C.S.

2003-02-27T23:59:59.000Z

232

Corrective Action Decision Document for Corrective Action Unit 127: Areas 25 and 26 Storage Tanks, Nevada Test Site, Nevada: Revision 0  

SciTech Connect

This Corrective Action Decision Document identifies and rationalizes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's selection of recommended corrective action alternatives (CAAs) appropriate to facilitate the closure of Corrective Action Unit (CAU) 127: Areas 25 and 26 Storage Tanks, Nevada Test Site, Nevada, under the Federal Facility Agreement and Consent Order. Corrective Action Unit 127 consists of twelve corrective action sites (CASs). Corrective action investigation (CAI) activities were performed from February 24, 2003, through May 2, 2003, with additional sampling conducted on June 6, 2003, June 9, 2003, and June 24, 2003. Analytes detected during these investigation activities were evaluated against preliminary action levels to identify contaminants of concern (COCs) for each CAS, resulting in the determination that only two of the CASs did not have COCs exceeding regulatory levels. Based on the evaluation of analytical data from the CAI, review of future and current operations in Areas 25 and 26 of the Nevada Test Site, and the detailed and comparative analysis of the potential CAAs, the following alternatives were developed for consideration: (1) No Further Action is the preferred corrective action for the two CASs (25-02-13, 26-02-01) identified with no COCs; (2) Clean Closure is the preferred corrective action for eight of the CASs (25-01-05, 25-23-11, 25-12-01, 25-01-06, 26-01-01, 26-01-02, 26-99-01, 26-23-01); and (3) Closure in Place is the preferred corrective action for the remaining two CASs (25-01-07, 25-02-02). These three alternatives were judged to meet all requirements for the technical components evaluated. Additionally, these alternatives meet all applicable state and federal regulations for closure of the sites at CAU 127 and will reduce potential future exposure pathways to the contaminated media.

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

2003-09-26T23:59:59.000Z

233

Functions and requirements document for interim store solidified high-level and transuranic waste  

SciTech Connect

The functions, requirements, interfaces, and architectures contained within the Functions and Requirements (F{ampersand}R) Document are based on the information currently contained within the TWRS Functions and Requirements database. The database also documents the set of technically defensible functions and requirements associated with the solidified waste interim storage mission.The F{ampersand}R Document provides a snapshot in time of the technical baseline for the project. The F{ampersand}R document is the product of functional analysis, requirements allocation and architectural structure definition. The technical baseline described in this document is traceable to the TWRS function 4.2.4.1, Interim Store Solidified Waste, and its related requirements, architecture, and interfaces.

Smith-Fewell, M.A., Westinghouse Hanford

1996-05-17T23:59:59.000Z

234

NETL: Carbon Storage - Reference Shelf  

NLE Websites -- All DOE Office Websites (Extended Search)

Carbon Storage > Reference Shelf Carbon Storage > Reference Shelf Carbon Storage Reference Shelf Below are links to Carbon Storage Program documents and reference materials. Each of the 10 categories has a variety of documents posted for easy access to current information - just click on the category link to view all related materials. RSS Icon Subscribe to the Carbon Storage RSS Feed. Carbon Storage Collage 2012 Carbon Utilization and Storage Atlas IV Carbon Sequestration Project Portfolio DOE/NETL Carbon Dioxide Capture and Storage RD&D Roadmap Public Outreach and Education for Carbon Storage Projects Carbon Storage Technology Program Plan Carbon Storage Newsletter Archive Impact of the Marcellus Shale Gas Play on Current and Future CCS Activities Site Screening, Selection, and Initial Characterization for Storage of CO2 in Deep Geologic Formations Carbon Storage Systems and Well Management Activities Monitoring, Verification, and Accounting of CO2 Stored in Deep Geologic Formations

235

Site characterization plan: Conceptual design report, Volume 2: Chapters 4-9: Nevada Nuclear Waste Storage Investigations Project  

SciTech Connect

This document presents a description of a prospective geologic repository for high-level radioactive waste to support the development of the Site Characterization Plan for the Yucca Mountain site. The target horizon for waste emplacement is a sloping bed of densely welded tuff more than 650 ft below the surface and typically more than 600 ft above the water table. The conceptual design described in this report is unique among repository designs in that it uses ramps in addition to shafts to gain access to the underground facility, the emplacement horizon is located above the water table, and it is possible that 300- to 400-ft-long horizontal waste emplacement boreholes will be used. This report summarizes the design bases (site and properties of the waste package), design and performance criteria, and the design analyses performed. The current status of meeting the preclosure performance objectives for licensing and of resolving the repository design and preclosure issues is presented. The repository design presented in this report will be expanded and refined during the advanced conceptual design, the license application design, and the final procurement and construction design phases. 147 refs., 145 figs., 83 tabs.

MacDougall, H.R.; Scully, L.W.; Tillerson, J.R. (comps.)

1987-09-01T23:59:59.000Z

236

Site characterization plan: Conceptual design report, Volume 3: Appendices A-E: Nevada Nuclear Waste Storage Investigations Project  

SciTech Connect

This document presents a description of a prospective geologic repository for high-level radioactive waste to support the development of the Site Characterization Plan for the Yucca Mountain site. The site for the prospective repository is located at Yucca Mountain in southwestern Nevada, and the waste emplacement area will be constructed in the underlying volcanic tuffs. The target horizon for waste emplacement is a sloping bed of densely welded tuff more than 650 ft below the surface and typically more than 600 ft above the water table. The conceptual design described in this report is unique among repository designs in that it uses ramps in addition to shafts to gain access to the underground facility, the emplacement horizon is located above the water table, and it is possible that 300- to 400-ft-long horizontal waste emplacement boreholes will be used. This report summarizes the design bases, design and performance criteria, and the design analyses performed. The current status of meeting the preclosure performance objectives for licensing and of resolving the repository design and preclosure issues is presented. Volume 3 contains Appendices A through E.

MacDougall, H.R.; Scully, L.W.; Tillerson, J.R. (comps.)

1987-09-01T23:59:59.000Z

237

DNFSB recommendation 94-1 Hanford site integrated stabilization management plan  

SciTech Connect

In May 1994, the Defense Nuclear Facilities Safety Board (DNFSB) issued DNFSB Recommendation 94-1 (Conway 1994), which identified concerns related to US Department of Energy (DOE) management of legacy fissile materials remaining from past defense production activities. The DNFSB expressed concern about the existing storage conditions for these materials and the slow pace at which the conditions were being remediated. The DNFSB also expressed its belief that additional delays in stabilizing these fissile materials would be accompanied by further deterioration of safety and unnecessary increased risks to workers and the public. In February 1995, DOE issued the DNFSB Recommendation 94-1 Implementation Plan (O`Leary 1995) to address the concerns identified in DNFSB Recommendation 94-1. The Implementation Plan (IP) identifies several DOE commitments to achieve safe interim storage for the legacy fissile materials, and constitutes DOE`s baseline DNFSB Recommendation 94-1 Integrated Program Plan (IPP). The IPP describes the actions DOE plans to implement within the DOE complex to convert its excess fissile materials to forms or conditions suitable for safe interim storage. The IPP was subsequently supplemented with an Integrated Facilities Plan and a Research and Development Plan, which further develop complex-wide research and development and long-range facility requirements and plans. The additions to the baseline IPP were developed based on a systems engineering approach that integrated facilities and capabilities at the various DOE sites and focused on attaining safe interim storage with minimum safety risks and environmental impacts. Each affected DOE site has developed a Site Integrated Stabilization Management Plan (SISMP) to identify individual site plans to implement the DNFSB Recommendation 94-1 IPP. The SISMPs were developed based on the objectives, requirements, and commitments identified in the DNFSB Recommendation 94-1 IP. The SISMPs also supported formulation of the initial versions of the Integrated Facilities Plan and the Research and Development Plan. The SISMPs are periodically updated to reflect improved integration between DOE sites as identified during the IPP systems engineering evaluations. This document is the fifth update of the Hanford SISMP.

McCormack, R.L.

1997-05-07T23:59:59.000Z

238

DNFSB recommendation 94-1 Hanford site integrated stabilization management plan - VOLUMES 1-3  

SciTech Connect

The US Department of Energy (DOE) has developed an Integrated Program Plan (IPP) to address concerns identified in Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1. The IPP describes the actions that DOE plans to implement at its various sites to convert excess fissile materials to forms or conditions suitable for safe interim storage. The baseline IPP was issued as DOE's DNFSB Recommendation 94-1 Implementation Plan (IP), which was transmitted to the DNFSB on February 28, 1995. The IPP was subsequently supplemented with an Integrated Facilities Plan and a Research and Development Plan, which further develop complex-wide research and development and long-range facility requirements and plans. These additions to the baseline IPP were developed based on a systems engineering approach that integrated facilities and capabilities at the various DOE sites and focused on attaining safe interim storage with minimum safety risks and environmental impacts. Each affected DOE site has developed a Site Integrated Stabilization Management Plan (SISMP) to identify individual site plans to implement the DNFSB Recommendation 94-1 IPP. The SISMPs were developed based on the objectives, requirements, and commitments identified in the DNFSB Recommendation 94-1 IP. The SISMPs supported formulation of the initial versions of the Integrated Facilities Plan and the Research and Development Plan. The SISMPs are periodically updated to reflect improved integration between DOE sites as identified during the IPP systems engineering evaluations. This document constitutes the Hanford SISMP. This document includes the planned work scope, costs and schedules for activities at the Hanford site to implement the DNFSB Recommendation 94-1 IPP.

Gerber, E.W.

1996-09-23T23:59:59.000Z

239

Three-dimensional Computational Fluid Dynamics (CFD) modeling of dry spent nuclear fuel storage canisters  

SciTech Connect

One of the interim storage configurations being considered for aluminum-clad foreign research reactor fuel, such as the Material and Testing Reactor (MTR) design, is in a dry storage facility. To support design studies of storage options, a computational and experimental program was conducted at the Savannah River Site (SRS). The objective was to develop computational fluid dynamics (CFD) models which would be benchmarked using data obtained from a full scale heat transfer experiment conducted in the SRS Experimental Thermal Fluids Laboratory. The current work documents the CFD approach and presents comparison of results with experimental data. CFDS-FLOW3D (version 3.3) CFD code has been used to model the 3-dimensional convective velocity and temperature distributions within a single dry storage canister of MTR fuel elements. For the present analysis, the Boussinesq approximation was used for the consideration of buoyancy-driven natural convection. Comparison of the CFD code can be used to predict reasonably accurate flow and thermal behavior of a typical foreign research reactor fuel stored in a dry storage facility.

Lee, S.Y.

1997-06-01T23:59:59.000Z

240

Graduate School of Journalism Interim Grievance Procedures  

E-Print Network (OSTI)

Graduate School of Journalism Interim Grievance Procedures Introduction The following procedures the Dean to conduct a hearing under the formal grievance procedures described in this statement. Those procedures, like the procedures of other schools, provide for a final appeal to the University Provost

Qian, Ning

Note: This page contains sample records for the topic "interim storage site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

340 waste handling facility interim safety basis  

SciTech Connect

This document presents an interim safety basis for the 340 Waste Handling Facility classifying the 340 Facility as a Hazard Category 3 facility. The hazard analysis quantifies the operating safety envelop for this facility and demonstrates that the facility can be operated without a significant threat to onsite or offsite people.

VAIL, T.S.

1999-04-01T23:59:59.000Z

242

340 Waste handling facility interim safety basis  

SciTech Connect

This document presents an interim safety basis for the 340 Waste Handling Facility classifying the 340 Facility as a Hazard Category 3 facility. The hazard analysis quantifies the operating safety envelop for this facility and demonstrates that the facility can be operated without a significant threat to onsite or offsite people.

Stordeur, R.T.

1996-10-04T23:59:59.000Z

243

--Program --InterimVice Provost and  

E-Print Network (OSTI)

Ladusaw, Interim Dean of Humanities Stephen Thorsett, Dean of Physical & Biological Sciences Sheldon Kamieniecki, Dean of Social Sciences Thimann, sTraUss, and sTeck Family aWards -- recePTion -- #12;Excellence Sciences. The award was established in 2004-05 through a gift to the Physical and Biological Sciences

California at Santa Cruz, University of

244

Interim report spent nuclear fuel retrieval system fuel handling development testing  

SciTech Connect

Fuel handling development testing was performed in support of the Fuel Retrieval System (FRS) Sub-Project at the Hanford Site. The project will retrieve spent nuclear fuel, clean and remove fuel from canisters, repackage fuel into baskets, and load fuel into a multi-canister overpack (MCO) for vacuum drying and interim dry storage. The FRS is required to retrieve basin fuel canisters, clean fuel elements sufficiently of uranium corrosion products (or sludge), empty fuel from canisters, sort debris and scrap from whole elements, and repackage fuel in baskets in preparation for MCO loading. The purpose of fuel handling development testing was to examine the systems ability to accomplish mission activities, optimization of equipment layouts for initial process definition, identification of special needs/tools, verification of required design changes to support performance specification development, and validation of estimated activity times/throughput. The test program was set up to accomplish this purpose through cold development testing using simulated and prototype equipment; cold demonstration testing using vendor expertise and systems; and graphical computer modeling to confirm feasibility and throughput. To test the fuel handling process, a test mockup that represented the process table was fabricated and installed. The test mockup included a Schilling HV series manipulator that was prototypic of the Schilling Hydra manipulator. The process table mockup included the tipping station, sorting area, disassembly and inspection zones, fuel staging areas, and basket loading stations. The test results clearly indicate that the Schilling Hydra arm cannot effectively perform the fuel handling tasks required unless it is attached to some device that can impart vertical translation, azimuth rotation, and X-Y translation. Other test results indicate the importance of camera locations and capabilities, and of the jaw and end effector tool design. 5 refs., 35 figs., 3 tabs.

Ketner, G.L.; Meeuwsen, P.V.; Potter, J.D.; Smalley, J.T.; Baker, C.P.; Jaquish, W.R.

1997-06-01T23:59:59.000Z

245

Foreign programs for the storage of spent nuclear power plant fuels, high-level waste canisters and transuranic wastes  

SciTech Connect

The various national programs for developing and applying technology for the interim storage of spent fuel, high-level radioactive waste, and TRU wastes are summarized. Primary emphasis of the report is on dry storage techniques for uranium dioxide fuels, but data are also provided concerning pool storage.

Harmon, K.M.; Johnson, A.B. Jr.

1984-04-01T23:59:59.000Z

246

Corrective Action Decision Document for Corrective Action Unit 145: Wells and Storage Holes, Nevada Test Site, Nevada, Rev. No.: 0, with ROTC No. 1 and Addendum  

SciTech Connect

This Corrective Action Decision Document has been prepared for Corrective Action Unit (CAU) 145, Wells and Storage Holes in Area 3 of the Nevada Test Site, Nevada, in accordance with the ''Federal Facility Agreement and Consent Order'' (1996). Corrective Action Unit 145 is comprised of the following corrective action sites (CASs): (1) 03-20-01, Core Storage Holes; (2) 03-20-02, Decon Pad and Sump; (3) 03-20-04, Injection Wells; (4) 03-20-08, Injection Well; (5) 03-25-01, Oil Spills; and (6) 03-99-13, Drain and Injection Well. The purpose of this Corrective Action Decision Document is to identify and provide the rationale for the recommendation of a corrective action alternative for the six CASs within CAU 145. Corrective action investigation activities were performed from August 1, 2005, through November 8, 2005, as set forth in the CAU 145 Corrective Action Investigation Plan and Record of Technical Change No. 1. Analytes detected during the Corrective Action Investigation (CAI) were evaluated against appropriate final action levels to identify the contaminants of concern for each CAS. The results of the CAI identified contaminants of concern at one of the six CASs in CAU 145 and required the evaluation of corrective action alternatives. Assessment of the data generated from investigation activities conducted at CAU 145 revealed the following: CASs 03-20-01, 03-20-02, 03-20-04, 03-20-08, and 03-99-13 do not contain contamination; and CAS 03-25-01 has pentachlorophenol and arsenic contamination in the subsurface soils. Based on the evaluation of analytical data from the CAI, review of future and current operations at the six CASs, and the detailed and comparative analysis of the potential corrective action alternatives, the following corrective actions are recommended for CAU 145. No further action is the preferred corrective action for CASs 03-20-01, 03-20-02, 03-20-04, 03-20-08, and 03-99-13. Close in place is the preferred corrective action for CAS 03-25-01. The preferred corrective action alternatives were evaluated on technical merit focusing on performance, reliability, feasibility, safety, and cost. The alternatives were judged to meet all requirements for the technical components evaluated. The alternatives meet all applicable federal and state regulations for closure of the site and will reduce potential exposure pathways to the contaminated media to an acceptable level at CAU 145.

David Strand

2006-04-01T23:59:59.000Z

247

Superfund Record of Decision (EPA Region 1): Otis Air National Guard/Camp Edwards, MA. (First remedial action), May 1992. Interim report  

SciTech Connect

The 22,000-acre Otis National Guard/Camp Edwards site is a former military vehicle maintenance facility on Cape Cod, Massachusetts, within the Massachusetts Military Reservation (MMR). The Area of Contamination Chemical Spill Area Number 4 (AOC CS-4) plume extends 11,000 feet and is located 1.1 miles from the southern boundary of MMR. Wastes and equipment handled at AOC CS-4 included oils, solvents, antifreeze, battery electrolytes, paint, and waste fuels. Additionally, the northern portion of AOC CS-4 was used as a storage yard for wastes generated by shops and laboratories operating at MMR. Liquid wastes were stored in containers or underground storage tanks (USTs) in an unbermed area or deposited in USTs designated for motor gasoline. The ROD addresses OU2, the interim action for MMR AOC CS-4 ground water to prevent further down gradient migration of the contaminants. The primary contaminants of concern affecting the ground water are VOCs, including PCE and TCE.

Not Available

1992-05-20T23:59:59.000Z

248

Interim Management of Nuclear Materials  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Summary-1995.html[6/27/2011 12:50:20 PM] Summary-1995.html[6/27/2011 12:50:20 PM] SUMMARY The Atomic Energy Commission (AEC), a predecessor agency of the Department of Energy (DOE), established the Savannah River Site (SRS) in the early 1950s for the production of special radioactive isotopes. The primary SRS mission was to produce strategic isotopes (plutonium-239 and tritium) used in the development and production of nuclear weapons for national defense. The Site produced other special isotopes (californium-252, plutonium-238, americium-241, etc.) to support research in nuclear medicine, space exploration, and commercial applications. The historic production cycle at the SRS involved the fabrication of metal fuel and target assemblies for irradiation in the Site reactors, followed by chemical dissolution, separation, and conversion of the radioisotopes into solid forms for use

249

DOE/EA-1528: Environmental Assessment for the Storage of Tritium-Producing Burnable Absorber RODs in K-Area Transfer Bay at the Savannah River Site (6/2/05)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

28 28 JUNE 2005 U. S. DEPARTMENT OF ENERGY SAVANNAH RIVER OPERATIONS OFFICE SAVANNAH RIVER SITE ENVIRONMENTAL ASSESSMENT FOR THE STORAGE OF TRITIUM-PRODUCING BURNABLE ABSORBER RODS IN K-AREA TRANSFER BAY AT THE SAVANNAH RIVER SITE DOE/EA-1528 ENVIRONMENTAL ASSESSMENT FOR THE STORAGE OF TRITIUM-PRODUCING BURNABLE ABSORBER RODS IN K-AREA TRANSFER BAY AT THE SAVANNAH RIVER SITE June 2005 U. S. DEPARTMENT OF ENERGY SAVANNAH RIVER OPERATIONS OFFICE SAVANNAH RIVER SITE This page is intentionally left blank ii TABLE OF CONTENTS Page 1.0 INTRODUCTION 1 1.1 Background 1 1.2 Purpose and Need for Action 2 2.0 PROPOSED ACTION AND ALTERNATIVES 2 2.1 Proposed Action 2 2.2 Alternatives to the Proposed Action 3

250

Geological and Geotechnical Site Investigation for the Design of a CO2 Rich Flue Gas Direct Injection and Storage Facility  

SciTech Connect

With international efforts to limit anthropogenic carbon in the atmosphere, various CO{sub 2} sequestration methods have been studied by various facilities worldwide. Basalt rock in general has been referred to as potential host material for mineral carbonation by various authors, without much regard for compositional variations due to depositional environment, subsequent metamorphism, or hydrothermal alteration. Since mineral carbonation relies on the presence of certain magnesium, calcium, or iron silicates, it is necessary to study the texture, mineralogy, petrology, and geochemistry of specific basalts before implying potential for mineral carbonation. The development of a methodology for the characterization of basalts with respect to their susceptibility for mineral carbonation is proposed to be developed as part of this research. The methodology will be developed based on whole rock data, petrography and microprobe analyses for samples from the Caledonia Mine in Michigan, which is the site for a proposed small-scale demonstration project on mineral carbonation in basalt. Samples from the Keweenaw Peninsula will be used to determine general compositional trends using whole rock data and petrography. Basalts in the Keweenaw Peninsula have been subjected to zeolite and prehnite-pumpellyite facies metamorphism with concurrent native copper deposition. Alteration was likely due to the circulation of CO{sub 2}-rich fluids at slightly elevated temperatures and pressures, which is the process that is attempted to be duplicated by mineral carbonation.

Metz, Paul; Bolz, Patricia

2013-03-25T23:59:59.000Z

251

Site characterization plan: Conceptual design report: Volume 4, Appendices F-O: Nevada Nuclear Waste Storage Investigations Project  

SciTech Connect

The site for the prospective repository is located at Yucca Mountain in southwestern Nevada, and the waste emplacement area will be constructed in the underlying volcanic tuffs. The target horizon for waste emplacement is a sloping bed of densely welded tuff more than 650 ft below the surface and typically more than 600 ft above the water table. The conceptual design described in this report is unique among repository designs in that it uses ramps in addition to shafts to gain access to the underground facility, the emplacement horizon is located above the water table, and it is possible that 300- to 400-ft-long horizontal waste emplacement boreholes will be used. This report summarizes the design bases, design and performance criteria, and the design analyses performed. The current status of meeting the preclosure performance objectives for licensing and of resolving the repository design and preclosure issues is presented. The repository design presented in this report will be expanded and refined during the advanced conceptual design, the license application design, and the final procurement and construction design phases. Volume 4 contains Appendices F to O.

MacDougall, H R; Scully, L W; Tillerson, J R [comps.] [comps.

1987-09-01T23:59:59.000Z

252

Site characterization plan: Conceptual design report: Volume 5, Appendices P-R: Nevada Nuclear Waste Storage Investigations Project  

SciTech Connect

The site for the prospective respository is located at Yucca Mountain in southwestern Nevada, and the waste emplacement area will be constructed in the underlying volcanic tuffs. The target horizon for waste emplacement is a sloping bed of densely welded tuff more than 650 ft below the surface and typically more than 600 ft above the water table. The conceptual design described in this report is unique among repository designs in that it uses ramps in addition to shafts to gain access to the underground facility, the emplacement horizon is located above the water table, and it is possible that 300- to 400-ft-long horizontal waste emplacement boreholes will be used. This report summarizes the design bases, design and performance criteria, and the design analyses performed. The current status of meeting the preclosure performance objectives for licensing and of resolving the repository design and preclosure issues is presented. The repository design presented in this report will be expanded and refined during the advanced conceptual design, the license application design, and the final procurement and construction design phases. Volume 5 contains appendices P through R.

MacDougall, H.R.; Scully, L.W.; Tillerson, J.R. (comps.)

1987-09-01T23:59:59.000Z

253

DOE/EA-1538: Finding of No Significant Impact for the Safeguards and Security Upgrades for Storage of Plutonium Materials at the Savannah River Site (12/16/2005)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Safeguards and Security Upgrades for Storage of Plutonium Materials Safeguards and Security Upgrades for Storage of Plutonium Materials at the Savannah River Site Agency: U.S. Department of Energy Action: Finding of No Significant Impact Summary: The Department of Energy (DOE) has prepared an environmental assessment (EA) (DOE/EA-1538) to evaluate the potential environmental impacts associated with the implementation of proposed and alternative actions to enhance the safe and secure storage of plutonium-bearing materials at the Savannah River Site (SRS) to meet the enhanced terrorist threat. The draft EA was made available to the States of South Carolina and Georgia, and to the public, for a 30-day comment period. Based on the analyses in the EA, and after careful consideration of comments received, DOE has

254

Record of Technical Change 1 for Closure Report for Corrective Action Unit 204: Storage Bunkers, Nevada Test Site, Nevada, Revision 0  

SciTech Connect

Downgrade the FFACO UR at CAU 204, CAS 05-18-02, Chemical Explosives Storage to an Administrative UR.

Krauss, Mark J; Birney, Cathleen

2006-04-01T23:59:59.000Z

255

Nevada Test Site waste acceptance criteria [Revision 1  

SciTech Connect

Revision one updates the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document.

None

1997-08-01T23:59:59.000Z

256

TSPA Third Interim Report - March, 1998  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Third Interim Report Third Interim Report Total System Performance Assessment Peer Review Panel Preface Executive Summary I. Introduction II. The TSPA-VA Base Case Analysis 1. The TSPA-VA Base Case Analysis A. Results of the TSPA-VA Base Case Analysis B. The Plausibility of the Base Case C. Sensitivity Studies III. Component Models of TSPA A. Unsaturated Zone Infiltration and Flow B. Thermohydrology C. Near-Field Geochemical Environment D. Waste Package Degradation E. Waste Form Alteration/Mobilization F. Unsaturated Zone Transport G. Saturated Zone Flow and Transport H. Biosphere I. Disruptive Events and Climate IV. Conclusions and Recommendations A. Introductory Comments B. Critical Observations and Findings C. Other Issues V. References

257

TSPA First Interim Report - June 20, 1997  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

FIRST INTERIM REPORT FIRST INTERIM REPORT TOTAL SYSTEMS PERFORMANCE ASSESSMENT PEER REVIEW PANEL JUNE 20, 1997 i PREFACE The Peer Review Panel has written this report with two distinct audiences in mind: (1) those who are actively engaged in producing the Total Systems Performance Assessment and (2) those who are interested in the progress of the Total Systems Performance Assessment and its implications for future policy decisions. The first group will find some of the introductory information unnecessary and will want to concentrate on the technical findings and explanations. The Panel hopes that the report also contains enough background information and explanations of terms and is written clearly enough that it will be intelligible to the second group, namely those interested in the outcome, but not involved in the technical work. The Panel welcomes

258

TSPA Second Interim Report - December 12, 1997  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

SECOND INTERIM REPORT SECOND INTERIM REPORT TOTAL SYSTEM PERFORMANCE ASSESSMENT PEER REVIEW PANEL DECEMBER 12, 1997 i PREFACE This report is the second in a series from the Performance Assessment Peer Review Panel. The Panel considers each successive report as an integral part of a series. Issues that have been covered previously will not be repeated unless new information or concerns arise. In preparing this report, the Panel has directed its primary attention to the methods, data, and assumptions that have been developed or identified for the Total System Performance Assessment to be used in the Viability Assessment. The Panel's goals have been to note weaknesses that can be ameliorated through the use of more appropriate models and data, to seek clarification of the bases for certain of the analytical approaches

259

Stephenson is Interim ALD for Photon Sciences  

NLE Websites -- All DOE Office Websites (Extended Search)

Students at Argonne on the FaST Track to New Skills Students at Argonne on the FaST Track to New Skills How Did the Caterpillar Cross the Road? R&D 100 Awards for New X-ray Technologies In Nature: Fischetti on Minibeams Sidorowicz of AES Earns UChicago Argonne, LLC Board of Governors Outstanding Service Award for 2010 APS News Archives: 2012 | 2011 | 2010 | 2009 2008 | 2007 | 2006 | 2005 2004 | 2003 | 2002 | 2001 2000 Subscribe to APS News rss feed Stephenson is Interim ALD for Photon Sciences OCTOBER 1, 2010 Bookmark and Share G. Brian Stephenson Argonne Director Eric Isaacs has appointed G. Brian Stephenson as the Interim Associate Laboratory Director for Photon Sciences, effective Oct. 1, 2010. The text of Director Isaacs' announcement is below. Sept. 30, 2010 To: All employees From: Eric Isaacs, Argonne Director

260

Detailed compositional analysis of gas seepage at the National Carbon Storage Test Site, Teapot Dome, Wyoming, USA  

Science Journals Connector (OSTI)

A baseline determination of CO2 and CH4 fluxes and soil gas concentrations of CO2 and CH4 was made over the Teapot Dome oil field in the Naval Petroleum Reserve No. 3 (NPR-3) in Wyoming, USA. This was done in anticipation of experimentation with CO2 sequestration in the Pennsylvanian Tensleep Sandstone underlying the field at a depth of 1680m. The baseline data were collected during the winter, 2004 in order to minimize near-surface biological activity in the soil profile. The baseline data were used to select anomalous locations that may be the result of seeping thermogenic gas, along with background locations. Five 10-m holes were drilled, 3 of which had anomalous gas microseepage, and 2 were characterized as background. These were equipped for nested gas sampling at depths of 10-, 5-, 3-, 2-, and 1-m depths. Methane concentrations as high as 170,000ppmv (17%) were found, along with high concentrations of C2H6, C3H8, n-C4H10, and i-C4H10. Much smaller concentrations of C2H4 and C3H6 were observed indicating the beginning of hydrocarbon oxidation in the anomalous holes. The anomalous 10-m holes also had high concentrations of isotopically enriched CO2, indicating the oxidation of hydrocarbons. Concentrations of the gases decreased upward, as expected, indicating oxidation and transport into the atmosphere. The ancient source of the gases was confirmed by 14C determinations on CO2, with radiocarbon ages approaching 38ka within 5m of the surface. Modeling was used to analyze the distribution of hydrocarbons in the anomalous and background 10-m holes. Diffusion alone was not sufficient to account for the hydrocarbon concentration distributions, however the data could be fit with the addition of a consumptive reaction. First-order rate constants for methanotrophic oxidation were obtained by inverse modeling. High rates of oxidation were found, particularly near the surface in the anomalous 10-m holes, demonstrating the effectiveness of the process in the attenuation of CH4 microseepage. The results also demonstrate the importance of CH4 measurements in the planning of a monitoring and verification program for geological CO2 sequestration in sites with significant remaining hydrocarbons (i.e. spent oil reservoirs).

Ronald W. Klusman

2006-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "interim storage site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

Nuclear Industry Input to the Development of Concepts for the Consolidated Storage of Used Nuclear Fuel - 13411  

SciTech Connect

EnergySolutions and its team partners, NAC International, Exelon Nuclear Partners, Talisman International, TerranearPMC, Booz Allen Hamilton and Sargent and Lundy, have carried out a study to develop concepts for a Consolidated Storage Facility (CSF) for the USA's stocks of commercial Used Nuclear Fuel (UNF), and the packaging and transport provisions required to move the UNF to the CSF. The UNF is currently stored at all 65 operating nuclear reactor sites in the US, and at 10 shutdown sites. The study was funded by the US Department of Energy and followed the recommendations of the Blue Ribbon Commission on America's Nuclear Future (BRC), one of which was that the US should make prompt efforts to develop one or more consolidated storage facilities for commercial UNF. The study showed that viable schemes can be devised to move all UNF and store it at a CSF, but that a range of schemes is required to accommodate the present widely varying UNF storage arrangements. Although most UNF that is currently stored at operating reactor sites is in water-filled pools, a significant amount is now dry stored in concrete casks. At the shutdown sites, the UNF is dry stored at all but two of the ten sites. Various types of UNF dry storage configurations are used at the operating sites and shutdown sites that include vertical storage casks that are also licensed for transportation, vertical casks that are licensed for storage only, and horizontally orientated storage modules. The shutdown sites have limited to nonexistent UNF handling infrastructure and several no longer have railroad connections, complicating UNF handling and transport off the site. However four methods were identified that will satisfactorily retrieve the UNF canisters within the storage casks and transport them to the CSF. The study showed that all of the issues associated with the transportation and storage of UNF from all sites in the US can be accommodated by adopting a staged approach to the construction of the CSF. Stage 1 requires only a cask storage pad and railroad interface to be constructed, and the CSF can then receive the UNF that is in transportable storage casks. Stage 2 adds a canister handling facility, a storage cask fabrication facility and an expanded storage pad, and enables the receipt of all canistered UNF from both operating and shutdown sites. Stage 3 provides a repackaging facility with a water-filled pool that provides flexibility for a range of repackaging scenarios. This includes receiving and repackaging 'bare' UNF into suitable canisters that can be placed into interim storage at the CSF, and enables UNF that is being received, or already in storage onsite, to be repackaged into canisters that are suitable for disposal at a geologic repository. The study used the 'Total System Model' (TSM) to analyze a range of CSF capacities and operating scenarios with differing parameters covering UNF pickup orders, one or more CSF sites, CSF start dates, CSF receipt rates and geologic repository start dates. The TSM was originally developed to model movement of UNF to the Yucca Mountain repository and was modified for this study to enable the CSF to become the 'gateway' to a future geologic repository. The TSM analysis enabled costs to be estimated for each scenario and showed how these are influenced by each of the parameters. This information will provide essential underpinning for a future Conceptual Design preparation. (authors)

Phillips, Chris; Thomas, Ivan; McNiven, Steven [EnergySolutions Federal EPC., 2345 Stevens Drive, Richland, WA, 99354 (United States)] [EnergySolutions Federal EPC., 2345 Stevens Drive, Richland, WA, 99354 (United States); Lanthrum, Gary [NAC International, 3930 East Jones Bridge Road, Norcross, GA, 30092 (United States)] [NAC International, 3930 East Jones Bridge Road, Norcross, GA, 30092 (United States)

2013-07-01T23:59:59.000Z

262

Northeast Site Non-Aqueous Phase Liquids Interim Measures Progress...  

Office of Legacy Management (LM)

cis-1,2- DCE (mgkg) Methylene Chloride (mgkg) Toluene (mgkg) TCE (mgkg) Florida Petroleum Range Organics (mgkg) NAPL Remediation Goals 71,000 227,000 15,000 20,400 2,500,000...

263

Hanford Advisory Board Fiscal Year 2015 Interim Work Plan  

NLE Websites -- All DOE Office Websites (Extended Search)

Advisor Nina Menard, Ecology Action: Public Involvement Presentation by DOE-RL RAP Hanford Advisory Board Fiscal Year 2015 Interim Work Plan Adopted by consensus September 5,...

264

Interim Report of the Task Force on Nuclear Nonproliferation  

Energy.gov (U.S. Department of Energy (DOE))

This interim report of the SEAB Task Force on Nuclear Nonproliferation sets forth its findings and recommendations to date in five timely and important areas

265

Finding of No Significant Impact for the Storage of Tritium-Producing Burnable Absorber Rods in K-Area Transfer Bay at the Savannah River Site (DOE/EA-1528) (06/01/05)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

the the Storage of Tritium-Producing Burnable Absorber Rods in K-Area Transfer Bay at the Savannah River Site Agency: U.S. Department of Energy (DOE) Action: Finding of No Significant Impact Summary: The DOE Savannah River Operations Office (SR) and the National Nuclear Security Administration (NNSA) Savannah River Site Office (SRSO) have prepared an environmental assessment (EA), DOE/EA-1528, to evaluate the potential environmental impacts of the temporary dry storage of a cask containing Tritium- Producing Burnable Absorber Rods (TPBARs) in the Transfer Bay in K Area at the Savannah River Site (SRS). Based on the analyses in the EA, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the

266

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

SciTech Connect

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

Not Available

1993-11-01T23:59:59.000Z

267

Interim Status Groundwater Monitoring Plan for Low-Level Waste Management Areas 1 to 4, RCRA Facilities, Hanford,Washington  

SciTech Connect

This document describes the monitoring plan to meet the requirements for interim status groundwater monitoring at Hanford Site low-level waste burial grounds as specified by 40 CFR 265, incorporated by reference in WAC 173-303-400. The monitoring will take place at four separate low-level waste management areas in the 200-West and 200-East Areas, in the central part of the site. This plan replaces the previous monitoring plan.

Dresel, P Evan

2004-10-25T23:59:59.000Z

268

The Effect of Weld Residual Stress on Life of Used Nuclear Fuel Dry Storage Canisters  

SciTech Connect

With the elimination of Yucca Mountain as the long-term storage facility for spent nuclear fuel in the United States, a number of other storage options are being explored. Currently, used fuel is stored in dry-storage cask systems constructed of steel and concrete. It is likely that used fuel will continue to be stored at existing open-air storage sites for up to 100 years. This raises the possibility that the storage casks will be exposed to a salt-containing environment for the duration of their time in interim storage. Austenitic stainless steels, which are used to construct the canisters, are susceptible to stress corrosion cracking (SCC) in chloride-containing environments if a continuous aqueous film can be maintained on the surface and the material is under stress. Because steel sensitization in the canister welds is typically avoided by avoiding post-weld heat treatments, high residual stresses are present in the welds. While the environment history will play a key role in establishing the chemical conditions for cracking, weld residual stresses will have a strong influence on both crack initiation and propagation. It is often assumed for modeling purposes that weld residual stresses are tensile, high and constant through the weld. However, due to the strong dependence of crack growth rate on stress, this assumption may be overly conservative. In particular, the residual stresses become negative (compressive) at certain points in the weld. The ultimate goal of this research project is to develop a probabilistic model with quantified uncertainties for SCC failure in the dry storage casks. In this paper, the results of a study of the residual stresses, and their postulated effects on SCC behavior, in actual canister welds are presented. Progress on the development of the model is reported.

Ronald G. Ballinger; Sara E. Ferry; Bradley P. Black; Sebastien P. Teysseyre

2013-08-01T23:59:59.000Z

269

Interim Management of Nuclear Materials  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

1995/01_eis0220_for.html[6/27/2011 12:53:53 PM] 1995/01_eis0220_for.html[6/27/2011 12:53:53 PM] FOREWORD The Savannah River Site (SRS) is a major Department of Energy (DOE) installation. The past mission of the SRS was to produce nuclear materials that supported the defense, research, and medical programs of the United States. In 1992 the Secretary of Energy directed the SRS to phase out defense-related chemical separations activities. As a result of shutdowns and reduced demand for nuclear materials, the SRS presently has a large inventory of in-process solutions, reactor fuel assemblies, and reactor targets. These materials, due to their form or to the condition in which they are maintained, could represent a concern for the public, worker health and safety, and the environment. DOE published a Notice of Intent (NOI) to prepare this environmental impact statement (EIS) on March 17, 1994 (59

270

Interim Management of Nuclear Materials  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

1995/01_eis0220_for.html[6/27/2011 12:53:53 PM] 1995/01_eis0220_for.html[6/27/2011 12:53:53 PM] FOREWORD The Savannah River Site (SRS) is a major Department of Energy (DOE) installation. The past mission of the SRS was to produce nuclear materials that supported the defense, research, and medical programs of the United States. In 1992 the Secretary of Energy directed the SRS to phase out defense-related chemical separations activities. As a result of shutdowns and reduced demand for nuclear materials, the SRS presently has a large inventory of in-process solutions, reactor fuel assemblies, and reactor targets. These materials, due to their form or to the condition in which they are maintained, could represent a concern for the public, worker health and safety, and the environment. DOE published a Notice of Intent (NOI) to prepare this environmental impact statement (EIS) on March 17, 1994 (59

271

American Transmission Company Comments - 216h Interim Final Rules |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

American Transmission Company Comments - 216h Interim Final Rules American Transmission Company Comments - 216h Interim Final Rules American Transmission Company Comments - 216h Interim Final Rules American Transmission Company LLC, by its corporate manager, ATC Management Inc. (collectively "ATCLLC") is pleased to have the opportunity to provide the following comments on the additional matters to be considered by DOE in connection with the Rules. Interim Final Rule Comments, RIN 1901-AB18 Coordination of Federal Authorizations for Electric Transmission Facilities More Documents & Publications Comments of the Staff of the public utilities commission of the state of California on the interim final rule Comments on Notice of Proposed Rulemaking for Coordination of Federal Authorizations for Electric Transmission Facilities

272

A Comparison of Popular Remedial Technologies for Petroleum Contaminated Soils from Leaking Underground Storage Tanks  

E-Print Network (OSTI)

Underground Storage Tanks. Chelsea: Lewis Publishers.and Underground Storage Tank Sites. Database on-line.Michigan Underground Storage Tank Rules. Database on-line.

Kujat, Jonathon D.

1999-01-01T23:59:59.000Z

273

Revised Finding of No Significant Impact for Safeguards and Security Upgrades for Storage of Plutonium Materials at the Savannah River Site (DOE/EA-1538)(03/11/08)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Finding of No Significant Impact Finding of No Significant Impact for Safeguards and Security Upgrades for Storage of Plutonium Materials at the Savannah River Site Agency: U.S. Department of Energy Action: Revised Finding of No Significant Impact Summary: The Department of Energy (DOE) prepared an environmental assessment (EA) (DOEEA-1538) in 2005 to evaluate the potential environmental impacts associated with the implementation of proposed and alternative actions to enhance the safe and secure storage of plutonium-bearing materials at the Savannah River Site (SRS) to meet the enhanced terrorist threat that has existed since the events of September 11, 2001. Based on the analyses in the EA, DOE determined that the proposed action was not a major Federal action significantly affecting

274

TECHNOLOGY DEVELOPMENT AND DEPLOYMENT OF SYSTEMS FOR THE RETRIEVAL AND PROCESSING OF REMOTE-HANDLED SLUDGE FROM HANFORD K-WEST FUEL STORAGE BASIN  

SciTech Connect

In 2011, significant progress was made in developing and deploying technologies to remove, transport, and interim store remote-handled sludge from the 105-K West Fuel Storage Basin on the Hanford Site in south-central Washington State. The sludge in the 105-K West Basin is an accumulation of degraded spent nuclear fuel and other debris that collected during long-term underwater storage of the spent fuel. In 2010, an innovative, remotely operated retrieval system was used to successfully retrieve over 99.7% of the radioactive sludge from 10 submerged temporary storage containers in the K West Basin. In 2011, a full-scale prototype facility was completed for use in technology development, design qualification testing, and operator training on systems used to retrieve, transport, and store highly radioactive K Basin sludge. In this facility, three separate systems for characterizing, retrieving, pretreating, and processing remote-handled sludge were developed. Two of these systems were successfully deployed in 2011. One of these systems was used to pretreat knockout pot sludge as part of the 105-K West Basin cleanup. Knockout pot sludge contains pieces of degraded uranium fuel ranging in size from 600 {mu}m to 6350 {mu}m mixed with pieces of inert material, such as aluminum wire and graphite, in the same size range. The 2011 pretreatment campaign successfully removed most of the inert material from the sludge stream and significantly reduced the remaining volume of knockout pot product material. Removing the inert material significantly minimized the waste stream and reduced costs by reducing the number of transportation and storage containers. Removing the inert material also improved worker safety by reducing the number of remote-handled shipments. Also in 2011, technology development and final design were completed on the system to remove knockout pot material from the basin and transport the material to an onsite facility for interim storage. This system is scheduled for deployment in 2012. The prototype facility also was used to develop technology for systems to retrieve remote-handled transuranic sludge smaller than 6350 {mu}m being stored in underwater containers. After retrieving the sludge, the system will be used to load and transport the sludge for interim storage. During 2011, full-scale prototype systems were developed and tested to a Technology Readiness Level 6 as defined by U.S. Department of Energy standards. This system is scheduled for deployment in 2013. Operations also are scheduled for completion in 2014.

RAYMOND RE

2011-12-27T23:59:59.000Z

275

The used nuclear fuel problem - can reprocessing and consolidated storage be complementary?  

SciTech Connect

This paper describes our CISF (Consolidated Interim Storage Facilities) and Reprocessing Facility concepts and show how they can be combined with a geologic repository to provide a comprehensive system for dealing with spent fuels in the USA. The performance of the CISF was logistically analyzed under six operational scenarios. A 3-stage plan has been developed to establish the CISF. Stage 1: the construction at the CISF site of only a rail receipt interface and storage pad large enough for the number of casks that will be received. The construction of the CISF Canister Handling Facility, the Storage Cask Fabrication Facility, the Cask Maintenance Facility and supporting infrastructure are performed during stage 2. The construction and placement into operation of a water-filled pool repackaging facility is completed for Stage 3. By using this staged approach, the capital cost of the CISF is spread over a number of years. It also allows more time for a final decision on the geologic repository to be made. A recycling facility will be built, this facility will used the NUEX recycling process that is based on the aqueous-based PUREX solvent extraction process, using a solvent of tri-N-butyl phosphate in a kerosene diluent. It is capable of processing spent fuels at a rate of 5 MT per day, at burn-ups up to 50 GWD per ton of spent fuels and a minimum of 5 years out-of-reactor cooling.

Phillips, C.; Thomas, I. [EnergySolutions Federal EPC., 2345 Stevens Drive, Richland, WA 99354 (United States)

2013-07-01T23:59:59.000Z

276

Bulletin # 8 May 2003 It is the value of your records and data that should dictate the type of storage and protection  

E-Print Network (OSTI)

the type of storage and protection you need for them. Off-Site storage is generally an efficient.......................................................1 The Role of Off Site Records Storage......................1 Prerequisites......................................................2 Off Site Storage..................................................2 General Questions to Ask

Sheridan, Jennifer

277

PROJECT W-551 INTERIM PRETREATMENT SYSTEM PRECONCEPTUAL CANDIDATE TECHNOLOGY DESCRIPTIONS  

SciTech Connect

The Office of River Protection (ORP) has authorized a study to recommend and select options for interim pretreatment of tank waste and support Waste Treatment Plant (WTP) low activity waste (LAW) operations prior to startup of all the WTP facilities. The Interim Pretreatment System (IPS) is to be a moderately sized system which separates entrained solids and 137Cs from tank waste for an interim time period while WTP high level waste vitrification and pretreatment facilities are completed. This study's objective is to prepare pre-conceptual technology descriptions that expand the technical detail for selected solid and cesium separation technologies. This revision includes information on additional feed tanks.

MAY TH

2008-08-12T23:59:59.000Z

278

FINAL DOE/OR/21950-1016 RESPONSIVENESS SUMMARY= PRAXAIR INTERIM ACTIONS ENGINEERING  

Office of Legacy Management (LM)

p//l/ * :P/ p//l/ * :P/ 142366 _ FINAL DOE/OR/21950-1016 RESPONSIVENESS SUMMARY= PRAXAIR INTERIM ACTIONS ENGINEERING EVALUATION/COST ANALYSIS (EEKA) TONAWANDA, NEW YORK MAY 1996 prepared by U.S. Department of Energy, Oak Ridge Operations Off ice, Formerly Utilized Sites Remedial Action Program with technical assistance from Science Applications International Corporation ESC-FUSRAP under Contract No. DE-AC05-91OR21950 TABLE OF CONTENTS LISTOFTABLES ........................................... iii ACRONYMS AND ABBREVIATIONS ............................... v 1. INTRODUCTION ......................................... 1 2. SCOPE AND ORGANIZATION OF THE RESPONSIVENESS SUMMARY ..... 1 3. COMMENTSANDRESPONSES ....................... .: ... . .... 1 3.1 THE PREFERRED REMEDY .............................

279

Acquisition Career Management Program Manual Interim Guidance  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Management Program Manual Management Program Manual Interim Guidance Partial Revision Chapter 11 Contracting Officers Representatives (COR) Contracting Officers Representatives Background FAI published a report in 2003 on the competencies necessary for the COR job function and the US Merit Systems Protection Board published a report in 2005 entitled "Contracting Officer Representatives: Managing the Government's Technical Experts to Achieve Positive Contract Outcomes." Both reports are available at www.fai.gov. A common theme in these reports is the need to organize and support the COR community to ensure that acquisition management is implemented effectively. Some of the findings and recommendations of the reports are: * CORs must be formally delegated authority to work on particular contracts

280

Corrective Action Investigation Plan for Corrective Action Unit 214: Bunkers and Storage Areas Nevada Test Site, Nevada: Revision 0, Including Record of Technical Change No. 1 and No. 2  

SciTech Connect

This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 214 under the Federal Facility Agreement and Consent Order. Located in Areas 5, 11, and 25 of the Nevada Test Site, CAU 214 consists of nine Corrective Action Sites (CASs): 05-99-01, Fallout Shelters; 11-22-03, Drum; 25-99-12, Fly Ash Storage; 25-23-01, Contaminated Materials; 25-23-19, Radioactive Material Storage; 25-99-18, Storage Area; 25-34-03, Motor Dr/Gr Assembly (Bunker); 25-34-04, Motor Dr/Gr Assembly (Bunker); and 25-34-05, Motor Dr/Gr Assembly (Bunker). These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). The suspected contaminants and critical analyte s for CAU 214 include oil (total petroleum hydrocarbons-diesel-range organics [TPH-DRO], polychlorinated biphenyls [PCBs]), pesticides (chlordane, heptachlor, 4,4-DDT), barium, cadmium, chronium, lubricants (TPH-DRO, TPH-gasoline-range organics [GRO]), and fly ash (arsenic). The land-use zones where CAU 214 CASs are located dictate that future land uses will be limited to nonresidential (i.e., industrial) activities. The results of this field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the corrective action decision document.

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

2003-05-16T23:59:59.000Z

Note: This page contains sample records for the topic "interim storage site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

The Humboldt House-Rye Patch geothermal district: an interim...  

Open Energy Info (EERE)

search OpenEI Reference LibraryAdd to library Conference Paper: The Humboldt House-Rye Patch geothermal district: an interim view Abstract The Humboldt House - Rye Patch...

282

TANK FARM INTERIM SURFACE BARRIER MATERIALS AND RUNOFF ALTERNATIVES STUDY  

SciTech Connect

This report identifies candidate materials and concepts for interim surface barriers in the single-shell tank farms. An analysis of these materials for application to the TY tank farm is also provided.

HOLM MJ

2009-06-25T23:59:59.000Z

283

DOE - Office of Legacy Management -- Monticello Mill Site - UT 03  

NLE Websites -- All DOE Office Websites (Extended Search)

Mill Site - UT 03 Mill Site - UT 03 FUSRAP Considered Sites Site: Monticello Mill Site (UT.03) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Monticello, Utah, Disposal and Processing Sites Documents Related to Monticello Mill Site Monticello Mill Tailings Site Operable Unit III Interim Remedial Action Progress Report July 1999-July 2000. GJO-2000-163-TAR. September 2000 U.S. Department of Energy at Grand Junction 2003 Annual Inspection Monticello, Utah November 2003 2005 Annual Inspection of the Monticello Mill Tailings (USDOE) and Monticello Radioactively Contaminated Properties Sites December 2005 Office

284

Interim Safety Basis for Fuel Supply Shutdown Facility  

SciTech Connect

This ISB, in conjunction with the IOSR, provides the required basis for interim operation or restrictions on interim operations and administrative controls for the facility until a SAR is prepared in accordance with the new requirements or the facility is shut down. It is concluded that the risks associated with tha current and anticipated mode of the facility, uranium disposition, clean up, and transition activities required for permanent closure, are within risk guidelines.

BENECKE, M.W.

2000-09-07T23:59:59.000Z

285

Ground water remediation at the Moab, Utah, USA, former uranium-ore processing site  

Science Journals Connector (OSTI)

Seepage from the Moab, Utah, USA, former uranium-ore processing site resulted in ammonia and uranium contamination of naturally occurring saline ground water in alluvium adjacent to the Colorado River. An interim...

Donald R. Metzler; Joseph D. Ritchey; Kent A. Bostick

2008-01-01T23:59:59.000Z

286

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

SciTech Connect

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

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

2013-07-01T23:59:59.000Z

287

Hazard Evaluation for Storage of Spent Nuclear Fuel (SNF) Sludge at the Solid Waste Treatment Facility  

SciTech Connect

As part of the Spent Nuclear Fuel (SNF) storage basin clean-up project, sludge that has accumulated in the K Basins due to corrosion of damaged irradiated N Reactor will be loaded into containers and placed in interim storage. The Hanford Site Treatment Complex (T Plant) has been identified as the location where the sludge will be stored until final disposition of the material occurs. Long term storage of sludge from the K Basin fuel storage facilities requires identification and analysis of potential accidents involving sludge storage in T Plant. This report is prepared as the initial step in the safety assurance process described in DOE Order 5480.23, Nuclear Safety Analysis Reports and HNF-PRO-704, Hazards and Accident Analysis Process. This report documents the evaluation of potential hazards and off-normal events associated with sludge storage activities. This information will be used in subsequent safety analyses, design, and operations procedure development to ensure safe storage. The hazards evaluation for the storage of SNF sludge in T-Plant used the Hazards and Operability Analysis (HazOp) method. The hazard evaluation identified 42 potential hazardous conditions. No hazardous conditions involving hazardous/toxic chemical concerns were identified. Of the 42 items identified in the HazOp study, eight were determined to have potential for onsite worker consequences. No items with potential offsite consequences were identified in the HazOp study. Hazardous conditions with potential onsite worker or offsite consequences are candidates for quantitative consequence analysis. The hazardous conditions with potential onsite worker consequences were grouped into two event categories, Container failure due to overpressure - internal to T Plant, and Spill of multiple containers. The two event categories will be developed into accident scenarios that will be quantitatively analyzed to determine release consequences. A third category, Container failure due to overpressure--external to T Plant, was included for completeness but is not within the scope of the hazards evaluation. Container failures external to T Plant will be addressed as part of the transportation analysis. This document describes the HazOp analysis performed for the activities associated with the storage of SNF sludge in the T Plant.

SCHULTZ, M.V.

2000-08-22T23:59:59.000Z

288

NETL: Carbon Storage - Geologic Storage  

NLE Websites -- All DOE Office Websites (Extended Search)

Geologic Storage Geologic Storage Carbon Storage Geologic Storage Focus Area Geologiccarbon dioxide (CO2) storage involves the injection of supercritical CO2 into deep geologic formations (injection zones) overlain by competent sealing formations and geologic traps that will prevent the CO2 from escaping. Current research and field studies are focused on developing better understanding 11 major types of geologic storage reservoir classes, each having their own unique opportunities and challenges. Understanding these different storage classes provides insight into how the systems influence fluids flow within these systems today, and how CO2 in geologic storage would be anticipated to flow in the future. The different storage formation classes include: deltaic, coal/shale, fluvial, alluvial, strandplain, turbidite, eolian, lacustrine, clastic shelf, carbonate shallow shelf, and reef. Basaltic interflow zones are also being considered as potential reservoirs. These storage reservoirs contain fluids that may include natural gas, oil, or saline water; any of which may impact CO2 storage differently. The following summarizes the potential for storage and the challenges related to CO2 storage capability for fluids that may be present in more conventional clastic and carbonate reservoirs (saline water, and oil and gas), as well as unconventional reservoirs (unmineable coal seams, organic-rich shales, and basalts):

289

NOTICE OF AVAILABILITY - INTERIM RECORD OF DECISION FOR THE F-AREA TANK FARM, WASTE TANKS 17 AND 20  

NLE Websites -- All DOE Office Websites (Extended Search)

5 5 April 30, 2013 NOTICE OF AVAILABILITY - INTERIM RECORD OF DECISION FOR THE F-AREA TANK FARM, WASTE TANKS 17 AND 20 The Interim Record of Decision (IROD) Remedial Alternative Selection for the F-Area Tank Farm (FTF), Waste Tanks 17 and 20, is being issued by the U.S. Department of Energy (DOE), the lead agency for the Savannah River Site (SRS), with concur- rence by the U.S. Environmental Protection Agency - Region 4 (EPA), and South Carolina Department of Health and Environ- mental Control (SCDHEC). The IROD was completed to facilitate the terms of the Federal Facility Agreement (FFA) for SRS governing the investigation and cleanup of waste units. The FFA integrates the requirements of Resource Conservation and Re- covery Act and the Comprehensive Environmental Response, Compensation, and Liability Act.

290

NETL: Carbon Storage FAQs  

NLE Websites -- All DOE Office Websites (Extended Search)

Where is CO2 storage happening today? Where is CO2 storage happening today? Sleipner Project (Norway) Sleipner Project (Norway) Carbon dioxide (CO2) storage is currently happening across the United States and around the world. Large, commercial-scale projects, like the Sleipner CO2 Storage Site in Norway, the Weyburn-Midale CO2 Project in Canada, and the In Salah project in Algeria, have been injecting CO2 for many years. Each of these projects stores more than 1 million tons of CO2 per year. Large-scale efforts are currently underway in Africa, China, Australia, and Europe, too. These commercial-scale projects are demonstrating that large volumes of CO2 can be safely and permanently stored. Additionally, a multitude of pilot efforts are underway in different parts of the world to determine suitable locations and technologies for future

291

Compressed Air Energy Storage Act (Kansas)  

Energy.gov (U.S. Department of Energy (DOE))

This act lays out regulations for the local authorities related to site selection, design, operation and monitoring for underground storage of compressed air.

292

Distributed Generation with Heat Recovery and Storage  

E-Print Network (OSTI)

selection of on-site power generation with combined heat andTotal Electricity Generation Figure 13. Small MercantileWeekday Total Electricity Generation (No Storage Adoption

Siddiqui, Afzal S.; Marnay, Chris; Firestone, Ryan M.; Zhou, Nan

2008-01-01T23:59:59.000Z

293

Nuclear materials management storage study  

SciTech Connect

The Office of Weapons and Materials Planning (DP-27) requested the Planning Support Group (PSG) at the Savannah River Site to help coordinate a Departmental complex-wide nuclear materials storage study. This study will support the development of management strategies and plans until Defense Programs` Complex 21 is operational by DOE organizations that have direct interest/concerns about or responsibilities for nuclear material storage. They include the Materials Planning Division (DP-273) of DP-27, the Office of the Deputy Assistant Secretary for Facilities (DP-60), the Office of Weapons Complex Reconfiguration (DP-40), and other program areas, including Environmental Restoration and Waste Management (EM). To facilitate data collection, a questionnaire was developed and issued to nuclear materials custodian sites soliciting information on nuclear materials characteristics, storage plans, issues, etc. Sites were asked to functionally group materials identified in DOE Order 5660.1A (Management of Nuclear Materials) based on common physical and chemical characteristics and common material management strategies and to relate these groupings to Nuclear Materials Management Safeguards and Security (NMMSS) records. A database was constructed using 843 storage records from 70 responding sites. The database and an initial report summarizing storage issues were issued to participating Field Offices and DP-27 for comment. This report presents the background for the Storage Study and an initial, unclassified summary of storage issues and concerns identified by the sites.

Becker, G.W. Jr.

1994-02-01T23:59:59.000Z

294

VIRUS DISEASE OF SOCKEYE SALMON Interim Report  

E-Print Network (OSTI)

pattern turin an epizootic Distribution 01 LnJ I i i-h in ha-. Symptomatology Factors possibly corr Demonstration of causative agent 21 Infectious nature 21 Filterability 21 Effect of storage 21 Effect of heat 23 caused severe losses in 3- to 12-month-old fingerling sock- eye salmon in hatcheries in the State

295

Gas Storage Technology Consortium  

SciTech Connect

Gas storage is a critical element in the natural gas industry. Producers, transmission and distribution companies, marketers, and end users all benefit directly from the load balancing function of storage. The unbundling process has fundamentally changed the way storage is used and valued. As an unbundled service, the value of storage is being recovered at rates that reflect its value. Moreover, the marketplace has differentiated between various types of storage services and has increasingly rewarded flexibility, safety, and reliability. The size of the natural gas market has increased and is projected to continue to increase towards 30 trillion cubic feet (TCF) over the next 10 to 15 years. Much of this increase is projected to come from electric generation, particularly peaking units. Gas storage, particularly the flexible services that are most suited to electric loads, is crucial in meeting the needs of these new markets. To address the gas storage needs of the natural gas industry, an industry-driven consortium was created - the Gas Storage Technology Consortium (GSTC). The objective of the GSTC is to provide a means to accomplish industry-driven research and development designed to enhance the operational flexibility and deliverability of the nation's gas storage system, and provide a cost-effective, safe, and reliable supply of natural gas to meet domestic demand. This report addresses the activities for the quarterly period of January1, 2007 through March 31, 2007. Key activities during this time period included: {lg_bullet} Drafting and distributing the 2007 RFP; {lg_bullet} Identifying and securing a meeting site for the GSTC 2007 Spring Proposal Meeting; {lg_bullet} Scheduling and participating in two (2) project mentoring conference calls; {lg_bullet} Conducting elections for four Executive Council seats; {lg_bullet} Collecting and compiling the 2005 GSTC Final Project Reports; and {lg_bullet} Outreach and communications.

Joel L. Morrison; Sharon L. Elder

2007-03-31T23:59:59.000Z

296

Fuel Pond Sludge - Lessons Learned from Initial De-sludging of Sellafield's Pile Fuel Storage Pond - 12066  

SciTech Connect

The Pile Fuel Storage Pond (PFSP) at Sellafield was built and commissioned between the late 1940's and early 1950's as a storage and cooling facility for irradiated fuel and isotopes from the two Windscale Pile reactors. The pond was linked via submerged water ducts to each reactor, where fuel and isotopes were discharged into skips for transfer along the duct to the pond. In the pond the fuel was cooled then de-canned underwater prior to export for reprocessing. The plant operated successfully until it was taken out of operation in 1962 when the First Magnox Fuel Storage Pond took over fuel storage and de-canning operations on the site. The pond was then used for storage of miscellaneous Intermediate Level Waste (ILW) and fuel from the UK's Nuclear Programme for which no defined disposal route was available. By the mid 1970's the import of waste ceased and the plant, with its inventory, was placed into a passive care and maintenance regime. By the mid 1990s, driven by the age of the facility and concern over the potential challenge to dispose of the various wastes and fuels being stored, the plant operator initiated a programme of work to remediate the facility. This programme is split into a number of key phases targeted at sustained reduction in the hazard associated with the pond, these include: - Pond Preparation: Before any remediation work could start the condition of the pond had to be transformed from a passive store to a plant capable of complex retrieval operations. This work included plant and equipment upgrades, removal of redundant structures and the provision of a effluent treatment plant for removing particulate and dissolved activity from the pond water. - Canned Fuel Retrieval: Removal of canned fuel, including oxide and carbide fuels, is the highest priority within the programme. Handling and export equipment required to remove the canned fuel from the pond has been provided and treatment routes developed utilising existing site facilities to allow the fuel to be reprocessed or conditioned for long term storage. - Sludge Retrieval: In excess of 300 m{sup 3} of sludge has accumulated in the pond over many years and is made up of debris arising from fuel and metallic corrosion, wind blown debris and bio-organic materials. The Sludge Retrieval Project has provided the equipment necessary to retrieve the sludge, including skip washer and tipper machines for clearing sludge from the pond skips, equipment for clearing sludge from the pond floor and bays, along with an 'in pond' corral for interim storage of retrieved sludge. Two further projects are providing new plant processing routes, which will initially store and eventually passivate the sludge. - Metal Fuel Retrieval: Metal Fuel from early Windscale Pile operations and various other sources is stored within the pond; the fuel varies considerably in both form and condition. A retrieval project is planned which will provide fuel handling, conditioning, sentencing and export equipment required to remove the metal fuel from the pond for export to on site facilities for interim storage and disposal. - Solid Waste Retrieval: A final retrieval project will provide methods for handling, retrieval, packaging and export of the remaining solid Intermediate Level Waste within the pond. This includes residual metal fuel pieces, fuel cladding (Magnox, aluminium and zircaloy), isotope cartridges, reactor furniture, and miscellaneous activated and contaminated items. Each of the waste streams requires conditioning to allow it to be and disposed of via one of the site treatment plants. - Pond Dewatering and Dismantling: Delivery of the above projects will allow operations to progressively remove the radiological inventory, thereby reducing the hazard/risk posed by the plant. This will then allow subsequent dewatering of the pond and dismantling of the structure. (authors)

Carlisle, Derek; Adamson, Kate [Sellafield Ltd, Sellafield, Cumbria (United Kingdom)

2012-07-01T23:59:59.000Z

297

NEXT GENERATION MELTER OPTIONEERING STUDY - INTERIM REPORT  

SciTech Connect

The next generation melter (NOM) development program includes a down selection process to aid in determining the recommended vitrification technology to implement into the WTP at the first melter change-out which is scheduled for 2025. This optioneering study presents a structured value engineering process to establish and assess evaluation criteria that will be incorporated into the down selection process. This process establishes an evaluation framework that will be used progressively throughout the NGM program, and as such this interim report will be updated on a regular basis. The workshop objectives were achieved. In particular: (1) Consensus was reached with stakeholders and technology providers represented at the workshop regarding the need for a decision making process and the application of the D{sub 2}0 process to NGM option evaluation. (2) A framework was established for applying the decision making process to technology development and evaluation between 2010 and 2013. (3) The criteria for the initial evaluation in 2011 were refined and agreed with stakeholders and technology providers. (4) The technology providers have the guidance required to produce data/information to support the next phase of the evaluation process. In some cases it may be necessary to reflect the data/information requirements and overall approach to the evaluation of technology options against specific criteria within updated Statements of Work for 2010-2011. Access to the WTP engineering data has been identified as being very important for option development and evaluation due to the interface issues for the NGM and surrounding plant. WRPS efforts are ongoing to establish precisely data that is required and how to resolve this Issue. It is intended to apply a similarly structured decision making process to the development and evaluation of LAW NGM options.

GRAY MF; CALMUS RB; RAMSEY G; LOMAX J; ALLEN H

2010-10-19T23:59:59.000Z

298

Radioactive waste storage issues  

SciTech Connect

In the United States we generate greater than 500 million tons of toxic waste per year which pose a threat to human health and the environment. Some of the most toxic of these wastes are those that are radioactively contaminated. This thesis explores the need for permanent disposal facilities to isolate radioactive waste materials that are being stored temporarily, and therefore potentially unsafely, at generating facilities. Because of current controversies involving the interstate transfer of toxic waste, more states are restricting the flow of wastes into - their borders with the resultant outcome of requiring the management (storage and disposal) of wastes generated solely within a state`s boundary to remain there. The purpose of this project is to study nuclear waste storage issues and public perceptions of this important matter. Temporary storage at generating facilities is a cause for safety concerns and underscores, the need for the opening of permanent disposal sites. Political controversies and public concern are forcing states to look within their own borders to find solutions to this difficult problem. Permanent disposal or retrievable storage for radioactive waste may become a necessity in the near future in Colorado. Suitable areas that could support - a nuclear storage/disposal site need to be explored to make certain the health, safety and environment of our citizens now, and that of future generations, will be protected.

Kunz, D.E.

1994-08-15T23:59:59.000Z

299

Energy Storage  

SciTech Connect

ORNL Distinguished Scientist Parans Paranthaman is discovering new materials with potential for greatly increasing batteries' energy storage capacity and bring manufacturing back to the US.

Paranthaman, Parans

2014-06-03T23:59:59.000Z

300

Energy Storage  

ScienceCinema (OSTI)

ORNL Distinguished Scientist Parans Paranthaman is discovering new materials with potential for greatly increasing batteries' energy storage capacity and bring manufacturing back to the US.

Paranthaman, Parans

2014-06-23T23:59:59.000Z

Note: This page contains sample records for the topic "interim storage site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

EIS-0283-S2: Interim Action Determination  

Energy.gov (U.S. Department of Energy (DOE))

Surplus Plutonium Disposition Supplemental Environmental Impact Statement (Use of H-Canyon/HB-Line to Prepare Feed for the Mixed Oxide Fuel Fabrication at the Savannah River Site)

302

Electrochemistry: Metal-free energy storage  

Science Journals Connector (OSTI)

... % of total energy capacity will require electric-energy storage systems to be deployed. For grid-scale applications and remote generation sites, cheap and flexible storage systems are needed, but ... level as a source of potential energy) or expensive (for example, conventional batteries, flywheels and superconductive electromagnetic storage). On page 195 of this issue, Huskinson et al. ...

Grigorii L. Soloveichik

2014-01-08T23:59:59.000Z

303

T Tank Farm Interim Surface Barrier Demonstration - Vadose Zone Monitoring FY08 Report  

SciTech Connect

DOEs Office of River Protection constructed a temporary surface barrier over a portion of the T Tank Farm as part of the T Farm Interim Surface Barrier Demonstration Project. The surface barrier is designed to minimize the infiltration of precipitation into the contaminated soil zone created by the Tank T-106 leak and minimize movement of the contamination. As part of the demonstration effort, vadose zone moisture is being monitored to assess the effectiveness of the barrier at reducing soil moisture. A solar-powered system was installed to continuously monitor soil water conditions at four locations (i.e., instrument Nests A, B, C, and D) beneath the barrier and outside the barrier footprint as well as site meteorological conditions. Nest A is placed in the area outside the barrier footprint and serves as a control, providing subsurface conditions outside the influence of the surface barrier. Nest B provides subsurface measurements to assess surface-barrier edge effects. Nests C and D are used to assess changes in soil-moisture conditions beneath the interim surface barrier.

Zhang, Z. F.; Strickland, Christopher E.; Field, Jim G.; Parker, Danny L.

2009-02-01T23:59:59.000Z

304

NETL: Carbon Storage - NETL Carbon Capture and Storage Database  

NLE Websites -- All DOE Office Websites (Extended Search)

CCS Database CCS Database Carbon Storage NETL's Carbon Capture, Utilization, and Storage Database - Version 4 Welcome to NETL's Carbon Capture, Utilization, and Storage (CCUS) Database. The database includes active, proposed, canceled, and terminated CCUS projects worldwide. Information in the database regarding technologies being developed for capture, evaluation of sites for carbon dioxide (CO2) storage, estimation of project costs, and anticipated dates of completion is sourced from publically available information. The CCUS Database provides the public with information regarding efforts by various industries, public groups, and governments towards development and eventual deployment of CCUS technology. As of November 2012, the database contained 268 CCUS projects worldwide. The 268 projects include 68 capture, 61 storage, and 139 for capture and storage in more than 30 countries across 6 continents. While most of the projects are still in the planning and development stage, or have recently been proposed, 37 are actively capturing and injecting CO2

305

Fail-safe storage rack for irradiated fuel rod assemblies  

DOE Patents (OSTI)

A fail-safe storage rack is provided for interim storage of spent but radioactive nuclear fuel rod assemblies. The rack consists of a checkerboard array of substantially square, elongate receiving tubes fully enclosed by a double walled container, the outer wall of which is imperforate for liquid containment and the inner wall of which is provided with perforations for admitting moderator liquid flow to the elongate receiving tubes, the liquid serving to take up waste heat from the stored nuclear assemblies and dissipate same to the ambient liquid reservoir. A perforated cover sealing the rack facilitates cooling liquid entry and dissipation.

Lewis, D.R.

1993-03-23T23:59:59.000Z

306

Fail-safe storage rack for irradiated fuel rod assemblies  

DOE Patents (OSTI)

A fail-safe storage rack is provided for interim storage of spent but radioactive nuclear fuel rod assemblies. The rack consists of a checkerboard array of substantially square, elongate receiving tubes fully enclosed by a double walled container, the outer wall of which is imperforate for liquid containment and the inner wall of which is provided with perforations for admitting moderator liquid flow to the elongate receiving tubes, the liquid serving to take up waste heat from the stored nuclear assemblies and dissipate same to the ambient liquid reservoir. A perforated cover sealing the rack facilitates cooling liquid entry and dissipation.

Lewis, Donald R. (Pocatello, ID)

1993-01-01T23:59:59.000Z

307

Amended Record of Decision: Storage of Surplus Plutonium Materials at the Savannah River Site (DOE/EIS-0229)(09/11/07)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

07 Federal Register 07 Federal Register / Vol. 72, No. 175 / Tuesday, September 11, 2007 / Notices 1 A container that complies with DOE-STD-3013, Stabilization, Packaging, and Storage of Plutonium- Bearing Materials. 2 The use of FFTF and the unirradiated fuel currently at Hanford is being considered in conjunction with the evaluation of reasonable alternatives in the Global Nuclear Energy Partnership (GNEP) Programmatic EIS. The planned shipment of the FFTF unirradiated fuel to SRS is scheduled for the second half of Fiscal Year 2009. If FFTF is still being considered as part of GNEP following completion of the PEIS (expected in 2008), DOE may choose not to ship the unirradiated FFTF fuel to SRS. 3 Based on DOE's current surplus plutonium disposition plans, DOE expects to disposition the

308

How to effectively recover free product at leaking underground storage tank sites. A guide for state regulators. Final report, January-October 1995  

SciTech Connect

The objective of the report is to provide guidance that will help state and local regulators to review free product recovery plans or that portion of a Corrective Action Plan (CAP) that proposes free product recovery technologies. The report focuses on appropriate technology use, taking into consideration site-specific conditions. It addresses the following three basic questions when reviewing a free product recovery plan: (1) is free product recovery necessary; (2) has an appropriate method been proposed for free product recovery; and (3) does the free product recovery plan provide a technically sound approach to remediating the site. The text focuses on scientific and engineering-related considerations for evaluating alternative technologies for the recovery of free product.

Faust, C.R.; Montroy, M.P.

1996-09-01T23:59:59.000Z

309

Assessment of technologies for hazardous waste site remediation: Non-treatment technologies and pilot scale facility implementation -- excavation -- storage technology -- safety analysis and review statement. Final report  

SciTech Connect

The purpose of this study is to assess the state-of-the-art of excavation technology as related to environmental remediation applications. A further purpose is to determine which of the excavation technologies reviewed could be used by the US Corp of Engineers in remediating contaminated soil to be excavated in the near future for construction of a new Lock and Dam at Winfield, WV. The study is designed to identify excavation methodologies and equipment which can be used at any environmental remediation site but more specifically at the Winfield site on the Kanawha River in Putnam County, West Virginia. A technical approach was determined whereby a functional analysis was prepared to determine the functions to be conducted during the excavation phase of the remediation operations. A number of excavation technologies were identified from the literature. A set of screening criteria was developed that would examine the utility and ranking of the technologies with respect to the operations that needed to be conducted at the Winfield site. These criteria were performance, reliability, implementability, environmental safety, public health, and legal and regulatory compliance. The Loose Bulk excavation technology was ranked as the best technology applicable to the Winfield site. The literature was also examined to determine the success of various methods of controlling fugitive dust. Depending upon any changes in the results of chemical analyses, or prior remediation of the VOCs from the vadose zone, consideration should be given to testing a new ``Pneumatic Excavator`` which removes the VOCs liberated during the excavation process as they outgas from the soil. This equipment however would not be needed on locations with low levels of VOC emissions.

Johnson, H.R.; Overbey, W.K. Jr.; Koperna, G.J. Jr.

1994-02-01T23:59:59.000Z

310

Determination of risk-based, site-specific cleanup levels for an industrial site in Seattle, Washington  

SciTech Connect

Risk-based, site-specific cleanup criteria were developed for an active industrial site where shallow soil was contaminated with bunker fuel. This approach resulted in defensible cleanup levels that eliminated the need for complicated and disruptive remedial measures and is expediting site closure under Washington State Department of Ecology`s (Ecology) Independent Remedial Action Program. Initially, in anticipation of the sale of the property, a site investigation was conducted to provide information on the extent of contamination resulting from a leaking underground storage tank. Results of the investigation indicated that at least 3,600 cubic yards of soil contained bunker fuel at concentrations exceeding Ecology`s Model Toxics Control Act (MTCA) default Method A cleanup value for heavy oil of 200 milligrams per kilogram. The contamination extended under two of the site structures. Following Ecology`s new interim policy for cleanup of total petroleum hydrocarbons under MTCA, a risk-based cleanup criterion was calculated using an approach in which aliphatic and aromatic fractions of weathered bunker fuel were represented by surrogates of known toxicity. The cleanup criterion yielded by the quantitative evaluation was more than an order of magnitude higher than the default MTCA Method A value for heavy oil. Cleanup criteria for carcinogenic polynuclear aromatic hydrocarbons (cPAHs) were also derived. Use of these risk-based cleanup levels eliminated the need for remedial measures outside of the immediate vicinity of the former tank location, reducing the volume of soil that required remediation from 3,600 cubic yards to 70 cubic yards.

Birkner, P.D.; Gaulke, S.W.; Tirao, A.C.; Veilleux, A.L. [Shannon & Wilson, Inc., Seattle, WA (United States)

1997-12-31T23:59:59.000Z

311

Site Index - Hanford Site  

NLE Websites -- All DOE Office Websites (Extended Search)

Site Index Site Index Calendar Hanford Blog Archive Search Site Feeds Site Index Weather What's New Site Index Email Email Page | Print Print Page |Text Increase Font Size Decrease...

312

Rockwell International Hot Laboratory decontamination and dismantlement interim progress report 1987-1996  

SciTech Connect

OAK A271 Rockwell International Hot Laboratory decontamination and dismantlement interim progress report 1987-1996. The Rockwell International Hot Laboratory (RIHL) is one of a number of former nuclear facilities undergoing decontamination and decommissioning (D&D) at the Santa Susana Field Laboratory (SSFL). The RIHL facility is in the later stages of dismantlement, with the final objective of returning the site location to its original natural state. This report documents the decontamination and dismantlement activities performed at the facility over the time period 1988 through 1996. At this time, the support buildings, all equipment associated with the facility, and the entire above-ground structure of the primary facility building (Building 020) have been removed. The basement portion of this building and the outside yard areas (primarily asphalt and soil) are scheduled for D&D activities beginning in 1997.

None

1997-05-06T23:59:59.000Z

313

40 CFR 265 interim-status ground-water monitoring plan for the 2101-M pond  

SciTech Connect

This report outlines a ground-water monitoring plan for the 2101-M pond, located in the southwestern part of the 200-East Area on the Hanford Site in south-central Washington State. It has been determined that hazardous materials may have been discharged to the pond. Installation of an interim-status ground-water monitoring system is required under the Resource Conservation and Recovery Act to determine if hazardous chemicals are moving out of the pond. This plan describes the location of new wells for the monitoring system, how the wells are to be completed, the data to be collected, and how those data can be used to determine the source and extent of any ground-water contamination from the 2101-M pond. Four new wells are planned, one upgradient and three downgradient. 35 refs., 12 figs., 9 tabs.

Chamness, M.A.; Luttrell, S.P.; Dudziak, S.

1989-03-01T23:59:59.000Z

314

Progress Report, December 2010: Improved Site Characterization And Storage Prediction Through Stochastic Inversion Of Time-Lapse Geophysical And Geochemical Data  

SciTech Connect

Over the last project six months, our project activities have concentrated on three areas: (1) performing a stochastic inversion of pattern 16 seismic data to deduce reservoir permeability, (2) development of the geochemical inversion strategy and implementation of associated software, and (3) completing the software implementation of TProGS and the geostatistical analysis that provides the information needed when using the software to produce realizations of the Midale reservoir. The report partially the following deliverables: D2: Model development: MCMC tool (synthetic fluid chemistry data); deliverable completed. D4: Model development/verification: MCMC tool (TProGS, field seismic/chemistry data) work product; deliverable requirements partially fulfilled. D5: Field-based single-pattern simulations work product; deliverable requirements partially fulfilled. When completed, our completed stochastic inversion tool will explicitly integrate reactive transport modeling, facies-based geostatistical methods, and a novel stochastic inversion technique to optimize agreement between observed and predicted storage performance. Such optimization will be accomplished through stepwise refinement of: (1) the reservoir model - principally its permeability magnitude and heterogeneity - and (2) geochemical parameters - primarily key mineral volume fractions and kinetic data. We anticipate that these refinements will facilitate significantly improved history matching and forward modeling of CO{sub 2} storage. Our tool uses the Markov Chain Monte Carlo (MCMC) methodology. Deliverable D1, previously submitted as a report titled ''Development of a Stochastic Inversion Tool To Optimize Agreement Between The Observed And Predicted Seismic Response To CO{sub 2} Injection/Migration in the Weyburn-Midale Project'' (Ramirez et al., 2009), described the stochastic inversion approach that will identify reservoir models that optimize agreement between the observed and predicted seismic response. The software that implements this approach has been completed, tested, and used to process seismic data from pattern 16. A previously submitted report titled ''Model verification: synthetic single pattern simulations using seismic reflection data'', Ramirez et al. 2010, partially fulfilled deliverable D3 by summarizing verification activities that evaluate the performance of the seismic software and its ability to recover reservoir model permeabilities using synthetic seismic reflection data. A future progress report will similarly describe summarizing verification activities of the geochemical inversion software, thereby completing deliverable D3. This document includes a chapter that shows and discusses permeability models produced by seismic inversion that used seismic data from pattern 16 in Phase 1A. It partially fulfills deliverable D5: Field-based single-pattern simulations work product. The D5 work product is supposed to summarize the results of applying NUFT/MCMC to refine the reservoir model and geochemical parameters by optimizing observation/prediction agreement for the seismic/geochemical response to CO{sub 2} injection/migration within a single pattern of Phase 1A/1B. A future progress report will show inversion results for the same pattern using geochemical data, thereby completing deliverable D5. This document also contains a chapter that fulfills deliverable D2: Model development: MCMC tool (synthetic fluid chemistry data). The chapter will summarize model development activities required to facilitate application of NUFT/MCMC to optimize agreement between the observed and predicted geochemical response to CO{sub 2} injection/migration. Lastly, this document also contains a chapter that partially fulfills deliverable D4: Model development/verification: MCMC tool (TProGS, field seismic/chemistry data) work product. This work product is supposed to summarize model development activities required for (1) application of TProGS to Weyburn, (2) use of TProGS within the MCMC tool, and (3) application of the MCMC tool to address field seismic and g

Ramirez, A; Mcnab, W; Carle, S; Hao, Y; White, D; Johnson, J

2010-12-17T23:59:59.000Z

315

cryogenic storage  

Science Journals Connector (OSTI)

Storage in which (a) the superconductive property of materials is used to store data and (b) use is made of the phenomenon that superconductivity is destroyed in the presence of a magnetic field, thus enabling...

2001-01-01T23:59:59.000Z

316

Hydrogen Storage  

Energy.gov (U.S. Department of Energy (DOE))

On-board hydrogen storage for transportation applications continues to be one of the most technically challenging barriers to the widespread commercialization of hydrogen-fueled vehicles. The EERE...

317

1 Direct Cost Finding Interim Compliance Testing  

E-Print Network (OSTI)

of Sponsor Review Desk Review Site Visit Audit Agreed Upon Procedures Review #12;Audit Process Flow Planning & Definition Fieldwork & Testing Results & Reporting Closeout & Corrective Action Plan 5 REQUEST #12;Common · Preparation is key!! · Be cooperative · Documentation Standard Vary ­ Keep best documentation you can #12

318

Microsoft Word - EM-TWS Interim Report 02-21-11 final  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

INTERIM REPORT TO THE ENVIRONMENTAL MANAGEMENT ADVISORY BOARD INTERIM REPORT TO THE ENVIRONMENTAL MANAGEMENT ADVISORY BOARD Environmental Management Tank Waste Subcommittee (EM-TWS) FY 2011 Work Plan Status Modeling for Life Cycle Cost Analysis (Interim Report) February 24, 2011 Hanford Tank Farms and WTP SRS Tank Farms Presented by the EM Tank Waste Subcommittee Las Vegas, Nevada EM-TWS Interim Report, February 2011 1 Business Sensitive INTERIM REPORT TO THE ENVIRONMENTAL MANAGEMENT ADVISORY BOARD Environmental Management Tank Waste Subcommittee (EM-TWS) Fiscal Year (FY) 2011 Work Plan Status Modeling for Life Cycle Cost (LCC) Analysis (Interim Report) February 24, 2011 1. Introduction 1.1 DOE EM response to FY 2010 EM-TWS Phase 1 Report and Recommendations (Attachment 1) The DOE Office of Environmental Management has adopted most of the

319

RTD Biodiesel (B20) Transit Bus Evaluation: Interim Review Summary  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

RTD Biodiesel (B20) Transit RTD Biodiesel (B20) Transit Bus Evaluation: Interim Review Summary K. Proc, R. Barnitt, and R.L. McCormick Technical Report NREL/TP-540-38364 August 2005 RTD Biodiesel (B20) Transit Bus Evaluation: Interim Review Summary K. Proc, R. Barnitt, and R.L. McCormick Prepared under Task No. FC05.9400 Technical Report NREL/TP-540-38364 August 2005 National Renewable Energy Laboratory 1617 Cole Boulevard, Golden, Colorado 80401-3393 303-275-3000 * www.nrel.gov Operated for the U.S. Department of Energy Office of Energy Efficiency and Renewable Energy by Midwest Research Institute * Battelle Contract No. DE-AC36-99-GO10337 NOTICE This report was prepared as an account of work sponsored by an agency of the United States government. Neither the United States government nor any agency thereof, nor any of their employees, makes any

320

King County Metro Transit Hybrid Articulated Buses: Interim Evaluation Results  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

King County Metro Transit King County Metro Transit Hybrid Articulated Buses: Interim Evaluation Results K. Chandler Battelle K. Walkowicz National Renewable Energy Laboratory Technical Report NREL/TP-540-39742 April 2006 King County Metro Transit Hybrid Articulated Buses: Interim Evaluation Results K. Chandler Battelle K. Walkowicz National Renewable Energy Laboratory Prepared under Task No. FC06.3000 Technical Report NREL/TP-540-39742 April 2006 National Renewable Energy Laboratory 1617 Cole Boulevard, Golden, Colorado 80401-3393 303-275-3000 * www.nrel.gov Operated for the U.S. Department of Energy Office of Energy Efficiency and Renewable Energy by Midwest Research Institute * Battelle Contract No. DE-AC36-99-GO10337 NOTICE This report was prepared as an account of work sponsored by an agency of the United States government.

Note: This page contains sample records for the topic "interim storage site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

,,"PARS II Interim Migration Template"  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

" " ,,"PARS II Interim Migration Template" ,,"Fields","Data" ,,"DOE Project ID:","DOE Project # and Project Name" ,,"Year:","Please select a Year" ,,"Month:","Please select a Month" ,,"Fields","Data (Entered in $K) [Data Entry field]" ,,"BCWS ($K):",0 ,,"BCWP ($K):",0 ,,"ACWP ($K):",0 ,,"Management Reserves Remaining ($K):",0 ,,"Percent Complete (%):",0 ,,"Instructions" ,,"1. Log into PARS II" ,,"2. Select the appropriate Project" ,,"3. While still on the Projects screen, click on ""Attachments""" ,,"4. Click on ""Add"""

322

DECOMMISSIONING OF THE NUCLEAR FACILITIES OF VKTA AT THE ROSSENDORF RESEARCH SITE  

SciTech Connect

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.

U. Helwig, W. Boessert

2003-02-27T23:59:59.000Z

323

1997 Hanford site report on land disposal restrictions for mixed waste  

SciTech Connect

The baseline land disposal restrictions (LDR) plan was prepared in 1990 in accordance with the Hanford Federal Facility Agreement and Consent Order (commonly referred to as the Tn-Party Agreement) Milestone M-26-00 (Ecology et al, 1989). The text of this milestone is below. ''LDR requirements include limitations on storage of specified hazardous wastes (including mixed wastes). In accordance with approved plans and schedules, the U.S. Department of Energy (DOE) shall develop and implement technologies necessary to achieve full compliance with LDR requirements for mixed wastes at the Hanford Site. LDR plans and schedules shall be developed with consideration of other action plan milestones and will not become effective until approved by the U.S. Environmental Protection Agency (EPA) (or Washington State Department of Ecology [Ecology]) upon authorization to administer LDRs pursuant to Section 3006 of the Resource Conservation and Recovery Act of 1976 (RCRA). Disposal of LDR wastes at any time is prohibited except in accordance with applicable LDR requirements for nonradioactive wastes at all times. The plan will include, but not be limited to, the following: Waste characterization plan; Storage report; Treatment report; Treatment plan; Waste minimization plan; A schedule depicting the events necessary to achieve full compliance with LDR requirements; and A process for establishing interim milestones.

Black, D.G.

1997-04-07T23:59:59.000Z

324

Interim Report of the Commission to Review the Effectiveness of the National Energy Laboratories  

Energy.gov (U.S. Department of Energy (DOE))

SUMMARY: This notice announces an opportunity to comment on the proposed Interim Report of the Commission to Review the Effectiveness of the National Energy Laboratories (Commission).

325

Data Report on Corrosion Testing of Stainless Steel SNF Storage Canisters |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Data Report on Corrosion Testing of Stainless Steel SNF Storage Data Report on Corrosion Testing of Stainless Steel SNF Storage Canisters Data Report on Corrosion Testing of Stainless Steel SNF Storage Canisters The report assesses the localized corrosion performance of container/cask materials used in the interim storage of used nuclear fuel. A detailed evaluation of the storage system environment, including uncertainties in temperature, humidity, and sea and continental salt occurrence is provided, and the potential impacts on corrosion are discussed. Initial results from a sampling program of in situ dust deposits on in-service storage canisters are provided. The results of dust deliquescence testing, to evaluate potential stifling of corrosion due the limited mass of the deposited salts, are presented. CorrosionTestStainlessSteelSNFStorContainer.pdf

326

Remaining Sites Verification Package for the 100-D-2 Lead Sheeting Waste Site, Waste Site Reclassification Form 2007-030  

SciTech Connect

The 100-D-2 Lead Sheeting waste site was located approximately 50 m southwest of the 185-D Building and approximately 16 m north of the east/west oriented road. The site consisted of a lead sheet covering a concrete pad. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

L. M. Dittmer

2008-03-19T23:59:59.000Z

327

EIS-0244: Plutonium Finishing Plant Stabilization, Hanford Site, Richland, WA  

Energy.gov (U.S. Department of Energy (DOE))

This EIS evaluates the impacts on the human environment of: Stabilization of residual, plutonium-bearing materials at the PFP Facility to a form suitable for interim storage at the PFP Facility. Immobilization of residual plutonium-bearing materials at the PFP Facility. Removal of readily retrievable, plutonium-bearing materials left behind in process equipment, process areas, and air and liquid waste management systems as a result of historic uses.

328

AQUIFER THERMAL ENERGY STORAGE  

E-Print Network (OSTI)

using aquifers for thermal energy storage. Problems outlinedmatical Modeling of Thermal Energy Storage in Aquifers,"ings of Aquifer Thermal Energy Storage Workshop, Lawrence

Tsang, C.-F.

2011-01-01T23:59:59.000Z

329

Monticello Mill site Federal Facility Agreement, December 22, 1988 Summary  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Monticello Monticello Agreement Name Monticello (Utah) Site: Monticello Vicinity Properties NPL Site and Monticello Millsite Federal Facility Agreement Pursuant to CERCLA Section 120, December 22, 1988 State Utah Agreement Type Federal Facility Agreement Legal Driver(s) CERCLA Scope Summary Establish a procedural framework and schedule for developing, implementing, and monitoring appropriate response actions at the Site Parties DOE; US EPA; State of Utah Department of Environmental Health Date 12/22/1988 SCOPE * Identify Interim Remedial Action (IRA) alternatives, if any, which are appropriate at the Site prior to the implementation of final remedial actions for the Site. * Evaluate all past investigative and response actions taken at the Site and documented

330

River Protection Project (RPP) Immobilized High Level Waste (HLW) Interim Storage Plan  

SciTech Connect

This document replaces HNF-1751, Revision 1. It incorporates updates to reflect changes in programmatic direction associated with the vitrification plant contract and associated DOE-ORP guidance. In addition it includes planning associated with failed/used melter and sample handling and disposition work scope. The document also includes format modifications and section numbering update consistent with CH2M HILL Hanford Group, Inc. procedures.

BRIGGS, M.G.

2000-09-22T23:59:59.000Z

331

Plutonium uranium extraction (PUREX) end state basis for interim operation (BIO) for surveillance and maintenance  

SciTech Connect

This Basis for Interim Operation (BIO) was developed for the PUREX end state condition following completion of the deactivation project. The deactivation project has removed or stabilized the hazardous materials within the facility structure and equipment to reduce the hazards posed by the facility during the surveillance and maintenance (S and M) period, and to reduce the costs associated with the S and M. This document serves as the authorization basis for the PUREX facility, excluding the storage tunnels, railroad cut, and associated tracks, for the deactivated end state condition during the S and M period. The storage tunnels, and associated systems and areas, are addressed in WHC-SD-HS-SAR-001, Rev. 1, PUREX Final Safety Analysis Report. During S and M, the mission of the facility is to maintain the conditions and equipment in a manner that ensures the safety of the workers, environment, and the public. The S and M phase will continue until the final decontamination and decommissioning (D and D) project and activities are begun. Based on the methodology of DOE-STD-1027-92, Hazards Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports, the final facility hazards category is identified as hazards category This considers the remaining material inventories, form and distribution of the material, and the energies present to initiate events of concern. Given the current facility configuration, conditions, and authorized S and M activities, there are no operational events identified resulting in significant hazard to any of the target receptor groups (e.g., workers, public, environment). The only accident scenarios identified with consequences to the onsite co-located workers were based on external natural phenomena, specifically an earthquake. The dose consequences of these events are within the current risk evaluation guidelines and are consistent with the expectations for a hazards category 2 facility.

DODD, E.N.

1999-05-12T23:59:59.000Z

332

Energy Storage  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Daniel R. Borneo, PE Daniel R. Borneo, PE Sandia National Laboratories September 27, 2007 San Francisco, CA PEER REVIEW 2007 DOE(SNL)/CEC Energy Storage Program FYO7 Projects Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy under contract DE-AC04-94AL85000. 2 Presentation Outline * DOE(SNL)/CEC Collaboration - Background of DOE(SNL)/CEC Collaboration - FY07 Project Review * Zinc Bromine Battery (ZBB) Demonstration * Palmdale Super capacitor Demonstration * Sacramento Municipal Utility District (SMUD) Regional Transit (RT) Super capacitor demonstration * Beacon Flywheel Energy Storage System (FESS) 3 Background of DOE(SNL)/CEC Collaboration * Memorandum of Understanding Between CEC and DOE (SNL). - In Place since 2004

333

Energy Storage  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Development Concept Development Concept Nitrogen-Air Battery F.M. Delnick, D. Ingersoll, K.Waldrip Sandia National Laboratories Albuquerque, NM presented to U.S. DOE Energy Storage Systems Research Program Washington, DC November 2-4, 2010 Sandia National Laboratories is a multi-program laboratory operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin company, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. Funded by the Energy Storage Systems Program of the U.S. Department Of Energy through Sandia National Laboratories Full Air Breathing Battery Concept * Concept is to use O 2 and N 2 as the electrodes in a battery * Novel because N 2 is considered inert * Our group routinely reacts N 2 electrochemically

334

Storage Tanks (Arkansas) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Storage Tanks (Arkansas) Storage Tanks (Arkansas) Storage Tanks (Arkansas) < Back Eligibility Commercial Construction Fuel Distributor Industrial Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Program Info State Arkansas Program Type Environmental Regulations Siting and Permitting Provider Department of Environmental Quality The Storage Tanks regulations is a set of rules and permit requirements mandated by the Arkansas Pollution and Ecology Commission in order to protect the public health and the lands and the waters of the State of Arkansas. They are promulgated pursuant to Arkansas Code Annotated 8-7-801 and the Petroleum Storage Trust Fund Act 8-7-901. It covers all storage tanks, above (AST) and underground (UST). Most importantly these regulations establish that all owners and operators of storage tanks must

335

Green River Lake and Dam interim plan benefits ecosystem By John Hickey  

E-Print Network (OSTI)

11 Green River Lake and Dam interim plan benefits ecosystem By John Hickey Hydrologic Engineering that water is released from Green River Dam in Kentucky. In May 2006, the interim plan was approved shown that operation of Green River Dam can be changed in ways that improve ecosystems while continuing

US Army Corps of Engineers

336

PROJECT W-551 INTERIM PRETREATMENT SYSTEM TECHNOLOGY SELECTION SUMMARY DECISION REPORT AND RECOMMENDATION  

SciTech Connect

This report provides the conclusions of the tank farm interim pretreatment technology decision process. It documents the methodology, data, and results of the selection of cross-flow filtration and ion exchange technologies for implementation in project W-551, Interim Pretreatment System. This selection resulted from the evaluation of specific scope criteria using quantitative and qualitative analyses, group workshops, and technical expert personnel.

CONRAD EA

2008-08-12T23:59:59.000Z

337

Li2O Particulate Flow Concept, APPLE APEX Interim Report November, 1999  

E-Print Network (OSTI)

Li2O Particulate Flow Concept, APPLE APEX Interim Report November, 1999 9-1 CHAPTER 9: Li2O PARTICULATE FLOW CONCEPT ­ APPLE DESIGN Contributors Lead Author: Dai Kai Sze Dai Kai Sze, Zhanhe Wang (ANL Particulate Flow Concept, APPLE APEX Interim Report November, 1999 9-2 9. LI2O PARTICULATE FLOW CONCEPT

California at Los Angeles, University of

338

Response to the Wood Commission interim report (Part 2) Cathy Howieson and Sheila Semple, Centre for Educational Sociology, Moray  

E-Print Network (OSTI)

1 Response to the Wood Commission interim report (Part 2) Cathy Howieson and Sheila Semple, Centre, Moray House School of Education's response to the Wood Commission interim report comes in two parts people. The Wood Commission interim report notes the use by young people of online sources of information

Hall, Christopher

339

Systems engineering study: tank 241-C-103 organic skimming,storage, treatment and disposal options  

SciTech Connect

This report evaluates alternatives for pumping, storing, treating and disposing of the separable phase organic layer in Hanford Site Tank 241-C-103. The report provides safety and technology based preferences and recommendations. Two major options and several varations of these options were identified. The major options were: 1) transfer both the organic and pumpable aqueous layers to a double-shell tank as part of interim stabilization using existing salt well pumping equipment or 2) skim the organic to an above ground before interim stabilization of Tank 241-C-103. Other options to remove the organic were considered but rejected following preliminary evaluation.

Klem, M.J.

1996-10-23T23:59:59.000Z

340

Web Site Map  

NLE Websites -- All DOE Office Websites (Extended Search)

Help » Web Site Map Help » Web Site Map Web Site Map The links listed below include all pages on the site except document topic pages. Home Privacy/Security Help Web Site Map Mailing Services Remove me from the List Contact Us About Us News and Events News Archives News/Media FAQs Internet Resources Documents DUF6 EIS Historical Context What is an EIS? Why EIS is Needed Who is Responsible? EIS Process EIS Topics EIS Alternatives EIS Schedule Public Involvement Opportunities Public Comment Form For More Info DUF6 Management and Uses Management Responsibilities DUF6 Storage How DUF6 is Stored Where DUF6 is Stored Cylinder Leakage DUF6 Storage Safety DUF6 PEIS Cylinder Surveillance and Maintenance Conversion Potential DU Uses "Business Case" for R&D on Beneficial Uses of DU Catalysts for Destruction of Air Pollutants

Note: This page contains sample records for the topic "interim storage site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

Microsoft Word - N01221_NE Site IRAP final.doc  

Office of Legacy Management (LM)

Northeast Site Northeast Site August 2008 Office of Legacy Management LMS/PIN/N01221 Work Performed Under DOE Contract No. for the U.S. Department of Energy Office of Legacy Management. DE-AM01-07LM00060 Approved for public release; distribution is unlimited. Office of Legacy Management Office of Legacy Management Office of Legacy Management U.S. Department of Energy This page intentionally left blank LMS/PIN/N01221 Pinellas Environmental Restoration Project Interim Remedial Action Plan for Source Removal at the Northeast Site August 2008 This page intentionally left blank U.S. Department of Energy Interim Remedial Action Plan for Source Removal at the Northeast Site August 2008 Doc. No. N0122100 Page iii Contents Acronyms and Abbreviations .........................................................................................................

342

Storage of Carbon Dioxide in Offshore Sediments  

Science Journals Connector (OSTI)

...year into a sandstone reservoir that lies 1000 m below...formation requires a good reservoir with adequate porosity and permeability and thick, impermeable cap rocks that will prevent the...storage sites require reservoirs with high permeability...

Daniel P. Schrag

2009-09-25T23:59:59.000Z

343

Considered Sites | Department of Energy  

Office of Legacy Management (LM)

Sites » Considered Sites Sites » Considered Sites Considered Sites View Considered Sites View Other Sites DOE maintains the Considered Sites Database to provide information to the public about sites that were formerly used in the nation's nuclear weapons and early atomic energy programs and that had the potential for residual radioactive contamination on site. Formerly Utilized Sites Remedial Action Program The U.S. Atomic Energy Commission (AEC) established the Formerly Utilized Sites Remedial Action Program (FUSRAP) in March 1974 under the authority of the Atomic Energy Act of 1954 to identify, investigate, and take appropriate cleanup action at sites where work was performed in support of the Manhattan Engineer District (MED) and early AEC programs. Site activities included uranium ore storage and processing, uranium metal

344

Comments of NRDC on Department of Energy Interim Final Rule: Energy  

NLE Websites -- All DOE Office Websites (Extended Search)

NRDC on Department of Energy Interim Final Rule: Energy NRDC on Department of Energy Interim Final Rule: Energy Conservation for New Federal Commercial and Multi-Family High-Rise Residential Buildings and New Federal Low-Rise Residential Buildings Comments of NRDC on Department of Energy Interim Final Rule: Energy Conservation for New Federal Commercial and Multi-Family High-Rise Residential Buildings and New Federal Low-Rise Residential Buildings NRDC's comments on Interim Final Rule: Energy Conservation for New Federal Commercial and Multi-Family High-Rise Residential Buildings and New Federal Low-Rise Residential Buildings Comments of NRDC on Department of Energy Interim Final Rule: Energy Conservation for New Federal Commercial and Multi-Family High-Rise Residential Buildings and New Federal Low-Rise Residential Buildings

345

Microsoft Word - Policy_Flash_09_01_Interim_Certification.doc  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

JANUARY 16, 2009 JANUARY 16, 2009 MEMORANDUM FOR ALL PROGRAM ELEMENTS FROM: PMCDP CERTIFICATION REVIEW BOARD SUBJECT: Project Management Career Development Interim Certification The Project Management Career Development Program (PMCDP) Certification Review Board (CRB) established a new process whereby candidates with strong project management experience from outside the Department, hired into project director positions, may be granted an interim PMCDP certification. Interim certification allows the federal employee to act as a certified federal project director. Interim certifications are granted by the sponsoring CRB member, or their designee. If the sponsoring program office is not a voting member of the CRB, the Office of Engineering and Construction Management will act as the grantor of interim certification.

346

Waste Encapsulation and Storage Facility - Hanford Site  

NLE Websites -- All DOE Office Websites (Extended Search)

of heat were removed from the high level waste tanks at Hanford. Called cesium and strontium, these elements had to be taken out of single shell waste tanks to reduce the...

347

Hydrogeology of the 200 Areas low-level burial grounds: An interim report: Volume 1, Text  

SciTech Connect

This report presents information derived from the installation of 35 ground-water monitoring wells around six low-level radioactive/hazardous waste burial grounds located in the 200 Areas of the Hanford Site in southeastern Washington State. This information was collected between May 20, 1987 and August 1, 1988. The contents of this report have been divided into two volumes. This volume contains the main text. Volume 2 contains the appendixes, including data and supporting information that verify content and results found in the main text. This report documents information collected by the Pacific Northwest Laboratory at the request of Westinghouse Hanford Company. Presented in this report are the preliminary interpretations of the hydrogeologic environment of six low-level burial grounds, which comprise four waste management areas (WMAs) located in the 200 Areas of the Hanford Site. This information and its accompanying interpretations were derived from sampling and testing activities associated with the construction of 35 ground-water monitoring wells as well as a multitude of previously existing boreholes. The new monitoring wells were installed as part of a ground-water monitoring program initiated in 1986. This ground-water monitoring program is based on requirements for interim status facilities in compliance with the Resource Conservation and Recovery Act (1976).

Last, G.V.; Bjornstad, B.N.; Bergeron, M.P.; Wallace, D.W.; Newcomer, D.R.; Schramke, J.A.; Chamness, M.A.; Cline, C.S.; Airhart, S.P.; Wilbur, J.S.

1989-01-01T23:59:59.000Z

348

Middlesex FUSRAP Site - A Path to Site-Wide Closure - 13416  

SciTech Connect

The road-map to obtaining closure of the Middlesex Sampling Plant FUSRAP site in Middlesex, New Jersey (NJ) has required a multi-faceted approach, following the CERCLA Process. Since 1998, the US ACE, ECC, and other contractors have completed much of the work required for regulatory acceptance of site closure with unrestricted use. To date, three buildings have been decontaminated, demolished, and disposed of. Two interim storage piles have been removed and disposed of, followed by the additional removal and disposal of over 87,000 tons of radiologically and chemically-impacted subsurface soils by the summer of 2008. The US ACE received a determination from the EPA for the soils Operable Unit, (OU)-1, in September 2010 that the remedial excavations were acceptable, and meet the criteria for unrestricted use as required by the 2004 Record of Decision (ROD) for OU-1. Following the completion of OU-1, the project delivery team performed additional field investigation of the final Operable Unit for Middlesex, OU-2, Groundwater. As of December 2012, the project delivery team has completed a Supplemental Remedial Investigation, which will be followed with a streamlined Feasibility Study, Proposed Plan, and ROD. Several years of historical groundwater data was available from previous investigations and the FUSRAP Environmental Surveillance Program. Historical data indicated sporadic detections of Volatile Organic Compounds (VOCs), primarily trichloroethylene (TCE), carbon tetrachloride (CT), and methyl tert-butyl ether (MTBE), with no apparent trend or pattern indicating extent or source of the VOC impact. In 2008, the project delivery team initiated efforts to re-assess the Conceptual Site Model (CSM) for groundwater. The bedrock was re-evaluated as a leaky multi-unit aquifer, and a plan was developed for additional investigations for adequate bedrock characterization and delineation of groundwater contaminated primarily by CT, TCE, and tetrachloroethene (PCE). The investigation was designed to accumulate multiple lines of evidence to determine the source and to delineate the extent of contamination, as required to complete the CERCLA Process and gain regulatory acceptance. Investigative techniques included in-well vertical flow tracing, borehole geophysics and packer testing of temporary test holes to characterize contamination in the bedrock fractures beneath the site, and to delineate likely source areas. (authors)

Miller, David M. [ECC, 110 Fieldcrest Ave, Ste 31, Edison, NJ, 08837 (United States)] [ECC, 110 Fieldcrest Ave, Ste 31, Edison, NJ, 08837 (United States); Edge, Helen [US Army Corps of Engineers - NYD, 26 Federal Plaza, Room 1811, New York, NY, 10278 (United States)] [US Army Corps of Engineers - NYD, 26 Federal Plaza, Room 1811, New York, NY, 10278 (United States)

2013-07-01T23:59:59.000Z

349

Microsoft Word - HZEB_Retail_InterimReport_Final.docx  

NLE Websites -- All DOE Office Websites (Extended Search)

! ! ! Healthy!Zero!Energy!Buildings!(HZEB)!Program-! ! ! Interim!Report!on!Cross"Sectional!Study!of!Contaminant!! ! ! Levels,!Source!Strengths,!and!Ventilation!Rates!in!Retail!Stores! ! ! ! ! Wanyu!R.!Chan,!Meera!Sidheswaran,!Douglas!Sullivan,!! ! ! Sebastian!Cohn,!William!J.!Fisk!! ! ! ! Environmental!Energy!Technologies!Division! ! ! Indoor!Environment!Group! ! ! Lawrence!Berkeley!National!Laboratory! ! ! Berkeley,!CA!94720! ! ! ! ! ! ! ! ! ! ! November!5,!2012! ! ! ! ! ! ! ! ! ! ! The!research!reported!here!was!supported!by!the!California!Energy!Commission! ! ! Public!Interest!Energy!Research!Program,!Energy"Related!Environmental!! ! ! Research!Program,!award!number!500"09"049.!!The!project!was!also!supported! ! ! by!the!U.S.!Dept.!of!Energy!Building!Technologies!Program,!Office!of!Energy!

350

EIS-0225: Continued Operation of the Pantex Plant and Associated Storage of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

25: Continued Operation of the Pantex Plant and Associated 25: Continued Operation of the Pantex Plant and Associated Storage of Nuclear Weapon Components EIS-0225: Continued Operation of the Pantex Plant and Associated Storage of Nuclear Weapon Components Summary This EIS evaluates the potential environemental impact of a proposal to continue operation of the Pantex Plant and associated storage of nuclear weapon components. Alternatives considered include: (1) Continuing nuclear weapon operations involving assembly and disassembly of nuclear weapons at the Pantex Plant; (2) implementing facility projects, including upgrades and construction consistent with conducting these operations; and (3) continuing to provide interim pit storage at the Pantex Plant and increasing the storage level from 12,000 to 20,000 pits.

351

Gas storage materials, including hydrogen storage materials  

DOE Patents (OSTI)

A material for the storage and release of gases comprises a plurality of hollow elements, each hollow element comprising a porous wall enclosing an interior cavity, the interior cavity including structures of a solid-state storage material. In particular examples, the storage material is a hydrogen storage material, such as a solid state hydride. An improved method for forming such materials includes the solution diffusion of a storage material solution through a porous wall of a hollow element into an interior cavity.

Mohtadi, Rana F; Wicks, George G; Heung, Leung K; Nakamura, Kenji

2014-11-25T23:59:59.000Z

352

Site status monitoring report for underground storage tanks 1219-U, 1222-U, 2082-U, and 2068-U at the Rust Garage Facility, Buildings 9720-15 and 9754-1, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee, Facility ID No. 0-010117  

SciTech Connect

The purpose of this document is to provide hydrogeologic, geochemical, and vapor monitoring data required for site status monitoring of underground storage tanks (UST) 1219-U, 1222-U, 2082-U, and 2068-U at the Rust Garage Facility. Comprehensive monitoring was conducted at the site in May 1994 as part of a Monitoring Only program approved by Tennessee Department of Environment and Conservation (TDEC) based on review and approval of Site Ranking. In September 1994, the first semiannual site status monitoring was conducted. This document presents the results of the second semiannual site status monitoring, which was conducted in February 1995. Site status monitoring and preparation of this report have been conducted in accordance with the requirements of the TDEC Rule 1200-1-15, the TDEC UST Reference Handbook, Second Edition, and direction from TDEC. This document is organized into three sections. Section 1 presents introductory information relative to the site including regulatory initiative and a site description. Section 2 includes the results of sampling of monitoring wells GW-508, GW-631, GW-632, and GW-634. Section 3 presents data from vapor monitoring conducted in subsurface utilities present at the site.

NONE

1995-03-01T23:59:59.000Z

353

The Evolution of LTS at DOE's Hanford Site  

SciTech Connect

Hanford's Long-Term Stewardship (LTS) Program has evolved from a small, informal process, with minimal support, to a robust program that provides comprehensive transitions from cleanup contractors to long-term stewardship for post-cleanup requirements specified in the associated cleanup decision documents. The LTS Program has the responsibility for almost 100,000 acres of land, along with over 200 waste sites and will soon have six cocooned reactors. Close to 2,600 documents have been identified and tagged for storage in the LTS document library. The program has successfully completed six consecutive transitions over the last two years in support of the U.S. DOE Richland Operations Office's (DOE-RL) near-term cleanup objectives of significantly reducing the footprint of active cleanup operations for the River Corridor. The program has evolved from one that was initially responsible for defining and measuring Institutional Controls for the Hanford Site, to a comprehensive, post remediation surveillance and maintenance program that begins early in the transition process. In 2013, the first reactor area -- the cocooned 105-F Reactor and its surrounding 1,100 acres, called the F Area was transitioned. In another first, the program is expected to transition the five remaining cocooned reactors into the program through using a Transition and Turnover Package (TTP). As Hanford's LTS Program moves into the next few years, it will continue to build on a collaborative approach. The program has built strong relationships between contractors, regulators, tribes and stakeholders and with the U.S. Department of Energy's Office of Legacy Management (LM). The LTS Program has been working with LM since its inception. The transition process utilized LM's Site Transition Framework as one of the initial requirement documents and the Hanford Program continues to collaborate with LM today. One example of this collaboration is the development of the LTS Program's records management system in which, LM has been instrumental. The development of a rigorous data collection and records management systems has been influenced and built off of LMs success, which also ensures compatibility between what Hanford's LTS Program develops and LM. In another example, we are exploring a pilot project to ship records from the Hanford Site directly to LM for long-term storage. This pilot would gain program efficiencies so that records would be handled only once. Rather than storage on-site, then shipment to an interim Federal Records Center in Seattle, records would be shipped directly to LM. The Hanford LTS Program is working to best align programmatic processes, find efficiencies, and to benchmark site transition requirements. Involving the Hanford LTS Program early in the transition process with an integrated contractor and DOE team is helping to ensure that there is time to work through details on the completed remediation of transitioning areas. It also will allow for record documentation and storage for the future, and is an opportunity for the program to mature through the experiences that will be gained by implementing LTS Program activities over time.

Moren, Richard J. [Mission Support Alliance, Richland, WA (United States); Grindstaff, Keith D. [USDOE Richland Operations Office, Richland, WA (United States)

2013-11-12T23:59:59.000Z

354

Underground Storage Tank Regulations | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Underground Storage Tank Regulations Underground Storage Tank Regulations Underground Storage Tank Regulations < Back Eligibility Agricultural Commercial Construction Developer Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Program Info State Mississippi Program Type Environmental Regulations Siting and Permitting Provider Department of Environmental Quality The Underground Storage Tank Regulations is relevant to all energy projects

355

Carbon Storage Monitoring, Verification and Accounting Research |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Monitoring, Verification and Accounting Research Monitoring, Verification and Accounting Research Carbon Storage Monitoring, Verification and Accounting Research Reliable and cost-effective monitoring, verification and accounting (MVA) techniques are an important part of making geologic sequestration a safe, effective, and acceptable method for greenhouse gas control. MVA of geologic storage sites is expected to serve several purposes, including addressing safety and environmental concerns; inventory verification; project and national accounting of greenhouse gas emissions reductions at geologic storage sites; and evaluating potential regional, national, and international greenhouse gas reduction goals. The goal of our program area is to develop and demonstrate a broad portfolio of technologies, applications, and accounting requirements that

356

Analysis of removal alternatives for the Heavy Water Components Test Reactor at the Savannah River Site. Revision 1  

SciTech Connect

This engineering study evaluates different alternatives for decontamination and decommissioning of the Heavy Water Components Test Reactor (HWCTR). Cooled and moderated with pressurized heavy water, this uranium-fueled nuclear reactor was designed to test fuel assemblies for heavy water power reactors. It was operated for this purpose from march of 1962 until December of 1964. Four alternatives studied in detail include: (1) dismantlement, in which all radioactive and hazardous contaminants would be removed, the containment dome dismantled and the property restored to a condition similar to its original preconstruction state; (2) partial dismantlement and interim safe storage, where radioactive equipment except for the reactor vessel and steam generators would be removed, along with hazardous materials, and the building sealed with remote monitoring equipment in place to permit limited inspections at five-year intervals; (3) conversion for beneficial reuse, in which most radioactive equipment and hazardous materials would be removed and the containment building converted to another use such as a storage facility for radioactive materials, and (4) entombment, which involves removing hazardous materials, filling the below-ground structure with concrete, removing the containment dome and pouring a concrete cap on the tomb. Also considered was safe storage, but this approach, which has, in effect, been followed for the past 30 years, did not warrant detailed evaluation. The four other alternatives were evaluate, taking into account factors such as potential effects on the environment, risks, effectiveness, ease of implementation and cost. The preferred alternative was determined to be dismantlement. This approach is recommended because it ranks highest in the comparative analysis, would serve as the best prototype for the site reactor decommissioning program and would be most compatible with site property reuse plans for the future.

Owen, M.B.

1997-04-01T23:59:59.000Z

357

Potential Release Sites  

NLE Websites -- All DOE Office Websites (Extended Search)

PRS PRS Potential Release Sites Legacy sites where hazardous materials are found to be above acceptable levels are collectively called potential release sites. Contact Environmental Communication & Public Involvement P.O. Box 1663 MS M996 Los Alamos, NM 87545 (505) 667-0216 Email Less than 10 percent of the total number of potential release sites need to go through the full corrective action process. What are potential release sites? Potential release sites are areas around the Laboratory and the town of Los Alamos at which hazardous materials from past activities have been found. Some examples of potential release sites include septic tanks and associated drain lines chemical storage areas wastewater outfalls material disposal areas incinerators sumps firing ranges

358

EIS-0212: Record of Decision | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Hanford Site, Richland, WA (December 1995) DOE and the Washington State Department of Ecology (Ecology) have jointly prepared the Safe Interim Storage of Hanford Tank Wastes Final...

359

EIS-0276: Notice of Intent to Prepare an Environmental Impact...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Intent to Prepare an Environmental Impact Statement Interim Storage of Plutonium at the Rocky Flats Environmental Technology Site, Golden, Colorado The Department of Energy (DOE)...

360

Solid-State Hydrogen Storage: Storage Capacity,Thermodynamics...  

NLE Websites -- All DOE Office Websites (Extended Search)

Hydrogen Storage: Storage Capacity,Thermodynamics and Kinetics. Solid-State Hydrogen Storage: Storage Capacity,Thermodynamics and Kinetics. Abstract: Solid-state reversible...

Note: This page contains sample records for the topic "interim storage site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Nuclear Fuels Storage & Transportation Planning Project | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Fuels Storage & Nuclear Fuels Storage & Transportation Planning Project Nuclear Fuels Storage & Transportation Planning Project Independent Spent Fuel Storage Installation (ISFSI) at the shutdown Connecticut Yankee site. The ISFSI includes 40 multi-purpose canisters, within vertical concrete storage casks, containing 1019 used nuclear fuel assemblies [412.3 metric ton heavy metal (MTHM)] and 3 canisters of greater-than-class-C (GTCC) low-level radioactive waste. Photo courtesy of Connecticut Yankee (http://www.connyankee.com/html/fuel_storage.html). Independent Spent Fuel Storage Installation (ISFSI) at the shutdown Connecticut Yankee site. The ISFSI includes 40 multi-purpose canisters, within vertical concrete storage casks, containing 1019 used nuclear fuel

362

Considered Sites | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Considered Sites Considered Sites Considered Sites View Considered Sites View Other Sites DOE maintains the Considered Sites Database to provide information to the public about sites that were formerly used in the nation's nuclear weapons and early atomic energy programs and that had the potential for residual radioactive contamination on site. Formerly Utilized Sites Remedial Action Program The U.S. Atomic Energy Commission (AEC) established the Formerly Utilized Sites Remedial Action Program (FUSRAP) in March 1974 under the authority of the Atomic Energy Act of 1954 to identify, investigate, and take appropriate cleanup action at sites where work was performed in support of the Manhattan Engineer District (MED) and early AEC programs. Site activities included uranium ore storage and processing, uranium metal

363

DOE/EIA-0193/P PRELIMINARY CONSERVATION TABLES FROM THE NATIONAL INTERIM ENERGY CONSUMPTION SURVEY  

U.S. Energy Information Administration (EIA) Indexed Site

193/P 193/P PRELIMINARY CONSERVATION TABLES FROM THE NATIONAL INTERIM ENERGY CONSUMPTION SURVEY OFFICE OF THE CONSUMPTION DATA SYSTEM OFFICE OF PROGRAM DEVELOPMENT ENERGY INFORMATION ADMINISTRATION AUGUST 1, 1979 PRELIMINARY CONSERVATION TABLES FROM THE NATIONAL INTERIM ENERGY CONSUMPTION SURVEY Attached is the first report of the Office of the Consumption Data System, Office of Program Development, Energy Information Administration, presenting preliminary data from the National Interim Energy Consumption Survey (NIECS). The focus of this report is the conservation activities performed by households since January 1977, and the status of households with respect to insulation, storm windows, and other energy conserving characteristics. These tables are from preliminary data files.

364

Savannah River Site Robotics  

ScienceCinema (OSTI)

Meet Sandmantis and Frankie, two advanced robotic devices that are key to cleanup at Savannah River Site. Sandmantis cleans hard, residual waste off huge underground storage tanks. Frankie is equipped with unique satellite capabilities and sensing abilties that can determine what chemicals still reside in the tanks in a cost effective manner.

None

2012-06-14T23:59:59.000Z

365

Dry storage of spent nuclear fuel in UAE Economic aspect  

Science Journals Connector (OSTI)

Abstract Cost analysis of dry storage of spent nuclear fuel (SNF) discharged from Barakah nuclear power plants in the UAE was performed using three variables: average fuel discharge rate (FD), discount rate (d), and cooling time in a spent fuel pool (Tcool). The costs of dry storage as an interim spent fuel storage option in the UAE were estimated and compared between the following two scenarios: Scenario 1 is accelerated transfer of spent fuel to dry storage that SNF will be transferred to dry storage facilities as soon as spent fuel has been sufficiently cooled down in a pool for the dry storage; Scenario 2 is defined as maximum use of spent fuel pool that SNF will be stored in a pool as long as possible till the amount of stored SNF in the pool reaches the capacity of the pools and, then, to be moved to dry storage. A sensitivity analysis on the costs was performed and multiple regression analysis was applied to the resulting net present values (NPVs) for Scenarios 1 and 2 and ?NPV that is difference in the net present values between the two scenarios. The results showed that \\{NPVs\\} and ?NPV could be approximately expressed by single equations with the three variables. Among the three variables, the discount rate had the largest effect on the \\{NPVs\\} of the dry storage costs. However, ?NPV was turned out to be equally sensitive to the discount rate and cooling period. Over the ranges of the variables, the additional cost for accelerated fuel transfer (Scenario 1) ranged from 86.4 to 212.9 million $. Calculated using the maximum difference (212.9M$) between the two scenarios, the accelerated fuel transfer to dry storage could incur the additional electricity rate 8.0נ10?5USD/kWh, which is not considered to be significant, compared to the overall electricity generation cost.

Sara Al Saadi; Yongsun Yi

2015-01-01T23:59:59.000Z

366

AQUIFER THERMAL ENERGY STORAGE  

E-Print Network (OSTI)

and Zakhidov, 1971. "Storage of Solar Energy in a Sandy-Aquifer Storage of Hot Water from Solar Energy Collectors,"with solar energy systems, aquifer energy storage provides a

Tsang, C.-F.

2011-01-01T23:59:59.000Z

367

Carbon Storage in Basalt  

Science Journals Connector (OSTI)

...immobile and thus the storage more secure, though...continental margins have huge storage capacities adjacent...unlimited supplies of seawater. On the continents...present in the target storage formation can be pumped up and used to dissolve...

Sigurdur R. Gislason; Eric H. Oelkers

2014-04-25T23:59:59.000Z

368

AQUIFER THERMAL ENERGY STORAGE  

E-Print Network (OSTI)

Zakhidov, 1971. "Storage of Solar Energy in a Sandy-Gravelwith solar energy systems, aquifer energy storage provides aAquifer Storage of Hot Water from Solar Energy Collectors,"

Tsang, C.-F.

2011-01-01T23:59:59.000Z

369

Seasonal thermal energy storage  

SciTech Connect

This report describes the following: (1) the US Department of Energy Seasonal Thermal Energy Storage Program, (2) aquifer thermal energy storage technology, (3) alternative STES technology, (4) foreign studies in seasonal thermal energy storage, and (5) economic assessment.

Allen, R.D.; Kannberg, L.D.; Raymond, J.R.

1984-05-01T23:59:59.000Z

370

Solar Thermal Energy Storage  

Science Journals Connector (OSTI)

Various types of thermal energy storage systems are introduced and their importance and desired characteristics are outlined. Sensible heat storage, which is one of the most commonly used storage systems in pract...

E. Payko; S. Kaka

1987-01-01T23:59:59.000Z

371

Evaluation of groundwater flow and transport at the Shoal underground nuclear test: An interim report  

SciTech Connect

Since 1962, all United States nuclear tests have been conducted underground. A consequence of this testing has been the deposition of large amounts of radioactive materials in the subsurface, sometimes in direct contact with groundwater. The majority of this testing occurred on the Nevada Test Site, but a limited number of experiments were conducted in other locations. One of these is the subject of this report, the Project Shoal Area (PSA), located about 50 km southeast of Fallon, Nevada. The Shoal test consisted of a 12-kiloton-yield nuclear detonation which occurred on October 26, 1963. Project Shoal was part of studies to enhance seismic detection of underground nuclear tests, in particular, in active earthquake areas. Characterization of groundwater contamination at the Project Shoal Area is being conducted by the US Department of Energy (DOE) under the Federal Facility Agreement and Consent Order (FFACO) with the State of Nevada Department of Environmental Protection and the US Department of Defense (DOD). This order prescribes a Corrective Action Strategy (Appendix VI), which, as applied to underground nuclear tests, involves preparing a Corrective Action Investigation Plan (CAIP), Corrective Action Decision Document (CADD), Corrective Action Plan, and Closure Report. The scope of the CAIP is flow and transport modeling to establish contaminant boundaries that are protective of human health and the environment. This interim report describes the current status of the flow and transport modeling for the PSA.

Pohll, G.; Chapman, J.; Hassan, A.; Papelis, C.; Andricevic, R.; Shirley, C.

1998-07-01T23:59:59.000Z

372

Energy Storage (II): Developing Advanced Technologies  

Science Journals Connector (OSTI)

...hydrogen could be stored or transported to appropriate sites via pipelines; and at the load site the hy-drogen could be used directly...among other materials, or-ganic materials, such as paraffin waxes, for storage where a long cycle life is re-quired. For...

Arthur L. Robinson

1974-05-24T23:59:59.000Z

373

Interaction of Sr-90 with site candidate soil for demonstration disposal facility at Serpong  

SciTech Connect

Interaction of radiostrontium (Sr-90) with site candidate soil for demonstration disposal facility to be constructed in the near future at Serpong has been done. This activity is to anticipate the interim storage facility at Serpong nuclear area becomes full off condition, and show to the public how radioactive waste can be well managed with the existing technology. To ensure that the location is save, a reliability study of site candidate soil becomes very importance to be conducted through some experiments consisted some affected parameters such as contact time, effect of ionic strength, and effect of Sr{sup +} ion in solution. Radiostrontium was used as a tracer on the experiments and has role as radionuclide reference in low-level radioactive waste due to its long half-live and it's easy to associate with organism in nature. So, interaction of radiostrontium and soil samples from site becomes important to be studied. Experiment was performed in batch method, and soil sample-solution containing radionuclide was mixed in a 20 ml of PE vial. Ratio of solid: liquid was 10{sup ?2} g/ml. Objective of the experiment is to collect the specific characteristics data of radionuclide sorption onto soil from site candidate. Distribution coefficient value was used as indicator where the amount of initial and final activities of radiostrontium in solution was compared. Result showed that equilibrium condition was reached after contact time 10 days with Kd values ranged from 1600-2350 ml/g. Increased in ionic strength in solution made decreased of Kd value into soil sample due to competition of background salt and radiostrontium into soil samples, and increased in Sr ion in solution caused decreased of Kd value in soil sample due to limitation of sorption capacity in soil samples. Fast condition in saturated of metal ion into soil samples was reached due to a simple reaction was occurred.

Setiawan, Budi, E-mail: bravo@batan.go.id [Radwaste Technology Center-National Nuclear Energy Agency, PUSPIPTEK, Serpong-Tangerang 15310 (Indonesia); Mila, Oktri; Safni [Dept. of Chemistry, Fac. of Math. and Nat. Sci., Andalas University, Kampus Limau Manis, Padang-West Sumatra 25163 (Indonesia)

2014-03-24T23:59:59.000Z

374

OE/EIA-0272 The National Interim Energy Consumption Survey:  

U.S. Energy Information Administration (EIA) Indexed Site

272 272 The National Interim Energy Consumption Survey: Exploring the Variability in Energy Consumption July 1981 U.S. Department of Energy Energy Information Administration Assistant Administrator for Program Development Office of the Consumption Data System Industrial Data Systems Division This publication is available from the Superintendent of Documents, U.S. Government Printing Office, at the following address: Superintendent of Documents U.S. Government Printing Office Washington, D.C. 20402 Order Desk: (202) 783-3238 Stock Number: 061-003-00205-6 Price: $4.25 For questions on energy statistics or information on availability of other EIA publications, contact: National Energy Information Center, El-20 Forrestal Building U.S. Department of Energy Washington, D.C. 20585

375

Guidance For Preparatioon of Basis For Interim Operation (BIO) Documents  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3011-2002 3011-2002 December 2002 Superceding DOE-STD-3011-94 November 1994 DOE STANDARD GUIDANCE FOR PREPARATION OF BASIS FOR INTERIM OPERATION (BIO) DOCUMENTS U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE DOE-STD-3011-2002 ii This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161;

376

Establishing interim authorization bases for resumption of plutonium operations  

SciTech Connect

DOE Order 5480.23, Nuclear Safety Analysis Reports, requires that DOE facilities have an approved SAR (Safety Analysis Report). Rocky Flats Plant has a number of facilities for which no SAR exists. DOE Order 5480.21, Unreviewed Safety Questions, makes allowance for the operation of facilities without adequate SARs, through the establishment of an interim Authorization Basis (AB). In order to establish an AB, the nuclear facility must define the population of documents comprising the various elements of the AB and must use this defined population of documents as the basis for performing safety evaluations under DOE requirements. This short note explains the steps Rocky Flats Plant is taking to catalog the large body of documents available in order to establish an AB for those facilities needed to resume plutonium operations.

Ealy, K.; Satterwhite, D.

1993-06-01T23:59:59.000Z

377

SUPERCONDUCTING MAGNETIC ENERGY STORAGE  

E-Print Network (OSTI)

hydro, compressed air, and battery energy storage are allenergy storage sys tem s suc h as pumped hydro and compressed air.

Hassenzahl, W.

2011-01-01T23:59:59.000Z

378

NNSA Sites | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NNSA Sites NNSA Sites NNSA Sites Compliance agreements for National Nuclear Security Administration sites are listed here with accompanying summaries. Los Alamos National Laboratory Consent Agreement, December 10, 1993 Los Alamos National Laboratory Consent Agreement, December 10, 1993 Summary Los Alamos National Laboratory Compliance Order, October 4, 1995 Los Alamos National Laboratory Compliance Order, October 4, 1995 Summary South Valley Compliance Agreement South Valley Compliance Agreement Summary Mutual Consent Agreement for Storage of LDR, January 6, 1994 Mutual Consent Agreement for Storage of LDR, January 6, 1994 Summary Nevada Test Site FFCA Consent Order, March 27, 1996 Nevada Test Site FFCA Consent Order, March 27, 1996 Summary Nevada Test Site FFCA Consent Order, May 10, 1996

379

Interim reports for data monitoring committee review vs final reports for regulatory filing  

Science Journals Connector (OSTI)

Since a statistical analysis plan serves as a benchmark for the final analysis and the final report for regulatory filing, it needs to be explicit about ... analyses to be used. An interim analysis plan, however,...

KyungMann Kim

2011-12-01T23:59:59.000Z

380

King County Metro Transit Hybrid Articulated Transit Buses: Interim Evaluation Results  

SciTech Connect

Interim technical report compares and evaluates new diesel and diesel hybrid-electric articulated buses operated as part of the King County Metro Transit (KC Metro) fleet in Seattle, Washington.

Chandler, K.; Walkowicz, K.

2006-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "interim storage site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

Pooling Authority Interim Enforcement Program Adopted Dec 19, 2011 Section 1: Definitions  

E-Print Network (OSTI)

Conservation and Development Commission. General Manager: The person responsible for implementing the Pooling Pooling Authority. Pooling Authority: Power & Water Resources Pooling Authority. Renewable EnergyPooling Authority Interim Enforcement Program ­ Adopted Dec 19, 2011 1 Section 1: Definitions

382

Marine wind and wave height trends at different ERA-Interim forecast ranges  

Science Journals Connector (OSTI)

Trends in marine wind speed and significant wave height are investigated using the global reanalysis ERA-Interim over the period 1979-2012, based on monthly mean and maximum data. Besides the traditional reanalysis, we include trends obtained at ...

Ole Johan Aarnes; Saleh Abdalla; Jean-Raymond Bidlot; yvind Breivik

383

Calculating Energy and Demand Retrofit Savings for Victoria High School: Interim Report  

E-Print Network (OSTI)

ESL-TR-92/12-03 Calculating Energy and Demand Retrofit Savings For Victoria High School Yue Liu, T. Agami Reddy, S. Katipamula and David E. Claridge. Interim Report Energy Systems Laboratory Texas A&M University College Station, TX 77843 December... 1992 Calculating Energy and Demand Retrofit Savings For Victoria High School Yue Liu, T. Agami Reddy, S. Katipamula and David E. Claridge. Interim Report Energy Systems Laboratory Texas A&M University College Station, TX 77843 December 1992 Abstract...

Liu, Y.; Reddy, T. A.; Katipamula, S.; Claridge, D. E.

1992-01-01T23:59:59.000Z

384

NETL: Carbon Storage - Knowledge Sharing  

NLE Websites -- All DOE Office Websites (Extended Search)

Knowledge Sharing Knowledge Sharing Carbon Storage Knowledge Sharing Outreach Efforts at SECARB's Anthropogenic Test Site in Alabama Outreach Efforts at SECARB's Anthropogenic Test Site in Alabama In order to achieve the commercialization of CO2 storage technologies, the U.S. Department of Energy (DOE) acknowledges that knowledge sharing between various entities is essential. Distribution of the results and lessons learned from both field projects and Core R&D efforts will provide the foundation for future, large-scale CCS field tests across North America and in addressing future challenges associated with public acceptance, infrastructure (pipelines, compressor stations, etc.), and regulatory framework. DOE promotes information and knowledge sharing through various avenues including the Regional Carbon Sequestration Partnerships (RCSP)

385

Pore Water Extraction Test Near 241-SX Tank Farm at the Hanford Site, Washington, USA  

SciTech Connect

A proof-of-principle test is underway near the Hanford Site 241-SX Tank Farm. The test will evaluate a potential remediation technology that will use tank farm-deployable equipment to remove contaminated pore water from vadose zone soils. The test system was designed and built to address the constraints of working within a tank farm. Due to radioactive soil contamination and limitations in drilling near tanks, small-diameter direct push drilling techniques applicable to tank farms are being utilized for well placement. To address space and weight limitations in working around tanks and obstacles within tank farms, the above ground portions of the test system have been constructed to allow deployment flexibility. The test system utilizes low vacuum over a sealed well screen to establish flow into an extraction well. Extracted pore water is collected in a well sump,and then pumped to the surface using a small-diameter bladder pump.If pore water extraction using this system can be successfully demonstrated, it may be possible to target local contamination in the vadose zone around underground storage tanks. It is anticipated that the results of this proof-of-principle test will support future decision making regarding interim and final actions for soil contamination within the tank farms.

Eberlein, Susan J. [Washington River Protection Systems, Richland, WA (United States); Parker, Danny L. [Washington River Protection Systems, Richland, WA (United States); Tabor, Cynthia L. [Washington River Protection Systems, Richland, WA (United States); Holm, Melissa J. [Washington River Protection Systems, Richland, WA (United States)

2013-11-11T23:59:59.000Z

386

Hydrogen Storage Based on Physisorption  

Science Journals Connector (OSTI)

Thermochemistry analysis was conducted at the same temperatures and pressures as those used experimentally to determine the wt % of hydrogen stored based on the physisorption process. ... A clear difference obsd. in gas evolution from SWNTs and peapods shows that the storage site for the hydrogen mol. is an inter-tube space and that 'sub-nanometer' sized spaces are indispensable for storing hydrogen mols. in this system. ...

L. G. Scanlon; W. A. Feld; P. B. Balbuena; G. Sandi; X. Duan; K. A. Underwood; N. Hunter; J. Mack; M. A. Rottmayer; M. Tsao

2009-03-10T23:59:59.000Z

387

Guidance Regarding Actions That May Proceed During the National Environmental Policy Act (NEPA) Process: Interim Actions (6/17/03)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Exhibit 3 Exhibit 3 Steps to Follow for Determining Whether Actions May Proceed During the NEPA Process: Interim Actions Would the Interim Action Prejudice the Ultimate Programmatic Decision (i.e., would it tend to determine subsequent development or Limit alternatives)? Is the Proposed Interim Action Within the Scope of a Programmatic or Project-Specific EIS that is Being Prepared? Is the EIS Programmatic in Nature? (If proposed interim action is covered by a CX or EA/FONSI,see footnote 4, page 4, of text) Provisions of 40 CFR 1506.1 Do Not Apply: Follow Normal DOE NEPA Review and Documentation Procedures No Yes No No Would the Interim Action Have An Adverse Impact? Would the Interim Action Limit the Choice of Reasonable Alternatives (e.g., by level of resources

388

Savannah River Operations Office; Interim Management of Nuclear Materials at the Savannah River Site  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

474 474 Federal Register / Vol. 61, No. 179 / Friday, September 13, 1996 / Notices James R. Holbein, United States Secretary, NAFTA Secretariat, Suite 2061, 14th and Constitution Avenue, Washington, DC 20230, (202) 482-5438. SUPPLEMENTARY INFORMATION: On April 30, 1996 the Binational Panel issued its decision affirming in part and remanding in part the Final Determination in this matter. The Determination Remand was filed by the International Trade Administration on June 14, 1996. No challenge to that Redetermination on Remand was filed under Rule 73 of the Article 1904 Panel Rules. Therefore, pursuant to Rule 73(5) the Panel issued an Order on July 19, 1996 affirming the Redetermination on Remand and instructing the Secretariat to issue a Notice of Final Panel Action. The Notice of Final Panel Action was

389

Savannah River Site Contractor Achieves Tank Waste Milestone | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Contractor Achieves Tank Waste Milestone Contractor Achieves Tank Waste Milestone Savannah River Site Contractor Achieves Tank Waste Milestone February 2, 2012 - 12:00pm Addthis Pictured here is a component of the Interim Salt Disposition Process — known as Modular Caustic Side Solvent Extraction Unit (MCU) — that helped Savannah River Remediation process more than 500,000 gallons of salt waste since October last year, a contract milestone. Pictured here is a component of the Interim Salt Disposition Process - known as Modular Caustic Side Solvent Extraction Unit (MCU) - that helped Savannah River Remediation process more than 500,000 gallons of salt waste since October last year, a contract milestone. AIKEN, S.C. - The Savannah River Site's liquid waste contractor recently achieved a contract milestone by processing 500,000 gallons of

390

Storage | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Storage Storage Storage Energy storage isn’t just for AA batteries. Thanks to investments from the Energy Department's Advanced Research Projects Agency-Energy (ARPA-E), energy storage may soon play a bigger part in our electricity grid, making it possible to generate more renewable electricity. Learn more. Energy storage isn't just for AA batteries. Thanks to investments from the Energy Department's Advanced Research Projects Agency-Energy (ARPA-E), energy storage may soon play a bigger part in our electricity grid, making it possible to generate more renewable electricity. Learn more.

391

NREL: Vehicles and Fuels Research - Energy Storage  

NLE Websites -- All DOE Office Websites (Extended Search)

Research Research Search More Search Options Site Map NREL's Energy Storage Project is leading the charge on battery thermal management, modeling, and systems solutions to enhance the performance of fuel cell, hybrid electric, and electric vehicles (FCVs, HEVs, and EVs) for a cleaner, more secure transportation future. NREL's experts work closely with the U.S. Department of Energy (DOE), industry, and automotive manufacturers to improve energy storage devices, such as battery modules and ultracapacitors, by enhancing their thermal performance and life-cycle cost. Activities also involve modeling and simulation to evaluate technical targets and energy storage parameters, and investigating combinations of energy storage systems to increase vehicle efficiency. Much of this research is conducted at our state-of-the-art energy storage

392

Thermal energy storage  

Science Journals Connector (OSTI)

Various types of thermal stares for solar systems are surveyed which include: long-term water stores for solar systems; ground storage using soil as an interseasonal energy store; ground-water aquifers; pebble or rock bed storage; phase change storage; solar ponds; high temperature storage; and cold stores for solar air conditioning system. The use of mathematical models for analysis of the storage systems is considered

W.E.J. Neal

1981-01-01T23:59:59.000Z

393

National Ignition Facility Cryogenic Target Systems Interim Management Plan  

SciTech Connect

Restricted availability of funding has had an adverse impact, unforeseen at the time of the original decision to projectize the National Ignition Facility (NIF) Cryogenic Target Handling Systems (NCTS) Program, on the planning and initiation of these efforts. The purpose of this document is to provide an interim project management plan describing the organizational structure and management processes currently in place for NCTS. Preparation of a Program Execution Plan (PEP) for NCTS has been initiated, and a current draft is provided as Attachment 1 to this document. The National Ignition Facility is a multi-megajoule laser facility being constructed at Lawrence Livermore National Laboratory (LLNL) by the National Nuclear Security Administration (NNSA) in the Department of Energy (DOE). Its primary mission is to support the Stockpile Stewardship Program (SSP) by performing experiments studying weapons physics, including fusion ignition. NIF also supports the missions of weapons effects, inertial fusion energy, and basic science in high-energy-density physics. NIF will be operated by LLNL under contract to the University of California (UC) as a national user facility. NIF is a low-hazard, radiological facility, and its operation will meet all applicable federal, state, and local Environmental Safety & Health (ES&H) requirements. The NCTS Interim Management Plan provides a summary of primary design criteria and functional requirements, current organizational structure, tracking and reporting procedures, and current planning estimates of project scope, cost, and schedule. The NIF Director controls the NIF Cryogenic Target Systems Interim Management Plan. Overall scope content and execution schedules for the High Energy Density Physics Campaign (SSP Campaign 10) are currently undergoing rebaselining and will be brought into alignment with resources expected to be available throughout the NNSA Future Years National Security Plan (FYNSP). The revised schedule for delivering this system will be decided at the national level, based on experiment campaign requirement dates that will be derived through this process. The current milestone date for achieving indirect-drive ignition on the NIF is December 2010. Maintaining this milestone requires that the cryogenic systems be complete and available for fielding experiments early enough that the planned experimental campaigns leading up to ignition can be carried out. The capability of performing non-ignition cryogenic experiments is currently required by March 2006, when the NIF's first cluster of beams is operational. Plans for cryogenic and non-cryogenic experiments on the NIF are contained in NNSA's Campaign 10 Program Plans for Ignition (MTE 10.1) and High Energy Density Sciences (MTE 10.2). As described in this document, the NCTS Program Manager is responsible for managing NIF Cryogenic Target Systems development, engineering, and deployment. Through the NIF Director, the NCTS Program Manager will put in place an appropriate Program Execution Plan (draft attached) at a later time consistent with the maturing and funding these efforts. The PEP will describe management methods for carrying out these activities.

Warner, B

2002-04-25T23:59:59.000Z

394

Please Note, effective September 1, 2011, the UCSC Student Policies and Regulations Handbook is an Interim document undergoing review. During this interim period, all  

E-Print Network (OSTI)

Please Note, effective September 1, 2011, the UCSC Student Policies and Regulations Handbook;University of California, Santa Cruz Student Policies and Regulations Handbook, Interim Table of Contents of California, Santa Cruz PREFACE The Student Policies and Regulations Handbook ("Handbook") integrates

California at Santa Cruz, University of

395

NREL: Energy Storage - Energy Storage Thermal Management  

NLE Websites -- All DOE Office Websites (Extended Search)

Energy Storage Thermal Management Infrared image of rectangular battery cell. Infrared thermal image of a lithium-ion battery cell with poor terminal design. Graph of relative...

396

NREL: Energy Storage - Energy Storage Systems Evaluation  

NLE Websites -- All DOE Office Websites (Extended Search)

Energy Storage Systems Evaluation Photo of man standing between two vehicles and plugging the vehicle on the right into a charging station. NREL system evaluation has confirmed...

397

Georgia Underground Storage Tank Act (Georgia) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Underground Storage Tank Act (Georgia) Underground Storage Tank Act (Georgia) Georgia Underground Storage Tank Act (Georgia) < Back Eligibility Agricultural Commercial Construction Developer Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Program Info State Georgia Program Type Environmental Regulations Siting and Permitting Provider Georgia Department of Natural Resources The Georgia Underground Storage Act (GUST) provides a comprehensive program to prevent, detect, and correct releases from underground storage tanks

398

1994 Report on Hanford Site land disposal restrictions for mixed waste  

SciTech Connect

The baseline land disposal restrictions (LDR) plan was prepared in 1990 in accordance with the Hanford Federal Facility Agreement and Consent Order (commonly referred to as the Tri-Party Agreement) Milestone M-26-00 (Ecology et al. 1992). The text of this milestone is below. LDR requirements include limitations on storage of specified hazardous wastes (including mixed wastes). In accordance with approved plans and schedules, the US Department of Energy (DOE) shall develop and implement technologies necessary to achieve full compliance with LDR requirements for mixed wastes at the Hanford Site. LDR plans and schedules shall be developed with consideration at other action plan milestones and will not become effective until approved by the US Environmental Protection Agency (EPA) (or Washington State Department of Ecology [Ecology]) upon authorization to administer LDRs pursuant to Section 3006 of the Resource Conservation and Recovery Act of 1976 (RCRA). Disposal of LDR wastes at any time is prohibited except in accordance with applicable LDR requirements for nonradioactive wastes at all times. The plan will include, but not be limited to, the following: waste characterization plan; storage report; treatment report; treatment plan; waste minimization plan; a schedule depicting the events necessary to achieve full compliance with LDR requirements; a process for establishing interim milestones. The original plan was published in October 1990. This is the fourth of a series of annual updates required by Tri-Party Agreement Milestone M-26-01. A Tri-Party Agreement change request approved in March 1992 changed the annual due date from October to April and consolidated this report with a similar one prepared under Milestone M-25-00. The reporting period for this report is from April 1, 1993, to March 31, 1994.

Black, D.G.

1994-04-01T23:59:59.000Z

399

Environmental Survey preliminary report, Hanford Site, Richland, Washington  

SciTech Connect

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

Not Available

1987-08-01T23:59:59.000Z

400

Hanford Site Tours - Hanford Site  

NLE Websites -- All DOE Office Websites (Extended Search)

Site Tours Hanford Site Tours Hanford Tour Restrictions Hanford Site Tours Hanford Tours for Governmental Officials Hanford Tours for Tribal Affairs Hanford Private Tours Media...

Note: This page contains sample records for the topic "interim storage site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

Spent Fuel Working Group report on inventory and storage of the Department`s spent nuclear fuel and other reactor irradiated nuclear materials and their environmental, safety and health vulnerabilities. Volume 3, Site team reports  

SciTech Connect

A self assessment was conducted of those Hanford facilities that are utilized to store Reactor Irradiated Nuclear Material, (RINM). The objective of the assessment is to identify the Hanford inventories of RINM and the ES & H concerns associated with such storage. The assessment was performed as proscribed by the Project Plan issued by the DOE Spent Fuel Working Group. The Project Plan is the plan of execution intended to complete the Secretary`s request for information relevant to the inventories and vulnerabilities of DOE storage of spent nuclear fuel. The Hanford RINM inventory, the facilities involved and the nature of the fuel stored are summarized. This table succinctly reveals the variety of the Hanford facilities involved, the variety of the types of RINM involved, and the wide range of the quantities of material involved in Hanford`s RINM storage circumstances. ES & H concerns are defined as those circumstances that have the potential, now or in the future, to lead to a criticality event, to a worker radiation exposure event, to an environmental release event, or to public announcements of such circumstances and the sensationalized reporting of the inherent risks.

Not Available

1993-11-01T23:59:59.000Z

402

Double tracks test site characterization report  

SciTech Connect

This report presents the results of site characterization activities performed at the Double Tracks Test Site, located on Range 71 North, of the Nellis Air Force Range (NAFR) in southern Nevada. Site characterization activities included reviewing historical data from the Double Tracks experiment, previous site investigation efforts, and recent site characterization data. The most recent site characterization activities were conducted in support of an interim corrective action to remediate the Double Tracks Test Site to an acceptable risk to human health and the environment. Site characterization was performed using a phased approach. First, previously collected data and historical records sere compiled and reviewed. Generalized scopes of work were then prepared to fill known data gaps. Field activities were conducted and the collected data were then reviewed to determine whether data gaps were filled and whether other areas needed to be investigated. Additional field efforts were then conducted, as required, to adequately characterize the site. Characterization of the Double Tracks Test Site was conducted in accordance with the US Department of Energy`s (DOE) Streamlined Approach for Environmental Restoration (SAFER).

NONE

1996-05-01T23:59:59.000Z

403

Responsiveness summary for the engineering evaluation/cost analysis for decontamination at the St. Louis Downtown Site, St. Louis, Missouri  

SciTech Connect

The US Department of Energy (DOE) is responsible for conducting remedial actions at the Mallinckrodt Chemical Plant, also referred to as the St. Louis Downtown Site (SLDS), located in the city of St. Louis, Missouri. Remedial activities at the SLDS are being carried out under DOE's Formerly Utilized Sites Remedial Action Program (FUSRAP) as part of the overall cleanup planned for three noncontiguous areas in St. Louis, which are collectively referred to as the St. Louis Site. Potential response action alternatives for managing the contaminated material generated at the SLDS have been evaluated in accordance with US Environmental Protection Agency (EPA) guidance for conducting interim actions under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. An engineering evaluation/cost analysis (EE/CA) report was prepared to document this process. On the basis of the analysis presented in the EE/CA, the preferred alternative for the management of contaminated wastes generated by DOE-supported plant activities is the provision of temporary storage capacity, which can be made available by modifying an existing building (i.e., Building 116) at SLDS. This alternative would enable DOE and Mallinckrodt to coordinate efforts to prevent the uncontrolled relocation of contamination and ensure that ultimate site cleanup objectives are not complicated by plant activities implemented by Mallinckrodt. The EE/CA, dated May 1991, was issued to the general public on June 7, 1991, and a public comment period was held from June 7 through July 10, 1991, in accordance with the public participation process identified in CERCLA. Comments on the proposed action were received in writing from the Missouri Department of Health, private citizen Kay Drey, and the EPA Region 7. This responsiveness summary has been prepared to respond to issues identified in these comment letters on the proposed action.

Picel, M.H.; Peterson, J.M. (Argonne National Lab., IL (United States)); Williams, M.J. (Bechtel National, Inc., Oak Ridge, TN (United States))

1991-12-01T23:59:59.000Z

404

Responsiveness summary for the engineering evaluation/cost analysis for decontamination at the St. Louis Downtown Site, St. Louis, Missouri  

SciTech Connect

The US Department of Energy (DOE) is responsible for conducting remedial actions at the Mallinckrodt Chemical Plant, also referred to as the St. Louis Downtown Site (SLDS), located in the city of St. Louis, Missouri. Remedial activities at the SLDS are being carried out under DOE`s Formerly Utilized Sites Remedial Action Program (FUSRAP) as part of the overall cleanup planned for three noncontiguous areas in St. Louis, which are collectively referred to as the St. Louis Site. Potential response action alternatives for managing the contaminated material generated at the SLDS have been evaluated in accordance with US Environmental Protection Agency (EPA) guidance for conducting interim actions under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. An engineering evaluation/cost analysis (EE/CA) report was prepared to document this process. On the basis of the analysis presented in the EE/CA, the preferred alternative for the management of contaminated wastes generated by DOE-supported plant activities is the provision of temporary storage capacity, which can be made available by modifying an existing building (i.e., Building 116) at SLDS. This alternative would enable DOE and Mallinckrodt to coordinate efforts to prevent the uncontrolled relocation of contamination and ensure that ultimate site cleanup objectives are not complicated by plant activities implemented by Mallinckrodt. The EE/CA, dated May 1991, was issued to the general public on June 7, 1991, and a public comment period was held from June 7 through July 10, 1991, in accordance with the public participation process identified in CERCLA. Comments on the proposed action were received in writing from the Missouri Department of Health, private citizen Kay Drey, and the EPA Region 7. This responsiveness summary has been prepared to respond to issues identified in these comment letters on the proposed action.

Picel, M.H.; Peterson, J.M. [Argonne National Lab., IL (United States); Williams, M.J. [Bechtel National, Inc., Oak Ridge, TN (United States)

1991-12-01T23:59:59.000Z

405

DRAFT INTERIM REPORT: NATIONAL PROGRAM PLAN FOR PASSIVE AND HYBRID SOLAR HEATING AND COOLING  

E-Print Network (OSTI)

w/Storage Floor Storage Col , Solar 15. Ground Preheat LA.l-to existing storage assemblies suitable for passive solarwith isolated storage (e.g. , solar ponds) 15. Ground

Authors, Various

2012-01-01T23:59:59.000Z

406

Underground Natural Gas Storage by Storage Type  

NLE Websites -- All DOE Office Websites (Extended Search)

1973-2014 Withdrawals 43,752 63,495 73,368 47,070 52,054 361,393 1973-2014 Salt Cavern Storage Fields Natural Gas in Storage 381,232 399,293 406,677 450,460 510,558 515,041...

407

EA-1914: Draft Site-Wide Environmental Assessment | Department...  

Office of Environmental Management (EM)

Facilities areas (Zone 1 and Zone 2); Increase site use and density by adding wind turbines, meteorological towers and associated infrastructure, and grid storage test...

408

Study identifies two Northwest basalt rock caverns sites for...  

NLE Websites -- All DOE Office Websites (Extended Search)

PNNL and BPA have identified two possible sites in eastern Washington to build compressed air energy storage facilities that could temporarily store the Northwest's excess wind...

409

Sandia National Laboratories: Energy Storage  

NLE Websites -- All DOE Office Websites (Extended Search)

New Mexico Renewable Energy Storage Task Force On January 28, 2014, in Energy, Energy Storage, Energy Storage Systems, Infrastructure Security, News, News & Events, Partnership,...

410

Spent Fuel Storage Operational Experience With Increased Crud Activities  

SciTech Connect

A significant part of the electricity production in Hungary is provided by 4 units of VVER 440 nuclear reactors at the Paks Nuclear Power Plant. Interim dry storage of the spent fuel assemblies that are generated during the operation of the reactors is provided in a Modular Vault Dry Storage (MVDS) facility that is located in the immediate vicinity of the Paks Nuclear Power Plant. The storage capacity of the MVDS is being continuously extended in accordance with spent the fuel production rate from the four reactors. An accident occurred at unit 2 of the Paks Nuclear Power Plant in 2003, when thirty irradiated fuel assemblies were damaged during a cleaning process. The fuel assemblies were not inside the reactor at the time of the accident, but in a separate tank within the adjacent fuel decay pool. As a result of this accident, contamination from the badly damaged fuel assemblies spread to the decay pool water and also became deposited onto the surface of (hermetic) spent fuel assemblies within the decay pool. Therefore, it was necessary to review the design basis of the MVDS and assess the effects of taking the surface contaminated spent fuel assemblies into dry storage. The contaminated hermetic assemblies were transferred from the unit 2 pool to the interim storage facility in the period between 2005 and 2007. Continuous inspection and measurement was carried out during the transfer of these fuel assemblies. On the basis of the design assessments and measurement of the results during the fuel transfer, it was shown that radiological activity values increased due to the consequences of the accident but that these levels did not compromise the release and radiation dose limits for the storage facility. The aim of this paper is to show the effect on the operation of the MVDS interim storage facility as a result of the increased activity values due to the accident that occurred in 2003, as well as to describe the measurements that were taken, and their results and experience gained. In summary: On the basis of the design assessments and measurement of the results during the fuel transfer operations, it was shown that radiological activity values increased due to the consequences of the 2003 accident but that these levels did not compromise the release and dose limits for the fuel storage facility. In the environment there was no measurable radioactivity as a result of the operation of the Paks ISFSI. The exposure of the surrounding population was calculated on measured releases and meteorological data. The calculations show negligible doses until 2004. Due to the increased surface contamination on the spent fuel assemblies the dose rate increased almost 5 times compared to the least annual value, but still less then 0.01 percent of the allowed dose restriction. (authors)

Barnabas, I. [Public Agency for Radioactive Waste, Management (PURAM) (Hungary); Eigner, T. [Paks NPP (Hungary); Gresits, I. [Technical University of Budapest (Hungary); Ordagh, M. [SOM System Llc, (Hungary)

2008-07-01T23:59:59.000Z

411

Onboard Storage Tank Workshop  

Energy.gov (U.S. Department of Energy (DOE))

The U.S. Department of Energy (DOE) and Sandia National Laboratories co-hosted the Onboard Storage Tank Workshop on April 29th, 2010. Onboard storage tank experts gathered to share lessons learned...

412

Solar Energy Storage  

Science Journals Connector (OSTI)

The intermittent nature of the solar energy supply makes the provision of adequate energy storage essential for the majority of practical applications. Thermal storage is needed for both low-temperature and high-...

Brian Norton BSc; MSc; PhD; F Inst E; C Eng

1992-01-01T23:59:59.000Z

413

Storage of Solar Energy  

Science Journals Connector (OSTI)

Energy storage provides a means for improving the performance and efficiency of a wide range of energy systems. It also plays an important role in energy conservation. Typically, energy storage is used when there...

H. P. Garg

1987-01-01T23:59:59.000Z

414

Chemical Energy Storage  

Science Journals Connector (OSTI)

The oldest and most commonly practiced method to store solar energy is sensible heat storage. The underlying technology is well developed and the basic storage materials, water and rocks, are available ... curren...

H. P. Garg; S. C. Mullick; A. K. Bhargava

1985-01-01T23:59:59.000Z

415

Cool Storage Performance  

E-Print Network (OSTI)

Utilities have promoted the use of electric heat and thermal storage to increase off peak usage of power. High daytime demand charges and enticing discounts for off peak power have been used as economic incentives to promote thermal storage systems...

Eppelheimer, D. M.

1985-01-01T23:59:59.000Z

416

Safe Home Food Storage  

E-Print Network (OSTI)

Proper food storage can preserve food quality and prevent spoilage and food/borne illness. The specifics of pantry, refrigerator and freezer storage are given, along with helpful information on new packaging, label dates, etc. A comprehensive table...

Van Laanen, Peggy

2002-08-22T23:59:59.000Z

417

Northward Propagation Mechanisms of the Boreal Summer Intraseasonal Oscillation in the ERA-Interim and SP-CCSM  

E-Print Network (OSTI)

of the ASM domain except in the Arabian Sea during the early stages of the monsoon life cycle. Reduced NP) are investigated using data from the interim ECMWF Re- Analysis (ERA-Interim, herein called ERAI from the model's ability to simulate reasonable mean wind and moisture fields, a realistic spectrum

Collett Jr., Jeffrey L.

418

Warm Conveyor Belts in the ERA-Interim Dataset (19792010). Part I: Climatology and Potential Vorticity Evolution  

Science Journals Connector (OSTI)

A global climatology of warm conveyor belts (WCBs) is presented for the years 19792010, based on trajectories calculated with Interim ECMWF Re-Analysis (ERA-Interim) data. WCB trajectories are identified as strongly ascending air parcels (600 hPa ...

Erica Madonna; Heini Wernli; Hanna Joos; Olivia Martius

2014-01-01T23:59:59.000Z

419

Photo Gallery - Hanford Site  

NLE Websites -- All DOE Office Websites (Extended Search)

2012 Keywords: N Reactor, cocooning, aerial Area: 100N Description: This is an aerial photo of the N Reactor complex just before work to place the reactor in interim safe...

420

Photo Gallery - Hanford Site  

NLE Websites -- All DOE Office Websites (Extended Search)

2005 Keywords: N Reactor, cocooning, aerial Area: 100N Description: This is an aerial photo of the N Reactor complex in 2005, before the reactor was placed in interim safe...

Note: This page contains sample records for the topic "interim storage site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

Thermochemical Energy Storage  

Energy.gov (U.S. Department of Energy (DOE))

This presentation summarizes the introduction given by Christian Sattler during the Thermochemical Energy Storage Workshop on January 8, 2013.

422

Energy Storage Systems  

SciTech Connect

Energy Storage Systems An Old Idea Doing New Things with New Technology article for the International Assoication of ELectrical Inspectors

Conover, David R.

2013-12-01T23:59:59.000Z

423

BNL Gas Storage Achievements, Research Capabilities, Interests...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

BNL Gas Storage Achievements, Research Capabilities, Interests, and Project Team Metal hydride gas storage Cryogenic gas storage Compressed gas storage Adsorbed gas storage...

424

Integrated Hydrogen Storage System Model  

NLE Websites -- All DOE Office Websites (Extended Search)

WSRC-TR-2007-00440, REVISION 0 WSRC-TR-2007-00440, REVISION 0 Keywords: Hydrogen Kinetics, Hydrogen Storage Vessel Metal Hydride Retention: Permanent Integrated Hydrogen Storage System Model Bruce J. Hardy November 16, 2007 Washington Savannah River Company Savannah River Site Aiken, SC 29808 Prepared for the U.S. Department of Energy Under Contract Number DEAC09-96-SR18500 DISCLAIMER This report was prepared for the United States Department of Energy under Contract No. DE-AC09-96SR18500 and is an account of work performed under that contract. Neither the United States Department of Energy, nor WSRC, nor any of their employees makes any warranty, expressed or implied, or assumes any legal liability or responsibility for accuracy, completeness, or usefulness, of any information,

425

Hanford Site Groundwater Monitoring for Fiscal Year 2005  

SciTech Connect

This report is one of the major products and deliverables of the Groundwater Remediation and Closure Assessment Projects detailed work plan for FY 2006, and reflects the requirements of The Groundwater Performance Assessment Project Quality Assurance Plan (PNNL-15014). This report presents the results of groundwater and vadose zone monitoring and remediation for fiscal year 2005 on the U.S. Department of Energy's Hanford Site, Washington. The most extensive contaminant plumes in groundwater are tritium, iodine-129, and nitrate, which all had multiple sources and are very mobile in groundwater. The largest portions of these plumes are migrating from the central Hanford Site to the southeast, toward the Columbia River. Carbon tetrachloride and associated organic constituents form a relatively large plume beneath the west-central part of the Hanford Site. Hexavalent chromium is present in plumes beneath the reactor areas along the river and beneath the central part of the site. Strontium-90 exceeds standards beneath all but one of the reactor areas. Technetium-99 and uranium plumes exceeding standards are present in the 200 Areas. A uranium plume underlies the 300 Area. Minor contaminant plumes with concentrations greater than standards include carbon-14, cesium-137, cis-1,2-dichloroethene, cyanide, fluoride, plutonium, and trichloroethene. Monitoring for the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 is conducted in 11 groundwater operable units. The purpose of this monitoring is to define and track plumes and to monitor the effectiveness of interim remedial actions. Interim groundwater remediation in the 100 Areas continued with the goal of reducing the amount of chromium (100-K, 100-D, and 100-H) and strontium-90 (100-N) reaching the Columbia River. The objective of two interim remediation systems in the 200 West Area is to prevent the spread of carbon tetrachloride and technetium-99/uranium plumes. Resource Conservation and Recovery Act of 1976 groundwater monitoring continued at 25 waste management areas during fiscal year 2005: 15 under interim or final status detection programs and data indicate that they are not adversely affecting groundwater, 8 under interim status groundwater quality assessment programs to assess contamination, and 2 under final status corrective-action programs. During calendar year 2005, drillers completed 27 new monitoring wells, and decommissioned (filled with grout) 115 unneeded wells. Vadose zone monitoring, characterization, and remediation continued in fiscal year 2005. Remediation and associated monitoring continued at a soil-vapor extraction system in the 200 West Area, which removes gaseous carbon tetrachloride from the vadose zone. DOE uses geophysical methods to monitor potential movement of contamination beneath former waste sites.

Hartman, Mary J.; Morasch, Launa F.; Webber, William D.

2006-02-28T23:59:59.000Z

426

Request for Rehearing and Request for Interim Clarification by David K.  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Rehearing and Request for Interim Clarification by Rehearing and Request for Interim Clarification by David K. Paylor, Director of the Virginia Department of Environmental Quality Request for Rehearing and Request for Interim Clarification by David K. Paylor, Director of the Virginia Department of Environmental Quality Docket No. EO-05-01: Pursuant to Federal Power Act § 313, David K. Paylor, Director of the Virginia Department of Environmental Quality, through his counsel Robert F. McDonnell, the Attorney General of Virginia, requests rehearing of Order No. 202-05-3 entered by the Secretary of Energy on December 20, 2005. Specifically, Director Paylor requests rehearing based on the following assignments of error: 1. The Secretary erred by holding that the FPA preempts the Clean Air Act and related state laws;

427

Interim Transmittal Letter dated July 27 2005 | U.S. DOE Office of Science  

Office of Science (SC) Website

Interim Transmittal Letter dated July 27 2005 Interim Transmittal Letter dated July 27 2005 High Energy Physics Advisory Panel (HEPAP) HEPAP Home Meetings Members .pdf file (20KB) Charges/Reports Charter .pdf file (44KB) HEP Committees of Visitors HEP Home Charges/Reports Interim Transmittal Letter dated July 27 2005 Print Text Size: A A A RSS Feeds FeedbackShare Page July 27, 2005 Harold T. Shapiro, Chair Sally Dawson, Vice Chair Elementary Particle Physics 2010 Committee The National Academies 500 Fifth Street, NW Washington, D.C. 20001 Dear Harold and Sally, Thank you again for your letter of March 15, 2005 to me as Chair of the High Energy Physics Advisory Panel (HEPAP) and for the opportunity to answer your questions about the International Linear Collider (ILC) along the broad themes of 1) the physics case, 2) the research and development

428

Interim Test Procedures for Evaluating Electrical Performance and Grid Integration of Vehicle-to-Grid Applications  

NLE Websites -- All DOE Office Websites (Extended Search)

Interim Test Procedures for Interim Test Procedures for Evaluating Electrical Performance and Grid Integration of Vehicle-to-Grid Applications S. Chakraborty, W. Kramer, B. Kroposki, G. Martin, P. McNutt, M. Kuss, T. Markel, and A. Hoke Technical Report NREL/TP-5500-51001 June 2011 NREL is a national laboratory of the U.S. Department of Energy, Office of Energy Efficiency & Renewable Energy, operated by the Alliance for Sustainable Energy, LLC. National Renewable Energy Laboratory 1617 Cole Boulevard Golden, Colorado 80401 303-275-3000 * www.nrel.gov Contract No. DE-AC36-08GO28308 Interim Test Procedures for Evaluating Electrical Performance and Grid Integration of Vehicle-to-Grid Applications S. Chakraborty, W. Kramer, B. Kroposki, G. Martin, P. McNutt, M. Kuss, T. Markel,

429

90-day Interim Report on Shale Gas Production - Secretary of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

90-day Interim Report on Shale Gas Production - Secretary of Energy 90-day Interim Report on Shale Gas Production - Secretary of Energy Advisory Board 90-day Interim Report on Shale Gas Production - Secretary of Energy Advisory Board The Shale Gas Subcommittee of the Secretary of Energy Advisory Board is charged with identifying measures that can be taken to reduce the environmental impact and improve the safety of shale gas production. Natural gas is a cornerstone of the U.S. economy, providing a quarter of the country's total energy. Owing to breakthroughs in technology, production from shale formations has gone from a negligible amount just a few years ago to being almost 30 percent of total U.S. natural gas production. This has brought lower prices, domestic jobs, and the prospect of enhanced national security due to the potential of substantial

430

The Humboldt House-Rye Patch Geothermal District: An Interim View | Open  

Open Energy Info (EERE)

The Humboldt House-Rye Patch Geothermal District: An Interim View The Humboldt House-Rye Patch Geothermal District: An Interim View Jump to: navigation, search OpenEI Reference LibraryAdd to library Conference Paper: The Humboldt House-Rye Patch Geothermal District: An Interim View Abstract The Humboldt House - Rye Patch Geothermal District extends about 6 miles along the northwestern flank of the Humboldt Range in Pershing County, Nevada and is composed of a number of geothermal cells. The northern Humboldt House portion of the district hosts hot wells and silicic sinter deposits extending from within the Humboldt Range, westward for at least four miles, out into the Humboldt River Valley. The southern Rye Patch portion of the District has scant surface geothermal features, and is identified from well data. Exploration in the District in the mid to late

431

Nuclear Fuels Storage & Transportation Planning Project Documents |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Fuel Cycle Technologies » Nuclear Fuels Storage & Fuel Cycle Technologies » Nuclear Fuels Storage & Transportation Planning Project » Nuclear Fuels Storage & Transportation Planning Project Documents Nuclear Fuels Storage & Transportation Planning Project Documents September 30, 2013 Preliminary Evaluation of Removing Used Nuclear Fuel From Shutdown Sites In January 2013, the Department of Energy issued the Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste. Among the elements contained in this strategy is an initial focus on accepting used nuclear fuel from shutdown reactor sites. February 22, 2013 Public Preferences Related to Consent-Based Siting of Radioactive Waste Management Facilities for Storage and Disposal This report provides findings from a set of social science studies

432

Storage Sub-committee  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Storage Sub-committee Storage Sub-committee 2012 Work Plan Confidential 1 2012 Storage Subcommittee Work Plan * Report to Congress. (legislative requirement) - Review existing and projected research and funding - Review existing DOE, Arpa-e projects and the OE 5 year plan - Identify gaps and recommend additional topics - Outline distributed (review as group) * Develop and analysis of the need for large scale storage deployment (outline distributed again) * Develop analysis on regulatory issues especially valuation and cost recovery Confidential 2 Large Scale Storage * Problem Statement * Situation Today * Benefits Analysis * Policy Issues * Technology Gaps * Recommendations * Renewables Variability - Reserves and capacity requirements - Financial impacts - IRC Response to FERC NOI and update

433

FCT Hydrogen Storage: Hydrogen Storage R&D Activities  

NLE Websites -- All DOE Office Websites (Extended Search)

Hydrogen Storage R&D Activities Hydrogen Storage R&D Activities to someone by E-mail Share FCT Hydrogen Storage: Hydrogen Storage R&D Activities on Facebook Tweet about FCT Hydrogen Storage: Hydrogen Storage R&D Activities on Twitter Bookmark FCT Hydrogen Storage: Hydrogen Storage R&D Activities on Google Bookmark FCT Hydrogen Storage: Hydrogen Storage R&D Activities on Delicious Rank FCT Hydrogen Storage: Hydrogen Storage R&D Activities on Digg Find More places to share FCT Hydrogen Storage: Hydrogen Storage R&D Activities on AddThis.com... Home Basics Current Technology DOE R&D Activities National Hydrogen Storage Compressed/Liquid Hydrogen Tanks Testing and Analysis Quick Links Hydrogen Production Hydrogen Delivery Fuel Cells Technology Validation Manufacturing Codes & Standards

434

EIA - Natural Gas Pipeline Network - Underground Natural Gas Storage  

U.S. Energy Information Administration (EIA) Indexed Site

Storage Storage About U.S. Natural Gas Pipelines - Transporting Natural Gas based on data through 2007/2008 with selected updates Underground Natural Gas Storage Overview | Regional Breakdowns Overview Underground natural gas storage provides pipelines, local distribution companies, producers, and pipeline shippers with an inventory management tool, seasonal supply backup, and access to natural gas needed to avoid imbalances between receipts and deliveries on a pipeline network. There are three principal types of underground storage sites used in the United States today. They are: · depleted natural gas or oil fields (326), · aquifers (43), or · salt caverns (31). In a few cases mine caverns have been used. Most underground storage facilities, 82 percent at the beginning of 2008, were created from reservoirs located in depleted natural gas production fields that were relatively easy to convert to storage service, and that were often cl