WorldWideScience

Sample records for river site spent

  1. Savannah River Site FY 1998 Spent Nuclear Fuel Interim Management Plan

    International Nuclear Information System (INIS)

    Dupont, M.E.

    1998-01-01

    This document has been prepared to present in one place the near and long-term plans for safe management of Savannah River Site (SRS) spent nuclear fuel inventories until final disposition has been identified and implemented. The activities described are consistent with FY 1998 Annual Operational Plan guidance and with the December 1997 SRS Accelerated Cleanup Plan update. Summarized are highlights, key decision dates, and baseline assumptions of this plan

  2. Savannah River Site Spent Nuclear Fuel Management Final Environmental Impact Statement

    Energy Technology Data Exchange (ETDEWEB)

    N/A

    2000-04-14

    The proposed DOE action considered in this environmental impact statement (EIS) is to implement appropriate processes for the safe and efficient management of spent nuclear fuel and targets at the Savannah River Site (SRS) in Aiken County, South Carolina, including placing these materials in forms suitable for ultimate disposition. Options to treat, package, and store this material are discussed. The material included in this EIS consists of approximately 68 metric tons heavy metal (MTHM) of spent nuclear fuel 20 MTHM of aluminum-based spent nuclear fuel at SRS, as much as 28 MTHM of aluminum-clad spent nuclear fuel from foreign and domestic research reactors to be shipped to SRS through 2035, and 20 MTHM of stainless-steel or zirconium-clad spent nuclear fuel and some Americium/Curium Targets stored at SRS. Alternatives considered in this EIS encompass a range of new packaging, new processing, and conventional processing technologies, as well as the No Action Alternative. A preferred alternative is identified in which DOE would prepare about 97% by volume (about 60% by mass) of the aluminum-based fuel for disposition using a melt and dilute treatment process. The remaining 3% by volume (about 40% by mass) would be managed using chemical separation. Impacts are assessed primarily in the areas of water resources, air resources, public and worker health, waste management, socioeconomic, and cumulative impacts.

  3. Overview of the spent nuclear fuel storage facilities at the Savannah River Site

    International Nuclear Information System (INIS)

    Thomas, Jay

    1999-01-01

    The May 1996 Record of Decision on a Proposed Nuclear Weapons Nonproliferation Policy concerning Foreign Research Reactor Spent Nuclear Fuel initiated a 13 year campaign renewing a policy to support the return of spent nuclear fuel containing uranium of U.S.-origin from foreign research reactors to the United States. As of July 1999, over 18% of the approximately 13,000 spent nuclear fuel assemblies from participating countries have been returned to the Savannah River Site (SRS). These 2400 assemblies are currently stored in two dedicated SRS wet storage facilities. One is the Receiving Basin for Off-site Fuels (RBOF) and the other as L-Basin. RBOF, built in the early 60's to support the 'Atoms for Peace' program, has been receiving off-site fuel for over 35 years. RBOF has received approximately 1950 casks since startup and has the capability of handling all of the casks currently used in the FRR program. However, RBOF is 90% filled to capacity and is not capable of storing all of the fuel to be received in the program. L-Basin was originally used as temporary storage for materials irradiated in SRS's L-Reactor. New storage racks and other modifications were completed in 1996 that improved water quality and allowed L-Basin to receive, handle and store spent nuclear fuel assemblies and components from off-site. The first foreign cask was received into L-Area in April 1997 and approximately 86 foreign and domestic casks have been received since that time. This paper provides an overview of activities related to fuel receipt and storage in both the Receiving Basin for Off-site Fuels (RBOF) and L-Basin facilities. It will illustrate each step of the fuel receipt program from arrival of casks at SRS through cask unloading and decontamination. It will follow the fuel handling process, from fuel unloading, through the cropping and bundling stages, and final placement in the wet storage rack. Decontamination methods and equipment will be explained to show how the empty

  4. Overview of the spent nuclear fuel storage facilities at the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Conatser, E.R.; Thomas, J.E. [Westinghouse Savannah River Company, Aiken, SC 29808 (United States)

    2000-07-01

    The May 1996 Record of Decision on a Proposed Nuclear Weapons Nonproliferation Policy concerning Foreign Research Reactor Spent Nuclear Fuel initiated a 13 year campaign renewing a policy to support the return of spent nuclear fuel containing uranium of U.S. origin from foreign research reactors to the United States. As of December 1999, over 22% of the approximately 13,000 spent nuclear fuel assemblies from participating countries have been returned to the Savannah River Site (SRS). These {approx}2650 assemblies are currently stored in two dedicated SRS wet storage facilities. One is the Receiving Basin for Off-site Fuels (RBOF) and the other as L-Basin. RBOF, built in the early 60's to support the 'Atoms for Peace' program, has been receiving off-site fuel for over 35 years. RBOF has received approximately 1950 casks since startup and has the capability of handling all of the casks currently used in the FRR program. However, RBOF is 90% filled to capacity and is not capable of storing all of the fuel to be received in the program. L-Basin was originally used as temporary storage for materials irradiated in SRS's L-Reactor. New storage racks and other modifications were completed in 1996 that improved water quality and allowed the L-Basin to receive, handle and store spent nuclear fuel assemblies and components from off-site. The first foreign cask was received into the L-Area in April 1997 and approximately 105 foreign and domestic casks have been received since that time. This paper provides an overview of activities related to fuel receipt and storage in both the Receiving Basin for Off-site Fuels (RBOF) and L-Basin facilities. It will illustrate each step of the fuel receipt program from arrival of casks at SRS through cask unloading and decontamination. It will follow the fuel handling process, from fuel unloading, through the cropping and bundling stages, and final placement in the wet storage rack. Decontamination methods and equipment

  5. Overview of the spent nuclear fuel storage facilities at the Savannah River Site

    International Nuclear Information System (INIS)

    Conatser, E.R.; Thomas, J.E.

    2000-01-01

    The May 1996 Record of Decision on a Proposed Nuclear Weapons Nonproliferation Policy concerning Foreign Research Reactor Spent Nuclear Fuel initiated a 13 year campaign renewing a policy to support the return of spent nuclear fuel containing uranium of U.S. origin from foreign research reactors to the United States. As of December 1999, over 22% of the approximately 13,000 spent nuclear fuel assemblies from participating countries have been returned to the Savannah River Site (SRS). These ∼2650 assemblies are currently stored in two dedicated SRS wet storage facilities. One is the Receiving Basin for Off-site Fuels (RBOF) and the other as L-Basin. RBOF, built in the early 60's to support the 'Atoms for Peace' program, has been receiving off-site fuel for over 35 years. RBOF has received approximately 1950 casks since startup and has the capability of handling all of the casks currently used in the FRR program. However, RBOF is 90% filled to capacity and is not capable of storing all of the fuel to be received in the program. L-Basin was originally used as temporary storage for materials irradiated in SRS's L-Reactor. New storage racks and other modifications were completed in 1996 that improved water quality and allowed the L-Basin to receive, handle and store spent nuclear fuel assemblies and components from off-site. The first foreign cask was received into the L-Area in April 1997 and approximately 105 foreign and domestic casks have been received since that time. This paper provides an overview of activities related to fuel receipt and storage in both the Receiving Basin for Off-site Fuels (RBOF) and L-Basin facilities. It will illustrate each step of the fuel receipt program from arrival of casks at SRS through cask unloading and decontamination. It will follow the fuel handling process, from fuel unloading, through the cropping and bundling stages, and final placement in the wet storage rack. Decontamination methods and equipment will be explained to show

  6. Achieving the timely receipt of foreign research reactor spent nuclear fuel at the Savannah River site

    International Nuclear Information System (INIS)

    Brizes, C.M.; Clark, W.D; Thomas, J.; Andes, T.

    1998-01-01

    The May 1996 Record of Decision on a Proposed Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel states that the United States will accept spent nuclear fuel containing uranium of U.S.-origin from foreign research reactors through the year 2009. The best information available indicates that approximately 13,000 assemblies of Material Test Reactor (MTR) spent nuclear fuel from 29 countries are expected to be shipped to the Savannah River Site during the 13 years of the program. As of July 1998, 1,371 spent nuclear fuel assemblies from 12 foreign research reactors have been received at the SRS. That is, after more than two years of the FRR program (approximately 15 percent of the program time), 11 percent of the total assemblies have been received at SRS. Current projections show that most of the assemblies can be received by 2009, however if some of the eligible, non-participating countries decide to rejoin the program, a bottleneck would occur at the end of the program. Also adding to the potential for the bottleneck is a trend of shipments being moved out in the timeline. The Savannah River Site is working to be proactive in avoiding a bottleneck at the end of the program, but cooperation is required from all program participants to be successful. Activities currently in progress include inventory/information questionnaires, verifying fuel against cask(s) certificate of compliance (C. of C.), and collecting Appendix A information well in advance of shipping the SNF. The inventory/information sheets have been distributed to a select number of reactor facilities in the past, but work is in progress to refine the process. Information requested in the questionnaire includes inventory numbers, preferred shipping dates, and cask preferences. This information allows for improved shipment planning and helps to ensure that we are working to meet the needs of the reactor facilities. Current plans are to send the questionnaires to

  7. Nonproliferation impacts assessment for the management of the Savannah River Site aluminum-based spent nuclear fuel

    International Nuclear Information System (INIS)

    1998-12-01

    On May 13, 1996, the US established a new, 10-year policy to accept and manage foreign research reactor spent nuclear fuel containing uranium enriched in the US. The goal of this policy is to reduce civilian commerce in weapons-usable highly enriched uranium (HEU), thereby reducing the risk of nuclear weapons proliferation. Two key disposition options under consideration for managing this fuel include conventional reprocessing and new treatment and packaging technologies. The Record of Decision specified that, while evaluating the reprocessing option, ''DOE will commission or conduct an independent study of the nonproliferation and other (e.g., cost and timing) implications of chemical separation of spent nuclear fuel from foreign research reactors.'' DOE's Office of Arms Control and Nonproliferation conducted this study consistent with the aforementioned Record of Decision. This report addresses the nonproliferation implications of the technologies under consideration for managing aluminum-based spent nuclear fuel at the Savannah River Site. Because the same technology options are being considered for the foreign research reactor and the other aluminum-based spent nuclear fuels discussed in Section ES.1, this report addresses the nonproliferation implications of managing all the Savannah River Site aluminum-based spent nuclear fuel, not just the foreign research reactor spent nuclear fuel. The combination of the environmental impact information contained in the draft EIS, public comment in response to the draft EIS, and the nonproliferation information contained in this report will enable the Department to make a sound decision regarding how to manage all aluminum-based spent nuclear fuel at the Savannah River Site

  8. Savannah River Site, spent nuclear fuel management, draft environmental impact statement

    International Nuclear Information System (INIS)

    1998-12-01

    The management of spent nuclear fuel (SNF) has been an integral part of the mission of the Savannah River Site (SRS) for more than 40 years. Until the early 1990s, SNF management consisted primarily of short-term onsite storage and reprocessing in the SRS chemical separation facilities to produce strategic nuclear materials. With the end of the Cold War, the US Department of Energy (DOE) decided to phase out reprocessing of SNF for the production of nuclear weapons materials. Therefore, the management strategy for this fuel has shifted from short-term storage and reprocessing for the recovery of highly-enriched uranium and transuranic isotopes to stabilization, when necessary, and interim storage pending final disposition that includes preparing aluminum-based SNF for placement in a geologic repository. In addition to the fuel already onsite, the SRS will receive SNF from foreign research reactors until 2009 and from domestic research reactors until, potentially, 2035. As a result, the safe and efficient management of SNF will continue to be an important SRS mission. This EIS evaluates the potential environmental impacts of DOE's proposed plans for management SNF assigned to SRS

  9. 78 FR 20625 - Spent Nuclear Fuel Management at the Savannah River Site

    Science.gov (United States)

    2013-04-05

    ... Engineering Laboratory Environmental Restoration and Waste Management Programs Final Environmental Impact... generated at the Oak Ridge National Laboratory and approximately 1,000 bundles of aluminum-clad SNF... processing is a chemical separations process that involves dissolving spent fuel in nitric acid and...

  10. Alternative dispositioning methods for HEU spent nuclear fuel at the Savannah River Site

    International Nuclear Information System (INIS)

    Krupa, J.F.; McKibben, J.M.; Parks, P.B.; DuPont, M.E.

    1995-01-01

    The United States has a strong policy on prevention of the international spread of nuclear weapons. This policy was announced in Presidential Directive PDD-13 and summarized in a White House press release September 27, 1993. Two cornerstones of this policy are: seek to eliminate where possible the accumulation of stockpiles of highly- enriched uranium or plutonium; propose hor-ellipsis prohibiting the production of highly-enriched uranium (HEU) or plutonium for nuclear explosives purposes or outside international safeguards. The Department of Energy is currently struggling to devise techniques that safely and efficiently dispose of spent nuclear fuel (SNF) while satisfying national non-proliferation policies. SRS plans and proposals for disposing of their SNF are safe and cost effective, and fully satisfy non-proliferation objectives

  11. Report on the Savannah River Site aluminum-based spent nuclear fuel alternatives cost study

    International Nuclear Information System (INIS)

    1998-12-01

    Initial estimates of costs for the interim management and disposal of aluminum-based spent nuclear fuel (SNF) were developed during preparation of the Environmental Impact Statement (EIS) on the Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel. The Task Team evaluated multiple alternatives, assessing programmatic, technical, and schedule risks, and generated life-cycle cost projections for each alternative. The eight technology alternatives evaluated were: direct co-disposal; melt and dilute; reprocessing; press and dilute; glass material oxidation dissolution system (GMODS); electrometallurgical treatment; dissolve and vitrify; and plasma arc. In followup to the Business Plan that was developed to look at SNF dry storage, WSRC prepared an addendum to the cost study. This addendum estimated the costs for the modification and use of an existing (105L) reactor facility versus a greenfield approach for new facilities (for the Direct Co-Disposal and Melt and Dilute alternatives). WSRC assessed the impacts of a delay in reprocessing due to the potential reservation of H-Canyon for other missions (i.e., down blending HEU for commercial use or the conversion of plutonium to either MOX fuel or an immobilized repository disposal form). This report presents the relevant results from these WSRC cost studies, consistent with the most recent project policy, technology implementation, canyon utilization, and inventory assumptions. As this is a summary report, detailed information on the technical alternatives or the cost assumptions raised in each of the above-mentioned cost studies is not provided. A comparison table that briefly describes the bases used for the WSRC analyses is included as Appendix A

  12. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement. Volume 1, Appendix C, Savannah River Site Spent Nuclear Fuel Mangement Program

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    The US Department of Energy (DOE) is engaged in two related decision making processes concerning: (1) the transportation, receipt, processing, and storage of spent nuclear fuel (SNF) at the DOE Idaho National Engineering Laboratory (INEL) which will focus on the next 10 years; and (2) programmatic decisions on future spent nuclear fuel management which will emphasize the next 40 years. DOE is analyzing the environmental consequences of these spent nuclear fuel management actions in this two-volume Environmental Impact Statement (EIS). Volume 1 supports broad programmatic decisions that will have applicability across the DOE complex and describes in detail the purpose and need for this DOE action. Volume 2 is specific to actions at the INEL. This document, which limits its discussion to the Savannah River Site (SRS) spent nuclear fuel management program, supports Volume 1 of the EIS. Following the introduction, Chapter 2 contains background information related to the SRS and the framework of environmental regulations pertinent to spent nuclear fuel management. Chapter 3 identifies spent nuclear fuel management alternatives that DOE could implement at the SRS, and summarizes their potential environmental consequences. Chapter 4 describes the existing environmental resources of the SRS that spent nuclear fuel activities could affect. Chapter 5 analyzes in detail the environmental consequences of each spent nuclear fuel management alternative and describes cumulative impacts. The chapter also contains information on unavoidable adverse impacts, commitment of resources, short-term use of the environment and mitigation measures.

  13. Assessment of the requirements for placing and maintaining Savannah River Site spent fuel storage basins under International Atomic Energy Agency safeguards

    International Nuclear Information System (INIS)

    Amacker, O.P. Jr.; Curtis, M.M.; Delegard, C.H.; Hsue, S.T.; Whitesel, R.N.

    1997-03-01

    The United States is considering the offer of irradiated research reactor spent fuel (RRSF) for international safeguards applied by the International Atomic Energy Agency (IAEA). The offer would be to add one or more spent fuel storage basins to the list of facilities eligible for IAEA safeguards. The fuel to be safeguarded would be stored in basins on the Savannah River Site (SRS). This RRSF potentially can include returns of Material Test Reactor (MTR) VAX fuel from Argentina, Brazil, and Chile (ABC); returns from other foreign research reactors; and fuel from domestic research reactors. Basins on the SRS being considered for this fuel storage are the Receiving Basin for Offsite Fuel (RBOF) and the L-Area Disassembly Basin (L-Basin). A working group of SRS, U.S. Department of Energy International Safeguards Division (NN-44), and National Laboratory personnel with experience in IAEA safeguards was convened to consider the requirements for applying the safeguards to this material. The working group projected the safeguards requirements and described alternatives

  14. Conceptual design report for the away from reactor spent fuel storage facility, Savannah River Plant

    International Nuclear Information System (INIS)

    1978-12-01

    The Department of Energy (DOE) requested that Du Pont prepare a conceptual design and appraisal of cost for Federal budget planning for an away from reactor spent fuel storage facility that could be ready to store fuel by December 1982. This report describes the basis of the appraisal of cost in the amount of $270,000,000 for all facilities. The proposed action is to provide a facility at the Savannah River Plant. The facility will have an initial storage capacity of 5000 metric tons of spent fuel and will be capable of receiving 1000 metric tons per year. The spent fuel will be stored in water-filled concrete basins that are lined with stainless steel. The modular construction of the facility will allow future expansion of the storage basins and auxiliary services in a cost-effective manner. The facility will be designed to receive, handle, decontaminate and reship spent fuel casks; to remove irradiated fuel from casks; to place the fuel in a storage basin; and to cool and control the quality of the water. The facility will also be designed to remove spent fuel from storage basins, load the spent fuel into shipping casks, decontaminated loaded casks and ship spent fuel. The facility requires a license by the Nuclear Regulatory Commission (NRC). Features of the design, construction and operations that may affect the health and safety of the workforce and the public will conform with NRC requirements. The facility would be ready to store fuel by January 1983, based on normal Du Pont design and construction practices for DOE. The schedule does not include the effect of licensing by the NRC. To maintain this option, preparation of the documents and investigation of a site at the Savannah River Plant, as required for licensing, were started in FY '78

  15. Savannah River Site's Site Specific Plan

    International Nuclear Information System (INIS)

    1991-01-01

    This Site Specific Plan (SSP) has been prepared by the Savannah River Site (SRS) in order to show the Environmental Restoration and Waste Management activities that were identified during the preparation of the Department of Energy-Headquarters (DOE-HQ) Environmental Restoration and Waste Management Five-Year Plan (FYP) for FY 1992--1996. The SSP has been prepared in accordance with guidance received from DOE-HQ. DOE-SR is accountable to DOE-HQ for the implementation of this plan. The purpose of the SSP is to develop a baseline for policy, budget, and schedules for the DOE Environmental Restoration and Waste Management activities. The plan explains accomplishments since the Fiscal Year (FY) 1990 plan, demonstrates how present and future activities are prioritized, identifies currently funded activities and activities that are planned to be funded in the upcoming fiscal year, and describes future activities that SRS is considering

  16. Savannah River Site computing architecture

    Energy Technology Data Exchange (ETDEWEB)

    1991-03-29

    A computing architecture is a framework for making decisions about the implementation of computer technology and the supporting infrastructure. Because of the size, diversity, and amount of resources dedicated to computing at the Savannah River Site (SRS), there must be an overall strategic plan that can be followed by the thousands of site personnel who make decisions daily that directly affect the SRS computing environment and impact the site`s production and business systems. This plan must address the following requirements: There must be SRS-wide standards for procurement or development of computing systems (hardware and software). The site computing organizations must develop systems that end users find easy to use. Systems must be put in place to support the primary function of site information workers. The developers of computer systems must be given tools that automate and speed up the development of information systems and applications based on computer technology. This document describes a proposal for a site-wide computing architecture that addresses the above requirements. In summary, this architecture is standards-based data-driven, and workstation-oriented with larger systems being utilized for the delivery of needed information to users in a client-server relationship.

  17. HANFORD SITE RIVER CORRIDOR CLEANUP

    International Nuclear Information System (INIS)

    BAZZELL, K.D.

    2006-01-01

    In 2005, the US Department of Energy (DOE) launched the third generation of closure contracts, including the River Corridor Closure (RCC) Contract at Hanford. Over the past decade, significant progress has been made on cleaning up the river shore that bordes Hanford. However, the most important cleanup challenges lie ahead. In March 2005, DOE awarded the Hanford River Corridor Closure Contract to Washington Closure Hanford (WCH), a limited liability company owned by Washington Group International, Bechtel National and CH2M HILL. It is a single-purpose company whose goal is to safely and efficiently accelerate cleanup in the 544 km 2 Hanford river corridor and reduce or eliminate future obligations to DOE for maintaining long-term stewardship over the site. The RCC Contract is a cost-plus-incentive-fee closure contract, which incentivizes the contractor to reduce cost and accelerate the schedule. At $1.9 billion and seven years, WCH has accelerated cleaning up Hanford's river corridor significantly compared to the $3.2 billion and 10 years originally estimated by the US Army Corps of Engineers. Predictable funding is one of the key features of the new contract, with funding set by contract at $183 million in fiscal year (FY) 2006 and peaking at $387 million in FY2012. Another feature of the contract allows for Washington Closure to perform up to 40% of the value of the contract and subcontract the balance. One of the major challenges in the next few years will be to identify and qualify sufficient subcontractors to meet the goal

  18. Savannah River Site computing architecture

    Energy Technology Data Exchange (ETDEWEB)

    1991-03-29

    A computing architecture is a framework for making decisions about the implementation of computer technology and the supporting infrastructure. Because of the size, diversity, and amount of resources dedicated to computing at the Savannah River Site (SRS), there must be an overall strategic plan that can be followed by the thousands of site personnel who make decisions daily that directly affect the SRS computing environment and impact the site's production and business systems. This plan must address the following requirements: There must be SRS-wide standards for procurement or development of computing systems (hardware and software). The site computing organizations must develop systems that end users find easy to use. Systems must be put in place to support the primary function of site information workers. The developers of computer systems must be given tools that automate and speed up the development of information systems and applications based on computer technology. This document describes a proposal for a site-wide computing architecture that addresses the above requirements. In summary, this architecture is standards-based data-driven, and workstation-oriented with larger systems being utilized for the delivery of needed information to users in a client-server relationship.

  19. Savannah River Site dose control

    International Nuclear Information System (INIS)

    Smith, L.S.

    1992-01-01

    Health physicists from the Brookhaven National Laboratory (BNL) visited the Savannah River Site (SRS) as one of 12 facilities operated by the Department of Energy (DOE) contractors with annual collective dose equivalents greater than 100 person-rem (100 person-cSv). Their charter was to review, evaluate and summarize as low as reasonably achievable (ALARA) techniques, methods and practices as implemented. This presentation gives an overview of the two selected ALARA practices implemented at the SRS: Administrative Exposure Limits and Goal Setting. These dose control methods are used to assure that individual and collective occupational doses are ALARA and within regulatory limits

  20. Savannah River Site Environmental Implentation Plan

    International Nuclear Information System (INIS)

    1989-01-01

    This report describes the organizational responsibilities for the Savannah River Site Environmental program. Operations, Engineering and projects, Environment, safety, and health, Quality assurance, and the Savannah River Laboratory are described

  1. Pre-Shipment Preparations at the Savannah River Site

    International Nuclear Information System (INIS)

    Thomas, J.E.

    2000-01-01

    This paper will provide a detailed description of each of the pre-shipment process steps WSRC performs to produce the technical basis for approving the receipt and storage of spent nuclear fuel at the Savannah River Site. It is intended to be a guide to reactor operators who plan on returning ''U.S. origin'' SNF and to emphasize the need for accurate and timely completion of pre-shipment activities

  2. Site selection - siting of the final repository for spent nuclear fuel

    International Nuclear Information System (INIS)

    2011-03-01

    SKB has selected Forsmark as the site for the final repository for spent nuclear fuel. The site selection is the end result of an extensive siting process that began in the early 1990s. The strategy and plan for the work was based on experience from investigations and development work over a period of more than ten years prior to then. This document describes the siting work and SKB's choice of site for the final repository. It also presents the information on which the choice was based and the reasons for the decisions made along the way. The document comprises Appendix PV to applications under the Nuclear Activities Act and the Environmental Code for licences to build and operate an encapsulation plant adjacent to the central interim storage facility for spent nuclear fuel in Oskarshamn, and to build and operate a final repository for spent nuclear fuel in Forsmark in Oesthammar Municipality

  3. Site selection - siting of the final repository for spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    2011-03-15

    SKB has selected Forsmark as the site for the final repository for spent nuclear fuel. The site selection is the end result of an extensive siting process that began in the early 1990s. The strategy and plan for the work was based on experience from investigations and development work over a period of more than ten years prior to then. This document describes the siting work and SKB's choice of site for the final repository. It also presents the information on which the choice was based and the reasons for the decisions made along the way. The document comprises Appendix PV to applications under the Nuclear Activities Act and the Environmental Code for licences to build and operate an encapsulation plant adjacent to the central interim storage facility for spent nuclear fuel in Oskarshamn, and to build and operate a final repository for spent nuclear fuel in Forsmark in Oesthammar Municipality

  4. Shipment of gas generating spent fuel on the U.S. Department of Energy Hanford Site

    International Nuclear Information System (INIS)

    Edwards, W.S.

    1998-01-01

    Approximately 2,100 metric tons of unprocessed, irradiated nuclear fuel elements are stored in the two K Basins at the US Department of Energy (DOE) Hanford Site near Richland, Washington. The basin water contains significant quantities of dissolved nuclear isotopes and radioactive fuel corrosion particles. The condition of the spent fuel elements varies from intact to severely damaged, where the cladding is badly split or has peeled, with substantial fuel missing. The K Basins are located within a few hundred meters of the Columbia River and have leaked twice in the past. One of the highest priorities of the DOE is to remove the spent fuel from the K Basins, stabilize it, and move it to a Canister Storage Building (CSB), built well away from the Columbia River, for long-term storage prior to final disposition at a repository. Transportation of the K Basin spent fuel will occur entirely within the confines of the Hanford Site, which does not have routine public access. Consequently, the transport is onsite, and does not fall under the Federal Hazardous Materials Regulations (DOT 1997). DOE Order 460.1 (DOE 1995) enables DOE facilities to develop onsite transportation programs that provide equivalent safety to the Federal Hazardous Materials Regulations (DOT 1997). The basis for the Hanford Site onsite transportation program is detailed in HNF-PRO-1 54 (FDH 1998). The Hanford Site onsite transportation program was developed to meet the equivalent safety requirement, be consistent with analogous commercial operations, interface appropriately with facility safety analysis requirements, and utilize a risk-based management approach to ensure effort is applied consistent with the risk. The program focus is on the establishment of defendable safety bases. Authorization to use an onsite transportation system is granted by the approval of the applicable Safety Analysis Report for Packaging (Onsite). The K Basin spent fuel transportation activity is similar, in some respects

  5. Final disposal of spent nuclear fuel - basis for site selection

    International Nuclear Information System (INIS)

    Anttila, P.

    1995-05-01

    International organizations, e.g. IAEA, have published several recommendations and guides for the safe disposal of radioactive waste. There are three major groups of issues affecting the site selection process, i.e. geological, environmental and socioeconomic. The first step of the site selection process is an inventory of potential host rock formations. After that, potential study areas are screened to identify sites for detailed investigations, prior to geological conditions and overall suitability for the safe disposal. This kind of stepwise site selection procedure has been used in Finland and in Sweden. A similar approach has been proposed in Canada, too. In accordance with the amendment to the Nuclear Energy Act, that entered into force in the beginning of 1995, Imatran Voima Oy has to make preparations for the final disposal of spent fuel in the Finnish bedrock. Relating to the possible site selection, the following geological factors, as internationally recommended and used in the Nordic countries, should be taken into account: topography, stability of bedrock, brokenness and fracturing of bedrock, size of bedrock block, rock type, predictability and natural resources. The bedrock of the Loviisa NPP site is a part of the Vyborg rapakivi massif. As a whole the rapakivi granite area forms a potential target area, although other rock types or areas cannot be excluded from possible site selection studies. (25 refs., 7 figs.)

  6. Optimum MRS site location to minimize spent fuel transportation impacts

    International Nuclear Information System (INIS)

    Hoskins, R.E.

    1987-01-01

    A range of spent fuel transportation system parameters are examined in terms of attributes important to minimizing transportation impacts as a basis for identifying geographic regions best suited for siting a monitored retrievable storage (MRS) facility. Transportation system parameters within existing transport cask design and transportation mode capabilities were systematically analyzed. The optimum MRS location was found to be very sensitive to transportation system assumptions particularly with regard to the relative efficiencies of the reactor-to-MRS and MRS-to-repository components of the system. Moreover, dramatic improvements in the reactor-to-MRS component can be made through use of multiple cask shipment of the largest practical casks by dedicated train compared to the traditional single cask rail (70%) and truck (30%) shipments assumed the Department of Energy in their studies that defined the optimum MRS location in the vicinity of Tennessee. It is important to develop and utilize an efficient transportation system irrespective of whether or not an MRS is in the system. Assuming reasonably achievable efficiency in reactor-to-MRS spent fuel transportation and assigning equal probabilities to the three western sites selected for characterization of being the repository site, the optimum MRS location would be in the far-mid-western states. Based on various geographic criteria including barge access and location in a nuclear service area, the State of Tennessee ranks any place from 12th to the 25th at a penalty of about 30% over the minimum achievable impacts. While minimizing transportation impacts is an important factor, other criteria should also be considered in selecting an MRS site

  7. Savannah River Site Environmental Report for 1997

    Energy Technology Data Exchange (ETDEWEB)

    Arnett, M.W.; Mamatey, A.R. [eds.

    1998-08-01

    The mission at the Savannah River Site has changed from the production of nuclear weapons materials for national defense to the management of waste, restoration of the environment, and the development of industry in and around the site.

  8. Savannah River Site Environmental Report for 1997

    International Nuclear Information System (INIS)

    Arnett, M.W.; Mamatey, A.R.

    1998-01-01

    The mission at the Savannah River Site has changed from the production of nuclear weapons materials for national defense to the management of waste, restoration of the environment, and the development of industry in and around the site

  9. Development of on-site spent fuel transfer system designs

    International Nuclear Information System (INIS)

    Lambert, R.W.; Pennington, C.W.; Guerra, G.V.

    1993-01-01

    The Electric Power Research Institute (EPRI) of the United States has sponsored development of conceptual designs for accomplishing spent fuel transfer from spent fuel pools to casks and from one cask to another. Under an EPRI research contract, transnuclear has developed several concepts for spent fuel transfer systems. (J.P.N.)

  10. Electrometallurgical treatment of metallic spent nuclear fuel stored at the Hanford Site

    International Nuclear Information System (INIS)

    Laidler, J.J.; Gay, E.C.

    1996-01-01

    The major component of the DOE spent nuclear fuel inventory is the metallic fuel stored at the Hanford site in the southeastern part of the state of Washington. Most of this fuel was discharged from the N-Reactor; a small part of the inventory is fuel from the early Hanford production reactors. The U.S. Department of Energy (DOE) plans to remove these fuels from the spent fuel storage pools in which they are presently stored, dry them, and place them in interim storage at a location at the Hanford site that is far removed from the Columbia River. It is not yet certain that these fuels will be acceptable for disposal in a mined geologic repository without further treatment, due to their potential pyrophoric character. A practical method for treatment of the Hanford metallic spent fuel, based on an electrorefining process, has been developed and has been demonstrated with unirradiated N-Reactor fuel and with simulated single-pass reactor (SPR) spent fuel. The process can be operated with any desired throughput rates; being a batch process, it is simply a matter of setting the size of the electrorefiner modules and the number of such modules. A single module, prototypic of a production-scale module, has been fabricated and testing is in progress at a throughput rate of 150 kg (heavy metal) per day. The envisioned production version would incorporate additional anode baskets and cathode tubes and provide a throughput rate of 333 kgHM/day. A system with four of these modules would permit treatment of Hanford metallic fuels at a rate of at least 250 metric tons per year

  11. Site investigations for the disposal of spent fuel - investigation program

    International Nuclear Information System (INIS)

    Aeikaes, Timo

    1985-11-01

    The Industrial Power Company Ltd (TVO) is making preparations for the final disposal of spent nuclear fuel into the Finnish bedrock. The revised site investigation program for the years 1986-2010 is presented in this report. The objectives and activities in the near future are described in more detail. The main objectives and frame programs for the investigations in the more distant future are described. The program planning of these investigations are being developed in the preceding site investigations. The investigations for the site selection are divided into four phases: 1983-1985 selection of the investigation areas, preparations for the field investigations, drilling and investigations in a deep test borehole; 1986-1992 preliminary site investigations in 5-10 investigation areas; 1993-2000 detailed site investigations in 2-3 investigation areas. Site selection in the year 2000; 2001-2010 complementary investigations on the selected site. The first investigation phase will be carried out as planned. In this phase a 1001 m deep test borehole was drilled at Lavia in western Finland. With the investigations in the borehole and related development work, preparations were made for the future field investigations. The equipment and investigation methods are being developed during the site investigations. The equipment for taking groundwater samples and the unit for hydraulic testing have been developed. In the future the emphasis in the work will be in developing equipment for monitoring of the hydraulic head and measuring the volumetric flow. In groundwater sampling the present procedure can be improved by adding the test for the in-situ measurements. The results of the field investigations will be stored and processed in a centralized data base. The data base will transmit the results for the interpretation and then the interpreted results transmitted for model calculations and reporting. The cost estimate for the investigations in 1986-2010 is 110-125 million

  12. Structural geology report: Spent Fuel Test - Climax Nevada Test Site

    International Nuclear Information System (INIS)

    Wilder, D.G.; Yow, J.L. Jr.

    1984-10-01

    We performed underground mapping and core logging in the Climax Stock, a granitic intrusive at the Nevada Test Site, as part of a major field test to determine the feasibility of using granitic or crystalline rock for the underground storage of spent fuel from a nuclear reactor. This mapping and logging identified more than 2500 fractures, over 1500 of which were described in enough detail to allow statistical analyses and orientation studies to be performed. We identified eight joint sets, three major shear sets, and a fault zone within the Spent Fuel Test - Climax (SFT-C) portion of the Stock. Joint sets identified within the SFT-C and elsewhere in the Stock correlated well. The orientations of joint sets identified by other investigators were consistent with our findings, indicating that the joint sets are persistent and have a relatively uniform orientation throughout a major portion of the Stock. The one joint set not seen elsewhere in the Stock is healed and the wall rock is altered, implying that healed joints were not included in the mapping criteria used by other investigators. The shear sets were distinguished from the joint sets by virtue of crushed minerals, continuous clay infilling, and other evidences of shearing, and from faults by the lack of offsetting. Previous investigators working mainly in the Pile Driver Drifts identified two of the shear sets. The third set, being nearly parallel to these Drifts had not been identified previously. The fault zone identified at the far (Receiving Room) end of the project is oriented approximately N45 0 E-75 0 SE, similar to both the Boundary and Shaft Station Faults. We have, therefore, concluded that the Receiving Room Fault is one of a series of normal faults that occur within the Climax Stock and that are possibly related, in both age and genesis, to the Boundary Fault. 52 refs., 26 figs., 11 tabs

  13. Potential sites for a spent unreprocessed fuel facility (SURFF), southwesten part of the Nevada Test Site

    International Nuclear Information System (INIS)

    Hoover, D.L.; Eckel, E.B.; Ohl, J.P.

    1978-01-01

    In the absence of specific criteria, the topography, geomorphology, and geology of Jackass Flats and vicinity in the southwestern part of the Nevada Test Site are evaluated by arbitrary guidelines for a Spent Unreprocessed Fuel Facility. The guidelines include requirements for surface slopes of less than 5%, 61 m of alluvium beneath the site, an area free of active erosion or deposition, lack of faults, a minimum area of 5 km 2 , no potential for flooding, and as many logistical support facilities as possible. The geology of the Jackass Flats area is similar to the rest of the Nevada Test Site in topographic relief (305-1,200 m), stratigraphy (complexly folded and faulted Paleozoic sediments overlain by Tertiary ash-flow tuffs and lavas overlain in turn by younger alluvium), and structure (Paleozoic thrust faults and folds, strike-slip faults, proximity to volcanic centers, and Basin and Range normal faults). Of the stratigraphic units at the potential Spent Unreprocessed Fuel Facility site in Jackass Flats, only the thickness and stability of the alluvium are of immediate importance. Basin and Range faults and a possible extension of the Mine Mountain fault need further investigation. The combination of a slope map and a simplified geologic and physiographic map into one map shows several potential sites for a Spent Unreprocessed Fuel Facility in Jackass Flats. The potential areas have slopes of less than 5% and contain only desert pavement or segmented pavement--the two physiographic categories having the greatest geomorphic and hydraulic stability. Before further work can be done, specific criteria for a Spent Unreprocessed Fuel Facility site must be defined. Following criteria definition, potential sites will require detailed topographic and geologic studies, subsurface investigations (including geophysical methods, trenching, and perhaps shallow drilling for faults in alluvium), detailed surface hydrologic studies, and possibly subsurface hydrologic studies

  14. Time Spent on Social Network Sites and Psychological Well-Being: A Meta-Analysis.

    Science.gov (United States)

    Huang, Chiungjung

    2017-06-01

    This meta-analysis examines the relationship between time spent on social networking sites and psychological well-being factors, namely self-esteem, life satisfaction, loneliness, and depression. Sixty-one studies consisting of 67 independent samples involving 19,652 participants were identified. The mean correlation between time spent on social networking sites and psychological well-being was low at r = -0.07. The correlations between time spent on social networking sites and positive indicators (self-esteem and life satisfaction) were close to 0, whereas those between time spent on social networking sites and negative indicators (depression and loneliness) were weak. The effects of publication outlet, site on which users spent time, scale of time spent, and participant age and gender were not significant. As most included studies used student samples, future research should be conducted to examine this relationship for adults.

  15. Transportation Packages to Support Savannah River Site Missions

    International Nuclear Information System (INIS)

    Opperman, E.

    2001-01-01

    The Savannah River Site's missions have expanded from primarily a defense mission to one that includes environmental cleanup and the stabilization, storage, and preparation for final disposition of nuclear materials. The development of packaging and the transportation of radioactive materials are playing an ever-increasing role in the successful completion of the site's missions. This paper describes the Savannah River Site and the three strategic mission areas of (1) nuclear materials stewardship, (2) environmental stewardship, and (3) nuclear weapons stockpile stewardship. The materials and components that need to be shipped, and associated packaging, will be described for each of the mission areas. The diverse range of materials requiring shipment include spent fuel, irradiated target assemblies, excess plutonium and uranium materials, high level waste canisters, transuranic wastes, mixed and low level wastes, and nuclear weapons stockpile materials and components. Since many of these materials have been in prolonged storage or resulted from disassembly of components, the composition, size and shape of the materials present packaging and certification challenges that need to be met. Over 30 different package designs are required to support the site's missions. Approximately 15 inbound shipping-legs transport materials into the Savannah River Site and the same number (15) of outgoing shipment-legs are carrying materials from the site for further processing or permanent disposal

  16. Site Specific Analyses of a Spent Nuclear Fuel Transportation Accident

    International Nuclear Information System (INIS)

    Biwer, B. M.; Chen, S. Y.

    2003-01-01

    The number of spent nuclear fuel (SNF) shipments is expected to increase significantly during the time period that the United States' inventory of SNF is sent to a final disposal site. Prior work estimated that the highest accident risks of a SNF shipping campaign to the proposed geologic repository at Yucca Mountain were in the corridor states, such as Illinois. The largest potential human health impacts would be expected to occur in areas with high population densities such as urban settings. Thus, our current study examined the human health impacts from the most plausible severe SNF transportation accidents in the Chicago metropolitan area. The RISKIND 2.0 program was used to model site-specific data for an area where the largest impacts might occur. The results have shown that the radiological human health consequences of a severe SNF rail transportation accident on average might be similar to one year of exposure to natural background radiation for those persons living a nd working in the most affected areas downwind of the actual accident location. For maximally exposed individuals, an exposure similar to about two years of exposure to natural background radiation was estimated. In addition to the accident probabilities being very low (approximately 1 chance in 10,000 or less during the entire shipping campaign), the actual human health impacts are expected to be lower if any of the accidents considered did occur, because the results are dependent on the specific location and weather conditions, such as wind speed and direction, that were selected to maximize the results. Also, comparison of the results of longer duration accident scenarios against U.S. Environmental Protection Agency guidelines was made to demonstrate the usefulness of this site-specific analysis for emergency planning purposes

  17. Savannah River Site Environmental Report for 1998

    Energy Technology Data Exchange (ETDEWEB)

    Arnett, M

    1999-06-09

    The mission at the Savannah River Site (SRS) is focused primarily on support of the national defense, nonproliferation, and environmental cleanup. SRS-through its prime operating contractor, Westinghouse Savannah River Company-continues to maintain a comprehensive environmental monitoring program.

  18. Savannah River Site Environmental Report for 1998

    International Nuclear Information System (INIS)

    Arnett, M.

    1999-01-01

    The mission at the Savannah River Site (SRS) is focused primarily on support of the national defense, nonproliferation, and environmental cleanup. SRS-through its prime operating contractor, Westinghouse Savannah River Company-continues to maintain a comprehensive environmental monitoring program

  19. Advanced separations at Savannah River Site

    International Nuclear Information System (INIS)

    Thompson, M.; McCabe, D.

    1996-01-01

    The Savannah River Site (SRS) has many waste streams that are contaminated with radionuclides and/or hazardous materials that must be treated to remove the radioactivity (cesium, strontium, tritium, actinides) and hazardous components (polychlorinated biphenyls (PCBs), cyanide, metal ions)

  20. Finding a site to store spent fuel in the Pacific Basin

    International Nuclear Information System (INIS)

    Selvaduray, G.S.; Goldstein, M.K.; Anderson, R.N.

    1979-01-01

    How can one decide on a site to store spent LWR fuel, after the Presidential embargo on reprocessing. Palmyra Island is identified as the best site for the nations bordering the Pacific to store spent fuel. The quantitative methods used to reach this decision are outlined. (author)

  1. Land Use Baseline Report Savannah River Site

    International Nuclear Information System (INIS)

    Noah, J.C.

    1995-01-01

    This document is to serve as a resource for Savannah River Site managers, planners, and SRS stakeholders by providing a general description of the site and land-use factors important to future use decisions and plans. The intent of this document is to be comprehensive in its review of SRS and the surrounding area

  2. Land Use Baseline Report Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Noah, J.C.

    1995-06-29

    This document is to serve as a resource for Savannah River Site managers, planners, and SRS stakeholders by providing a general description of the site and land-use factors important to future use decisions and plans. The intent of this document is to be comprehensive in its review of SRS and the surrounding area.

  3. 76 FR 71342 - Proposed CERCLA Administrative Cost Recovery Settlement; River Forest Dry Cleaners Site, River...

    Science.gov (United States)

    2011-11-17

    ... Settlement; River Forest Dry Cleaners Site, River Forest, Cook County, IL AGENCY: Environmental Protection... response costs concerning the River Forest Dry Cleaners site in River Forest, Cook County, Illinois with... code: C-14J, Chicago, Illinois 60604. Comments should reference the River Forest Dry Cleaners Site...

  4. On-site interim storage of spent nuclear fuel: Emerging public issues

    International Nuclear Information System (INIS)

    Feldman, D.L.; Tennessee Univ., Knoxville, TN

    1992-01-01

    Failure to consummate plans for a permanent repository or above- ground interim Monitored Retrievable Storage (MRS) facility for spent nuclear fuel has spurred innovative efforts to ensure at-reactor storage in an environmentally safe and secure manner. This article examines the institutional and socioeconomic impacts of Dry Cask Storage Technology (DCST)-an approach to spent fuel management that is emerging as the preferred method of on-site interim spent fuel storage by utilities that exhaust existing storage capacity

  5. Spent fuel handling system for a geologic storage test at the Nevada Test Site

    International Nuclear Information System (INIS)

    Duncan, J.E.; House, P.A.; Wright, G.W.

    1980-01-01

    The Lawrence Livermore Laboratory is conducting a test of the geologic storage of encapsulated spent commercial reactor fuel assemblies in a granitic rock at the Nevada Test Site. The test, known as the Spent Fuel Test-Climax (SFT-C), is sponsored by the US Department of Energy, Nevada Operations Office. Eleven pressurized-water-reactor spent fuel assemblies are stored retrievably for three to five years in a linear array in the Climax stock at a depth of 420 m

  6. Savannah River Site's H-Canyon Facility: Impacts of Foreign Obligations on Special Nuclear Material Disposition

    International Nuclear Information System (INIS)

    Magoulas, Virginia

    2013-01-01

    The US has a non-proliferation policy to receive foreign and domestic research reactor returns of spent fuel materials of US origin. These spent fuel materials are returned to the Department of Energy (DOE) and placed in storage in the L-area spent fuel basin at the Savannah River Site (SRS). The foreign research reactor returns fall subject to the 123 agreements for peaceful cooperation. These ''123 agreements'' are named after section 123 of the Atomic Energy Act of 1954 and govern the conditions of nuclear cooperation with foreign partners. The SRS management of these foreign obligations while planning material disposition paths can be a challenge.

  7. Radioiodine in the Savannah River Site environment

    Energy Technology Data Exchange (ETDEWEB)

    Kantelo, M.V.; Bauer, L.R.; Marter, W.L.; Murphy, C.E. Jr.; Zeigler, C.C.

    1993-01-15

    Radioiodine, which is the collective term for all radioactive isotopes of the element iodine, is formed at the Savannah River Site (SRS) principally as a by-product of nuclear reactor operations. Part of the radioiodine is released to the environment during reactor and reprocessing operations at the site. The purpose of this report is to provide an introduction to radioiodine production and disposition, its status in the environment, and the radiation dose and health risks as a consequence of its release to the environment around the Savannah River Plant. A rigorous dose reconstruction study is to be completed by thee Center for Disease Control during the 1990s.

  8. Radioiodine in the Savannah River Site environment

    International Nuclear Information System (INIS)

    Kantelo, M.V.; Bauer, L.R.; Marter, W.L.; Murphy, C.E. Jr.; Zeigler, C.C.

    1993-01-01

    Radioiodine, which is the collective term for all radioactive isotopes of the element iodine, is formed at the Savannah River Site (SRS) principally as a by-product of nuclear reactor operations. Part of the radioiodine is released to the environment during reactor and reprocessing operations at the site. The purpose of this report is to provide an introduction to radioiodine production and disposition, its status in the environment, and the radiation dose and health risks as a consequence of its release to the environment around the Savannah River Plant. A rigorous dose reconstruction study is to be completed by thee Center for Disease Control during the 1990s

  9. On-site concrete cask storage system for spent nuclear fuel

    International Nuclear Information System (INIS)

    Craig, P.A.; Haelsig, R.T.; Kent, J.D.; Schmoker, D.S.

    1989-01-01

    A method is described of storing spent nuclear fuel assemblies including the steps of: transferring the fuel assemblies from a spent-fuel pool to a moveable concrete storage cask located outside the spent-fuel pool; maintaining a barrier between the fuel and the concrete in the cask to prevent contamination of the concrete by the fuel; maintaining the concrete storage cask containing the spent-fuel on site at the reactor complex for some predetermined period; transferring the fuel assemblies from the concrete storage cask to a shipping container; and, recycling the concrete storage cask

  10. The Savannah River Site's groundwater monitoring program

    International Nuclear Information System (INIS)

    1991-01-01

    This report summarizes the Savannah River Site (SRS) groundwater monitoring program conducted by EPD/EMS in the first quarter of 1991. In includes the analytical data, field data, data review, quality control, and other documentation for this program, provides a record of the program's activities and rationale, and serves as an official document of the analytical results

  11. The Savannah River Site's Groundwater Monitoring Program

    International Nuclear Information System (INIS)

    1992-01-01

    This report summarizes the Savannah River Site (SRS) groundwater monitoring program conducted during the first quarter of 1992. It includes the analytical data, field data, data review, quality control, and other documentation for this program; provides a record of the program's activities; and serves as an official document of the analytical results

  12. Wildflowers of the Savannah River Site

    Science.gov (United States)

    T. Segar

    2015-01-01

    This guidebook is a resource to help field personnel (nonbotanists) identify plants on the Savannah River Site (SRS) premises. Although not a complete flora guide, this publication contains information about 123 plant species found on the SRS. Plants are listed by their common names and arranged by the color of the flower.

  13. Savannah River Site (SRS) environmental overview

    International Nuclear Information System (INIS)

    O'Rear, M.G.; Steele, J.L.; Kitchen, B.G.

    1990-01-01

    The environmental surveillance activities at and in the vicinity of the Savannah River Site (SRS) [formerly the Savannah River Plant (SRP)] comprise one of the most comprehensive and extensive environmental monitoring programs in the United States. This overview contains monitoring data from routine and nonroutine radiological and nonradiological environmental surveillance activities, summaries of environmental protection programs in progress, a summary of National Environmental Policy Act (NEPA) activities, and a listing of environmental permits (Appendix A) issued by regulatory agencies. This overview provides information about the impact of SRS operations on the public and the environment. The SRS occupies a large area of approximately 300 square miles along the Savannah River, principally in Aiken and Barnwell counties of South Carolina. SRS's primary function is the production of tritium, plutonium, and other special nuclear materials for national defense, for other governmental uses, and for some civilian purposes. From August 1950 to March 31, 1989, SRS was operated for the Department of Energy (DOE) by E. I. du Pont de Nemours ampersand Co. On April 1, 1989 the Westinghouse Savannah River Company assumed responsibility as the prime contractor for the Savannah River Site

  14. Remote technology in RBMK-1000 spent fuel management at NPP site

    International Nuclear Information System (INIS)

    Makarchuk, T.F.; Kozlov, Y.V.; Tikhonov, N.S.; Tokarenko, A.I.; Spichev, V.V.; Kaljazin, N.N.

    1999-01-01

    The report describes the remote technologies employed in the nuclear power plant with RBMK-1000 type. Spent fuel transfer and handling operations at reactor (AR) and away from reactor (AFR) on reactor site (RS) facilities are illustrated by the example of the Leningradskaya NPP and are typical for all NPPs with RBMK-1000. The current approach to spent fuel management at NPP sites is also presented. (author)

  15. Conceptual design of the Clinch River Breeder Reactor spent-fuel shipping cask

    International Nuclear Information System (INIS)

    Pope, R.B.; Diggs, J.M.

    1982-04-01

    Details of a baseline conceptual design of a spent fuel shipping cask for the Clinch River Breeder Reactor (CRBR) are presented including an assessment of shielding, structural, thermal, fabrication and cask/plant interfacing problems. A basis for continued cask development and for new technological development is established. Alternates to the baseline design are briefly presented. Estimates of development schedules, cask utilization and cost schedules, and of personnel dose commitments during CRBR in-plant handling of the cask are also presented

  16. Savannah River Site environmental report for 1995

    Energy Technology Data Exchange (ETDEWEB)

    Arnett, M.W.; Mamatey, A. [eds.

    1995-12-31

    The 1990s have brought dramatic change to the Savannah River Site (SRS) in its role as a key part of the U.S. Department of Energy`s (DOE) weapons complex. Shrinking federal budgets, sharp workforce reductions, the end of the Cold War, and a major shift in mission objectives have combined to severely test the mettle of SRS-South Carolina`s largest employer. But the sprawling 310-square-mile site`s employees have responded to the test in admirable fashion, effectively shifting their emphasis from weapons production to environmental restoration. This report describes the environmental report for the SRS for 1995.

  17. Savannah River Site environmental report for 1993

    International Nuclear Information System (INIS)

    Arnett, M.W.; Karapatakis, L.K.; Mamatey, A.R.

    1994-01-01

    Savannah River Site (SRS) conducts effluent monitoring and environmental surveillance to ensure the safety of the public and the well-being of the environment. DOE Order 5400,1, ''General Environmental Protection Program,'' requires the submission of an environmental report that documents the impact of facility operations on the environment and on public health. SRS has had an extensive environmental surveillance program in place since 1951 (before site startup). At that time, data generated by the on-site surveillance program were reported in site documents. Beginning in 1959, data from off-site environmental monitoring activities were presented in reports issued for public dissemination. Separate reporting of SRS's on- and off-site environmental monitoring activities continued until 1985, when data from both surveillance programs were merged into a single public document. The Savannah River Site Environmental Report for 1993 is an overview of effluent monitoring and environmental surveillance activities conducted on and in the vicinity of SRS from January 1 through December 31, 1993. For complete program descriptions, consult the ''SRS Environmental Monitoring Plan'' (WSRC-3Ql-2-1000). It documents the rationale and design criteria for the monitoring program, the frequency of monitoring and analysis, the specific analytical and sampling procedures, and the quality assurance requirements

  18. Savannah River Site environmental report for 1993

    Energy Technology Data Exchange (ETDEWEB)

    Arnett, M.W.; Karapatakis, L.K.; Mamatey, A.R. [eds.

    1994-08-01

    Savannah River Site (SRS) conducts effluent monitoring and environmental surveillance to ensure the safety of the public and the well-being of the environment. DOE Order 5400,1, ``General Environmental Protection Program,`` requires the submission of an environmental report that documents the impact of facility operations on the environment and on public health. SRS has had an extensive environmental surveillance program in place since 1951 (before site startup). At that time, data generated by the on-site surveillance program were reported in site documents. Beginning in 1959, data from off-site environmental monitoring activities were presented in reports issued for public dissemination. Separate reporting of SRS`s on- and off-site environmental monitoring activities continued until 1985, when data from both surveillance programs were merged into a single public document. The Savannah River Site Environmental Report for 1993 is an overview of effluent monitoring and environmental surveillance activities conducted on and in the vicinity of SRS from January 1 through December 31, 1993. For complete program descriptions, consult the ``SRS Environmental Monitoring Plan`` (WSRC-3Ql-2-1000). It documents the rationale and design criteria for the monitoring program, the frequency of monitoring and analysis, the specific analytical and sampling procedures, and the quality assurance requirements.

  19. Savannah River Site Environmental Report for 1994

    Energy Technology Data Exchange (ETDEWEB)

    Arnett, M.W.; Mamatey, A.; Spitzer, D.

    1994-12-16

    The mission at the Savannah River Site has changed from producing nuclear weapons materials for national defense to managing the waste it has generated, restoring the environment, and enhancing industrial development in and around the site. But no matter what the site`s mission is, it will continue to maintain its comprehensive environmental monitoring and surveillance program. In 1994, effluent monitoring and environmental surveillance were conducted within a 30,000-square-mile area in and around SRS that includes neighboring cities, towns, and counties in Georgia and South Carolina and extends up to 100 miles from the site. Thousands of samples of air, surface water, groundwater, foodstuffs, drinking water, wildlife, rainwater, soil, sediment, and vegetation were collected and analyzed for radioactive and nonradioactive contaminants.

  20. Siting factors for the Swedish deep repository for spent fuel

    International Nuclear Information System (INIS)

    Stroem, A.; Ericsson, Lars O.; Svemar, C.; Almen, K.E.; Andersson, Johan

    1998-01-01

    A project entitled Siting factors and criteria for site evaluation was initiated at the SKB in 1997. The project comprises an important part of the work of siting and site selection that is being pursued within SKB. The purpose of the project is to create a logical structure for the continued siting work, and its results should also be able to be used to assist in evaluating sites. The project will thereby also provide a means - in accordance with the Government's decision regarding Research Programme 95 - to obtain more detailed and quantified siting factors and criteria than those previously presented in the supplement to Research Programme 92. The overall goals of the project are to identify and quantify requirements and preferences regarding the properties of the rock and the soil from the perspectives of long-term safety, performance and planning and design of the rock works, and to identify siting factors and criteria. The latter should be able to be used to determine whether requirements and preferences are satisfied, both when screening sites for site investigation and after completed site investigation. Presented requirements, preferences, factors and criteria must be acceptable to national and municipal authorities or others with influence over the siting work. To start with, requirements and preferences regarding the performance of the rock in a deep repository have been clarified. These requirements and preferences are based on many years of experience of safety assessments and construction analyses within SKB. What is new here is the structuring that has been done, where a classification is made into different geoscientific disciplines, and the formalism that has been developed for the concepts requirements, preferences and performance. This is a prerequisite for a consistent and hopefully comprehensive set of requirements from a functional perspective. Work has continued on siting factors with reference to a coming site investigation programme. A

  1. Climatology of the Savannah River Plant site

    International Nuclear Information System (INIS)

    Hoel, D.D.

    1983-01-01

    This document is intended as a reference for those involved in environmental research, and preparing environmental and safety analysis reports about aspects of operations of production and support facilities at the Savannah River Plant (SRP). The information in this document is drawn from appropriate references and from the extensive meteorological data base collected on SRP. This document contains information on the climatological characteristics of the SRP site, as well as information on relative concentrations and deposition for specific radionuclides

  2. Watershed modeling at the Savannah River Site.

    Energy Technology Data Exchange (ETDEWEB)

    Vache, Kellie [Oregon State University

    2015-04-29

    The overall goal of the work was the development of a watershed scale model of hydrological function for application to the US Department of Energy’s (DOE) Savannah River Site (SRS). The primary outcomes is a grid based hydrological modeling system that captures near surface runoff as well as groundwater recharge and contributions of groundwater to streams. The model includes a physically-based algorithm to capture both evaporation and transpiration from forestland.

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

    International Nuclear Information System (INIS)

    1997-03-01

    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

  4. Characterization of stored defense production spent nulcear fuel and associated materials at Hanford Site, Richland Washington: Environmental assessment

    International Nuclear Information System (INIS)

    1995-03-01

    There are about 2,100 tonnes (2,300 tons) of defense production spent nuclear fuel stored in the 100-K Area Basins located along the south shore of the Columbia River in the northern part of the Hanford Site. Some of the fuel which has been in storage for a number of years is in poor condition and continues to deteriorate. The basins also contain fuel fragments and radioactively contaminated sludge. The DOE needs to characterize defense production spent nuclear fuel and associated materials stored on the Hanford Site. In order to satisfy that need, the Department of Energy (DOE) proposes to select, collect and transport samples of spent nuclear fuel and associated materials to the 327 Building for characterization. As a result of that characterization, modes of interim storage can be determined that would be compatible with the material in its present state and alternative treatment processes could be developed to permit a broader selection of storage modes. Environmental impacts of the proposed action were determined to be limited principally to radiation exposure of workers, which, however, were found to be small. No health effects among workers or the general public would be expected under routine operations. Implementation of the proposed action would not result in any impacts on cultural resources, threatened, endangered and candidate species, air or water quality, socioeconomic conditions, or waste management

  5. Savannah River Site 1996 epidemiologic surveillance report

    International Nuclear Information System (INIS)

    2000-01-01

    This report provides a summary of epidemiologic surveillance data collected from Savannah River Site from January 1, 1996 through December 31, 1996. The data were collected by a coordinator at Savannah River Site and submitted to the Epidemiologic Surveillance Data Center located at Oak Ridge Institute for Science and Education, where quality control procedures and preliminary data analyses were carried out. The analyses were interpreted and the final report prepared by the DOE Office of Epidemiologic Studies. The information in this report provides highlights of the data analyses conducted on the 1996 data collected from Savannah River Site. The main sections of the report include: work force characteristics; absences due to injury or illness lasting 5 or more consecutive workdays; workplace illnesses, injuries, and deaths that were reportable to the Occupational Safety and Health Administration (''OSHA-recordable'' events); and disabilities and deaths among current workers. The 1996 report includes a new section on time trends that provides comparative information on the health of the work force from 1994 through 1996

  6. Savannah River Site 1997 epidemiologic surveillance report

    International Nuclear Information System (INIS)

    2000-01-01

    This report provides a summary of epidemiologic surveillance data collected from Savannah River Site from January 1, 1997 through December 31, 1997. The data were collected by a coordinator at Savannah River Site and submitted to the Epidemiologic Surveillance Data Center located at Oak Ridge Institute for Science and Education, where quality control procedures and preliminary data analyses were carried out. The analyses were interpreted and the final report prepared by the DOE Office of Epidemiologic Studies. The information in this report provides highlights of the data analyses conducted on the 1997 data collected from Savannah River Site. The main sections of the report include: work force characteristics; absences due to injury or illness lasting 5 or more consecutive workdays; workplace illnesses, injuries, and deaths that were reportable to the Occupational Safety and Health Administration (''OSHA-recordable'' events); and disabilities and deaths among current workers. The 199 7 report includes a section on time trends that provides comparative information on the health of the work force from 1994 through 1997

  7. SAVANNAH RIVER SITE ENVIRONMENTAL REPORT FOR 2007

    International Nuclear Information System (INIS)

    Mamatey, A

    2008-01-01

    The Savannah River Site Environmental Report for 2007 (WSRC-STI-2008-00057) prepared for the US Department of Energy (DOE) according to requirements of DOE Order 231.1A, 'Environment, Safety and Health Reporting', and DOE Order 5400.5, 'Radiation Protection of the Public and Environment'. The report's purpose is to: (1) present summary environmental data that characterize site environmental management performance; (2) confirm compliance with environmental standards and requirements; (3) highlight significant programs and efforts; (4) assess the impact of SRS operations on the public and the environment

  8. Savannah River Site Environmental Report for 2004

    International Nuclear Information System (INIS)

    Mamatey, Albert R.

    2005-01-01

    The Savannah River Site Environmental Report for 2004 (WSRC-TR-2005-00005) is prepared for the U.S. Department of Energy (DOE) according to requirements of DOE Order 231.1A, ''Environment, Safety and Health Reporting,'' and DOE Order 5400.5, ''Radiation Protection of the Public and Environment''. The report's purpose is to present summary environmental data that characterize site environmental management performance; confirm compliance with environmental standards and requirements; highlight significant programs and efforts; and assess the impact of SRS operations on the public and the environment

  9. Savannah River Site environmental report for 1995

    International Nuclear Information System (INIS)

    Arnett, M.W.; Mamatey, A.

    1997-01-01

    The 1990s have brought dramatic change to the Savannah River Site (SRS) in its role as a key part of the U.S. Department of Energy's (DOE) weapons complex. Shrinking federal budgets, sharp workforce reductions, the end of the Cold War, and a major shift in mission objectives have combined to severely test the mettle of SRS-South Carolina's largest employer. But the sprawling 310-square-mile site's employees have responded to the test in admirable fashion, effectively shifting their emphasis from weapons production to environmental restoration. This report describes the environmental report for the SRS for 1995

  10. Savannah River Site Environmental Report for 2004

    Energy Technology Data Exchange (ETDEWEB)

    Mamatey, Albert R.

    2005-06-07

    The Savannah River Site Environmental Report for 2004 (WSRC-TR-2005-00005) is prepared for the U.S. Department of Energy (DOE) according to requirements of DOE Order 231.1A, ''Environment, Safety and Health Reporting,'' and DOE Order 5400.5, ''Radiation Protection of the Public and Environment''. The report's purpose is to present summary environmental data that characterize site environmental management performance; confirm compliance with environmental standards and requirements; highlight significant programs and efforts; and assess the impact of SRS operations on the public and the environment.

  11. SAVANNAH RIVER SITE ENVIRONMENTAL REPORT FOR 2007

    Energy Technology Data Exchange (ETDEWEB)

    Mamatey, A

    2008-08-27

    The Savannah River Site Environmental Report for 2007 (WSRC-STI-2008-00057) prepared for the US Department of Energy (DOE) according to requirements of DOE Order 231.1A, 'Environment, Safety and Health Reporting', and DOE Order 5400.5, 'Radiation Protection of the Public and Environment'. The report's purpose is to: (1) present summary environmental data that characterize site environmental management performance; (2) confirm compliance with environmental standards and requirements; (3) highlight significant programs and efforts; (4) assess the impact of SRS operations on the public and the environment.

  12. Savannah River Site Environmental Report for 1994

    International Nuclear Information System (INIS)

    Arnett, M.W.; Mamatey, A.; Spitzer, D.

    1994-01-01

    The mission at the Savannah River Site has changed from producing nuclear weapons materials for national defense to managing the waste it has generated, restoring the environment, and enhancing industrial development in and around the site. But no matter what the site's mission is, it will continue to maintain its comprehensive environmental monitoring and surveillance program. In 1994, effluent monitoring and environmental surveillance were conducted within a 30,000-square-mile area in and around SRS that includes neighboring cities, towns, and counties in Georgia and South Carolina and extends up to 100 miles from the site. Thousands of samples of air, surface water, groundwater, foodstuffs, drinking water, wildlife, rainwater, soil, sediment, and vegetation were collected and analyzed for radioactive and nonradioactive contaminants

  13. Postulated accident scenarios for the on-site transport of spent nuclear fuel

    International Nuclear Information System (INIS)

    Morandin, G.; Sauve, R.

    2004-01-01

    Once a spent fuel container is loaded with spent fuel it typically travels on-site to a processing building for permanent lid attachment. During on-site transport a lid clamp is utilized to ensure the container lid remains in place. The safe on-site transport of spent nuclear fuel must rely on the structural integrity of the transport container and system of transport. Regard for on-site traffic and safe, efficient travel routes are important and manageable with well thought-out planning. Non-manageable incidences, such as flying debris from tornado force winds or postulated blasts in proximity to the transport container, that may result in high velocity impact and shock loading on the transport system must be considered. This paper consists of simulations that consider these types of postulated accident scenarios using detailed nonlinear finite element techniques

  14. Savannah River site environmental report for 1996

    Energy Technology Data Exchange (ETDEWEB)

    Arnett, M.; Mamatey, A. [eds.

    1998-12-31

    The mission at the Savannah River Site (SRS) has changed from the production of nuclear weapons materials for national defense to the management of site-generated waste, restoration of the surrounding environment, and the development of industry in and around the site. However, SRS-through its prime operating contractor, Westinghouse Savannah River Company (WSRC)-continues to maintain a comprehensive environmental monitoring program. In 1996, effluent monitoring and environmental surveillance were conducted within a 31,000-square-mile area in and around SRS that includes neighboring cities, towns, and counties in Georgia and South Carolina and extends up to 100 miles from the site. Though the environmental monitoring program was streamlined in 1996-to improve its cost-effectiveness without compromising data quality or reducing its overall ability to produce critical information-thousands of samples of air, surface water, groundwater, food products, drinking water, wildlife, rainwater, soil, sediment, and vegetation were collected and analyzed for radioactive and nonradioactive contaminants.

  15. Savannah River site environmental report for 1996

    International Nuclear Information System (INIS)

    Arnett, M.; Mamatey, A.

    1998-01-01

    The mission at the Savannah River Site (SRS) has changed from the production of nuclear weapons materials for national defense to the management of site-generated waste, restoration of the surrounding environment, and the development of industry in and around the site. However, SRS-through its prime operating contractor, Westinghouse Savannah River Company (WSRC)-continues to maintain a comprehensive environmental monitoring program. In 1996, effluent monitoring and environmental surveillance were conducted within a 31,000-square-mile area in and around SRS that includes neighboring cities, towns, and counties in Georgia and South Carolina and extends up to 100 miles from the site. Though the environmental monitoring program was streamlined in 1996-to improve its cost-effectiveness without compromising data quality or reducing its overall ability to produce critical information-thousands of samples of air, surface water, groundwater, food products, drinking water, wildlife, rainwater, soil, sediment, and vegetation were collected and analyzed for radioactive and nonradioactive contaminants

  16. Cesium in the Savannah River Site environment

    International Nuclear Information System (INIS)

    Carlton, W.H.; Bauer, L.R.; Evans, A.G.; Geary, L.A.; Murphy, C.E. Jr.; Pinder, J.E.; Strom, R.N.

    1992-03-01

    Cesium in the Savannah River Site Environment is published as a part of the Radiological Assessment Program (RAP). It is the fourth in a series of eight documents on individual radioisotopes released to the environment as a result of Savannah River Site (SRS) operations. The earlier documents describe the environmental consequences of tritium, iodine, and uranium. Documents on plutonium, strontium, carbon, and technetium will be published in the future. These are dynamic documents and current plans call for revising and updating each one on a two-year schedule.Radiocesium exists in the environment as a result of above-ground nuclear weapons tests, the Chernobyl accident, the destruction of satellite Cosmos 954, small releases from reactors and reprocessing plants, and the operation of industrial, medical, and educational facilities. Radiocesium has been produced at SRS during the operation of five production reactors. Several hundred curies of 137 Cs was released into streams in the late 50s and 60s from leaking fuel elements. Smaller quantities were released from the fuel reprocessing operations. About 1400 Ci of 137 Cs was released to seepage basins where it was tightly bound by clay in the soil. A much smaller quantity, about four Ci. was released to the atmosphere. Radiocesium concentration and mechanisms for atmospheric, surface water, and groundwater have been extensively studied by Savannah River Technology Center (SRTC) and ecological mechanisms have been studied by Savannah River Ecology Laboratory (SREL). The overall radiological impact of SRS releases on the offsite maximum individual can be characterized by total doses of 033 mrem (atmospheric) and 60 mrem (liquid), compared with a dose of 12,960 mrem from non-SRS sources during the same period of time. Isotope 137 Cs releases have resulted in a negligible risk to the environment and the population it supports

  17. Cesium in the Savannah River Site environment

    Energy Technology Data Exchange (ETDEWEB)

    Carlton, W.H.; Bauer, L.R.; Evans, A.G.; Geary, L.A.; Murphy, C.E. Jr.; Pinder, J.E.; Strom, R.N.

    1992-03-01

    Cesium in the Savannah River Site Environment is published as a part of the Radiological Assessment Program (RAP). It is the fourth in a series of eight documents on individual radioisotopes released to the environment as a result of Savannah River Site (SRS) operations. The earlier documents describe the environmental consequences of tritium, iodine, and uranium. Documents on plutonium, strontium, carbon, and technetium will be published in the future. These are dynamic documents and current plans call for revising and updating each one on a two-year schedule.Radiocesium exists in the environment as a result of above-ground nuclear weapons tests, the Chernobyl accident, the destruction of satellite Cosmos 954, small releases from reactors and reprocessing plants, and the operation of industrial, medical, and educational facilities. Radiocesium has been produced at SRS during the operation of five production reactors. Several hundred curies of [sup 137]Cs was released into streams in the late 50s and 60s from leaking fuel elements. Smaller quantities were released from the fuel reprocessing operations. About 1400 Ci of [sup 137]Cs was released to seepage basins where it was tightly bound by clay in the soil. A much smaller quantity, about four Ci. was released to the atmosphere. Radiocesium concentration and mechanisms for atmospheric, surface water, and groundwater have been extensively studied by Savannah River Technology Center (SRTC) and ecological mechanisms have been studied by Savannah River Ecology Laboratory (SREL). The overall radiological impact of SRS releases on the offsite maximum individual can be characterized by total doses of 033 mrem (atmospheric) and 60 mrem (liquid), compared with a dose of 12,960 mrem from non-SRS sources during the same period of time. Isotope [sup 137]Cs releases have resulted in a negligible risk to the environment and the population it supports.

  18. Cesium in the Savannah River Site environment

    Energy Technology Data Exchange (ETDEWEB)

    Carlton, W.H.; Bauer, L.R.; Evans, A.G.; Geary, L.A.; Murphy, C.E. Jr.; Pinder, J.E.; Strom, R.N.

    1992-03-01

    Cesium in the Savannah River Site Environment is published as a part of the Radiological Assessment Program (RAP). It is the fourth in a series of eight documents on individual radioisotopes released to the environment as a result of Savannah River Site (SRS) operations. The earlier documents describe the environmental consequences of tritium, iodine, and uranium. Documents on plutonium, strontium, carbon, and technetium will be published in the future. These are dynamic documents and current plans call for revising and updating each one on a two-year schedule.Radiocesium exists in the environment as a result of above-ground nuclear weapons tests, the Chernobyl accident, the destruction of satellite Cosmos 954, small releases from reactors and reprocessing plants, and the operation of industrial, medical, and educational facilities. Radiocesium has been produced at SRS during the operation of five production reactors. Several hundred curies of {sup 137}Cs was released into streams in the late 50s and 60s from leaking fuel elements. Smaller quantities were released from the fuel reprocessing operations. About 1400 Ci of {sup 137}Cs was released to seepage basins where it was tightly bound by clay in the soil. A much smaller quantity, about four Ci. was released to the atmosphere. Radiocesium concentration and mechanisms for atmospheric, surface water, and groundwater have been extensively studied by Savannah River Technology Center (SRTC) and ecological mechanisms have been studied by Savannah River Ecology Laboratory (SREL). The overall radiological impact of SRS releases on the offsite maximum individual can be characterized by total doses of 033 mrem (atmospheric) and 60 mrem (liquid), compared with a dose of 12,960 mrem from non-SRS sources during the same period of time. Isotope {sup 137}Cs releases have resulted in a negligible risk to the environment and the population it supports.

  19. Savannah River Site environmental report for 1991

    Energy Technology Data Exchange (ETDEWEB)

    Arnett, M.W.; Karapatakis, L.K.; Mamatey, A.R.; Todd, J.L.

    1991-01-01

    This report describes environmental activities conducted on and in the vicinity of the Savannah River Site (SRS) in Aiken, S.C., from Jan. 1 to Dec. 31, 1991, with an update on compliance activities through April 1, 1992. The report is a single volume with a separate summary pamphlet highlighting the major findings for 1991. The report is divided into an executive summary and 14 chapters containing information on environmental compliance issues, environmental monitoring methods and programs, and environmental research activities for 1991, as well as historical data from previous years. Analytical results, figures, charts, and data tables relevant to the environmental monitoring program for 1991 at SRS are included.

  20. Savannah River Site environmental report for 1991

    International Nuclear Information System (INIS)

    Arnett, M.W.; Karapatakis, L.K.; Mamatey, A.R.; Todd, J.L.

    1991-01-01

    This report describes environmental activities conducted on and in the vicinity of the Savannah River Site (SRS) in Aiken, S.C., from Jan. 1 to Dec. 31, 1991, with an update on compliance activities through April 1, 1992. The report is a single volume with a separate summary pamphlet highlighting the major findings for 1991. The report is divided into an executive summary and 14 chapters containing information on environmental compliance issues, environmental monitoring methods and programs, and environmental research activities for 1991, as well as historical data from previous years. Analytical results, figures, charts, and data tables relevant to the environmental monitoring program for 1991 at SRS are included

  1. Electronic Denitration Savannah River Site Radioactive Waste

    International Nuclear Information System (INIS)

    Hobbs, D.T.

    1995-01-01

    Electrochemical destruction of nitrate in radioactive Savannah River Site Waste has been demonstrated in a bench-scale flow cell reactor. Greater than 99% of the nitrate can be destroyed in either an undivided or a divided cell reactor. The rate of destruction and the overall power consumption is dependent on the cell configuration and electrode materials. The fastest rate was observed using an undivided cell equipped with a nickel cathode and nickel anode. The use of platinized titanium anode increased the energy requirement and costs compared to a nickel anode in both the undivided and divided cell configurations

  2. Savannah River Site environmental report for 1988

    Energy Technology Data Exchange (ETDEWEB)

    Cummins, C.L.; Hetrick, C.S.; Stevenson, D.A. (eds.); Davis, H.A.; Martin, D.K.; Todd, J.L.

    1989-01-01

    This volume of Savannah River Site Environmental report for 1988 (WSRC-RP-89-59-1) contains the figures and tables referenced in Volume 1. The figures contain graphic illustrations of sample locations and/or data. The tables contain summaries of the following types of data: Federal and State standards and guides applicable to SRS operations; concentrations of radioactivity in environmental media; the quantity of radioactivity released to the environment from SRS operations; offsite radiation dose commitments from SRS operations; measurements of physical properties, chemicals, and metals concentrations in environmental media; and interlaboratory comparison of analytical results.

  3. Spent-fuel storage - MRS and/or on-site?

    International Nuclear Information System (INIS)

    Fuierer, A.A.

    1991-01-01

    The US government through the Office of Civilian Radioactive Waste Management (OCRWM) is seeking by the use of an authorized negotiator a site for a monitored retrievable storage (MRS) facility. Based on a public information document provided by the office of the negotiator, the MRS will be an integral part of the federal system for safe and permanent disposal of the nation's high-level radioactive wastes. It is planned that the MRS will accept and store spent fuel above ground until a repository opens and spent fuel that has been stored is shipped from the MRS to the repository. Additional spent fuel stored at reactor sites will be shipped to the MRS, which will be used as a staging area to assemble dedicated trains for shipment to the repository. The intent of the MRS is to reduce utilities' needs to expand on-site storage of spent fuel. A utility viewpoint may emphasize an alternate set of priorities. The waste management system must be considered as an overall system involving both the utility and DOE that begins with the first discharge of spent nuclear fuel from a commercial reactor and ends with high-level waste in a final repository. Many studies have been made on individual components of a waste system. This study, with the benefit of past hands-on experience as a guide, looks at costs and reliability for a total system concept with particular emphasis on the interface between the utility and Department of Energy

  4. Savannah River Site Environmental Implementation Plan

    International Nuclear Information System (INIS)

    1989-01-01

    Formal sitewide environmental planning at the . Savannah River Site (SRS) began in 1986 with the development and adoption of the Strategic Environmental Plan. The Strategic Environmental Plan describes the philosophy, policy, and overall program direction of environmental programs for the operation of the SRS. The Strategic Environmental Plan (Volume 2) provided the basis for development of the Environmental Implementation Plan (EIP). The EIP is the detailed, comprehensive environmental master plan for operating contractor organizations at the SRS. The EIP provides a process to ensure that all environmental requirements and obligations are being met by setting specific measurable goals and objectives and strategies for implementation. The plan is the basis for justification of site manpower and funding requests for environmental projects and programs over a five-year planning period

  5. Savannah River Site environmental report for 1989

    International Nuclear Information System (INIS)

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

    1989-01-01

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

  6. Waste reduction at the Savannah River Site

    International Nuclear Information System (INIS)

    Stevens, W.E.; Lee, R.A.; Reynolds, R.W.

    1990-01-01

    The Savannah River Site (SRS) is a key installation for the production and research of nuclear materials for national defense and peace time applications and has been operating a full nuclear fuel cycle since the early 1950s. Wastes generated include high level radioactive, transuranic, low level radioactive, hazardous, mixed, sanitary, and aqueous wastes. Much progress has been made during the last several years to reduce these wastes including management systems, characterization, and technology programs. The reduction of wastes generated and the proper handling of the wastes have always been a part of the Site's operation. This paper summarizes the current status and future plans with respect to waste reduction to waste reduction and reviews some specific examples of successful activities

  7. Savannah River Site Environmental Report For 2008

    International Nuclear Information System (INIS)

    Mamatey, A.

    2009-01-01

    The Savannah River Site Environmental Report for 2008 (SRNS-STI-2009-00190) is prepared for the U.S. Department of Energy (DOE) according to requirements of DOE Order 231.1A, 'Environment, Safety and Health Reporting,' and DOE Order 5400.5, 'Radiation Protection of the Public and Environment.' The annual SRS Environmental Report has been produced for more than 50 years. Several hundred copies are distributed each year to government officials, universities, public libraries, environmental and civic groups, news media, and interested individuals. The report's purpose is to: (1) present summary environmental data that characterize site environmental management performance; (2) confirm compliance with environmental standards and requirements; and (3) highlight significant programs and efforts

  8. Savannah River Site environmental report for 1989

    Energy Technology Data Exchange (ETDEWEB)

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

    1989-01-01

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

  9. Savannah River Site Environmental Implementation Plan

    Energy Technology Data Exchange (ETDEWEB)

    1989-08-01

    Formal sitewide environmental planning at the . Savannah River Site (SRS) began in 1986 with the development and adoption of the Strategic Environmental Plan. The Strategic Environmental Plan describes the philosophy, policy, and overall program direction of environmental programs for the operation of the SRS. The Strategic Environmental Plan (Volume 2) provided the basis for development of the Environmental Implementation Plan (EIP). The EIP is the detailed, comprehensive environmental master plan for operating contractor organizations at the SRS. The EIP provides a process to ensure that all environmental requirements and obligations are being met by setting specific measurable goals and objectives and strategies for implementation. The plan is the basis for justification of site manpower and funding requests for environmental projects and programs over a five-year planning period.

  10. SAVANNAH RIVER SITE ENVIRONMENTAL REPORT FOR 2005

    Energy Technology Data Exchange (ETDEWEB)

    Mamatey, A

    2006-07-18

    The ''Savannah River Site Environmental Report for 2005'' (WSRC-TR-2006-00007) is prepared for the U.S. Department of Energy (DOE) according to requirements of DOE Order 231.1A, ''Environment, Safety and Health Reporting'', and DOE Order 5400.5, ''Radiation Protection of the Public and Environment''. The report's purpose is to: present summary environmental data that characterize site environmental management performance; confirm compliance with environmental standards and requirements; highlight significant programs and efforts; and assess the impact of SRS operations on the public and the environment.

  11. Savannah River Site environmental implementation plan

    International Nuclear Information System (INIS)

    1989-01-01

    Formal sitewide environmental planning at the Savannah River Site (SRS) began in 1986 with the development and adoption of the Strategic Environmental Plan. The Strategic Environmental Plan describes the philosophy, policy, and overall program direction of environmental programs for the operation of the SRS. The Strategic Environmental Plan provided the basis for development of the Environmental Implementation Plan (EIP). The EIP is the detailed, comprehensive environmental master plan for operating contractor organizations at the SRS. The EIP provides a process to ensure that all environmental requirements and obligations are being met by setting specific measurable goals and objectives and strategies for implementation. The plan is the basis for justification of site manpower and funding requests for environmental projects and programs over a five-year planning period

  12. SAVANNAH RIVER SITE ENVIRONMENTAL REPORT FOR 2008

    Energy Technology Data Exchange (ETDEWEB)

    Mamatey, A.

    2009-09-15

    The Savannah River Site Environmental Report for 2008 (SRNS-STI-2009-00190) is prepared for the U.S. Department of Energy (DOE) according to requirements of DOE Order 231.1A, 'Environment, Safety and Health Reporting,' and DOE Order 5400.5, 'Radiation Protection of the Public and Environment.' The annual SRS Environmental Report has been produced for more than 50 years. Several hundred copies are distributed each year to government officials, universities, public libraries, environmental and civic groups, news media, and interested individuals. The report's purpose is to: (1) present summary environmental data that characterize site environmental management performance; (2) confirm compliance with environmental standards and requirements; and (3) highlight significant programs and efforts.

  13. Optimization Review: Carson River Mercury Superfund Site, Carson City, Nevada

    Science.gov (United States)

    The Carson River Mercury Site (CRMS) (Figure 1) is located in northwest Nevada and was designated a Superfund site in 1990 because of elevated mercury concentrations observed in surface water, sediments and biota inhabiting the site.

  14. Savannah River Site's Site Specific Plan

    Energy Technology Data Exchange (ETDEWEB)

    1991-08-01

    This Site Specific Plan (SSP) has been prepared by the Savannah River Site (SRS) in order to show the Environmental Restoration and Waste Management activities that were identified during the preparation of the Department of Energy-Headquarters (DOE-HQ) Environmental Restoration and Waste Management Five-Year Plan (FYP) for FY 1992--1996. The SSP has been prepared in accordance with guidance received from DOE-HQ. DOE-SR is accountable to DOE-HQ for the implementation of this plan. The purpose of the SSP is to develop a baseline for policy, budget, and schedules for the DOE Environmental Restoration and Waste Management activities. The plan explains accomplishments since the Fiscal Year (FY) 1990 plan, demonstrates how present and future activities are prioritized, identifies currently funded activities and activities that are planned to be funded in the upcoming fiscal year, and describes future activities that SRS is considering.

  15. Corrosion surveillance program of aluminum spent fuel elements in wet storage sites

    International Nuclear Information System (INIS)

    Linardi, E; Haddad, R

    2012-01-01

    Due to different degradation issues observed in aluminum-clad spent fuel during long term storage in water, the IAEA implemented in 1996 a Coordinated Research Project (CRP) and a Regional Project for Latin America, on Corrosion of Research Reactor Aluminum Clad Spent Fuel in Water. Argentine has been among the participant countries of these projects, carrying out spent fuel corrosion surveillance activities in its storage facilities. As a result of the research a large database on corrosion of aluminum-clad fuel has been generated. It was determined that the main types of corrosion affecting the spent fuel are pitting and galvanic corrosion due to contact with stainless steel. It was concluded that the quality of the water is the critical factor to control in a spent fuel storage facility. Another phase of the program is being conducted currently, which began in 2011 with the immersion of test racks in the RA1 reactor pool, and in the Research Reactor Spent Fuel Storage Facility (FACIRI), located in Ezeiza Atomic Center. This paper presents the results of the chemical analysis of the water performed so far, and its relationship with the examination of the coupons extracted from the sites (author)

  16. Safeguards for final disposal of spent nuclear fuel. Methods and technologies for the Olkiluoto site

    International Nuclear Information System (INIS)

    Okko, O.

    2003-05-01

    The final disposal of the nuclear material shall introduce new safeguards concerns which have not been addressed previously in IAEA safeguards approaches for spent fuel. The encapsulation plant to be built at the site will be the final opportunity for verification of spent fuel assemblies prior to their transfer to the geological repository. Moreover, additional safety and safeguards measures are considered for the underground repository. Integrated safeguards verification systems will also concentrate on environmental monitoring to observe unannounced activities related to possible diversion schemes at the repository site. The final disposal of spent nuclear fuel in geological formation will begin in Finland within 10 years. After the geological site investigations and according to legal decision made in 2001, the final repository of the spent nuclear fuel shall be located at the Olkiluoto site in Eurajoki. The next phase of site investigations contains the construction of an underground facility, called ONKALO, for rock characterisation purposes. The excavation of the ONKALO is scheduled to start in 2004. Later on, the ONKALO may form a part of the final repository. The plans to construct the underground facility for nuclear material signify that the first safeguards measures, e.g. baseline mapping of the site area, need to take prior to the excavation phase. In order to support the development and implementation of the regulatory control of the final disposal programme, STUK established an independent expert group, LOSKA. The group should support the STUK in the development of the technical safeguards requirements, in the implementation of the safeguards and in the evaluation of the plans of the facility operator. This publication includes four background reports produced by this group. The first of these 'NDA verification of spent fuel, monitoring of disposal canisters, interaction of the safeguards and safety issues in the final disposal' describes the new

  17. Savannah River Site Approved Site Treatment Plan, 1998 Annual Update

    Energy Technology Data Exchange (ETDEWEB)

    Lawrence, B. [Westinghouse Savannah River Company, AIKEN, SC (United States); Berry, M.

    1998-03-01

    The U.S. Department of Energy, Savannah River Operations Office (DOE- SR),has prepared the Site Treatment Plan (STP) for Savannah River Site (SRS) mixed wastes in accordance with RCRA Section 3021(b), and SCDHEC has approved the STP (except for certain offsite wastes) and issued an order enforcing the STP commitments in Volume I. DOE-SR and SCDHEC agree that this STP fulfills the requirements contained in the FFCAct, RCRA Section 3021, and therefore,pursuant to Section 105(a) of the FFCAct (RCRA Section 3021(b)(5)), DOE`s requirements are to implement the plan for the development of treatment capacities and technologies pursuant to RCRA Section 3021.Emerging and new technologies not yet considered may be identified to manage waste more safely, effectively, and at lower cost than technologies currently identified in the plan. DOE will continue to evaluate and develop technologies that offer potential advantages in public acceptance, privatization, consolidation, risk abatement, performance, and life-cycle cost. Should technologies that offer such advantages be identified, DOE may request a revision/modification of the STP in accordance with the provisions of Consent Order 95-22-HW.The Compliance Plan Volume (Volume I) identifies project activity schedule milestones for achieving compliance with Land Disposal Restrictions (LDR). Information regarding the technical evaluation of treatment options for SRS mixed wastes is contained in the Background Volume (Volume II) and is provided for information.

  18. Seismic hazard analysis for the NTS spent reactor fuel test site

    International Nuclear Information System (INIS)

    Campbell, K.W.

    1980-01-01

    An experiment is being directed at the Nevada Test Site to test the feasibility for storage of spent fuel from nuclear reactors in geologic media. As part of this project, an analysis of the earthquake hazard was prepared. This report presents the results of this seismic hazard assessment. Two distinct components of the seismic hazard were addressed: vibratory ground motion and surface displacement

  19. SAVANNAH RIVER SITE ENVIRONMENTAL REPORT FOR 2010

    Energy Technology Data Exchange (ETDEWEB)

    Mamatey, A.; Dunaway-Ackerman, J.

    2011-08-16

    This report was prepared in accordance with U.S. Department of Energy (DOE) Order 231.1A, 'Environment, Safety and Health Reporting,' to present summary environmental data for the purpose of: (a) characterizing site's environmental management performance; (b) summarizing environmental occurrences and responses reported during the calendar year; (c) describing compliance status with respect to environmental standards and requirements; and (d) highlighting significant site programs and efforts. This report is the principal document that demonstrates compliance with the requirements of DOE Order 5400.5, 'Radiation Protection of the Public and the Environment,' and is a key component of DOE's effort to keep the public informed of environmental conditions at Savannah River Site (SRS). SRS has four primary missions: (1) Environmental Management - Cleaning up the legacy of the Cold War efforts and preparing decommissioned facilities and areas for long-term stewardship; (2) Nuclear Weapons Stockpile Support - Meeting the needs of the U.S. nuclear weapons stockpile through the tritium programs of the National Nuclear Security Administration (NNSA); (3) Nuclear Nonproliferation Support - Meeting the needs of the NNSA's nuclear nonproliferation programs by safely storing and dispositioning excess special nuclear materials; and (4) Research and Development - Supporting the application of science by the Savannah River National Laboratory (SRNL) to meet the needs of SRS, the DOE complex, and other federal agencies During 2010, SRS worked to fulfill these missions and position the site for future operations. SRS continued to work with the South Carolina Department of Health and Environmental Control (SCDHEC), the Environmental Protection Agency (EPA), and the Nuclear Regulatory Commission to find and implement solutions and schedules for waste management and disposition. As part of its mission to clean up the Cold War legacy, SRS will continue

  20. The independent relationship between trouble controlling Facebook use, time spent on the site and distress.

    Science.gov (United States)

    Muench, Fredrick; Hayes, Marie; Kuerbis, Alexis; Shao, Sijing

    2015-09-01

    There is an emerging literature base on the relationship between maladaptive traits and "addiction" to social networking sites. These studies have operationalized addiction as either spending excessive amounts of time on social networking sites (SNS) or trouble controlling SNS use, but have not assessed the unique contribution of each of these constructs on outcomes in the same models. Moreover, these studies have exclusively been conducted with younger people rather than a heterogeneous sample. This study examined the independent relationship of a brief Facebook addiction scale, time spent on Facebook, and Facebook checking on positive and negative social domains, while controlling for self-esteem and social desirability. Participants were recruited using e-mail, SNS posts and through Amazon's MTurk system. The sample included 489 respondents ages from 18 to approximately 70, who completed a 10-15 minute survey. Results indicate that neither time spent on Facebook nor Facebook checking was significantly associated with either self-esteem, fear of negative social evaluation or social comparison, while SNS addiction symptoms were each independently associated with Facebook usage. Neither time spent on Facebook nor SNS addiction symptoms were associated with positive social relationships. Overall results suggest that time on SNS and trouble controlling use should be considered independent constructs and that interventions should target underlying loss of control as the primary intervention target above ego syntonic time spent on the site.

  1. The independent relationship between trouble controlling Facebook use, time spent on the site and distress

    Science.gov (United States)

    Muench, Fredrick; Hayes, Marie; Kuerbis, Alexis; Shao, Sijing

    2015-01-01

    Background and Aims There is an emerging literature base on the relationship between maladaptive traits and “addiction” to social networking sites. These studies have operationalized addiction as either spending excessive amounts of time on social networking sites (SNS) or trouble controlling SNS use, but have not assessed the unique contribution of each of these constructs on outcomes in the same models. Moreover, these studies have exclusively been conducted with younger people rather than a heterogeneous sample. This study examined the independent relationship of a brief Facebook addiction scale, time spent on Facebook, and Facebook checking on positive and negative social domains, while controlling for self-esteem and social desirability. Methods Participants were recruited using e-mail, SNS posts and through Amazon’s MTurk system. The sample included 489 respondents ages from 18 to approximately 70, who completed a 10–15 minute survey. Results Results indicate that neither time spent on Facebook nor Facebook checking was significantly associated with either self-esteem, fear of negative social evaluation or social comparison, while SNS addiction symptoms were each independently associated with Facebook usage. Neither time spent on Facebook nor SNS addiction symptoms were associated with positive social relationships. Discussion Overall results suggest that time on SNS and trouble controlling use should be considered independent constructs and that interventions should target underlying loss of control as the primary intervention target above ego syntonic time spent on the site. PMID:26551906

  2. Robotics at Savannah River site: activity report

    International Nuclear Information System (INIS)

    Byrd, J.S.

    1984-09-01

    The objectives of the Robotics Technology Group at the Savannah River Laboratory are to employ modern industrial robots and to develop unique automation and robotic systems to enhance process operations at the Savannah River site (SRP and SRL). The incentives are to improve safety, reduce personnel radiation exposure, improve product quality and productivity, and to reduce operating costs. During the past year robotic systems have been installed to fill chemical dilution vials in a SRP laboratory at 772-F and remove radioactive waste materials in the SRL Californium Production Facility at 773-A. A robotic system to lubricate an extrusion press has been developed and demonstrated in the SRL robotics laboratory and is scheduled for installation at the 321-M fuel fabrication area. A mobile robot was employed by SRP for a radiation monitoring task at a waste tank top in H-Area. Several other robots are installed in the SRL robotics laboratories and application development programs are underway. The status of these applications is presented in this report

  3. Mammals of the Savannah River Site

    International Nuclear Information System (INIS)

    Cothran, E.G.; Smith, M.H.; Wolff, J.O.; Gentry, J.B.

    1991-01-01

    This book is designed to be used as a field guide, reference book, bibliography, and introduction to the basic biology and ecology of the 54 mammal species that currently or potentially exist on or near the Savannah River Site (SRS). For 50 of these species, we present basic descriptions, distinguishing morphological features, distribution and habitat preferences, food habits, reproductive biology, social behavior, ecological relationships with other species, and economic importance to man. For those species that have been studied on the SRS, we summarize the results of these studies. Keys and illustrations are provided for whole body and skull identification. A selected glossary defines technical terminology. Illustrations of tracks of the more common larger mammals will assist in field identifications. We also summarize the results of two major long-term SRS studies, ''The Forbearer Census'' and ''White-tailed Deer Studies''. A cross-indexed list of over 300 SRS publications on mammals classifies each publication by 23 categories such as habitat, reproduction, genetics, etc., and also for each mammal species. The 149 Master's theses and Ph.D. dissertations that have been conducted at the Savannah River Ecology Laboratory are provided as additional references

  4. Mammals of the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Cothran, E.G.; Smith, M.H.; Wolff, J.O.; Gentry, J.B.

    1991-01-01

    This book is designed to be used as a field guide, reference book, bibliography, and introduction to the basic biology and ecology of the 54 mammal species that currently or potentially exist on or near the Savannah River Site (SRS). For 50 of these species, we present basic descriptions, distinguishing morphological features, distribution and habitat preferences, food habits, reproductive biology, social behavior, ecological relationships with other species, and economic importance to man. For those species that have been studied on the SRS, we summarize the results of these studies. Keys and illustrations are provided for whole body and skull identification. A selected glossary defines technical terminology. Illustrations of tracks of the more common larger mammals will assist in field identifications. We also summarize the results of two major long-term SRS studies, The Forbearer Census'' and White-tailed Deer Studies''. A cross-indexed list of over 300 SRS publications on mammals classifies each publication by 23 categories such as habitat, reproduction, genetics, etc., and also for each mammal species. The 149 Master's theses and Ph.D. dissertations that have been conducted at the Savannah River Ecology Laboratory are provided as additional references.

  5. Mammals of the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Cothran, E.G.; Smith, M.H.; Wolff, J.O.; Gentry, J.B.

    1991-12-31

    This book is designed to be used as a field guide, reference book, bibliography, and introduction to the basic biology and ecology of the 54 mammal species that currently or potentially exist on or near the Savannah River Site (SRS). For 50 of these species, we present basic descriptions, distinguishing morphological features, distribution and habitat preferences, food habits, reproductive biology, social behavior, ecological relationships with other species, and economic importance to man. For those species that have been studied on the SRS, we summarize the results of these studies. Keys and illustrations are provided for whole body and skull identification. A selected glossary defines technical terminology. Illustrations of tracks of the more common larger mammals will assist in field identifications. We also summarize the results of two major long-term SRS studies, ``The Forbearer Census`` and ``White-tailed Deer Studies``. A cross-indexed list of over 300 SRS publications on mammals classifies each publication by 23 categories such as habitat, reproduction, genetics, etc., and also for each mammal species. The 149 Master`s theses and Ph.D. dissertations that have been conducted at the Savannah River Ecology Laboratory are provided as additional references.

  6. Savannah River Site Environmental Report for 2003

    International Nuclear Information System (INIS)

    A. MAMATEY

    2003-01-01

    The ''Savannah River Site Environmental Report for 2003'' (WSRC-TR-2004-00015) is prepared for the U.S. Department of Energy (DOE) according to requirements of DOE Order 231.1, ''Environment, Safety and Health Reporting'', and DOE Order 5400.5, ''Radiation Protection of the Public and Environment''. The report's purpose is to: (1) present summary environmental data that characterize site environmental management performance; (2) confirm compliance with environmental standards and requirements; (3) highlight significant programs and efforts; and (4) assess the impact of SRS operations on the public and the environment. This year's report reflects a continuing effort (begun in 2001) to streamline the document and thereby increase its cost effectiveness--without omitting valuable technical data. To that end each author will continue to work toward presenting results in summary fashion, focusing on historical trends. Complete data tables again are included on the CD inside the back cover of the report. The CD also features an electronic version of the report; an appendix of site, environmental sampling location, dose, and groundwater maps; and complete 2003 reports from a number of other SRS organizations

  7. Savannah River Site Environmental Report for 2003

    Energy Technology Data Exchange (ETDEWEB)

    A. MAMATEY

    2003-01-01

    The ''Savannah River Site Environmental Report for 2003'' (WSRC-TR-2004-00015) is prepared for the U.S. Department of Energy (DOE) according to requirements of DOE Order 231.1, ''Environment, Safety and Health Reporting'', and DOE Order 5400.5, ''Radiation Protection of the Public and Environment''. The report's purpose is to: (1) present summary environmental data that characterize site environmental management performance; (2) confirm compliance with environmental standards and requirements; (3) highlight significant programs and efforts; and (4) assess the impact of SRS operations on the public and the environment. This year's report reflects a continuing effort (begun in 2001) to streamline the document and thereby increase its cost effectiveness--without omitting valuable technical data. To that end each author will continue to work toward presenting results in summary fashion, focusing on historical trends. Complete data tables again are included on the CD inside the back cover of the report. The CD also features an electronic version of the report; an appendix of site, environmental sampling location, dose, and groundwater maps; and complete 2003 reports from a number of other SRS organizations.

  8. Deer monitoring at the Savannah River Site

    International Nuclear Information System (INIS)

    Fledderman, P.D.

    1992-01-01

    To protect public health, all deer and feral hogs harvested at the Savannah River Site (SRS) during controlled hunts are monitored for Cs-137. A new monitoring program has been developed by the Environmental Monitoring Section (EMS). To provide increased confidence in dose data and compliance with regulations, many changes have been made to the deer and hog monitoring program. Using field count information, a computerized database determines Cs-137 concentration and calculates the committed effective dose equivalent (CEDE) resulting from consumption of the animal. The database then updates each hunter's cumulative CEDE in real time. Also, enhancements to the instrument calibration and quality control portions of the monitoring program were implemented. These include improved monitor calibration, intercomparison of field results from the same animal using different detectors, and regular use of check sources to verify equipment performance. With these program changes, EMS can produce more accurate and verifiable dose data

  9. Advanced separations at Savannah River site

    Energy Technology Data Exchange (ETDEWEB)

    Thompson, M.C. [Savannah River Technology Center, Aiken, SC (United States)

    1997-10-01

    The Savannah River Site (SRS) has many waste streams that are contaminated with radionuclides and/or hazardous materials that must be treated to remove the radioactivity (Cs, Sr, tritium, actinides) and hazardous components (poly-chlorinated biphenyls [PCBs], cyanide, metal ions). This task provides testbeds for ESP-developed materials and technology using actual SRS waste streams. The work includes different SRS waste streams: high-level waste (HLW) solutions currently stored in underground tanks onsite, water recycled from the waste vitrification plant, groundwater and other aqueous streams contaminated with metal ions and radionuclides, and reactor basin water in excess facilities. Another part of this task is to provide a report on materials for Cs removal from aqueous solutions for use as a reference.

  10. Wildflowers of the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Seger, Tona [Savannah River Site (SRS), Aiken, SC (United States). USDA Forest Service

    2015-08-01

    This guidebook is a resource to help field personnel (nonbotanists) identify plants on the Savannah River Site (SRS) premises. Although not a complete flora guide, this publication contains information about 123 plant species found on the SRS. Plants are listed by their common names and arranged by the color of the flower. The SRS supports a diverse array of plant communities. Land use history, the establishment of the SRS, and current land management practices have shaped the flora presently found on the SRS. Located south of Aiken, SC, SRS spans 198,344 acres with land covering Aiken, Allendale, and Barnwell Counties. Situated on the Upper Coastal Plain and Sandhills physiographic provinces, the SRS has more than 50 distinct soil types. The topography is rolling to flat with elevation ranges from 50 to 400 feet above sea level.

  11. Modern NDA needs at Savannah River Site

    International Nuclear Information System (INIS)

    Holt, S.H.

    1995-01-01

    As the missions within the nuclear weapons complex change, so do the accountability measurement needs. Non-Destructive Assay (NDA) measurements have played a key role in accounting for special nuclear materials (SNM), and as time goes on, more and more reliance is made on this type of measurement. Key questions NDA instrument designers ask are: Which isotopes are of interest? What matrix are they in? What other isotopes are present? What container configuration will it be measured through? What precision and accuracy is required? What level of resolution is required? At the Savannah River Site (SRS) the desire to make direct measurements of SNM isotopes has prompted the evaluation to these and other questions. This paper will outline the current NDA needs at SRS. The discussion includes the types of materials that require measurement ,including the very difficult waste measurements. The special challenges associated with these measurement efforts will also be discussed

  12. Savannah River Site environmental data for 1993

    Energy Technology Data Exchange (ETDEWEB)

    Arnett, M.W. [ed.

    1994-05-01

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

  13. Savannah River Site environmental report for 1989

    International Nuclear Information System (INIS)

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

    1989-01-01

    this volume of Savannah River Site Environmental Report for 1989 (WSRC-IM-90-60) contains the figures and tables referenced in Volume I. The figures contain graphic illustrations of sample locations and/or data. The tables present summaries of the following types of data federal and state standards and guides applicable to SRS operations; concentrations of radioactivity in environmental media; the quantity of radioactivity released to the environment from SRS operations; offsite radiation committed dose from SRS operations; measurements of physical properties, chemicals, and metals concentrations in environmental media; and interlaboratory comparison of analytical results. The figures and tables in this report contain information about the routine environmental monitoring program at SRS unless otherwise indicated. No attempt has been made to include all data from environmental research programs. Variations in the report's content from year to year reflect changes in the routine environmental monitoring program or the inability to obtain certain samples from a specific location. 42 figs., 188 tabs

  14. Savannah River Site generic data base development

    International Nuclear Information System (INIS)

    Blanchard, A.

    2000-01-01

    This report describes the results of a project to improve the generic component failure database for the Savannah River Site (SRS). Additionally, guidelines were developed further for more advanced applications of database values. A representative list of components and failure modes for SRS risk models was generated by reviewing existing safety analyses and component failure data bases and from suggestions from SRS safety analysts. Then sources of data or failure rate estimates were identified and reviewed for applicability. A major source of information was the Nuclear Computerized Library for Assessing Reactor Reliability, or NUCLARR. This source includes an extensive collection of failure data and failure rate estimates for commercial nuclear power plants. A recent Idaho National Engineering Laboratory report on failure data from the Idaho Chemical Processing Plant was also reviewed. From these and other recent sources, failure data and failure rate estimates were collected for the components and failure modes of interest. For each component failure mode, this information was aggregated to obtain a recommended generic failure rate distribution (mean and error factor based on a lognormal distribution). Results are presented in a table in this report. A major difference between generic database and previous efforts is that this effort estimates failure rates based on actual data (failure events) rather than on existing failure rate estimates. This effort was successful in that over 75% of the results are now based on actual data. Also included is a section on guidelines for more advanced applications of failure rate data. This report describes the results of a project to improve the generic component failure database for the Savannah River site (SRS). Additionally, guidelines were developed further for more advanced applications of database values

  15. Knife River Indian Villages National Historic Site: Teacher's Guide.

    Science.gov (United States)

    National Park Service (Dept. of Interior), Washington, DC. National Register of Historic Places.

    This guide provides history and social studies teachers, at all grade levels, with information and activities about the American Indians of the Northern Plains who lived in the area of the Knife River where it enters the Missouri River. Located in what is now North Dakota, this area is the Knife River Indian Villages National Historic Site. The…

  16. The site selection process for a spent fuel repository in Finland. Summary report

    Energy Technology Data Exchange (ETDEWEB)

    McEwen, T. [EnvirosQuantiSci (United Kingdom); Aeikaes, T. [Posiva Oy, Helsinki (Finland)

    2000-12-01

    This Summary Report describes the Finnish programme for the selection and characterisation of potential sites for the deep disposal of spent nuclear fuel and explains the process by which Olkiluoto has been selected as the single site proposed for the development of a spent fuel disposal facility. Its aim is to provide an overview of this process, initiated almost twenty years ago, which has entered its final phase. It provides information in three areas: a review of the early site selection criteria, a description of the site selection process, including all the associated site characterisation work, up to the point at which a single site was selected and an outline of the proposed work, in particular that proposed underground, to characterise further the Olkiluoto site. In 1983 the Finnish Government made a policy decision on the management of nuclear waste in which the main goals and milestones for the site selection programme for the deep disposal of spent fuel were presented. According to this decision several site candidates, whose selection was to be based on careful studies of the whole country, should be characterised and the site for the repository selected by the end of the year 2000. This report describes the process by which this policy decision has been achieved. The report begins with a discussion of the definition of the geological and environmental site selection criteria and how they were applied in order to select a small number of sites, five in all, that were to be the subject of the preliminary investigations. The methods used to investigate these sites and the results of these investigations are described, as is the evaluation of the results of these investigations and the process used to discard two of the sites and continue more detailed investigations at the remaining three. The detailed site investigations that commenced in 1993 are described with respect to the overall strategy followed and the investigation techniques applied. The

  17. Savannah River Site disaggregated seismic spectra

    International Nuclear Information System (INIS)

    Stephenson, D.E.

    1993-02-01

    The objective of this technical note is to characterize seismic ground motion at the Savannah River Site (SRS) by postulated earthquakes that may impact facilities at the site. This task is accomplished by reviewing the deterministic and probabilistic assessments of the seismic hazard to establish the earthquakes that control the hazard to establish the earthquakes that control the hazard at the site and then evaluate the associated seismic ground motions in terms of response spectra. For engineering design criteria of earthquake-resistant structures, response spectra serve the function of characterizing ground motions as a function of period or frequency. These motions then provide the input parameters that are used in the analysis of structural response. Because they use the maximum response, the response spectra are an inherently conservative design tool. Response spectra are described in terms of amplitude, duration, and frequency content, and these are related to source parameters, travel path, and site conditions. Studies by a number of investigators have shown by statistical analysis that for different magnitudes the response spectrum values are different for differing periods. These facts support Jennings' position that using different shapes of design spectra for earthquakes of different magnitudes and travel paths is a better practice than employing a single, general-purpose shape. All seismic ground motion characterization results indicate that the PGA is controlled by a local event with M w < 6 and R < 30km. The results also show that lower frequencies are controlled by a larger, more distant event, typically the Charleston source. The PGA of 0.2 g, based originally on the Blume study, is consistent with LLNL report UCRL-15910 (1990) and with the DOE position on LLNL/EPRI

  18. Savannah River Site environmental report for 1988

    Energy Technology Data Exchange (ETDEWEB)

    Cummins, C.L.; Hetrick, C.S.; Stevenson, D.A. (eds.); Davis, H.A.; Martin, D.K.; Todd, J.L.

    1989-01-01

    During 1988, as in previous years, Savannah River Site operations had no adverse impact on the general public or the environment. Based on the SRS site-specific code, the maximum radiation dose commitment to a hypothetical individual at the SRS boundary from 1988 SRS atmospheric releases of radioactive materials was 0.46 millirem (mrem) (0.0046 millisievert (mSv)). To obtain the maximum dose, an individual would have had to reside on the SRS boundary at the location of highest dose for 24 hours per day, 365 days per year, consume a maximum amount of foliage and meat which originated from the general vicinity of the plant boundary, and drink a maximum amount of milk from cows grazing at the plant boundary. The average radiation dose commitment from atmospheric releases to the hypothetical individual on the SRS boundary in 1988 was 0.18 mrem (0. 0018 mSv). This person, unlike the maximumly exposed individual, consumes an average amount of foliage, meat, and milk which originated from the foliage and animals living at the plant boundary.

  19. Savannah River Site. Environmental report for 2001

    Energy Technology Data Exchange (ETDEWEB)

    Arnett, Margaret W. [Westinghouse Savannah River Co., Aiken, SC (United States). Savannah River Site. ed; Mamatey, Albert R. [Westinghouse Savannah River Co., Aiken, SC (United States). Savannah River Site. ed

    2001-12-31

    The goal of the Savannah River Site (SRS)—and that of the U.S. Department of Energy (DOE)—is positive environmental stewardship and full regulatory compliance, with zero violations. The site’s employees maintained progress toward achievement of this goal in 2001, as demonstrated by examples in this chapter. The site’s compliance efforts were near-perfect again in 2001. No notices of violation (NOVs) were issued in 2001 under the Resource Conservation and Recovery Act (RCRA), the Safe Drinking Water Act (SDWA), or the Clean Water Act (CWA). Two NOVs were issued to SRS during 2001—one, associated with permit requirement compliance, was issued under the Clean Air Act (CAA); the other, related to an oil release, was issued under the South Carolina Pollution Control Act. Under the CWA, the site’s National Pollutant Discharge Elimination System (NPDES) compliance rate was 99.6 percent. Also, 274 National Environmental Policy Act (NEPA) reviews of newly proposed actions were conducted and formally documented in 2001, and only one of the year’s 799 Site Item Reportability and Issues Management (SIRIM) program-reportable events was categorized as environmental; it was classified as an off-normal event.

  20. Tritium in the Savannah River Site environment

    Energy Technology Data Exchange (ETDEWEB)

    Murphy, C.E. Jr.; Bauer, L.R.; Hayes, D.W.; Marter, W.L.; Zeigler, C.C.; Stephenson, D.E.; Hoel, D.D.; Hamby, D.M.

    1991-05-01

    Tritium is released to the environment from many of the operations at the Savannah River Site. The releases from each facility to the atmosphere and to the soil and streams, both from normal operations and inadvertent releases, over the period of operation from the early 1950s through 1988 are presented. The fate of the tritium released is evaluated through environmental monitoring, special studies, and modeling. It is concluded that approximately 91% of the tritium remaining after decay is now in the oceans. A dose and risk assessment to the population around the site is presented. It is concluded that about 0.6 fatal cancers may be associated with the tritium released during all the years of operation to the population of about 625,000. This same population (based on the overall US cancer statistics) is expected to experience about 105,000 cancer fatalities from all types of cancer. Therefore, it is considered unlikely that a relationship between any of the cancer deaths occurring in this population and releases of tritium from the SRS will be found.

  1. The Savannah River Site's groundwater monitoring program

    International Nuclear Information System (INIS)

    1991-01-01

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site's (SRS) Groundwater Monitoring Program. During third quarter 1990 (July through September) EPD/EMS conducted routine sampling of monitoring wells and drinking water locations. EPD/EMS established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead they aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. All analytical results from third quarter 1990 are listed in this report, which is distributed to all site custodians. One or more analytes exceeded Flag 2 in 87 monitoring well series. Analytes exceeded Flat 2 for the first since 1984 in 14 monitoring well series. In addition to groundwater monitoring, EPD/EMS collected drinking water samples from SRS drinking water systems supplied by wells. The drinking water samples were analyzed for radioactive constituents

  2. Tritium in the Savannah River Site environment

    International Nuclear Information System (INIS)

    Murphy, C.E. Jr.; Bauer, L.R.; Hayes, D.W.; Marter, W.L.; Zeigler, C.C.; Stephenson, D.E.; Hoel, D.D.; Hamby, D.M.

    1991-05-01

    Tritium is released to the environment from many of the operations at the Savannah River Site. The releases from each facility to the atmosphere and to the soil and streams, both from normal operations and inadvertent releases, over the period of operation from the early 1950s through 1988 are presented. The fate of the tritium released is evaluated through environmental monitoring, special studies, and modeling. It is concluded that approximately 91% of the tritium remaining after decay is now in the oceans. A dose and risk assessment to the population around the site is presented. It is concluded that about 0.6 fatal cancers may be associated with the tritium released during all the years of operation to the population of about 625,000. This same population (based on the overall US cancer statistics) is expected to experience about 105,000 cancer fatalities from all types of cancer. Therefore, it is considered unlikely that a relationship between any of the cancer deaths occurring in this population and releases of tritium from the SRS will be found

  3. Savannah River Site Environmental Report for 1998 Summary

    International Nuclear Information System (INIS)

    Arnett, M.

    1999-01-01

    This pamphlet gives a brief overview of the Savannah River Site and its activities, summarizes the impact of 1998 site operations on the environment and the public, and provides a brief explanation of radiation and dose

  4. Design considerations for on-site spent-fuel transfer systems

    International Nuclear Information System (INIS)

    Jones, R.H.; Jones, C.R.

    1989-06-01

    Studies on spent fuel shipping logistics and operation make it clear that the use of large casks, i.e., 100--125 tons, is superior to smaller casks of similar construction. This superiority manifests itself in both transportation and/or shipping economics and safety as well as reduced personnel exposure in the processing of the casks. An on-site system for the transfer of spent fuel from the storage pool to a large shipping or storage cask, as well as the transfer of spent fuel directly from a storage cask to a shipping cask, could bring the large cask benefits to those restricted reactors. Sensing the need to look more closely at this opportunity, EPRI contracted with S. Levy, Incorporated of Campbell, CA to develop a set of design considerations for such transfer systems. Rather then embark on another design study, EPRI decided to first identify the system considerations that must be factored into any design. The format for this effort presents both the Consideration and the Rationale for the consideration. The resulting work identified thirty-six General Considerations and two Special Considerations. The Considerations are in the form of mandatory requirements and desirable but nonmandatory requirements. Additionally, a brief economic study was performed to get a feel for the cost considerations of on-site transfers. The study results suggest a relatively narrow set of scenarios where on-site transfers are economically superior to alternatives. These scenarios generally involve the use of concrete casks as on-site storage devices

  5. Fuel Assemblies Thermal Analysis in the New Spent Fuel Storage Facility at Inshass Site

    International Nuclear Information System (INIS)

    Khattab, M.; Mariy, Ahmed

    1999-01-01

    New Wet Storage Facility (NSF) is constructed at Inshass site to solve the problem of spent fuel storage capacity of ETRR-1 reactor . The Engineering Safety Heat Transfer Features t hat characterize the new facility are presented. Thermal analysis including different scenarios of pool heat load and safety limits are discussed . Cladding temperature limit during handling and storage process are specified for safe transfer of fuel

  6. On-site storage of spent nuclear fuel assemblies in German nuclear power plants

    International Nuclear Information System (INIS)

    Banck, J.

    1999-01-01

    The selection of back-end strategies for spent fuel assemblies is influenced by a number of different factors depending on the given situation in any specific country. In Germany, the back-end strategy implemented in the past was almost exclusively reprocessing. This strategy was required by the German Atomic Energy Act. Since 1994, when the Atomic Energy Act was amended, the option of direct final disposal has been granted the equivalent status by law to that afforded to reprocessing (and reuse of valuable materials). As a result, German utilities may now choose between these two alternatives. Another important condition for optimizing the back-end policy is the fact that fuel cycle costs in Germany are directly dependent on spent fuel volumes (in contrast to the US, for example, such costs are related to the amount of power generated). Another boundary condition for German utilities with respect to spent fuel management is posed by the problems with militant opponents of nuclear energy during transportation of spent fuel to interim storage sites. These facts have given rise to a reconsideration of the fuel cycle back-end, which has resulted in a change in strategy by most German utilities in favour of the following: Preference for long-term storage and maximized use of on-site storage capacity; Reduction in the amount of spent fuel by increasing burnup as much as possible. These decisions have also been driven by the deregulation of energy markets in Europe, where utilities are now permitted to sell electric power to consumers beyond their original supply network and must therefore offer electric power on a very cost competitive basis. (author)

  7. Natural Remediation at Savannah River Site

    International Nuclear Information System (INIS)

    Lewis, C. M.; Van Pelt, R.

    2002-01-01

    Natural remediation is a general term that includes any technology or strategy that takes advantage of natural processes to remediate a contaminated media to a condition that is protective of human health and the environment. Natural remediation techniques are often passive and minimally disruptive to the environment. They are generally implemented in conjunction with traditional remedial solutions for source control (i.e., capping, stabilization, removal, soil vapor extraction, etc.). Natural remediation techniques being employed at Savannah River Site (SRS) include enhanced bio-remediation, monitored natural attenuation, and phytoremediation. Enhanced bio-remediation involves making nutrients available and conditions favorable for microbial growth. With proper precautions and feeding, the naturally existing microbes flourish and consume the contaminants. Case studies of enhanced bio-remediation include surface soils contaminated with PCBs and pesticides, and Volatile Organic Compound (VOC) contamination in both the vadose zone and groundwater. Monitored natural attenuation (MNA) has been selected as the preferred alternative for groundwater clean up at several SRS waste units. Successful implementation of MNA has been based on demonstration that sources have been controlled, groundwater modeling that indicates that plumes will not expand or reach surface water discharge points at levels that exceed regulatory limits, and continued monitoring. Phytoremediation is being successfully utilized at several SRS waste units. Phytoremediation involves using plants and vegetation to uptake, break down, or manage contaminants in groundwater or soils. Case studies at SRS include managing groundwater plumes of tritium and VOCs with pine trees that are native to the area. Significant decreases in tritium discharge to a site stream have been realized in one phytoremediation project. Studies of other vegetation types, methods of application, and other target contaminants are

  8. Site safety progress review of spent fuel central interim storage facility. Final report

    International Nuclear Information System (INIS)

    Gurpinar, A.; Serva, L.; Giuliani

    1995-01-01

    Following the request of the Czech Power Board (CEZ) and within the scope of the Technical Cooperation Project CZR/9/003, a progress review of the site safety of the Spent Fuel Central Interim Storage Facility (SFCISF) was performed. The review involved the first two stages of the works comprising the regional survey and identification of candidate sites for the underground and surface storage options. Five sites have been identified as a result of the previous works. The following two stages will involved the identification of the preferred candidate sites for the two options and the final site qualification. The present review had the purpose of assessing the work already performed and making recommendations for the next two stages of works

  9. Environmental justice at the Savannah River Site

    International Nuclear Information System (INIS)

    Flemming, R.; Hooker, K.L.

    1995-01-01

    Environmental justice is the conscious commitment to ensure that poor and/or minority communities are not disproportionately bearing adverse human health and environmental effects from the production, processing, or disposal of hazardous or toxic waste. To focus federal attention on assessing the environmental and human health conditions in minority and/or low-income communities surrounding federal facilities, on February 11, 1994, President Clinton signed Executive Order (EO) 12898. As part of the strategy to comply with EO 12898, the President required all federal agencies to develop localized strategies to ensure that their programs and policies are consistent with EO 12898. This would incorporate mechanisms for increasing public participation opportunities for involvement in the decision making, easier access to information, and the collection and analysis of economic, demographic, and food consumption data in surrounding communities. The U.S. Department of Energy (DOE) responded by issuing its Environmental Justice Strategy 2 (April 1995), although many of its field offices had been actively implementing activities in support of the executive order since its issuance. One DOE facility, the Savannah River Site (SRS), which is located in west central South Carolina, is making great strides toward implementing a successful public participation program, which includes environmental justice initiatives

  10. Savannah River Site environmental report for 1989

    Energy Technology Data Exchange (ETDEWEB)

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

    1989-01-01

    this volume of Savannah River Site Environmental Report for 1989 (WSRC-IM-90-60) contains the figures and tables referenced in Volume I. The figures contain graphic illustrations of sample locations and/or data. The tables present summaries of the following types of data federal and state standards and guides applicable to SRS operations; concentrations of radioactivity in environmental media; the quantity of radioactivity released to the environment from SRS operations; offsite radiation committed dose from SRS operations; measurements of physical properties, chemicals, and metals concentrations in environmental media; and interlaboratory comparison of analytical results. The figures and tables in this report contain information about the routine environmental monitoring program at SRS unless otherwise indicated. No attempt has been made to include all data from environmental research programs. Variations in the report's content from year to year reflect changes in the routine environmental monitoring program or the inability to obtain certain samples from a specific location. 42 figs., 188 tabs.

  11. Remedial Investigation of Hanford Site Releases to the Columbia River

    International Nuclear Information System (INIS)

    Lerch, J.A.

    2009-01-01

    In south-central Washington State, the Columbia River flows through the U.S. Department of Energy Hanford Site. A primary objective of the Hanford Site cleanup mission is protection of the Columbia River, through remediation of contaminated soil and groundwater that resulted from its weapons production mission. Within the Columbia River system, surface water, sediment, and biota samples related to potential Hanford Site hazardous substance releases have been collected since the start of Hanford operations. The impacts of Hanford Site hazardous substance releases to the Columbia River in areas upstream, within, and downstream of the Hanford Site boundary have been previously investigated as mandated by the U.S. Department of Energy requirements under the Atomic Energy Act. The impacts are now being assessed under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 via a remedial investigation. The Remedial Investigation Work Plan for Hanford Site Releases to the Columbia River has been developed and issued to initiate the remedial investigation. The work plan establishes a phased approach to characterize contaminants, assess current risks, and determine whether or not there is a need for any cleanup actions. Field investigation activities began in October 2008 and are anticipated to continue into Fall 2009 over a 120 mile stretch of the Columbia River. Information gained from performing this remedial investigation will ultimately be used to help make final regulatory decisions for cleaning up Hanford Site contamination that exists in and along the Columbia River. (authors)

  12. Used nuclear materials at Savannah River Site: asset or waste?

    International Nuclear Information System (INIS)

    Magoulas, Virginia

    2013-01-01

    The nuclear industry, both in the commercial and the government sectors, has generated large quantities of material that span the spectrum of usefulness, from highly valuable ''assets'' to worthless ''wastes''. In many cases, the decision parameters are clear. Transuranic waste and high level waste, for example, have no value, and is either in a final disposition path today, or - in the case of high level waste - awaiting a policy decision about final disposition. Other materials, though discardable, have intrinsic scientific or market value that may be hidden by the complexity, hazard, or cost of recovery. An informed decision process should acknowledge the asset value, or lack of value, of the complete inventory of materials, and the structure necessary to implement the range of possible options. It is important that informed decisions are made about the asset value for the variety of nuclear materials available. For example, there is a significant quantity of spent fuel available for recycle (an estimated $4 billion value in the Savannah River Site's (SRS) L area alone); in fact, SRS has already blended down more than 300 metric tons of uranium for commercial reactor use. Over 34 metric tons of surplus plutonium is also on a path to be used as commercial fuel. There are other radiological materials that are routinely handled at the site in large quantities that should be viewed as strategically important and / or commercially viable. In some cases, these materials are irreplaceable domestically, and failure to consider their recovery could jeopardize our technological leadership or national defense. The inventories of nuclear materials at SRS that have been characterized as ''waste'' include isotopes of plutonium, uranium, americium, and helium. Although planning has been performed to establish the technical and regulatory bases for their discard and disposal, recovery of these materials is both economically attractive and in the national interest.

  13. Management of legacy spent nuclear fuel wastes at the Chalk River Laboratories: operating experience and progress towards waste remediation

    International Nuclear Information System (INIS)

    Cox, D.S.; Bainbridge, I.B.; Greenfield, K.R.

    2006-01-01

    AECL has been managing and storing a diversity of spent nuclear fuel, arising from operations at its Chalk River Laboratories (CRL) site over more than 50 years. A subset of about 22 tonnes of research reactor fuels, primarily metallic uranium, have been identified as a high priority for remediation, based on monitoring and inspection that has determined that these fuels and their storage containers are corroding. This paper describes the Fuel Packaging and Storage (FPS) project, which AECL has launched to retrieve these fuels from current storage, and to emplace them in a new above-ground dry storage system, as a prerequisite step to decommissioning some of the early-design waste storage structures at CRL. The retrieved fuels will be packaged in a new storage container, and subjected to a cold vacuum drying process that will remove moisture, and thereby reduce the extent of future corrosion and degradation. The FPS project will enable improved interim storage to be implemented for legacy fuels at CRL, until a decision is made on the ultimate disposition of legacy fuels in Canada. (author)

  14. SAVANNAH RIVER SITE ENVIRONMENTAL REPORT FOR 2009

    Energy Technology Data Exchange (ETDEWEB)

    Mamatey, A.; Fanning, R.

    2010-08-19

    The Savannah River Site Environmental Report for 2009 (SRNS-STI-2010-00175) is prepared for the U.S. Department of Energy (DOE) according to requirements of DOE Order 231.1A,'Environment, Safety and Health Reporting,' and DOE Order 5400.5, 'Radiation Protection of the Public and Environment.' The annual SRS Environmental Report has been produced for more than 50 years. Several hundred copies are distributed each year to government officials, universities, public libraries, environmental and civic groups, news media, and interested individuals. The report's purpose is to: (1) present summary environmental data that characterize site environmental management performance; (2) confirm compliance with environmental standards and requirements; and (3) highlight significant programs and efforts. SRS maintained its record of environmental excellence in 2009, as its operations continued to result in minimal impact to the offsite public and the surrounding environment. The site's radioactive and chemical discharges to air and water were well below regulatory standards for environmental and public health protection; its air and water quality met applicable requirements; and the potential radiation dose from its discharges was less than the national dose standards. The largest radiation dose that an offsite, hypothetical, maximally exposed individual could have received from SRS operations during 2009 was estimated to be 0.12 millirem (mrem). (An mrem is a standard unit of measure for radiation exposure.) The 2009 SRS dose is just 0.12 percent of the DOE all-pathway dose standard of 100 mrem per year, and far less than the natural average dose of about 300 mrem per year (according to Report No. 160 of the National Council of Radiation Protection and Measurements) to people in the United States. This 2009 all-pathway dose of 0.12 mrem was the same as the 2008 dose. Environmental monitoring is conducted extensively within a 2,000-square-mile network

  15. General siting study 95. Siting of a deep repository for spent nuclear fuel

    International Nuclear Information System (INIS)

    1995-10-01

    General Siting Study 95 is a detailed description of the work carried out to put the siting of a deep repository in a national and regional context. The report is based on SKB's siting factors, which have been applied on a national scale. Different factors of importance or of possible importance for the long-term radiological safety, technology, land and environment as well as society are described and evaluated. This report is the overall description on general siting studies which the government considered that SKB should report in connection with the RD and D Programme 95. 121 refs, 40 figs

  16. General siting study 95. Siting of a deep repository for spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    General Siting Study 95 is a detailed description of the work carried out to put the siting of a deep repository in a national and regional context. The report is based on SKB`s siting factors, which have been applied on a national scale. Different factors of importance or of possible importance for the long-term radiological safety, technology, land and environment as well as society are described and evaluated. This report is the overall description on general siting studies which the government considered that SKB should report in connection with the RD and D Programme 95. 121 refs, 40 figs.

  17. Development of SKI's Regulatory Approach to the Siting of a Spent Nuclear Fuel Repository

    International Nuclear Information System (INIS)

    Westerlind, Magnus

    2003-01-01

    Since the beginning of the 1990s the Swedish Nuclear Fuel and Waste Management Co., SKB, is actively working with the siting of a spent nuclear fuel repository. Feasibility studies have been completed in a total of eight municipalities, and in December 2000 three municipalities (Oskarshamn, Tierp and Oesthammar) were proposed for further investigations. These site investigations include surface based site characterisation from deep bore holes but also further studies of infrastructure, land use, transportation etc. SKB's proposal was reviewed by SKI and about 60 other organisations, including municipalities, NGOs, government agencies etc. during the winter/spring 2000/2001. In June 2001 SKI reported the review findings to the Government. In parallel with SKI also the Swedish Council for Nuclear Waste (KASAM) reviewed SKB's proposal and reported to the Government. In its decision in November 2001 the Government supported SKB's proposal to continue with site investigations. Based on SKB's material, the reviews and the Government's decision the municipalities of Oesthammar and Oskarshamn have agreed to site investigations while Tierp have decided no to continue. The site investigations in Oesthammar and Oskarshamn started during 2002. The siting process has meant that several new actors have been engaged in nuclear waste management in general and disposal of spent nuclear fuel in particular. This has meant that 'old' actors, particularly SKB, the regulators (the Swedish Nuclear Power Inspectorate, SKI, and the Swedish Radiation Protection Authority, SSI) have had to evaluate, develop and clarify their roles and strategies for dialogue. This paper presents reflections on the impacts on some of SKI's regulatory activities

  18. Surface Wind Gust Statistics at the Savannah River Site

    International Nuclear Information System (INIS)

    Weber, A.H.

    2001-01-01

    The Atmospheric Technologies Group (ATG) of the Savannah River Technology Center (SRTC) collects meteorological data for many purposes at the Savannah River Site (SRS) including weather forecasting. This study focuses on wind gusts and also, to a lesser degree, turbulence intensities that occur in fair weather conditions near the surface over time periods from 1 hour to one week (168 hours)

  19. Technical concept for test of geologic storage of spent reactor fuel in the Climax granite, Nevada Test Site

    International Nuclear Information System (INIS)

    Ramspott, L.D.; Ballou, L.B.; Carlson, R.C.; Montan, D.N.; Butkovich, T.R.; Duncan, J.E.; Patrick, W.C.; Wilder, D.G.; Brough, W.G.; Mayr, M.C.

    1979-01-01

    The Spent Fuel Test in the Climax granite at the Nevada Test Site is a generic test in which spent fuel assemblies from an operating commercial nuclear reactor are emplaced at, and retrieved from, a plausible waste repository depth in a typical granite. Eleven canisters of spent fuel are emplaced in a storage drift 420 m below the surface along with six electrical simulator canisters. Two adjacent drifts contain electrical heaters which are operated so as to simulate the initial five years of the temperature-stress-displacement fields of a large repository. The site is described, and the pre-operational measurement program and characteristics of the spent fuel are given. Both thermal and mechanical response calculations are summarized. The field instrumentation and data acquisition systems are described, as well as the system for handling the spent fuel

  20. Spent nuclear fuel characterization for a bounding reference assembly for the receiving basin for off-site fuel

    International Nuclear Information System (INIS)

    Kahook, S.D.; Garrett, R.L.; Canas, L.R.

    1995-01-01

    A basis for interim operation 1 (BIO) for the receiving basin for off-site fuel (RBOF) facility at the U.S. Department of Energy's (DOE) Savannah River site nuclear materials production complex has been developed in accordance to draft DOE-STD-0019-93 (Ref. 2). The latter document requires a hazard categorization per DOE-STD-1027-92 (Ref. 3) for the safety analysis portion of the BIO. This classification places the facility in one of three categories as defined in DOE 5480.23 (Ref. 4) per the total radioactivity, which can be released during an accident. The diversity of spent nuclear fuels stored in the RBOF made an exacting assessment of the total radioactive inventory virtually impossible. This restriction led to a conservative calculation based on the concept of a hypothetical bounding reference fuel assembly (RFA) integrated over the total capacity of the facility. The RFA is derived from a systematic ranking of the real assemblies (current and expected) according to a maximum burnup criterion. The indicated scheme is not only simple but precluded a potential delay in the completion of the BIO

  1. Assessment of Radionuclides in the Savannah River Site Environment Summary

    Energy Technology Data Exchange (ETDEWEB)

    Carlton, W.H.

    1999-01-26

    This document summarizes the impact of radionuclide releases from Savannah River Site (SRS) facilities from 1954 through 1996. The radionuclides reported here are those whose release resulted in the highest dose to people living near SRS.

  2. 78 FR 14088 - Environmental Management Site-Specific Advisory Board, Savannah River Site

    Science.gov (United States)

    2013-03-04

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Savannah River Site. The Federal Advisory Committee Act requires that public notice of this meeting be announced in the Federal Register.

  3. Local negotiation on compensation siting of the spent nuclear fuel repository in Finland

    International Nuclear Information System (INIS)

    Kojo, Matti

    2007-01-01

    The aim of the paper is to analyse the local negotiation process between the Municipality of Eurajoki and the nuclear power company Teollisuuden Voima (TVO) and the nuclear waste management company Posiva Oy. The aim of the negotiations was to find an acceptable form of compensation for siting a spent nuclear fuel repository in Olkiluoto, Finland. The paper includes background information on the siting process in Finland, the local political setting in the Municipality of Eurajoki and a description of the negotiation process. The analysis of the negotiations on compensation is important for better understanding the progress of the Finnish siting process. The paper describes the picture of the contest to host the spent nuclear fuel repository. It also provides more information on the relationship between the Municipality of Eurajoki and the power company TVO. The negotiations on compensation and the roles of various players in the negotiations have not been studied in detail because the minutes of the Vuojoki liaison group were not available before the decision of the Supreme Administrative Court in May 2006. (author)

  4. Regulatory supervision of sites for spent fuel and radioactive waste storage in the Russian northwest.

    Science.gov (United States)

    Shandala, N K; Sneve, M K; Smith, G M; Kiselev, M F; Kochetkov, O A; Savkin, M N; Simakov, A V; Novikova, N Ya; Titov, A V; Romanov, V V; Seregin, V A; Filonova, A V; Semenova, M P

    2008-12-01

    In the 1960s two technical bases for the Northern Fleet were created in the Russian northwest at Andreeva Bay in the Kola Peninsula and Gremikha village on the coast of the Barents Sea. They maintained nuclear submarines, receiving and storing radioactive waste and spent nuclear fuel. No further waste was received after 1985, and the technical bases have since been re-categorised as temporary storage sites. The handling of these materials to put them into a safe condition is especially hazardous because of their degraded state. This paper describes regulatory activities which have been carried out to support the supervision of radiological protection during recovery of waste and spent fuel, and to support regulatory decisions on overall site remediation. The work described includes: an assessment of the radiation situation on-site; the development of necessary additional regulatory rules and standards for radiation protection assurance for workers and the public during remediation; and the completion of an initial threat assessment to identify regulatory priorities. Detailed consideration of measures for the control of radiation exposure of workers and radiation exposure of the public during and after operations and emergency preparedness and response are complete and provided in sister papers. The continuing requirements for regulatory activities relevant to the development and implementation of on-going and future remediation activities are also outlined. The Norwegian Radiation Protection Authority supports the work, as part of the Norwegian Government's plan of action to promote improvements in radiation protection and nuclear safety in northwest Russia.

  5. Site-selection studies for final disposal of spent fuel in Finland

    International Nuclear Information System (INIS)

    Vuorela, P.; Aeikaes, T.

    1984-02-01

    In the management of waste by the Industrial Power Company Ltd. (TVO) preparations are being made for the final disposal of unprocessed spent fuel into the Finnish bedrock. The site selection program will advance in three phases. The final disposal site must be made at the latest by the end of the year 2000, in accordance with a decision laid down by the Finnish Government. In the first phase, 1983-85, the main object is to find homogeneous stable bedrock blocks surrounded by fracture zones located at a safe distance from the planned disposal area. The work usually starts with a regional structural analysis of mosaics of Landsat-1 winter and summer imagery. Next an assortment of different maps, which cover the whole country, is used. Technical methods for geological and hydrogeological site investigations are being developed during the very first phase of the studies, and a borehole 1000 meters deep will be made in southwestern Finland. Studies for the final disposal of spent fuel or high-level reprocessing waste have been made since 1974 in Finland. General suitability studies of the bedrock have been going on since 1977. The present results indicate that suitable investigation areas for the final disposal of highly active waste can be found in Finland

  6. Regulatory supervision of sites for spent fuel and radioactive waste storage in the Russian Northwest

    Energy Technology Data Exchange (ETDEWEB)

    Shandala, N K; Kochetkov, O A; Savkin, M N; Simakov, A V; Novikova, N Ya; Titov, A V; Seregin, V A; Filonova, A V; Semenova, M P [Burnasyan Federal Medical Biophysical Centre, Moscow (Russian Federation); Sneve, M K [Norwegian Radiation Protection Authority, Oslo (Norway); Smith, G M [GMS Abingdon Ltd (United Kingdom); Kiselev, M F; Romanov, V V [Federal Medical-Biological Agency, Moscow (Russian Federation)], E-mail: shandala@srcibph.ru

    2008-12-15

    In the 1960s two technical bases for the Northern Fleet were created in the Russian northwest at Andreeva Bay in the Kola Peninsula and Gremikha village on the coast of the Barents Sea. They maintained nuclear submarines, receiving and storing radioactive waste and spent nuclear fuel. No further waste was received after 1985, and the technical bases have since been re-categorised as temporary storage sites. The handling of these materials to put them into a safe condition is especially hazardous because of their degraded state. This paper describes regulatory activities which have been carried out to support the supervision of radiological protection during recovery of waste and spent fuel, and to support regulatory decisions on overall site remediation. The work described includes: an assessment of the radiation situation on-site; the development of necessary additional regulatory rules and standards for radiation protection assurance for workers and the public during remediation; and the completion of an initial threat assessment to identify regulatory priorities. Detailed consideration of measures for the control of radiation exposure of workers and radiation exposure of the public during and after operations and emergency preparedness and response are complete and provided in sister papers. The continuing requirements for regulatory activities relevant to the development and implementation of on-going and future remediation activities are also outlined. The Norwegian Radiation Protection Authority supports the work, as part of the Norwegian Government's plan of action to promote improvements in radiation protection and nuclear safety in northwest Russia.

  7. Savannah River Site Environmental Report for 1997 Summary

    International Nuclear Information System (INIS)

    Arnett, M.

    1998-01-01

    The Savannah River Site (SRS) publishes an environmental report each year to provide environmental monitoring and surveillance results to the U. S. Department of Energy (DOE), the public, Congress, state and federal regulators, universities, local governments, the news media, and environmental and civic groups. The Savannah River Site Environmental Report for 1997 (WSRC-TR-97-00322) contains detailed information on site operations, environmental monitoring and surveillance programs, environmental compliance activities, and special projects for the calendar year 1997. The purpose of this documents is to give a brief overview of the site and its activities, to summarize the site environmental report and the impact of 1997 SRS operations on the environment and the public, and to provide a brief explanation of radiation and dose.The data used to compile the annual environmental report and this summary can be found in Savannah River Site Environmental Data for 1997 (WSRC-TR-97-00324)

  8. Detailed site characterization for final disposal of spent fuel in Finland - Case study Loviisa

    International Nuclear Information System (INIS)

    Anttila, P.; Ahokas, H.; Ruotsalainen, P.; Cosma, C.; Keskinen, J.; Hinkkanen, H.; Rouhiainen, P.; Oehberg, A.

    1998-01-01

    The spent fuel from the Finnish nuclear power plants will be disposed of in the Finnish bedrock. Pos iva Oy is responsible for the site selection programme carried out in accordance with the governmental decisions. Preliminary site investigations were made in five areas in 1987-1992. Based on the results, three areas, Romuvaara in Kuhmo, Kivetty in Aeaenekoski and Olkiluoto in Eurajoki, were selected for the detailed site characterization in 1993-2000. The final site will be selected by the end of the year 2000. The interim reporting of the detailed studies of the three areas was made in 1996. In 1997, the island of Haestholmen, as the host to the Loviisa NPP, was included as a fourth candidate site in the programme for the detailed site investigations. The goal is to characterize this site also in detail by the end of 2000 to attain the same level of knowledge as available from the three other sites. The background information existing from the studies made for the construction of the repository for the low-and intermediate-level wastes will create a good basis to reach the target. The research programme for the detailed site characterization has mainly been focused on groundwater flow and geochemistry due to their importance in terms of long-term safety of the repository. Equipment and methodology development by Posiva has introduced new tools that provide more accurate data on relevant parameters than the ones used in previous stages of site characterization. The programme also contains studies for additional information of the structural and geological properties of the bedrock towards the depth. Also predictive modelling has been made for evaluating the relevance of the assumptions made. The methods applied in the site characterization have comprised, e.g., geological mapping, deep core drilling, groundwater sampling and analyzing, hydraulic testing and geophysical measurements

  9. Detailed site characterization for final disposal of spent fuel in Finland - Case study Loviisa

    Energy Technology Data Exchange (ETDEWEB)

    Anttila, P. [IVO Power Engineering Ltd. (Finland); Ahokas, H.; Ruotsalainen, P. [Fintact Oy (Finland); Cosma, C.; Keskinen, J. [Vibrometric Oy (Finland); Hinkkanen, H. [Posiva Oy (Finland); Rouhiainen, P. [PRG-Tec Oy (Finland); Oehberg, A. [Saanio and Riekkola Consulting Engineers (Finland)

    1998-09-01

    The spent fuel from the Finnish nuclear power plants will be disposed of in the Finnish bedrock. Pos iva Oy is responsible for the site selection programme carried out in accordance with the governmental decisions. Preliminary site investigations were made in five areas in 1987-1992. Based on the results, three areas, Romuvaara in Kuhmo, Kivetty in Aeaenekoski and Olkiluoto in Eurajoki, were selected for the detailed site characterization in 1993-2000. The final site will be selected by the end of the year 2000. The interim reporting of the detailed studies of the three areas was made in 1996. In 1997, the island of Haestholmen, as the host to the Loviisa NPP, was included as a fourth candidate site in the programme for the detailed site investigations. The goal is to characterize this site also in detail by the end of 2000 to attain the same level of knowledge as available from the three other sites. The background information existing from the studies made for the construction of the repository for the low-and intermediate-level wastes will create a good basis to reach the target. The research programme for the detailed site characterization has mainly been focused on groundwater flow and geochemistry due to their importance in terms of long-term safety of the repository. Equipment and methodology development by Posiva has introduced new tools that provide more accurate data on relevant parameters than the ones used in previous stages of site characterization. The programme also contains studies for additional information of the structural and geological properties of the bedrock towards the depth. Also predictive modelling has been made for evaluating the relevance of the assumptions made. The methods applied in the site characterization have comprised, e.g., geological mapping, deep core drilling, groundwater sampling and analyzing, hydraulic testing and geophysical measurements 23 refs, 4 figs

  10. Rheology of Savannah River site tank 42 HLW radioactive sludge

    International Nuclear Information System (INIS)

    Ha, B.C.

    1997-01-01

    Knowledge of the rheology of the radioactive sludge slurries at the Savannah River Site is necessary in order to ensure that they can be retrieved from waste tanks and processed for final disposal. At Savannah River Site, Tank 42 sludge represents on of the first HLW radioactive sludges to be vitrified in the Defense Waste Processing Facility. The rheological properties of unwashed Tank 42 sludge slurries at various solids concentrations were measured remotely in the Shielded Cells at the Savannah River Technology Center using a modified Haake Rotovisco viscometer

  11. The dry spent RBMK fuel cask storage site at the Ignalina NPP in Lithuania

    International Nuclear Information System (INIS)

    Penkov, V.V.; Diersch, R.

    1999-01-01

    At present, there are about 15,000 spent RBMK fuel assemblies stored in the water pools near the reactors at the Ignalina Nuclear Power Plant (INPP). Part of them are cut in two bundles and stored in standardized baskets in the pools. Each basket is loaded with 102 bundles. For long-term interim storage of this fuel, it was decided to use dry storage in casks. For this reason, the total activity to be stored is split into individual units (casks). Each cask represents a closed and independent safety system, fulfilling all safety-relevant requirements for both normal operational and hypothetical accidental conditions. The main safety relevant features of the storage cask system are: (1) Inherent safety system; (2) Double barrier system; (3) Passive cooling by natural convection; (4) Safety against accidents. The cask dry storage system is a cost effective and multi-functional system for storage, transport after the operation time and final disposal under consideration of additional protective elements. From an economical point of view, cask storage has a number of advantages. Two cask types have been intended for the INPP storage site: (1) The CASTOR RBMK cask made of ductile cast iron; (2) The CONSTOR RBMK sandwich cask made of an inner and outer steel shell and reinforced heavy concrete. The CASTOR RBMK and the CONSTOR RBMK casks are designed to withstand severe storage site accidents and with help of impact limiters - to fulfil the IAEA test criteria for type B(U)F packages. The INPP spent RBMK fuel storage site is designed as an open air storage for an operational time of 50 years. The casks are arranged on the concrete storage pad. The site is equipped with a crane for cask handling and technological buildings and security systems. The safety analyses for fuel and cask handling and for cask handling and for cask technology at the site have been made and accepted by the Lithuanian Competent Authority. (author)

  12. Mixed waste disposal facilities at the Savannah River Site

    International Nuclear Information System (INIS)

    Wells, M.N.; Bailey, L.L.

    1991-01-01

    The Savannah River Site (SRS) is a key installation of the US Department of Energy (DOE). The site is managed by DOE's Savannah River Field Office and operated under contract by the Westinghouse Savannah River Company (WSRC). The Site's waste management policies reflect a continuing commitment to the environment. Waste minimization, recycling, use of effective pre-disposal treatments, and repository monitoring are high priorities at the site. One primary objective is to safely treat and dispose of process wastes from operations at the site. To meet this objective, several new projects are currently being developed, including the M-Area Waste Disposal Project (Y-Area) which will treat and dispose of mixed liquid wastes, and the Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF), which will store, treat, and dispose of solid mixed and hazardous wastes. This document provides a description of this facility and its mission

  13. Application of ultra-sons to on-site spent fuel assemblies metrology

    International Nuclear Information System (INIS)

    Gondard, C.; Saglio, R.; Vouillot, M.; Delaroche, P.; Vaubert, Y.; Van Craeynest, J.C.

    1983-12-01

    Fuel assemblies inspection on the site of a power reactor, between two irradiation campaigns, allows to estimate the behaviour of prototype fuel assemblies and to permit their refueling for the continuation of the irradiation; the utilization of non-destructive, reliable and high-performance techniques, is of a great interest in the application. For, this reason, the C.E.A. has been led to carry out new techniques allowing the visual examination and the dimensional inspection of spent fuel assemblies of 900 MWe French pressurized water reactors, with a transportable Fuel Examination Module (MEC) on every reactor site. This module includes a television camera, and uses for the first time as ''position sensor'' the properties offered by a set of ultrasonic transducers. The main principle of the design, of the operation way of the module, of the measuring methods, and, of the data acquisition and processing, are presented [fr

  14. Normal evolution of a spent fuel repository at the candidate sites in Finland

    International Nuclear Information System (INIS)

    Grawford, M.B.; Wilmot, R.D.

    1998-12-01

    The Finnish disposal concept for spent nuclear fuel envisages burial of the fuel in a repository excavated at a depth of around 500 m in crystalline bedrock. Since 1983, a programme has been underway in Finland to select a potential site for such a repository. The programme is now in the final stages of selecting one site for further detailed characterisation from a list of four candidate sites at Kivetty, Romuvaara, Olkiluoto, and Haestholmen. Each stage of the site selection process has been supported by a major performance assessment (PA) exercise. The aim of this report is to describe the normal evolution of a repository system at the four candidate Finnish sites as input to development of the next PA, known as TILA-99. The report summarises the disposal concept and the present-day characteristics of each candidate site, and considers the most likely future changes in both the natural environment and the engineered components of the disposal system. The description concentrates on the key features, events and processes (FEPs) controlling behaviour and evolution of the disposal system. It is assumed that all the canisters are intact following emplacement and repository closure. FEPs that occur but which do not significantly affect system behaviour and evolution are only briefly described. FEPs with a low probability of occurrence are mentioned as appropriate. The report provides a map to the key Finnish reports and other work that underlies and supports the description of normal evolution. Differences between the four candidate sites in terms of their expected normal evolution are summarised. None of the differences are sufficient to prevent each site from behaving as a 'normal' site, the evolution of which is summarised over time in the final section of the report. (author)

  15. Normal evolution of a spent fuel repository at the candidate sites in Finland

    Energy Technology Data Exchange (ETDEWEB)

    Grawford, M.B.; Wilmot, R.D. [Galson Sciences Limited, Rutland (United Kingdom)

    1998-12-01

    The Finnish disposal concept for spent nuclear fuel envisages burial of the fuel in a repository excavated at a depth of around 500 m in crystalline bedrock. Since 1983, a programme has been underway in Finland to select a potential site for such a repository. The programme is now in the final stages of selecting one site for further detailed characterisation from a list of four candidate sites at Kivetty, Romuvaara, Olkiluoto, and Haestholmen. Each stage of the site selection process has been supported by a major performance assessment (PA) exercise. The aim of this report is to describe the normal evolution of a repository system at the four candidate Finnish sites as input to development of the next PA, known as TILA-99. The report summarises the disposal concept and the present-day characteristics of each candidate site, and considers the most likely future changes in both the natural environment and the engineered components of the disposal system. The description concentrates on the key features, events and processes (FEPs) controlling behaviour and evolution of the disposal system. It is assumed that all the canisters are intact following emplacement and repository closure. FEPs that occur but which do not significantly affect system behaviour and evolution are only briefly described. FEPs with a low probability of occurrence are mentioned as appropriate. The report provides a map to the key Finnish reports and other work that underlies and supports the description of normal evolution. Differences between the four candidate sites in terms of their expected normal evolution are summarised. None of the differences are sufficient to prevent each site from behaving as a `normal` site, the evolution of which is summarised over time in the final section of the report. (author) 155 refs.

  16. Food production and consumption near the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Hamby, D.M.

    1991-12-31

    Routine operations at the Savannah River Site (SRS) result in the release of radionuclides to the atmosphere and to the Savannah River. The resulting radiological doses to the off-site maximum individual and the 80-km population are estimated on a yearly basis. These estimates are generated using dose models prescribed in the NRC Reg. Guide 1.109 for the commercial nuclear power industry. A study of land and water usage characteristics in the region of the Savannah River Site has been conducted to determine site-specific values of the NRC dose model parameters. The study`s scope included local characteristics of meat, milk, vegetable production; Savannah River recreational activities and fish harvests; meat, milk, vegetable, and seafood consumption rates; and Savannah River drinking-water populations. Average and maximum consumption rates of beef, milk, vegetables, and fish have been determined for individuals residing in the southern United States. The study suggest that many of the consumption rates provided by the NRC may not be appropriate for residents of the South. Average consumption rates are slightly higher than the defaults provided by the NRC. Maximum consumption rates, however, are typically lower than NRC values. Agricultural productivity in the SRS region was found to be quite different than NRC recommendations. Off-site doses have been predicted using both NRC and SRS parameter values to demonstrate the significance of site-specific data.

  17. Food production and consumption near the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Hamby, D.M.

    1991-01-01

    Routine operations at the Savannah River Site (SRS) result in the release of radionuclides to the atmosphere and to the Savannah River. The resulting radiological doses to the off-site maximum individual and the 80-km population are estimated on a yearly basis. These estimates are generated using dose models prescribed in the NRC Reg. Guide 1.109 for the commercial nuclear power industry. A study of land and water usage characteristics in the region of the Savannah River Site has been conducted to determine site-specific values of the NRC dose model parameters. The study's scope included local characteristics of meat, milk, vegetable production; Savannah River recreational activities and fish harvests; meat, milk, vegetable, and seafood consumption rates; and Savannah River drinking-water populations. Average and maximum consumption rates of beef, milk, vegetables, and fish have been determined for individuals residing in the southern United States. The study suggest that many of the consumption rates provided by the NRC may not be appropriate for residents of the South. Average consumption rates are slightly higher than the defaults provided by the NRC. Maximum consumption rates, however, are typically lower than NRC values. Agricultural productivity in the SRS region was found to be quite different than NRC recommendations. Off-site doses have been predicted using both NRC and SRS parameter values to demonstrate the significance of site-specific data.

  18. Inter-modal Transportation of Spent Nuclear Fuel from Office of Civilian Radioactive Waste Management Sites

    International Nuclear Information System (INIS)

    Schmid, St.; Thrower, A.; Best, R.E.

    2009-01-01

    U.S. Department of Energy (DOE) plans to ship most commercial spent nuclear fuel (SNF) by rail in sealed transportation, aging and disposal (TAD) canisters. Based on current and projected dry SNF storage programs, DOE believes the majority of commercial nuclear sites would have the capacity to load and prepare large-capacity, canister-based dry storage canisters such as the proposed TAD systems. Thus, only a small fraction of SNF, such as odd lots and SNF not meeting TAD criteria, is projected for truck (highway) shipment. However, at some commercial facilities rail tracks do not extend to the site, or on-site rail does not extend to the site's proposed loading spot, and inter-modal transfers will be required. Advance coordination between DOE and commercial site operators, commercial carriers, specialized carriers and riggers, and state, tribal and local routing officials will be necessary to establish inter-modal transfer areas and obtain necessary permits to move heavy loads over highways. Although inter-modal transfers can involve a number of steps and several different entities acting in close coordination, such moves are commonly performed by industry and the system requirements are well-understood. (authors)

  19. Siting of a deep repository for spent fuel - how are we communicating the risks?

    International Nuclear Information System (INIS)

    Hammarstroem, Monika

    2000-01-01

    During 1998 the strategy of the Swedish Nuclear Waste Management Company for the siting process was refined in order to strengthen the possibilities for implementing deep geological disposal of spent nuclear fuel. Our new organisation was formed to meet the demands of the strategy. The strategy implies focused activities in municipalities where we are performing so called feasibility studies. An important milestone for us is to be able to choose two sites for site investigations in 2001. The problem of waste exists and has to be taken care of in Sweden. The work is performed in steps to ensure dialogue and changes and modifications if needed. The method for solution is robust, a repository can be constructed in a reasonable time and ensure safety in a long-term perspective Our attitude shall be characterised by high quality and competence in all aspects.Honesty and openness are key words. The fear that people feels regarding radioactive waste shall be taken seriously. We are proud to be able to show one already existing waste management system and of our knowledge and experiences. The results so far from the various communication activities show that we are going in the right direction. The support we are gaining from various sectors in society together with our own motivation and clear objectives will, I'm sure, lead us to at least two sites for site investigations for a deep repository in Sweden by the end of 2001

  20. Waste management units - Savannah River Site

    International Nuclear Information System (INIS)

    1989-10-01

    This report is a compilation of worksheets from the waste management units of Savannah River Plant. Information is presented on the following: Solid Waste Management Units having received hazardous waste or hazardous constituents with a known release to the environment; Solid Waste Management Units having received hazardous waste or hazardous constituents with no known release to the environment; Solid Waste Management Units having received no hazardous waste or hazardous constituents; Waste Management Units having received source; and special nuclear, or byproduct material only

  1. Technical concept for a test of geologic storage of spent reactor fuel in the climax granite, Nevada Test Site

    International Nuclear Information System (INIS)

    Ramspott, L.D.; Ballou, L.B.; Carlson, R.C.; Montan, D.N.; Butkovich, T.R.; Duncan, J.E.; Patrick, W.C.; Wilder, D.G.; Brough, W.G.; Mayr, M.C.

    1979-01-01

    We plan to emplace spent fuel assemblies from an operating commercial nuclear reactor in the Climax granite at the US Department of Energy's Nevada Test Site. In this generic test, 11 canisters of spent fuel will be emplaced with 6 electrical simulator canisters in a storage drift 420 m below in surface and their effects compared. Two adjacent drifts will contain electrical heaters, operated to simulate the temperature-stress-displacement fields of a large repository. We describe the test objectives, the technical issues, the site, the preoperational measurement program, thermal and mechanical response calculations, the characteristics of the spent fuel, the field instrumentation and data-acquisition systems, and the system for handling the spent fuel

  2. Savannah River Site environmental report for 1993 summary pamphlet

    International Nuclear Information System (INIS)

    Karapatakis, L.

    1994-01-01

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

  3. Final disposal of spent nuclear fuel in Finnish bedrock - Kivetty site report

    International Nuclear Information System (INIS)

    Anttila, P.; Ahokas, H.; Front, K.

    1999-06-01

    Posiva Oy is studying the Finnish bedrock for the geological disposal of spent nuclear fuel. The study is based on the site selection research programme started originally in 1983. The programme is in accordance with the decision in principle by the Council of State in 1983 and aims at the selection of one site in 2000. Four sites, Haestholmen in Loviisa, Kivetty in Aeaenekoski, Olkiluoto in Eurajoki and Romuvaara in Kuhmo, have been studied in detail. This report summarises the results of the site investigations carried out at Kivetty. The bedrock of Kivetty belongs to the large Svecofennian granitoid complex of central Finland, about 1880 million years in age. The most common rock type is porphyritic granodiorite, which is cut by younger medium-grained granodiorite and porphyritic or even-grained granite. Minor bodies of gabbro, older than the porphyritic granodiorite, are also present. The granitoids show evidence of two deformation phases. Altogether 29 bedrock 'structures' (R-structures) have been modelled at the investigation site, most of them representing steeply dipping fracture zones. The rock mass between the fracture zones represents what is termed 'intact rock', which is typically hard, unweathered and sparsely fractured. The R-structures are generally hydraulically more conductive than the intact rock and their mean transmissivity is 1.3-10 -6 m 2 /s. The corresponding mean of the hydraulic conductivity values for the intact rock, measured using a 2 m packer interval is 4*10 -11 m 2 /s, if a lognormal distribution for all measured values is assumed. A clear decrease in hydraulic conductivity with depth has been found for the intact rock, and there seems to be a parallel decrease in the transmissivity of structures. In addition, the hydraulically conductive fractures seem to be more frequent and their transmissivities higher in the uppermost 100 - 200 m of the bedrock than at greater depths. The groundwater of Kivetty is classified as fresh water and

  4. Final disposal of spent nuclear fuel in Finnish bedrock - Romuvaara site report

    International Nuclear Information System (INIS)

    Anttila, P.; Ahokas, H.; Front, K.

    1999-06-01

    Posiva Oy is studying the Finnish bedrock for the geological disposal of spent nuclear fuel. The study is based on the site selection research programme started originally in 1983. The programme is in accordance with the decision in principle by the Council of State in 1983 and aims at the selection of one site in 2000. Four sites, Haestholmen in Loviisa, Kivetty in Aeaenekoski, Olkiluoto in Eurajoki and Romuvaara in Kuhmo, have been studied in detail. This report summarises the results of the site investigations carried out at Romuvaara. The bedrock of Romuvaara belongs to the Archean basement complex, whose oldest parts date back over 2800 million years. The bedrock consists mainly of migmatitic banded gneisses (tonalite, leucotonalite and mica gneiss), which are cut by granodiorite and metadiabase dykes. The rocks, excluding the metadiabase, have undergone a polyphase Archaean deformation. Altogether 31 bedrock structures (R-structures) have been modelled at the investigation site, most of them representing steeply dipping fracture zones. The rock mass between the fracture zones represents what is termed 'intact rock', which is typically hard, unweathered and sparsely fractured. The R-structures are generally hydraulically more conductive than the intact rock and their mean transmissivity is 1.6 x 10 -7 m 2 /s. The corresponding mean of the hydraulic conductivity values for the intact rock measured using a 2 m packer interval is 8 x 10 -12 m/s, if a lognormal distribution for all measured values is assumed. A clear decrease in hydraulic conductivity with depth has been found, for both the R-structures and the intact rock. In addition, the hydraulically conductive fractures seem to be more frequent and their transmissivities higher in the uppermost 100 - 200 m of the bedrock than at greater depths. The groundwater of Romuvaara is classified as fresh water and the Total Dissolved Solids (TDS) and chloride contents increase with depth. The chemically most evolved

  5. Final disposal of spent nuclear fuel in Finnish bedrock - Romuvaara site report

    Energy Technology Data Exchange (ETDEWEB)

    Anttila, P. [Fortum Engineering Oy (Finland); Ahokas, H. [Fintact Oy (Finland); Front, K. [VTT Communities and Infrastructure, Espoo (Finland)] [and others

    1999-06-01

    Posiva Oy is studying the Finnish bedrock for the geological disposal of spent nuclear fuel. The study is based on the site selection research programme started originally in 1983. The programme is in accordance with the decision in principle by the Council of State in 1983 and aims at the selection of one site in 2000. Four sites, Haestholmen in Loviisa, Kivetty in Aeaenekoski, Olkiluoto in Eurajoki and Romuvaara in Kuhmo, have been studied in detail. This report summarises the results of the site investigations carried out at Romuvaara. The bedrock of Romuvaara belongs to the Archean basement complex, whose oldest parts date back over 2800 million years. The bedrock consists mainly of migmatitic banded gneisses (tonalite, leucotonalite and mica gneiss), which are cut by granodiorite and metadiabase dykes. The rocks, excluding the metadiabase, have undergone a polyphase Archaean deformation. Altogether 31 bedrock structures (R-structures) have been modelled at the investigation site, most of them representing steeply dipping fracture zones. The rock mass between the fracture zones represents what is termed `intact rock`, which is typically hard, unweathered and sparsely fractured. The R-structures are generally hydraulically more conductive than the intact rock and their mean transmissivity is 1.6 x 10{sup -7} m{sup 2}/s. The corresponding mean of the hydraulic conductivity values for the intact rock measured using a 2 m packer interval is 8 x 10{sup -12} m/s, if a lognormal distribution for all measured values is assumed. A clear decrease in hydraulic conductivity with depth has been found, for both the R-structures and the intact rock. In addition, the hydraulically conductive fractures seem to be more frequent and their transmissivities higher in the uppermost 100 - 200 m of the bedrock than at greater depths. The groundwater of Romuvaara is classified as fresh water and the Total Dissolved Solids (TDS) and chloride contents increase with depth. The chemically

  6. Savannah River Site peer evaluator standards: Operator assessment for restart

    International Nuclear Information System (INIS)

    1990-01-01

    Savannah River Site has implemented a Peer Evaluator program for the assessment of certified Central Control Room Operators, Central Control Room Supervisors and Shift Technical Engineers prior to restart. This program is modeled after the nuclear Regulatory Commission's (NRC's) Examiner Standard, ES-601, for the requalification of licensed operators in the commercial utility industry. It has been tailored to reflect the unique differences between Savannah River production reactors and commercial power reactors

  7. Savannah River Site Environmental Report for 1995 Summary Pamphlet (U)

    International Nuclear Information System (INIS)

    Arnett, M.W.; Mamatey, A.

    1995-01-01

    Welcome to the Savannah River Site Environmental Report for 1995 Summary Pamphlet.Ibis pamphlet is written so you can better understand what goes on at the Savannah River Site and how it affects the environment and you personally. We hope this document also will help answer your questions on radiation and its effects. In this pamphlet we will discuss the operations at SRS, the potential impact of operations on the environment and the public, and special programs that SRS supports. This pamphlet is a summary of a detailed re- port entitled Savannah River Site Environmental Report for 1995 The report contains a summary of environmental Monitoring activities for the calendar year 1995. Additional data on groundwater are found in quarterly groundwater reports

  8. Climatology of the Savannah River Plant site

    International Nuclear Information System (INIS)

    Hoel, D.D.

    1984-06-01

    This document contains information on the climatological characteristics of the SRP site, as well as information on relative concentrations and deposition for specific radionuclides. 42 references, 42 figures, 45 tables

  9. Savannah River Site environmental report for 1997 summary

    International Nuclear Information System (INIS)

    Arnett, M.

    1997-01-01

    The Savannah River Site (SRS) publishes an environmental report each year to provide environmental monitoring and surveillance results to the US Department of Energy (DOE), the public, Congress, state and federal regulators, universities, local governments, the news media, and environmental and civic groups. The Savannah River Site Environmental Report for 1997 (WSRC-TR-97-00322) contains detailed information on site operations, environmental monitoring and surveillance programs, environmental compliance activities, and special projects for calendar year 1997. The purpose of this document is to give a brief overview of the site and its activities, to summarize the site environmental report and the impact of 1997 SRS operations on the environment and the public, and to provide a brief explanation of radiation and dose

  10. Robotics and Automation Activities at the Savannah River Site: A Site Report for SUBWOG 39F

    International Nuclear Information System (INIS)

    Teese, G.D.

    1995-01-01

    The Savannah River Site has successfully used robots, teleoperators, and remote video to reduce exposure to ionizing radiation, improve worker safety, and improve the quality of operations. Previous reports have described the use of mobile teleoperators in coping with a high level liquid waste spill, the removal of highly contaminated equipment, and the inspection of nuclear reactor vessels. This report will cover recent applications at the Savannah River, as well as systems which SRS has delivered to other DOE site customers

  11. Savannah River Site`s Site Specific Plan. Environmental restoration and waste management, fiscal year 1992

    Energy Technology Data Exchange (ETDEWEB)

    1991-08-01

    This Site Specific Plan (SSP) has been prepared by the Savannah River Site (SRS) in order to show the Environmental Restoration and Waste Management activities that were identified during the preparation of the Department of Energy-Headquarters (DOE-HQ) Environmental Restoration and Waste Management Five-Year Plan (FYP) for FY 1992--1996. The SSP has been prepared in accordance with guidance received from DOE-HQ. DOE-SR is accountable to DOE-HQ for the implementation of this plan. The purpose of the SSP is to develop a baseline for policy, budget, and schedules for the DOE Environmental Restoration and Waste Management activities. The plan explains accomplishments since the Fiscal Year (FY) 1990 plan, demonstrates how present and future activities are prioritized, identifies currently funded activities and activities that are planned to be funded in the upcoming fiscal year, and describes future activities that SRS is considering.

  12. Shutdown of the River Water System at the Savannah River Site: Draft environmental impact statement

    International Nuclear Information System (INIS)

    1996-11-01

    This environmental impact statement (EIS) evaluates alternative approaches to and environmental impacts of shutting down the River Water System at the Savannah River Site (SRS). Five production reactors were operated at the site.to support these facilities, the River Water System was constructed to provide cooling water to pass through heat exchangers to absorb heat from the reactor core in each of the five reactor areas (C, K, L, P, and R). The DOE Savannah River Strategic Plan directs the SRS to find ways to reduce operating costs and to determine what site infrastructure it must maintain and what infrastructure is surplus. The River Water System has been identified as a potential surplus facility. Three alternatives to reduce the River Water System operating costs are evaluated in this EIS. In addition to the No-Action Alternative, which consists of continuing to operate the River Water System, this EIS examines one alternative (the Preferred Alternative) to shut down and maintain the River Water System in a standby condition until DOE determines that a standby condition is no longer necessary, and one alternative to shut down and deactivate the River Water System. The document provides background information and introduces the River Water System at the SRS; sets forth the purpose and need for DOE action; describes the alternatives DOE is considering; describes the environment at the SRS and in the surrounding area potentially affected by the alternatives addressed and provides a detailed assessment of the potential environmental impacts of the alternatives; and identifies regulatory requirements and evaluates their applicability to the alternatives considered

  13. Savannah River Site Environmental Report for 1999

    International Nuclear Information System (INIS)

    Arnett, M.

    2000-01-01

    The purpose of this report is to present summary environmental data that characterize site environmental management performance, confirm compliance with environmental standards and requirements, highlight significant programs and efforts, and assess the impact of SRS operations on the public and the environment

  14. Savannah River Site Environmental Report for 1999

    Energy Technology Data Exchange (ETDEWEB)

    Arnett, M.

    2000-06-30

    The purpose of this report is to present summary environmental data that characterize site environmental management performance, confirm compliance with environmental standards and requirements, highlight significant programs and efforts, and assess the impact of SRS operations on the public and the environment.

  15. Savannah River Site Environmental report for 2012

    Energy Technology Data Exchange (ETDEWEB)

    Griffith, Michael; Jannik, Timothy; Cauthen, Kim; Bryant, Tracy; Coward, Lori; Eddy, Teresa; Vangelas, Karen; O' Quinn, Sadika; Meyer, Amy; Ackerman, Jana D.; Adams, John; Fanning, Greta; Thompson, Martha; Farfan, Eduardo B.; Dixon, Kenneth L.; Kemmerlin, Robert; Millings, Ted; Maxwell, Sherrod; Blas, Susan; Looney, Brian; Jackson, Dennis; Paller, Michael; Wabbersen, William

    2013-09-12

    This report is an overview of effluent monitoring and environmental surveillance activities conducted on and in the vicinity of SRS from January 1 through December 31, 2012 - including the Site's performance against applicable standards and requirements. Details are provided on major programs such as the Environmental Management System (EMS) and permit compliance.

  16. The Site Selected. The Local Decision-Making Regarding the Siting of the Spent Nuclear Fuel Repository in Olkiluoto

    International Nuclear Information System (INIS)

    Kojo, Matti

    2006-01-01

    In May 1999 Posiva, the company responsible for the final disposal of spent nuclear fuel in Finland, suggested that the Finnish Government considers only Olkiluoto in Eurajoki in its application of a decision in principle to be a final disposal site. In January 2000 the municipal council of Eurajoki made a positive statement on the decision in principle. The Government made the decision in principle in Dec 2000, and the Parliament ratified the decision in May 2001. The paper is focused on the decision making of Eurajoki municipality regarding the siting of the spent nuclear fuel repository. The paper shows how the interaction between the representatives of the candidate municipality and the nuclear energy industry was the crucial factor in the decision-making. Eurajoki serves as an example, in where the parties reached an agreement of the compensations for the final disposal repository. The negotiations between the Eurajoki municipality and the nuclear energy industry in reaching a positive decision are analysed from the beginning of the 1980s. The main emphasis is however on the years 1996-99, when the nuclear energy industry negotiated with the municipality on the compensation for the final disposal repository. The loss of income was an important reason why some of the councillors of Eurajoki were interested in having the final disposal repository in Olkiluoto. The industry's problem on the other hand was to safeguard the final disposal site. From the TVO's angle Olkiluoto was a potential final disposal site for example for its limited need for transport and for the existing infrastructure. The company used the financial benefits of the project as its trump card. The attitude of Eurajoki municipality to the final disposal of spent nuclear fuel turned positive with the Olkiluoto vision in December 1998, when still five years earlier the municipal council was prepared to act and prevent the final disposal. The future image presented by the municipality now matched

  17. The Site Selected. The Local Decision-Making Regarding the Siting of the Spent Nuclear Fuel Repository in Olkiluoto

    Energy Technology Data Exchange (ETDEWEB)

    Kojo, Matti [Univ. of Tampere (Finland). Dept. of Political Science and International Relations

    2006-09-15

    In May 1999 Posiva, the company responsible for the final disposal of spent nuclear fuel in Finland, suggested that the Finnish Government considers only Olkiluoto in Eurajoki in its application of a decision in principle to be a final disposal site. In January 2000 the municipal council of Eurajoki made a positive statement on the decision in principle. The Government made the decision in principle in Dec 2000, and the Parliament ratified the decision in May 2001. The paper is focused on the decision making of Eurajoki municipality regarding the siting of the spent nuclear fuel repository. The paper shows how the interaction between the representatives of the candidate municipality and the nuclear energy industry was the crucial factor in the decision-making. Eurajoki serves as an example, in where the parties reached an agreement of the compensations for the final disposal repository. The negotiations between the Eurajoki municipality and the nuclear energy industry in reaching a positive decision are analysed from the beginning of the 1980s. The main emphasis is however on the years 1996-99, when the nuclear energy industry negotiated with the municipality on the compensation for the final disposal repository. The loss of income was an important reason why some of the councillors of Eurajoki were interested in having the final disposal repository in Olkiluoto. The industry's problem on the other hand was to safeguard the final disposal site. From the TVO's angle Olkiluoto was a potential final disposal site for example for its limited need for transport and for the existing infrastructure. The company used the financial benefits of the project as its trump card. The attitude of Eurajoki municipality to the final disposal of spent nuclear fuel turned positive with the Olkiluoto vision in December 1998, when still five years earlier the municipal council was prepared to act and prevent the final disposal. The future image presented by the municipality

  18. Tiger Team Assessment of the Savannah River Site: Appendices

    International Nuclear Information System (INIS)

    1990-06-01

    This draft document contains findings identified during the Tiger Team Compliance Assessment of the US Department of Energy Savannah River Site (SRS), located in three countries (Aiken, Barnwell and Allendale), South Carolina. The Assessment was directed by the Department's Office of the Assistant Secretary for Environment, Safety, and Health (ES ampersand H) and was conducted from January 29 to March 23, 1990. The Savannah River Site Tiger Team Compliance Assessment was broad in scope covering the Environment, Safety and Health, and Management areas and was designed to determine the site's compliance with applicable Federal (including DOE), state, and local regulations and requirements. The scope of the Environmental assessment was sitewide while the Safety and Health assessments included site operating facilities (except reactors), and the sitewide elements of Aviation Safety, Emergency Preparedness, Medical Services, and Packaging and Transportation. This report contains the appendices to the assessment

  19. Tiger Team Assessment of the Savannah River Site

    International Nuclear Information System (INIS)

    1990-06-01

    This draft document contains findings identified during the Tiger Team Compliance Assessment of the US Department of Energy Savannah River Site (SRS), located in three counties (Aiken, Barnwell and Allendale), South Carolina. The Assessment was directed by the Department's Office of the Assistant Secretary for Environment, Safety, and Health (ES ampersand H) and was conducted from January 29 to March 23, 1990. The Savannah River Site Tiger Team Compliance Assessment was broad in scope covering the Environment, Safety and Health, and Management areas and was designed to determine the site's compliance with applicable Federal (including DOE), state, and local regulations and requirements. The scope of the Environmental assessment was sitewide while the Safety and Health assessments included site operating facilities (except reactors), and the sitewide elements of Aviation Safety, Emergency Preparedness, Medical Services, and Packaging and Transportation

  20. Savannah River Site environmental report for 1996 summary

    International Nuclear Information System (INIS)

    Arnett, M.W.

    1997-01-01

    The Savannah River Site (SRS) publishes an environmental report each year to provide environmental monitoring and surveillance results to the US department of Energy (DOE), the public, Congress, state and federal regulators, universities, local governments, the news media, environmental and civic groups. The Savannah River Site Environmental Report for 1996 (WSRC-TR-97-0171) contains detailed information on site operations, environmental monitoring and surveillance programs, environmental compliance activities, and special projects for the calendar year 1996. The purpose of this document is to give a brief overview of the site and its activities, to summarize the report and the impact of 1996 SRS operations on the environment and the public, and to provide a brief explanation of radiation and dose

  1. Savannah River Site environmental restoration lessons learned program

    International Nuclear Information System (INIS)

    Plunkett, R.A.; Leibfarth, E.C.; Treger, T.M.; Blackmon, A.M.

    1993-01-01

    For the past three years environmental restoration has been formally consolidated at Savannah River Site. Accomplishments include waste site investigations to closure activities. Positive, as well as negatively impacting, events have occurred. Until recently, lessons learned were captured on a less than formal basis. Now, a program based upon critiques, evaluations and corrective actions is being used. This presentation reviews the development, implementation and use of that program

  2. Savannah River Site Surplus Facilities Available for Reuse

    International Nuclear Information System (INIS)

    Clarke, R.M.; Owens, M.B.; Lentz, D.W.

    1995-01-01

    The purpose of this document is to provide a current, centralized list of Savannah River Site facilities, which are surplus and available for reuse. These surplus facilities may be made available for other DOE site missions, commercial economic development reuse, or other governmental reuse. SRS procedures also require that before new construction can be approved, available surplus facilities are screened for possible reuse in lieu of the proposed new construction

  3. Final disposal of spent nuclear fuel in Finnish bedrock. Olkiluoto site report

    International Nuclear Information System (INIS)

    Anttila, P.; Ahokas, H.; Front, K.

    1999-06-01

    Posiva Oy is studying the Finnish bedrock for the geological disposal of spent nuclear fuel. The study is based on the site selection research programme started originally in 1983. The programme is in accordance with the decision in principle by the Council of State in 1983 and aims at the selection of one site in 2000. Four sites, Haestholmen in Loviisa, Kivetty in Aeaenekoski, Olkiluoto in Eurajoki and Romuvaara in Kuhmo, have been studied in detail. This report summarises the results of the site investigations carried out at Olkiluoto. The bedrock of the Olkiluoto site consists of Svecofennian metasediments and platonic rocks, 1800-1900 million years in age. Migmatitic mica gneiss is the most abundant rock type, and is intruded by foliated tonalites and granodiorites and massive coarse-grained granites and pegmatites. Five successive plastic deformation phases have been defined. In total, 30 bedrock structures (R-structures) have been modelled at the site. Most of these represent steeply dipping fracture zones, but several sub-horizontal zones, gently dipping to the SE, have also been identified. The rock mass between the fracture zones represents what is termed 'intact rock', which is typically hard, unweathered and sparsely fractured. The R-structures are generally hydraulically more conductive than the intact rock and their mean transmissivity is 3 x 10 -7 m 2 /s. The corresponding mean of the hydraulic conductivity values for the intact rock measured using a 2 m packer interval, is 8 x 10 -13 m/s, if a lognormal distribution for all measured values is assumed. A clear decrease in hydraulic conductivity with depth has been found for the intact rock, and there seems to be a parallel decrease in the transmissivity of structures. In addition, the hydraulically conductive fractures seem to be more frequent and their transmissivities higher in the uppermost 100 - 200 m of the bedrock than at greater depths. The groundwater chemistry reflects the postglacial

  4. Final disposal of spent nuclear fuel in Finnish bedrock. Olkiluoto site report

    Energy Technology Data Exchange (ETDEWEB)

    Anttila, P. [Fortum Engineering Oy, Vantaa (Finland); Ahokas, H. [Fintact Oy, Helsinki (Finland); Front, K. [VTT Communication and Infrastructure, Espoo (Finland)] [and others

    1999-06-01

    Posiva Oy is studying the Finnish bedrock for the geological disposal of spent nuclear fuel. The study is based on the site selection research programme started originally in 1983. The programme is in accordance with the decision in principle by the Council of State in 1983 and aims at the selection of one site in 2000. Four sites, Haestholmen in Loviisa, Kivetty in Aeaenekoski, Olkiluoto in Eurajoki and Romuvaara in Kuhmo, have been studied in detail. This report summarises the results of the site investigations carried out at Olkiluoto. The bedrock of the Olkiluoto site consists of Svecofennian metasediments and platonic rocks, 1800-1900 million years in age. Migmatitic mica gneiss is the most abundant rock type, and is intruded by foliated tonalites and granodiorites and massive coarse-grained granites and pegmatites. Five successive plastic deformation phases have been defined. In total, 30 bedrock structures (R-structures) have been modelled at the site. Most of these represent steeply dipping fracture zones, but several sub-horizontal zones, gently dipping to the SE, have also been identified. The rock mass between the fracture zones represents what is termed `intact rock`, which is typically hard, unweathered and sparsely fractured. The R-structures are generally hydraulically more conductive than the intact rock and their mean transmissivity is 3 x 10{sup -7} m{sup 2}/s. The corresponding mean of the hydraulic conductivity values for the intact rock measured using a 2 m packer interval, is 8 x 10{sup -13} m/s, if a lognormal distribution for all measured values is assumed. A clear decrease in hydraulic conductivity with depth has been found for the intact rock, and there seems to be a parallel decrease in the transmissivity of structures. In addition, the hydraulically conductive fractures seem to be more frequent and their transmissivities higher in the uppermost 100 - 200 m of the bedrock than at greater depths. The groundwater chemistry reflects the

  5. The Savannah River Site's Groundwater Monitoring Program

    Energy Technology Data Exchange (ETDEWEB)

    1992-08-03

    This report summarizes the Savannah River Site (SRS) groundwater monitoring program conducted during the first quarter of 1992. It includes the analytical data, field data, data review, quality control, and other documentation for this program; provides a record of the program's activities; and serves as an official document of the analytical results.

  6. Numerical Weather Forecasting at the Savannah River Site

    International Nuclear Information System (INIS)

    Buckley, R.L.

    1999-01-01

    Facilities such as the Savannah River Site (SRS), which contain the potential for hazardous atmospheric releases, rely on the predictive capabilities of dispersion models to assess possible emergency response actions. The operational design in relation to domain size and forecast time is presented, along with verification of model results over extended time periods with archived surface observations

  7. The Savannah River Site's groundwater monitoring program

    Energy Technology Data Exchange (ETDEWEB)

    1991-10-18

    This report summarizes the Savannah River Site (SRS) groundwater monitoring program conducted by EPD/EMS in the first quarter of 1991. In includes the analytical data, field data, data review, quality control, and other documentation for this program, provides a record of the program's activities and rationale, and serves as an official document of the analytical results.

  8. Onsite transportation of radioactive materials at the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Watkins, R.

    2015-03-03

    The Savannah River Site (SRS) Transportation Safety Document (TSD) defines the onsite packaging and transportation safety program at SRS and demonstrates its compliance with Department of Energy (DOE) transportation safety requirements, to include DOE Order 460.1C, DOE Order 461.2, Onsite Packaging and Transfer of Materials of National Security Interest, and 10 CFR 830, Nuclear Safety Management (Subpart B).

  9. Regulatory Support of Treatment of Savannah River Site Purex Waste

    International Nuclear Information System (INIS)

    Reid, L.T.

    2009-01-01

    This paper describes the support given by federal and state regulatory agencies to Savannah River Site (SRS) during the treatment of an organic liquid mixed waste from the Plutonium Extraction (Purex) process. The support from these agencies allowed (SRS) to overcome several technical and regulatory barriers and treat the Purex waste such that it met LDR treatment standards. (authors)

  10. Radiological impact of 2016 operations at the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Minter, K. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Jannik, G. T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Dixon, K. M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-06-01

    This report presents the environmental dose assessment methods and the estimated potential doses to the offsite public from 2016 Savannah River Site (SRS) air and liquid radioactive releases. Also documented are potential doses from special-case exposure scenarios, such as the consumption of wildlife or goat milk.

  11. Site-specific issues related to structural/seismic design of an underground independent spent fuel storage installation (ISFSI)

    International Nuclear Information System (INIS)

    Tripathi, B.P.

    2005-01-01

    Utilities owning and operating commercial nuclear power plants (NPP) in USA may choose to build an underground Independent Spent Fuel Storage Installation (ISFSI) to store the spent nuclear fuels. The regulatory requirements and other guidance are based on 10 CFR Part 72, Regulatory Guide RG 3.73, Standard Review Plans NUREG-1536 and NUREG-1567, and Interim staff Guidance (ISG) documents as applicable. Structures, Systems, and Components (SSCs) classified as important to safety are designed to withstand the effects of site-specific environmental conditions and natural phenomena such as earthquake, tornado, flood, etc. An underground ISFSI for storage of spent nuclear fuel, presents some unique analysis and design challenges. This paper will briefly address some of these challenges and discuss site-specific loads, including seismic for the ISFSI design. (authors)

  12. New appraisement of siting for a NPP on Mures river

    International Nuclear Information System (INIS)

    Traian Mauna

    2010-01-01

    The studies for a second NPP siting on inner Romanian rivers began in a careful manner since 1982 as a first part of the Nuclear Power Plant Romanian Program adopted by political and governmental authorities at the time. The experience gained from Cernavoda NPP siting, the first mission of new multi-branch of specialists team was to choose new NPP sites adapting the CANDU type NPP Cernavoda project to the new parameters of close water cooling circuit and of hard less or no rock foundation strata. The new sites conditions mean a lot of changes of CANDU license and a decrease the output power supplied to the national electric grid. The studies on the Mures river as alternative site of Olt river in Transylvania region began in 1986 and were stopped after 1990. This paper tries to reconsider shortly the old analysis focused on geological and geotechnical aspects and other local sites characteristics according to the last IAEA Safety Standards taking into account also the last types of NPP generations and the number of units. (author)

  13. Final disposal of spent nuclear fuel in Finnish bedrock - Kivetty site report

    Energy Technology Data Exchange (ETDEWEB)

    Anttila, P. [Fortum Engineering Oy, Vantaa (Finland); Ahokas, H.; Front, K. [Fintact Oy (Finland)] [and others

    1999-06-01

    Posiva Oy is studying the Finnish bedrock for the geological disposal of spent nuclear fuel. The study is based on the site selection research programme started originally in 1983. The programme is in accordance with the decision in principle by the Council of State in 1983 and aims at the selection of one site in 2000. Four sites, Haestholmen in Loviisa, Kivetty in Aeaenekoski, Olkiluoto in Eurajoki and Romuvaara in Kuhmo, have been studied in detail. This report summarises the results of the site investigations carried out at Kivetty. The bedrock of Kivetty belongs to the large Svecofennian granitoid complex of central Finland, about 1880 million years in age. The most common rock type is porphyritic granodiorite, which is cut by younger medium-grained granodiorite and porphyritic or even-grained granite. Minor bodies of gabbro, older than the porphyritic granodiorite, are also present. The granitoids show evidence of two deformation phases. Altogether 29 bedrock 'structures' (R-structures) have been modelled at the investigation site, most of them representing steeply dipping fracture zones. The rock mass between the fracture zones represents what is termed 'intact rock', which is typically hard, unweathered and sparsely fractured. The R-structures are generally hydraulically more conductive than the intact rock and their mean transmissivity is 1.3-10{sup -6} m{sup 2}/s. The corresponding mean of the hydraulic conductivity values for the intact rock, measured using a 2 m packer interval is 4*10{sup -11} m{sup 2}/s, if a lognormal distribution for all measured values is assumed. A clear decrease in hydraulic conductivity with depth has been found for the intact rock, and there seems to be a parallel decrease in the transmissivity of structures. In addition, the hydraulically conductive fractures seem to be more frequent and their transmissivities higher in the uppermost 100 - 200 m of the bedrock than at greater depths. The groundwater of

  14. SKI's engagement in the process for siting a spent nuclear fuel repository

    Energy Technology Data Exchange (ETDEWEB)

    Paeivioe Jonsson, Josefin; Westerlind, Magnus [Swedish Nuclear Power Inspectorate, Stockholm (Sweden)

    2006-09-15

    In Sweden, issues concerning the disposal of nuclear waste historically required co-operation among primarily two main actors: The nuclear industry and the state. Municipalities involved in SKB's feasibility studies objected to the fact that they lacked resources to keep the people in the municipality informed about the ongoing work. As a result the Parliament decided that municipalities involved in SKB's siting process should receive money from the nuclear waste fund for their engagement. Since 2005 resources also have been made available for NGO's participating in SKB's ongoing EIA-process. In total they can yearly receive up to 2.5 million Swedish kronor. The fact that new actors continuously have been engaged in disposal of spent nuclear fuel has meant that 'old' actors, particularly SKB, the regulators (the Swedish Nuclear Power Inspectorate, SKI, and the Swedish Radiation Protection Authority, SSI) have had to evaluate, develop and clarify their roles and strategies for dialogue and regulatory oversight. This paper presents the effects the increased engagement has had on SKI's regulatory activities. Looking back it is possible to identify two well-defined break points in SKI's views on communication and active participation in the siting process. The first was the so-called DIALOGUE-project, which was initiated by SKI in the early 1990s. In this research project there were participants from e.g. SKI and SSI, municipalities and environmental organisations. The two most important conclusions for SKI were firstly that regulators can and should participate already in the early stages of a siting process, and that this can be done without loosing credibility as an independent reviewer of a licence application and secondly that actors (in the siting process) with conflicting interests and views can reach agreement on the basis for decisions. The second break point occurred in the mid 1990s when SKB announced that the

  15. Engineering assessment of inactive uranium mill tailings, Green River Site, Green River, Utah

    International Nuclear Information System (INIS)

    1981-08-01

    Ford, Bacon and Davis Utah Inc. has reevaluated the Green River site in order to revise the December 1977 engineering assessment of the problems resulting from the existence of radioactive uranium mill tailings at Green River, Utah. This evaluation has included the preparation of topographic maps, the performance of core drillings and radiometric measurements sufficient to determine areas and volumes of tailings and radiation exposures of individuals and nearby populations, the investigations of site hydrology and meteorology, and the evaluation and costing of alternative remedial actions. Radon gas released from the 123,000 tons of tailings at the Green River site constitutes the most significant environmental impact, although windblown tailings and external gamma radiation also are factors

  16. The Savannah River site`s groundwater monitoring program: second quarter 1997

    Energy Technology Data Exchange (ETDEWEB)

    Rogers, C.D. [Westinghouse Savannah River Company, AIKEN, SC (United States)

    1997-11-01

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During second quarter 1997, EPD/EMS conducted extensive sampling of monitoring wells. A detailed explanation of the flagging criteria is presented in the Flagging Criteria section of this document. Analytical results from second quarter 1997 are included in this report.

  17. The Savannah River Site`s Groundwater Monitoring Program, third quarter 1991

    Energy Technology Data Exchange (ETDEWEB)

    1992-02-17

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During third quarter 1991, EPD/EMS conducted extensive sampling of monitoring wells. Analytical results from third quarter 1991 are listed in this report.

  18. 78 FR 26005 - Environmental Management Site-Specific Advisory Board, Savannah River Site

    Science.gov (United States)

    2013-05-03

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Savannah River Site. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  19. 78 FR 65979 - Environmental Management Site-Specific Advisory Board, Savannah River Site

    Science.gov (United States)

    2013-11-04

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Savannah River Site. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  20. 78 FR 40130 - Environmental Management Site-Specific Advisory Board, Savannah River Site

    Science.gov (United States)

    2013-07-03

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Savannah River Site. The Federal Advisory Committee Act (Pub. L. No. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  1. 77 FR 24695 - Environmental Management Site-Specific Advisory Board, Savannah River Site

    Science.gov (United States)

    2012-04-25

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Savannah River Site. The Federal Advisory Committee Act (Pub. L. . 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  2. 77 FR 60688 - Environmental Management Site-Specific Advisory Board, Savannah River Site

    Science.gov (United States)

    2012-10-04

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Savannah River Site. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  3. 77 FR 13104 - Environmental Management Site-Specific Advisory Board, Savannah River Site

    Science.gov (United States)

    2012-03-05

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Savannah River Site. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  4. 77 FR 39235 - Environmental Management Site-Specific Advisory Board, Savannah River Site

    Science.gov (United States)

    2012-07-02

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Savannah River Site. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  5. 78 FR 716 - Environmental Management Site-Specific Advisory Board, Savannah River Site

    Science.gov (United States)

    2013-01-04

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Savannah River Site. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  6. 78 FR 16260 - Environmental Management Site-Specific Advisory Board, Savannah River Site

    Science.gov (United States)

    2013-03-14

    ...On March 4, 2013, the Department of Energy (DOE) published a notice of open meeting announcing a meeting on March 25-26, 2013 of the Environmental Management Site-Specific Advisory Board, Savannah River Site (78 FR 14088). This document makes a correction to that notice.

  7. 78 FR 54461 - Environmental Management Site-Specific Advisory Board, Savannah River Site

    Science.gov (United States)

    2013-09-04

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Savannah River Site. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  8. 77 FR 53193 - Environmental Management Site-Specific Advisory Board, Savannah River Site

    Science.gov (United States)

    2012-08-31

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Savannah River Site. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  9. Savannah River Site Environmental Report for 1990: Summary pamphlet

    International Nuclear Information System (INIS)

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

    1991-01-01

    The SRS publishes the Environmental Report each year to communicate the endings of the environmental monitoring and research programs to the public and government agencies. This pamphlet is intended to summarize important environmental activities at the Savannah River Site in 1990. Highlights include: In 1990, over 40,000 samples of environmental material were collected for radiological and nonradiological analyses. The largest radiation doses to the surrounding population were from the radionuclide ''tritium,'' which was released to air and water from SRS operations.; tritium concentrations measured near the site in air, rainwater, Savannah River water, milk from local dairies and downriver drinking water were higher than background levels; the maximum radiation dose to individuals offsite was estimated to be 0.16 millirem from atmospheric releases of radioactivity, and 0.17 millirem from liquid releases of radioactivity. There was one accidental release of tritium to air on February 7, when 100 curies were released from a K-Area stack. The maximum radiation dose offsite was calculated to be 0.003 millirem (mrem); SRS issued a detailed report on the impact of routine and accidental releases of tritium from 1964 to 1988 on the environment. Currently, SRS investigating possible causes for higher concentrations of mercury found in fish caught onsite, compared to those taken from the Savannah River. Mercury concentrations have been higher in onsite fish since 1989; and, n response to concerns expressed by the Georgia Department of Natural Resources (GDNR) over concentrations of radionuclides in fish collected from the Savannah River, the Savannah River Site is working with the GDNR to resolve technical issues regarding sampling and analyses of fish from the river and the resultant dose calculations

  10. Risk assessment for nuclear processes at the Savannah River Site

    International Nuclear Information System (INIS)

    Durant, W.S.

    1992-01-01

    The Savannah River Site, one of the US Department of Energy's nuclear materials processing facilities, has for many years conducted risk-based safety analyses for the nuclear processes conducted at the facilities. This approach has allowed comparisons of risks to established criteria for acceptability. When the risk-based program was begun, it was evident that its success would depend upon having a compilation of data that was site specific. The decision was made to create a data bank of undesirable events that had occurred at the site's nuclear fuel reprocessing facilities. From this modest beginning, five data banks have been created for nuclear fuel reprocessing, waste management, nuclear fuel fabrication, tritium operations, and the Savannah River Technology Center. In addition to the primary purpose of providing a sound basis for risk-based safety analyses, these highly versatile data banks are routinely used for equipment breakdown histories, incident investigations, design studies, project justifications, reliability studies, process problem solving, training, and audits

  11. The Savannah River Site's Groundwater Monitoring Program

    Energy Technology Data Exchange (ETDEWEB)

    1989-01-01

    The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site's Groundwater Monitoring Program. During fourth quarter 1989 (October--December), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria aid personnel in sample scheduling, interpretation of data, and trend identification. An explanation of flagging criteria for the fourth quarter is presented in the Flagging Criteria section of this document. All analytical results from fourth quarter 1989 are listed in this report, which is distributed to all waste-site custodians.

  12. Machinery Vibration Monitoring Program at the Savannah River Site

    International Nuclear Information System (INIS)

    Potvin, M.M.

    1990-01-01

    The Reactor Maintenance's Machinery Vibration Monitoring Program (MVMP) plays an essential role in ensuring the safe operation of the three Production Reactors at the Westinghouse Savannah River Company (WRSC) Savannah River Site (SRS). This program has increased machinery availability and reduced maintenance cost by the early detection and determination of machinery problems. This paper presents the Reactor Maintenance's Machinery Vibration Monitoring Program, which has been documented based on Electric Power Research Institute's (EPRI) NP-5311, Utility Machinery Monitoring Guide, and some examples of the successes that it has enjoyed

  13. Floodplain sedimentology and sediment accumulation assessment – Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Yeager, Kevin M. [Univ. of Kentucky, Lexington, KY (United States). Dept. of Earth and Environmental Sciences

    2016-01-03

    The primary goal of the larger research program, of which this work is one component, is to restore the hydrodynamics and energy gradients of targeted Savannah River Site (SRS) streams to a condition comparable to local natural streams or rivers of similar order, and to stabilize sediment transport (net degradation/aggregation) with the assumption that the faunal components of these systems will quickly recover on their own (e.g., Pen Branch; Lakly and McArthur, 2000). This work is specifically focused on the identification of near-stream floodplain areas that exhibit sediment deposition or erosion, and the quantification of these processes over a historical time scale (last ~100 years).

  14. Bagless transfer at the Savannah River Site

    International Nuclear Information System (INIS)

    Rogers, L.; Jones, R.H.

    1995-01-01

    With the end of the Cold War buildup, the U.S. Department of Energy (DOE) complex is shifting its focus from producing nuclear weapons to cleaning up, packaging, and storing excess materials and associated by-products. Old transfer and interim storage methods are now being reevaluated in the context of the recent long-term storage criteria. One of the methods used for the interim storage of plutonium/uranium products in the past involved the use of a bagout technique. In reviewing interim storage containers, it was found that the plastic bags used in this technique are not suitable for use inside long-term storage containers because they release gases that cause container pressurization and associated problems. As the DOE synthesized its long-term plutonium storage criteria, plastic bags and other organics were banned from use in future storage processes to prevent these types of problems. In response to these problems and the subsequent long-term storage criteria, the DOE sites began to pursue alternate material transferral methods

  15. Final disposal of spent nuclear fuel-equipment for site characterization

    International Nuclear Information System (INIS)

    Almen, K.; Hansson, K.; Johansson, B.E.; Nilsson, G.; Andersson, O.; Wikberg, P.; Aahagen, H.

    1983-05-01

    The suitability of a certain geological formation as a repository for the final disposal of spent nuclear fuel can be determined only after detailed investigation and analysis. The purpose of the investigations is to provide information on the geology and the hydrology and chemistry of the site concerned. The value of these data largely depends on the way in which they have been collected. The report of the findings should enable the investigating party to evaluate the function and the accuracy of the equipment with which field data have been collected for KBS 3. This report describes the geophysical equipment, the hydraulic testing equipment, the water chemistry sample extracting equipment and the core-logging equipment used. The objectives of the instrument development have been: - to obtain a high data quality. - to collect data automatically in logs and tape recorders for direct transfer to a central processing unit. - to provide back-up in order to counteract loss of data. - to make instrument more efficient. (author)

  16. Facility siting as a decision process at the Savannah River Site

    International Nuclear Information System (INIS)

    Wike, L.D.

    1995-01-01

    Site selection for new facilities at Savannah River Site (SRS) historically has been a process dependent only upon specific requirements of the facility. While this approach is normally well suited to engineering and operational concerns, it can have serious deficiencies in the modern era of regulatory oversight and compliance requirements. There are many issues related to the site selection for a facility that are not directly related to engineering or operational requirements; such environmental concerns can cause large schedule delays and budget impact,s thereby slowing or stopping the progress of a project. Some of the many concerns in locating a facility include: waste site avoidance, National Environmental Policy Act requirements, Clean Water Act, Clean Air Act, wetlands conservation, US Army Corps of Engineers considerations, US Fish and Wildlife Service statutes including threatened and endangered species issues, and State of South Carolina regulations, especially those of the Department of Health and Environmental Control. In addition, there are SRS restrictions on research areas set aside for National Environmental Research Park (NERP), Savannah River Ecology Laboratory, Savannah River Forest Station, University of South Carolina Institute of Archaeology and Anthropology, Southeastern Forest Experimental Station, and Savannah River Technology Center (SRTC) programs. As with facility operational needs, all of these siting considerations do not have equal importance. The purpose of this document is to review recent site selection exercises conducted for a variety of proposed facilities, develop the logic and basis for the methods employed, and standardize the process and terminology for future site selection efforts

  17. Site selection - location of the repository for spent nuclear fuel; Platsval - lokalisering av slutfoervaret foer anvaent kaernbraensle

    Energy Technology Data Exchange (ETDEWEB)

    2010-12-15

    This document describes the localization work and SKB's choice of site for the repository. Furthermore, SKB's basis and rationale for the decisions taken during the work are reported. The document is Appendix PV of applications under the Nuclear Activities Act and the Environmental Code to both build and operate an encapsulation plant adjacent to the central interim storage facility for spent nuclear fuel in Oskarshamn, and to construct and operate a disposal facility for spent nuclear fuel at Forsmark in Oesthammar municipality

  18. Nuclear engineering R ampersand D at the Savannah River Site

    International Nuclear Information System (INIS)

    Strosnider, D.R.; Ferrara, W.R.

    1991-01-01

    The Westinghouse Savannah River Company (WSRC) is the prime operating contractor for the US Department of Energy at the Savannah River Site (SRS), located near Aiken, South Carolina. One division of WSRC, the Savannah River Laboratory (SRL), has the primary responsibility for research and development, which includes supporting the safe and efficient operation of the SRS production reactors. Several Sections of SRL, as well as other organization in WSRC, pursue R ampersand D and oversight activities related to nuclear engineering. The Sections listed below are described in more detail in this document: (SRL) nuclear reactor technology and scientific computations department; (SRL) safety analysis and risk management department; (WSRC) new production reactor program; and (WSRC) environment, safety, health, and quality assurance division

  19. River and river-related drainage area parameters for site investigation program

    International Nuclear Information System (INIS)

    Blomqvist, P.; Brunberg, A.K.; Brydsten, L.

    2001-05-01

    In this paper, a number of parameters of importance to a determination of the function of running waters as transport channels for material from the continents to the sea are presented. We have assumed that retention mechanisms of material in the river and in the riparian zone will be covered by special investigations but tried to create a platform for such investigations by quantification of the extension of different main habitats. The choice of parameters has been made so that also the nature conservation value of the river can be preliminary established, and includes a general description of the river type and the inherent ecosystem. The material links directly to that presented in a previous report concerning site investigation programmes for lakes. The parameters have been divided into five groups: 1) The location of the object relative important gradients in the surrounding nature; 2) The river catchment area and its major constituents; 3) The river morphometry; 4) The river ecosystem; 5) Human-induced damages to the river ecosystem. The first two groups, principally based on the climate, hydrology, geology and vegetation of the catchment area, represent parameters that can be used to establish the rarity and representativity of the system, and will in the context of site investigation program be used as a basis for generalisation of the results. The third group, the river morphometry parameters, are standard parameters for the outline of sampling programmes and for calculations of the physical extension of key habitats in the system. The fourth group, the ecosystem of the river, includes physical, chemical and biological parameters required for determination of the influence from the terrestrial ecosystem of the catchment area, nutrient status, distribution of different habitats, and presence of fish in the system. In the context of site investigation program, the parameters in these two groups will be used for budget calculations of the flow of energy and

  20. River and river-related drainage area parameters for site investigation program

    Energy Technology Data Exchange (ETDEWEB)

    Blomqvist, P.; Brunberg, A.K. [Uppsala Univ. (Sweden). Dept. of Limnology; Brydsten, L. [Umeaa Univ. (Sweden). Dept. of Ecology and Environmental Science

    2001-05-01

    In this paper, a number of parameters of importance to a determination of the function of running waters as transport channels for material from the continents to the sea are presented. We have assumed that retention mechanisms of material in the river and in the riparian zone will be covered by special investigations but tried to create a platform for such investigations by quantification of the extension of different main habitats. The choice of parameters has been made so that also the nature conservation value of the river can be preliminary established, and includes a general description of the river type and the inherent ecosystem. The material links directly to that presented in a previous report concerning site investigation programmes for lakes. The parameters have been divided into five groups: 1) The location of the object relative important gradients in the surrounding nature; 2) The river catchment area and its major constituents; 3) The river morphometry; 4) The river ecosystem; 5) Human-induced damages to the river ecosystem. The first two groups, principally based on the climate, hydrology, geology and vegetation of the catchment area, represent parameters that can be used to establish the rarity and representativity of the system, and will in the context of site investigation program be used as a basis for generalisation of the results. The third group, the river morphometry parameters, are standard parameters for the outline of sampling programmes and for calculations of the physical extension of key habitats in the system. The fourth group, the ecosystem of the river, includes physical, chemical and biological parameters required for determination of the influence from the terrestrial ecosystem of the catchment area, nutrient status, distribution of different habitats, and presence of fish in the system. In the context of site investigation program, the parameters in these two groups will be used for budget calculations of the flow of energy and

  1. Radiological pathways analysis for spent solvents from the boiler chemical cleaning at the Pickering Nuclear Site

    International Nuclear Information System (INIS)

    Garisto, N.C.; Eslami, Z.; Hodgins, S.; Beaman, T.; Von Svoboda, S.; Marczak, J.

    2006-01-01

    Spent solvents are generated as a result of Boiler Chemical Cleanings (BCC) at CANDU reactor sites. These solutions contain small amount of radioactivity from a number of different sources including: Cut tubes - short sections of boiler tubes are infrequently removed from the boilers for a detailed characterization. These tubes are typically only plugged at the tubesheet allowing the primary side deposits to be exposed to BCC solvents. Tube leaks - primary to secondary side leaks also occur infrequently as a result of tube degradation. Radioactivity from the leaking fluid can consequently be deposited in the sludge on the secondary side of the tubes. Diffusion of tritium - during normal operation of the reactor units, tritium slowly diffuses from the heavy water in the primary heat-transfer system to the light-water coolant on the secondary side. Some of this tritium is retained in the secondary side deposits. The Pickering Nuclear Generating Station (PNGS) would like the flexibility to have several options for handling the spent solvent waste and associated rinse water from BCC. To this end, a radiological pathways analysis was undertaken to determine dose consequences associated with each option. Sample results from this study are included in this paper. The pathways analysis is used in this study to calculate dose to hypothetical receptors including individuals such as truck drivers, incinerator workers, residue (ash) handlers, residents who live near the landfill, inadvertent intruders into the landfill after closure and residents who live near the outfall. This dose is compared to a de minimis dose. A de minimis dose or dose rate represents a level of risk, which is generally accepted as being of no significance. Shipments of spent solvents and rinse water with corresponding doses below de minimis can be sent to conventional (i.e., non-radioactive) landfills for incineration and disposal as the radioactive dose associated with them is much less than natural

  2. Worker Alienation and Compensation at the Savannah River Site.

    Science.gov (United States)

    Ashwood, Loka; Wing, Steve

    2016-05-01

    Corporations operating U.S. nuclear weapons plants for the federal government began tracking occupational exposures to ionizing radiation in 1943. However, workers, scholars, and policy makers have questioned the accuracy and completeness of radiation monitoring and its capacity to provide a basis for workers' compensation. We use interviews to explore the limitations of broad-scale, corporate epidemiological surveillance through worker accounts from the Savannah River Site nuclear weapons plant. Interviewees report inadequate monitoring, overbearing surveillance, limited venues to access medical support and exposure records, and administrative failure to report radiation and other exposures at the plant. The alienation of workers from their records and toil is relevant to worker compensation programs and the accuracy of radiation dose measurements used in epidemiologic studies of occupational radiation exposures at the Savannah River Site and other weapons plants. © The Author(s) 2016.

  3. Remote video radioactive systems evaluation, Savannah River Site

    International Nuclear Information System (INIS)

    Heckendorn, F.M.; Robinson, C.W.

    1991-01-01

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

  4. The Savannah River Site's Groundwater Monitoring Program: Third quarter 1992

    International Nuclear Information System (INIS)

    Rogers, C.D.

    1993-01-01

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site's (SRS) Groundwater Monitoring Program. During third quarter 1992, EPD/EMS conducted extensive sampling of monitoring wells. Table 1 lists those well series with constituents in the groundwater above Flag 2 during third quarter 1992, organized by location. Results from all laboratory analyses are used to generate this table. Specific conductance and pH data from the field also are included in this table

  5. Final disposal of spent nuclear fuel in Finnish bedrock. Haestholmen site report

    International Nuclear Information System (INIS)

    Anttila, P.; Ahokas, H.; Front, K.

    1999-06-01

    Posiva Oy is studying the Finnish bedrock for the geological disposal of spent nuclear fuel. The study is based on the site selection research programme started originally in 1983. The programme is in accordance with the decision in principle by the Council of State in 1983 and aims at the selection of one site in 2000. Four sites, Haestholmen in Loviisa, Kivetty in Aeaenekoski, Olkiluoto in Eurajoki and Romuvaara in Kuhmo, have been studied in detail. This report summarises the results of the site investigations carried out at Haestholmen. The Haestholmen area is located within the anorogenic Wiborg rapakivi granite batholith, about 1630 million years in age, representing one of the youngest rock formations in Finland. Wiborgite, pyterlite, porphyritic rapakivi granite and even-grained rapakivi granite are the rock types present. 25 bedrock structures have been modelled at the site. Most of them are steeply-dipping fracture zones trending NW-SE and NE-SW, but several sub-horizontal zones, mainly dipping to the N-NE and the SW, are also present. The rock mass between the fracture zones represents what is termed 'intact rock', which is typically hard, unweathered and sparsely fractured. The bedrock structures are generally hydraulically more conductive than the intact rock and their mean transmissivity is 8 x 10 -6 m 2 /s or 1.3 x 10 -6 m 2 /s, depending on how structures are defined. The corresponding mean of the hydraulic conductivity values measured for the intact rock using a 2 m packer interval is 1 x 10 -12 m/s, if a lognormal distribution for all measured values is assumed. A clear decrease in hydraulic conductivity with depth has been found in the intact rock. In addition, the hydraulically conductive fractures seem to be more frequent and their transmissivities higher in the uppermost 100-200 m of the bedrock than at greater depths. The groundwater chemistry reflects the post-glacial history of the island of Haestholmen, which rose from the Baltic Sea some

  6. Final disposal of spent nuclear fuel in Finnish bedrock. Haestholmen site report

    Energy Technology Data Exchange (ETDEWEB)

    Anttila, P. [Fortum Engineering Oy, Vantaa (Finland); Ahokas, H. [Fintact Oy, Helsinki (Finland); Front, K. [VTT Communities and Infrastructure, Espoo (Finland)

    1999-06-01

    Posiva Oy is studying the Finnish bedrock for the geological disposal of spent nuclear fuel. The study is based on the site selection research programme started originally in 1983. The programme is in accordance with the decision in principle by the Council of State in 1983 and aims at the selection of one site in 2000. Four sites, Haestholmen in Loviisa, Kivetty in Aeaenekoski, Olkiluoto in Eurajoki and Romuvaara in Kuhmo, have been studied in detail. This report summarises the results of the site investigations carried out at Haestholmen. The Haestholmen area is located within the anorogenic Wiborg rapakivi granite batholith, about 1630 million years in age, representing one of the youngest rock formations in Finland. Wiborgite, pyterlite, porphyritic rapakivi granite and even-grained rapakivi granite are the rock types present. 25 bedrock structures have been modelled at the site. Most of them are steeply-dipping fracture zones trending NW-SE and NE-SW, but several sub-horizontal zones, mainly dipping to the N-NE and the SW, are also present. The rock mass between the fracture zones represents what is termed `intact rock`, which is typically hard, unweathered and sparsely fractured. The bedrock structures are generally hydraulically more conductive than the intact rock and their mean transmissivity is 8 x 10{sup -6} m{sup 2}/s or 1.3 x 10{sup -6} m{sup 2}/s, depending on how structures are defined. The corresponding mean of the hydraulic conductivity values measured for the intact rock using a 2 m packer interval is 1 x 10{sup -12} m/s, if a lognormal distribution for all measured values is assumed. A clear decrease in hydraulic conductivity with depth has been found in the intact rock. In addition, the hydraulically conductive fractures seem to be more frequent and their transmissivities higher in the uppermost 100-200 m of the bedrock than at greater depths. The groundwater chemistry reflects the post-glacial history of the island of Haestholmen, which rose

  7. 1996 Savannah River Site annual epidemiologic surveillance report

    Energy Technology Data Exchange (ETDEWEB)

    None

    2000-03-01

    This report provides a summary of epidemiologic surveillance data collected from Savannah River Site from January 1, 1996 through December 31, 1996. The data were collected by a coordinator at Savannah River Site and submitted to the Epidemiologic Surveillance Data Center located at Oak Ridge Institute for Science and Education, where quality control procedures and preliminary data analyses were carried out. The analyses were interpreted and the final report prepared by the DOE Office of Epidemiologic Studies. The information in this report provides highlights of the data analyses conducted on the 1996 data collected from Savannah River Site. The main sections of the report include: work force characteristics; absences due to injury or illness lasting 5 or more consecutive workdays; workplace illnesses, injuries, and deaths that were reportable to the Occupational Safety and Health Administration (''OSHA-recordable'' events); and disabilities and deaths among current workers. The 1996 report includes a new section on time trends that provides comparative information on the health of the work force from 1994 through 1996.

  8. 1997 Savannah River Site annual epidemiologic surveillance report

    Energy Technology Data Exchange (ETDEWEB)

    None

    2000-06-01

    This report provides a summary of epidemiologic surveillance data collected from Savannah River Site from January 1, 1997 through December 31, 1997. The data were collected by a coordinator at Savannah River Site and submitted to the Epidemiologic Surveillance Data Center located at Oak Ridge Institute for Science and Education, where quality control procedures and preliminary data analyses were carried out. The analyses were interpreted and the final report prepared by the DOE Office of Epidemiologic Studies. The information in this report provides highlights of the data analyses conducted on the 1997 data collected from Savannah River Site. The main sections of the report include: work force characteristics; absences due to injury or illness lasting 5 or more consecutive workdays; workplace illnesses, injuries, and deaths that were reportable to the Occupational Safety and Health Administration (''OSHA-recordable'' events); and disabilities and deaths among current workers. The 199 7 report includes a section on time trends that provides comparative information on the health of the work force from 1994 through 1997.

  9. An alternative proposal for the disposal of potentially contaminated railroad crossties at the Savannah River Site. Revision 1

    International Nuclear Information System (INIS)

    Hochel, R.C.

    1996-06-01

    The Savannah River Site (SRS) has accumulated approximately 300,000 crossties that have been replaced over a 40-year period of maintaining the site's 62 miles of railroad track. The ties reside in a pile on an open area of 2.3 acres near the site's F-Area facilities. A small fraction of the ties are potentially contaminated with radioactivity as a result of past site practices and service. Contamination was possible from occasional leaks in transport-casks moved by rail from the site's five nuclear materials production reactors to its two reprocessing facilities. Casks typically were filled with spent fuel, targets, and water from the reactor disassembly basins, which contained small amounts of fission and neutron activation product radioactivity normal to the operation of nuclear reactors

  10. Successful characterization of radioactive waste at the Savannah River Site

    International Nuclear Information System (INIS)

    Hughes, M.B.; Miles, G.M.

    1995-01-01

    Characterization of the low-level radioactive waste generated by forty five independent operating facilities at The Savannah River Site (SRS) experienced a slow start. However, the site effectively accelerated waste characterization based on findings of an independent assessment that recommended several changes to the existing process. The new approach included the development of a generic waste characterization protocol and methodology and the formulation of a technical board to approve waste characterization. As a result, consistent, detailed characterization of waste streams from SRS facilities was achieved in six months

  11. Summary of the engineering assessment of inactive uranium mill tailings, Green River site, Green River, Utah

    International Nuclear Information System (INIS)

    1981-08-01

    Radon gas released from the 123,000 tons of tailings at the Green River site constitutes the most significant environmental impact, although windblown tailings and external gamma radiation also are factors. The five alternative actions range from millsite decontamination with the addition of 3 m of stabilization cover material, to removal of the tailings to remote disposal sites and decontamination of the tailings site. Cost estimates for the five options range from about $4,300,000 for stabilization in-place, to about $9,600,000 for disposal at a distance of about 30 miles. Three principal alternatives for the reprocessing of the Green River tailings were examined: heap leaching, treatment at an existing mill, and reprocessing at a new conventional mill constructed for tailings reprocessing. The cost of the uranium recovered would be about $1,800/lb by heap leach and $1,600/lb by conventional plant processes

  12. The risks of the Taiwan research reactor spent fuel project

    International Nuclear Information System (INIS)

    1991-06-01

    The proposed action is to transport up to 118 spent fuel rods, to include canned spent fuel rod particulates immobilized on filters, from a research reactor in Taiwan by sea to Hampton Roads, Virginia, and then overland by truck to the Receiving Basin for Offsite Fuels at the Savannah River Site (SRS). At SRS, the spent fuel will be reprocessed to recover uranium and plutonium. 55 refs., 8 tabs

  13. The Savannah River Site`s Groundwater Monitoring Program, third quarter 1989

    Energy Technology Data Exchange (ETDEWEB)

    1989-12-31

    The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site`s Groundwater Monitoring Program. During third quarter 1989 (July--September), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead they aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. An explanation of flagging criteria for the third quarter is presented in the Flagging Criteria section of this document. All analytical results from third quarter 1989 are listed in this report, which is distributed to all waste-site custodians.

  14. The Savannah River Site`s Groundwater Monitoring Program. Fourth quarter, 1989

    Energy Technology Data Exchange (ETDEWEB)

    1989-12-31

    The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site`s Groundwater Monitoring Program. During fourth quarter 1989 (October--December), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria aid personnel in sample scheduling, interpretation of data, and trend identification. An explanation of flagging criteria for the fourth quarter is presented in the Flagging Criteria section of this document. All analytical results from fourth quarter 1989 are listed in this report, which is distributed to all waste-site custodians.

  15. The Savannah River Site`s Groundwater Monitoring Program, second quarter 1989

    Energy Technology Data Exchange (ETDEWEB)

    1989-12-31

    The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site`s Groundwater Monitoring Program. During second quarter 1989 (April--June), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. An explanation of flagging criteria for the second quarter is presented in the Flagging Criteria section of this document. All analytical results from second quarter 1989 are listed in this report, which is distributed to all waste-site custodians.

  16. The Savannah River Site`s Groundwater Monitoring Program: Third quarter 1992

    Energy Technology Data Exchange (ETDEWEB)

    Rogers, C.D. [Westinghouse Savannah River Co., Aiken, SC (United States)

    1993-02-04

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During third quarter 1992, EPD/EMS conducted extensive sampling of monitoring wells. Table 1 lists those well series with constituents in the groundwater above Flag 2 during third quarter 1992, organized by location. Results from all laboratory analyses are used to generate this table. Specific conductance and pH data from the field also are included in this table.

  17. The Savannah River Site`s Groundwater Monitoring Program. First quarter 1992

    Energy Technology Data Exchange (ETDEWEB)

    1992-08-03

    This report summarizes the Savannah River Site (SRS) groundwater monitoring program conducted during the first quarter of 1992. It includes the analytical data, field data, data review, quality control, and other documentation for this program; provides a record of the program`s activities; and serves as an official document of the analytical results.

  18. The Savannah River Site`s groundwater monitoring program. First quarter 1991

    Energy Technology Data Exchange (ETDEWEB)

    1991-10-18

    This report summarizes the Savannah River Site (SRS) groundwater monitoring program conducted by EPD/EMS in the first quarter of 1991. In includes the analytical data, field data, data review, quality control, and other documentation for this program, provides a record of the program`s activities and rationale, and serves as an official document of the analytical results.

  19. Risk assessment data bank design at the Savannah River Site

    International Nuclear Information System (INIS)

    Townsend, C.S.; Johnson, K.B.

    1992-01-01

    The Savannah River Site has designed and implemented a database system containing a series of compilations of incidents used primarily for risk assessment. Four databases have been designed and implemented using advanced database management system computer software. These databases exist for reprocessing, fuel fabrication, waste management, and the Savannah River Technology Center. They are combined into one system caged the Risk Assessment Methodology (RAM) Fault Tree Data Banks. This paper will discuss the logical design of the data, the menus, and the operating platform. Built-in updating features, such as batch and on-line data entry; data validation methods; automatic update features; and expert system programs, will also be discussed. User functions, such as on-line search/view/report and statistical functions, will be presented. Security features and backup and recovery methods will also be covered

  20. Savannah River Site TEP-SET tests uncertainty report

    International Nuclear Information System (INIS)

    Taylor, D.J.N.

    1993-09-01

    This document presents a measurement uncertainty analysis for the instruments used for the Phase I, II and III of the Savannah River One-Fourth Linear Scale, One-Sixth Sector, Tank/Muff/Pump (TMP) Separate Effects Tests (SET) Experiment Series. The Idaho National Engineering Laboratory conducted the tests for the Savannah River Site (SRS). The tests represented a range of hydraulic conditions and geometries that bound anticipated Large Break Loss of Coolant Accidents in the SRS reactors. Important hydraulic phenomena were identified from experiments. In addition, code calculations will be benchmarked from these experiments. The experimental system includes the following measurement groups: coolant density; absolute and differential pressures; turbine flowmeters (liquid phase); thermal flowmeters (gas phase); ultrasonic liquid level meters; temperatures; pump torque; pump speed; moderator tank liquid inventory via a load cells measurement; and relative humidity meters. This document also analyzes data acquisition system including the presampling filters as it relates to these measurements

  1. Characterization recommendations for waste sites at the Savannah River Plant

    International Nuclear Information System (INIS)

    Carlton, W.H.; Gordon, D.E.; Johnson, W.F.; Kaback, D.S.; Looney, B.B.; Nichols, R.L.; Shedrow, C.B.

    1987-11-01

    One hundred and sixty six disposal facilities that received or may have received waste materials resulting from operations at the Savannah River Plant (SRP) have been identified. These waste range from innocuous solid and liquid materials (e.g., wood piles) to process effluents that contain hazardous and/or radioactive constituents. The waste sites have been grouped into 45 categories according the the type of waste materials they received. Waste sites are located with SRP coordinates, a local Department of Energy (DOE) grid system whose grid north is 36 degrees 22 minutes west of true north. DOE policy is to close all waste sites at SRP in a manner consistent with protecting human health and environment and complying with applicable environmental regulations (DOE 1984). A uniform, explicit characterization program for SRP waste sites will provide a sound technical basis for developing closure plans. Several elements are summarized in the following individual sections including (1) a review of the history, geohydrology, and available characterization data for each waste site and (2) recommendations for additional characterization necessary to prepare a reasonable closure plan. Many waste sites have been fully characterized, while others have not been investigated at all. The approach used in this report is to evaluate available groundwater quality and site history data. For example, groundwater data are compared to review criteria to help determine what additional information is required. The review criteria are based on regulatory and DOE guidelines for acceptable concentrations of constituents in groundwater and soil

  2. Thermal calculations for the design, construction, operation, and evaluation of the Spent Fuel Test - Climax, Nevada Test Site

    International Nuclear Information System (INIS)

    Montan, D.N.; Patrick, W.C.

    1981-01-01

    The Spent Fuel Test-Climax (SFT-C) is a test of retrievable deep geologic storage of commercially generated spent nuclear reactor fuel in granitic rock. Eleven spent fuel assemblies, together with six electrical simulators and 20 guard heaters, are emplaced 420 m below the surface in the Climax granite at the US Department of Energy Nevada Test Site. On June 2, 1978 LLNL secured funding for the SFT-C, and completed spent fuel emplacement May 28, 1980. This report documents a series of thermal calculations that were performed in support of the SFT-C. Early calculations employed analytical solutions to address such design and construction issues as drift layout and emplacement hole spacings. Operational aspects of the test required more detailed numerical solutions dealing with ventilation and guard-heater power levels. The final set of calculations presented here provides temperature histories throughout the test facility for evaluation of the response of the SFT-C and for comparison of calculations with acquired data. This final set of calculations employs the as-built test geometry and best-available material properties

  3. Nuclear Material Processing at the Savannah River Site

    International Nuclear Information System (INIS)

    Severynse, T.F.

    1998-07-01

    Plutonium production for national defense began at Savannah River in the mid-1950s, following construction of production reactors and separations facilities. Following the successful completion of its production mission, the site's nuclear material processing facilities continue to operate to perform stabilization of excess materials and potentially support the disposition of these materials. A number of restoration and productivity improvement projects implemented in the 1980s, totaling nearly a billion dollars, have resulted in these facilities representing the most modern and only remaining operating large-scale processing facilities in the DOE Complex. Together with the Site's extensive nuclear infrastructure, and integrated waste management system, SRS is the only DOE site with the capability and mission of ongoing processing operations

  4. A cursory application of DRASTIC to the Savannah River Site

    International Nuclear Information System (INIS)

    Crider, S.S.

    1989-01-01

    Geohydrologists at the National Water Well Association (NWWA) created DRASTIC as a formalized decision-making procedure to assess the potential for groundwater pollution at existing and proposed industrial sites. It is a method to examine groundwater pollution potential anywhere in the country. DRASTIC is generalized because it is meant to be universal; therefore, NWWA stresses its qualitative nature. Its objective are: (1) to help direct resources and land use activities to appropriate areas; and, (2) to help prioritize groundwater protection, monitoring and cleanup efforts. Even though it is a general siting tool, usually applied where only scanty geohydrological information is available, it can be helpful -- perhaps in a modified form -- for locations like the Savannah River Site (SRS) that have relatively abundant data resources

  5. Waste certification review program at the Savannah River Site

    International Nuclear Information System (INIS)

    Faulk, G.W.; Kinney, J.C.; Knapp, D.C.; Burdette, T.E.

    1996-01-01

    After approving the waste certification programs for 45 generators of low-level radioactive and mixed waste, Westinghouse Savannah River Company (WSRC) moved forward to implement a performance-based approach for assuring that approved waste generators maintain their waste certification programs. WSRC implemented the Waste Certification Review Program, which is comprised of two sitewide programs, waste generator self-assessments and Facility Evaluation Board reviews, integrated with the WSRC Solid Waste Management Department Waste Verification Program Evaluations. The waste generator self-assessments ensure compliance with waste certification requirements, and Facility Evaluation Board reviews provide independent oversight of generators' waste certification programs. Waste verification evaluations by the TSD facilities serve as the foundation of the program by confirming that waste contents and generator performance continue to meet waste acceptance criteria (WSRC 1994) prior to shipment to treatment, storage, and disposal facilities. Construction of the Savannah River Site (SRS) was started by the US Government in 1950. The site covers approximately 300 square miles located along the Savannah River near Aiken, South Carolina. It is operated by the US Department of Energy (DOE). Operations are conducted by managing and operating contractors, including the Westinghouse Savannah River Company (WSRC). Historically, the primary purpose of the SRS was to produce special nuclear materials, primarily plutonium and tritium. In general, low-level radioactive and mixed waste is generated through activities in operations. Presently, 47 SRS facilities generate low-level radioactive and mixed waste. The policies, guidelines, and requirements for managing these wastes are determined by DOE and are reflected in DOE Order 5820.2A (US DOE 1988)

  6. Bats of the Savannah River Site and vicinity.

    Energy Technology Data Exchange (ETDEWEB)

    M.A. Menzel; J.M. Menzel; J.C. Kilgo; W.M. Ford; T.C. Carter; J.W. Edwards

    2003-10-01

    The U.S. Department of Energy's Savannah River Site supports a diverse bat community. Nine species occur there regularly, including the eastern pipistrelle (Pipistrellus subflavus), southeastern myotis (Myotis austroriparius), evening bat (Nycticeius humeralis), Rafinesque's big-eared bat (Corynorhinus rafinesquii), silver-haired bat (Lasionycteris noctivagans), eastern red bat (Lasiurus borealis), Seminole bat (L. seminolus), hoary bat (L. cinereus), and big brown bat (Eptesicus fuscus). There are extralimital capture records for two additional species: little brown bat (M. lucifigus) and northern yellow bat (Lasiurus intermedius). Acoustical sampling has documented the presence of Brazilian free-tailed bats (Tadarida brasiliensis), but none has been captured. Among those species common to the Site, the southeastern myotis and Rafinesque's big-eared bat are listed in South Carolina as threatened and endangered, respectively. The presence of those two species, and a growing concern for the conservation of forest-dwelling bats, led to extensive and focused research on the Savannah River Site between 1996 and 2002. Summarizing this and other bat research, we provide species accounts that discuss morphology and distribution, roosting and foraging behaviors, home range characteristics, habitat relations, and reproductive biology. We also present information on conservation needs and rabies issues; and, finally, identification keys that may be useful wherever the bat species we describe are found.

  7. PROTECTING GROUNDWATER & THE COLUMBIA RIVER AT THE HANFORD SITE

    Energy Technology Data Exchange (ETDEWEB)

    GERBER, M.S.

    2006-06-29

    Along the remote shores of the Columbia River in southeast Washington state, a race is on. Fluor Hanford, a prime cleanup contractor to the U.S. Department of Energy (DOE) at the Hanford Site, is managing a massive, multi-faceted project to remove contaminants from the groundwater before they can reach the Columbia. Despite the daunting nature and size of the problem--about 80 square miles of aquifer under the site contains long-lived radionuclides and hazardous chemicals--significant progress is being made. Many groups are watching, speaking out, and helping. A large. passionate, diverse, and geographically dispersed community is united in its desire to protect the Columbia River--the eighth largest in the world--and have a voice in Hanford's future. Fluor Hanford and the DOE, along with the US. Environmental Protection Agency (EPA) and the Washington Department of Ecology (Ecology) interact with all the stakeholders to make the best decisions. Together, they have made some remarkable strides in the battle against groundwater contamination under the site.

  8. Implementation of hearings in the Swedish process for siting a spent nuclear fuel repository

    International Nuclear Information System (INIS)

    Westerlind, Magnus; Wiklund, Aasa

    2001-01-01

    The problem of bringing all stakeholders on the scene to penetrate an issue of great complexity is not unique for nuclear waste management. There are an increasing number of site selection processes for disposal of nuclear waste around the world. During the 90's many of these siting processes have gone into a more decisive phase where public participation and transparency get more and more attention. Municipalities, NGOs and the public do no longer accept ready-made solutions but have legitimate claims to be part of the decision making and siting processes at an early stage. The attempts to increase the level of transparency and public involvement differ from country to country and depend e.g. on culture, history and societal conditions as well as on the precise phase in the siting process. However, many processes include public hearings as one tool to enhance transparency. In general, Sweden has not a long history of using hearings in decision making. In the area of nuclear waste management and disposal hearings have so far been rarely used. In 1997 and 1998 two public hearings were arranged by the Swedish Nuclear Power Inspectorate, SKI, in conjunction with the licensing of the enlargement of the Central Interim Storage for Spent Nuclear Fuel, CLAB. These hearings showed that hearings could improve the decision making process. SKI and SSI strongly believe the effort was worthwhile and that hearings will continue to be used in the nuclear waste programme. The hearings provided a forum for local stakeholders to pose questions and stretch both the implementer and to some extent also the authorities. The hearings managed to focus on relevant issues at this stage of the siting process and gave the audience a chance to evaluate and challenge the trustworthiness of the implementer and authorities. In this respect the hearings contributed to transparent and democratic decision making. Some of the keys to the success were: Unbiased and skilled moderators with capacity to

  9. M-area basin closure-Savannah River Site

    International Nuclear Information System (INIS)

    McMullin, S.R.; Horvath, J.G.

    1991-01-01

    M-Area, on the Savannah River Site, processes raw materials and manufactures fuel and target rods for reactor use. Effluent from these processes were discharged into the M-Area settling basin and Lost Lake, a natural wetland. The closure of this basin began in 1988 and included the removal and stabilization of basin fluids, excavation of all contaminated soils from affected areas and Lost Lake, and placement of all materials in the bottom of the emptied basin. These materials were covered with a RCRA style cap, employing redundant barriers of kaolin clay and geosynthetic material. Restoration of excavated uplands and wetlands is currently underway

  10. Savannah River Site Bagless Transfer - What Have We Learned?

    International Nuclear Information System (INIS)

    Wong, J.W.

    2001-01-01

    Conventional glovebox techniques for handling radioactive material include the use of plastic sleeving for ''bagging out'' material in order to remove it from the glovebox. This method has been used for many years, and has proven very effective when implemented by trained operators. One drawback to this method is that it is not suitable for removal of material for long-term storage, due to radiolytic decomposition of the plastic. In order to comply with long term storage criteria, engineers at the Savannah River Site developed an alternative process for removal of radioactive material known as ''bagless transfer''

  11. Savannah River Site environmental report for 1991. [Contains Glossary

    Energy Technology Data Exchange (ETDEWEB)

    Arnett, M.W.; Karapatakis, L.K.; Mamatey, A.R.; Todd, J.L.

    1991-01-01

    This report describes environmental activities conducted on and in the vicinity of the Savannah River Site (SRS) in Aiken, S.C., from Jan. 1 to Dec. 31, 1991, with an update on compliance activities through April 1, 1992. The report is a single volume with a separate summary pamphlet highlighting the major findings for 1991. The report is divided into an executive summary and 14 chapters containing information on environmental compliance issues, environmental monitoring methods and programs, and environmental research activities for 1991, as well as historical data from previous years. Analytical results, figures, charts, and data tables relevant to the environmental monitoring program for 1991 at SRS are included.

  12. Savannah River Site K-Reactor Probabilistic Safety Assessment

    International Nuclear Information System (INIS)

    Brandyberry, M.D.; Bailey, R.T.; Baker, W.H.; Kearnaghan, D.P.; O'Kula, K.R.; Wittman, R.S.; Woody, N.D.; Amos, C.N.; Weingardt, J.J.

    1992-12-01

    This report gives the results of a Savannah River Site (SRS) K-Reactor Probabilistic Safety Assessment (PSA). Measures of adverse consequences to health and safety resulting from representations of severe accidents in SRS reactors are presented. In addition, the report gives a summary of the methods employed to represent these accidents and to assess the resultant consequences. The report is issued to provide useful information to the U. S. Department of Energy (DOE) on the risk of operation of SRS reactors, for insights into severe accident phenomena that contribute to this risk, and in support of improved bases for other DOE programs in Heavy Water Reactor safety

  13. Savannah River Site Waste Management Program Plan, FY 1993

    International Nuclear Information System (INIS)

    1993-06-01

    The primary purpose of the Waste Management Program Plan is to provide an annual report on facilities being used to manage wastes, forces acting to change current waste management (WM) systems, and how operations are conducted. This document also reports on plans for the coming fiscal year and projects activities for several years beyond the coming fiscal year to adequately plan for safe handling and disposal of radioactive wastes generated at the Savannah River Site (SRS) and for developing technology for improved management of wastes

  14. Data banks for risk assessment at the Savannah River Site

    International Nuclear Information System (INIS)

    Durant, W.S.; Townsend, C.S.; Baughman, D.F.; Hang, P.

    1992-01-01

    One of the lessons learned from many years of risk assessment experience is that mistakes of the past are soon forgotten if no method is available to retrieve and review these events. Savannah River Site has maintained a computerized data bank system for recording, retrieving and reviewing its incident history. The system is based on a series of compilations developed primarily for risk assessment but has been found to be invaluable for many other uses such as equipment reliability, project justification, and incident investigations

  15. SKI's and SSI's experiences from their participation in the siting of a final repository for spent nuclear fuel

    International Nuclear Information System (INIS)

    Westerlind, M.; Hedberg, B.

    2000-01-01

    This paper summarises some experiences gained by the SKI and SSI during the ongoing process for siting a final repository for spent nuclear fuel. The focus is on activities in the municipalities involved in the siting process. In order to give the proper context some basic elements in the legislation, which are important for public participation and confidence in the siting process, are outlined. The importance of clearly defined responsibilities and early participation of the regulators in the siting process are emphasised. It should be pointed out that this paper is not a comprehensive review of the Swedish situation but only contains a few selected issues and personal remarks from the authors. Thus, the views and opinions do not necessarily coincide with those of SKI and SSI. (authors)

  16. Geological evaluation of spent fuel storage and low-intermediate level radwaste disposal in the site of NPP candidate

    International Nuclear Information System (INIS)

    Sucipta; Yatim, S.; Martono, H.; Pudyo, A.

    1997-01-01

    Based on the consideration of techno-economy and environmental safety, the radioactive waste treatment installation (RWI), interim storage of spen fuel (ISSF) and low-intermediate level disposal shall be sited in the surrounding of NPP area. The land suitability of NPP's site candidate at Muria Peninsula as spent fuel storage and low-intermediate level radwaste disposal need to be studied. Site selection was conducted by overlay method and scoring method, and based on safety criteria which include geological and environmental aspects. Land evaluation by overlay method has given result a potential site which have highest suitable land at surrounding of borehole L-15 about 17.5 hectares. Land evaluation by scoring method has given result two land suitability classes, i.e. moderate suitability class (includes 14 borehole) and high suitability class, include borehole L-2, L-14 and L-15 (author)

  17. The Savannah River Site's Groundwater Monitoring Program

    Energy Technology Data Exchange (ETDEWEB)

    1991-06-18

    This report summarizes the Savannah River Site (SRS) groundwater monitoring program conducted in the fourth quarter of 1990. It includes the analytical data, field data, well activity data, and other documentation for this program, provides a record of the program's activities and rationale, and serves as an official document of the analytical results. The groundwater monitoring program includes the following activities: installation, maintenance, and abandonment of monitoring wells, environmental soil borings, development of the sampling and analytical schedule, collection and analyses of groundwater samples, review of analytical and other data, maintenance of the databases containing groundwater monitoring data, quality assurance (QA) evaluations of laboratory performance, and reports of results to waste-site facility custodians and to the Environmental Protection Section (EPS) of EPD.

  18. Flood Hazard Assessment for the Savannah River Site

    International Nuclear Information System (INIS)

    Chen, K.F.

    1999-01-01

    'A method was developed to determine the probabilistic flood elevation curves for certain Savannah River Site (SRS) facilities. This paper presents the method used to determine the probabilistic flood elevation curve for F-Area due to runoff from the Upper Three Runs basin. Department of Energy (DOE) Order 420.1, Facility Safety, outlines the requirements for Natural Phenomena Hazard (NPH) mitigation for new and existing DOE facilities. The NPH considered in this paper is flooding. The facility-specific probabilistic flood hazard curve defines as a function of water elevation the annual probability of occurrence or the return period in years. Based on facility-specific probabilistic flood hazard curves and the nature of facility operations (e.g., involving hazardous or radioactive materials), facility managers can design permanent or temporary devices to prevent the propagation of flood on site, and develop emergency preparedness plans to mitigate the consequences of floods.'

  19. Savannah River Site Environmental Implementation Plan. Volume 2, Protection programs

    Energy Technology Data Exchange (ETDEWEB)

    1989-08-01

    Formal sitewide environmental planning at the . Savannah River Site (SRS) began in 1986 with the development and adoption of the Strategic Environmental Plan. The Strategic Environmental Plan describes the philosophy, policy, and overall program direction of environmental programs for the operation of the SRS. The Strategic Environmental Plan (Volume 2) provided the basis for development of the Environmental Implementation Plan (EIP). The EIP is the detailed, comprehensive environmental master plan for operating contractor organizations at the SRS. The EIP provides a process to ensure that all environmental requirements and obligations are being met by setting specific measurable goals and objectives and strategies for implementation. The plan is the basis for justification of site manpower and funding requests for environmental projects and programs over a five-year planning period.

  20. Epidemiologic surveillance. Annual report for Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    Epidemiologic surveillance at US Department of Energy (DOE) facilities consists of regular and systematic collection, analysis, and interpretation of data on absences due to illness and injury in the work force. Its purpose is to provide an early warning system for health problems occurring among employees at participating sites. In this annual report, the 1994 morbidity data for the Savannah River Site (SRS) are summarized. These analyses focus on absences of 5 or more consecutive workdays occurring among workers aged 16-75 years. They are arranged in five sets of tables that present: (1) the distribution of the labor force by occupational category and salary status; (2) the absences per person, diagnoses per absences, and diagnosis rates for the whole work force; (3) diagnosis rates by type of disease or injury; (4) diagnosis rates by occupational category; and (5) relative risks for specific types of disease or injury by occupational category.

  1. Technology implementation and cleanup progress at Savannah River site

    International Nuclear Information System (INIS)

    Papouchado, L.M.

    1996-01-01

    The integrated high level waste treatment system at Savannah River has started up and the process of converting 34 million gallons of liquid waste to glass and saltstone is in its initial phase. New waste disposal vaults and startup of several other facilities such as the Consolidated Incinerator Facility and a mixed waste vitrification facility will help completion of the integrated system to treat and dispose of SRS wastes. Technology was utilized from industry, other laboratories, or was developed at the Savannah River Technology Center if it was not available. Many SRTC developments involved academia and other labs. SRS also has over 400 waste sites (400 acres) in its characterization/remediation program. To date over 90 acres were remediated (23 percent) and by 1997 we plan to remediate 175 acres or 44 percent. Thirteen groundwater facility treatment sites will be in operation by 1997. SRS has provided and continues to provide unique test platforms for testing innovative remediation, characterization and monitoring technologies. We are currently testing DNAPL characterization and remediation and an in-situ Inorganic remediation technique for ground water

  2. Risk assessment data banks at the Savannah River Site

    International Nuclear Information System (INIS)

    Townsend, C.S.; Durant, W.S.; Baughman, D.F.

    1993-01-01

    In the risk assessment business, it is a well known fact that past mistakes will not be remembered if nothing is done to record them and make them available for future reference and review. The Savannah River Site maintains a computer database system for nonreactor facilities that contains a compilation of the incidents that have occurred since the start up of the Site in 1953. The nationally recognized data banks are highly valued across the US Department of Energy (DOE) complex for their use in risk-related analyses. They provide data for uses such as failure rate analyses, equipment reliability and breakdown studies, project justification, incident investigations, design studies, Safety Analysis Reports, Process Hazards Reviews, consequence analyses, quality assurance studies, trend analyses, management decision, administrative control effectiveness studies, and process problem solving. Five risk assessment data banks exist in the areas of reprocessing, fuel fabrication, waste management, tritium, and the Savannah River Technology Center. The data banks are comprised of approximately one-third million entries collectively and continue to grow at a rate of about two hundred entries per day

  3. The Frequency of Incipient Fires at the Savannah River Site

    International Nuclear Information System (INIS)

    Blanchard, A.

    1999-01-01

    Fire is a significant hazard in most industrial and nuclear facilities. As such it is important that adequate safeguards be provided to ensure a responsible level of safety. In determining this level of safety it is necessary to know three key parameters. These are the frequency of the incipient fire, the probability that a fire will grow from the incipient stage to cause the potential consequence, and the potential consequences (i.e., losses) from an unwanted fire. Consequence predictions have been modeled and evaluated extensively and can be readily confirmed by comparison with historic loss records. These loss records can also provide significant insight into the probability that given a fire it grows to create a defined consequence. The other key parameter, frequency, is the focus of this report. this report determines an alternative method for estimating Savannah River Site (SRS) building fire frequencies as a function of floor area to the linear method previously used. The frequency of an incipient fire is not easily derived from existing fire loss records. This occurs because the fire loss records do not make reference to the sample population. To derive an initiating frequency both the number of events (incipient fires) and the population (number of buildings and years in service) must be known. this report documents an evaluation that estimates the frequency of incipient fires in industrial and nuclear facilities. these estimates were developed from the unique historical record that has been maintained at the Savannah River Site

  4. Savannah River Site Bagless Transfer Technology Applied at Hanford

    International Nuclear Information System (INIS)

    Wong, J.W.

    2001-01-01

    A ''bagless transfer'' process was developed at the Savannah River Site (SRS) to remove radioactive materials from glovebox enclosures for long-term storage in conformance with DOE Standard 3013. This process, unlike the more conventional ''bag-out'' process, produces an all-metal, helium-filled, welded storage container that does not contain materials subject to radiolytic decomposition. A Bagless Transfer System (BTS), utilizing this bagless transfer process, has been in service at SRS since August 1997. It is a semi-automated system that has proven to be very reliable during its three years of operation.The Plutonium Finishing Plant (PFP) at Hanford has a similar need for long-term storage of radioactive materials. The successful operation of the Savannah River Site BTS led to the selection of the same technology to fulfill the packaging need at Hanford. However, there are a number of differences between the existing SRS BTS and the system currently in operation at Hanford. These differences will be discussed in this paper. Additionally, a system is necessary to produce another all-metal, welded container into which the container produced by the BTS can be placed. This container must be in conformance with the criteria specified in DOE-STD-3013 for an outer container. SRS Engineers are developing a system (outer container welder), based on the tungsten inert gas (TIG) welding equipment used in the BTS, to produce this outer container

  5. Remedial action at the Green River uranium mill tailings site, Green River, Utah: Environmental assessment

    International Nuclear Information System (INIS)

    1988-07-01

    The inactive Green River uranium mill tailings site is one mile southeast of Green River, Utah. The existing tailings pile is within the floodplain boundaries of the 100-year and 500-year flood events. The 48-acre designated site contains eight acres of tailings, the mill yard and ore storage area, four main buildings, a water tower, and several small buildings. Dispersion of the tailings has contaminated an additional 24 acres surrounding the designated site. Elevated concentrations of molybdenum, nitrate, selenium, uranium, and gross alpha activity exceed background levels and the proposed US Environmental Protection Agency (EPA) maximum concentration limits in the groundwater in the unconsolidated alluvium and in the shallow shales and limestones beneath the alluvium at the mill tailings site. The contamination is localized beneath, and slightly downgradient of, the tailings pile. The proposed action is to relocate the tailings and associated contaminated materials to an area 600 feet south of the existing tailings pile where they would be consolidated into one, below-grade disposal cell. A radon/infiltration barrier would be constructed to cover the stabilized pile and various erosion control measures would be taken to ensure the long-term stability of the stabilized pile. 88 refs., 12 figs., 20 tabs

  6. The Savannah River Site`s Groundwater Monitoring Program: First quarter 1993, Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Rogers, C.D. [Westinghouse Savannah River Co., Aiken, SC (United States)

    1993-08-01

    This report summarizes the Savannah River Site (SRS) Groundwater Monitoring Program conducted by the Environmental Protection Department`s Environmental Monitoring Section (EPD/EMS) during the first quarter of 1993. It includes the analytical data, field data, data review, quality control, and other documentation for this program; provides a record of the program`s activities; and serves as an official document of the analytical results.

  7. The Savannah River Site`s Groundwater Monitoring Program. Fourth quarter 1992

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-17

    This report summarizes the Savannah River Site (SRS) groundwater monitoring program conducted by the Environmental Protection Department`s Environmental Monitoring Section (EPD/EMS) during the fourth quarter of 1992. It includes the analytical data, field data, data review, quality control, and other documentation for this program, provides a record of the program`s activities; and serves as an official document of the analytical results.

  8. Integration of Environmental Compliance at the Savannah River Site - 13024

    Energy Technology Data Exchange (ETDEWEB)

    Hoel, David [United States Department of Energy - Savannah River Operations Office (United States); Griffith, Michael [Savannah River Nuclear Solutions, LLC (United States)

    2013-07-01

    The Savannah River Site (SRS) is a large federal installation hosting diverse missions and multiple organizations with competing regulatory needs. Accordingly, there was a need to integrate environmental compliance strategies to ensure the consistent flow of information between Department of Energy-Savannah River (DOE-SR), the regulatory agencies and other interested parties. In order to meet this objective, DOE and major SRS contractors and tenants have committed to a strategy of collaboratively working together to ensure that a consistent, integrated, and fully coordinated approach to environmental compliance and regulator relationships is maintained. DOE-SR and Savannah River Nuclear Solutions, LLC, the SRS management and operations contractor, have established an environmental compliance integration process that provides for the consistent flow down of requirements to projects, facilities, SRS contractors, and subcontractors as well as the upward flow of information to assist in the early identification and resolution of environmental regulatory issues and enhancement of compliance opportunities. In addition, this process strongly fosters teamwork to collaboratively resolve complex regulatory challenges, promote pollution prevention and waste minimization opportunities to advance site missions in a manner that balances near-term actions with the long-term site vision, while being protective of human health and the environment. Communication tools are being utilized, some with enhancements, to ensure appropriate information is communicated to all levels with environmental responsibility at SRS. SRS internal regulatory integration is accomplished through a variety of informational exchange forums (e.g., Challenges, Opportunities and Resolution (COR) Team, DOE's Joint Site Regulatory Integration Team, and the Senior Environmental Managers Council (SEMC)). SRS communications and problem-solving with the regulatory agencies have been enhanced through formation

  9. Integration of Environmental Compliance at the Savannah River Site - 13024

    International Nuclear Information System (INIS)

    Hoel, David; Griffith, Michael

    2013-01-01

    The Savannah River Site (SRS) is a large federal installation hosting diverse missions and multiple organizations with competing regulatory needs. Accordingly, there was a need to integrate environmental compliance strategies to ensure the consistent flow of information between Department of Energy-Savannah River (DOE-SR), the regulatory agencies and other interested parties. In order to meet this objective, DOE and major SRS contractors and tenants have committed to a strategy of collaboratively working together to ensure that a consistent, integrated, and fully coordinated approach to environmental compliance and regulator relationships is maintained. DOE-SR and Savannah River Nuclear Solutions, LLC, the SRS management and operations contractor, have established an environmental compliance integration process that provides for the consistent flow down of requirements to projects, facilities, SRS contractors, and subcontractors as well as the upward flow of information to assist in the early identification and resolution of environmental regulatory issues and enhancement of compliance opportunities. In addition, this process strongly fosters teamwork to collaboratively resolve complex regulatory challenges, promote pollution prevention and waste minimization opportunities to advance site missions in a manner that balances near-term actions with the long-term site vision, while being protective of human health and the environment. Communication tools are being utilized, some with enhancements, to ensure appropriate information is communicated to all levels with environmental responsibility at SRS. SRS internal regulatory integration is accomplished through a variety of informational exchange forums (e.g., Challenges, Opportunities and Resolution (COR) Team, DOE's Joint Site Regulatory Integration Team, and the Senior Environmental Managers Council (SEMC)). SRS communications and problem-solving with the regulatory agencies have been enhanced through formation of an

  10. Site specific plan. [Environmental Restoration and Waste Management, Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Hutchison, J.; Jernigan, G.

    1989-12-01

    The Environmental Restoration and Waste Management Five-Year Plan (FYP) covers the period for FY 1989 through FY 1995. The plan establishes a Department of Energy -- Headquarters (DOE-HQ) agenda for cleanup and compliance against which overall progress can be measured. The FYP covers three areas: Corrective Activities, Environmental Restoration, and Waste Management Operations. Corrective Activities are those activities necessary to bring active or standby facilities into compliance with local, state, and federal environmental regulations. Environmental restoration activities include the assessment and cleanup of surplus facilities and inactive waste sites. Waste management operations includes the treatment, storage, and disposal of wastes which are generated as a result of ongoing operations. This Site Specific Plan (SSP) has been prepared by the Savannah River Site (SRS) in order to show how environmental restoration and waste management activities that were identified during the preparation of the FYP will be implemented, tracked, and reported. The SSP describes DOE Savannah River (DOE-SR) and operating contractor, Westinghouse Savannah River Company (WSRC), organizations that are responsible, for undertaking the activities identified in this plan. The SSP has been prepared in accordance with guidance received from DOE-HQ. DOE-SR is accountable to DOE-HQ for the implementation of this plan. 8 refs., 46 figs., 23 tabs.

  11. Application of UAVs at the Savannah River Site

    International Nuclear Information System (INIS)

    Hofstetter, K.J.; Pendergast, M.M.

    1996-01-01

    Small, unmanned aerial vehicles (UAVs) equipped with sensors for physical, chemical, and radiochemical measurements of remote environments have been tested at the Savannah River Site (SRS). A miniature helicopter was used as an aerial platform for testing a variety of sensors with outputs integrated with the flight control system for real-time data acquisition and evaluation. The sensors included a precision magnetometer, two broad band infra-red radiometers, a 1-inch by 1-inch Nal(TI) scintillation detector, and an on-board color video camera. Included in the avionics package was an ultrasonic altimeter, a precision barometer, and a portable Global Positioning System. Two separate demonstration locations at SRS were flown that had been previously characterized by careful sampling and analyses and by aerial surveys at high altitudes. The Steed Pond demonstration site contains elevated levels of uranium in the soil and pond silt due to runoff from one of the site's uranium fuel and target production areas. The soil at the other site is contaminated with oil bearing materials and contains some buried objects. The results and limitations of the UAV surveys are presented and improvements for future measurements are discussed

  12. Storage of non-defense production reactor spent nuclear fuel at the Department of Energy's Hanford Site

    International Nuclear Information System (INIS)

    Carlson, A.B.

    1998-01-01

    In 1992, the US Department of Energy (DOE) established a program at the Hanford Site for management of DOE-owned spent nuclear fuel (SNF) until final disposition. Currently, the DOE-owned SNF Program is developing and implementing plans to assure existing storage, achieve interim storage, and prepare DOE-owned SNF for final disposition. Program requirements for management of the SNF are delineated in the DOE-owned SNF Program Plan.(DOE 1995a) and the DOE Spent Fuel Program's Requirements Document (DOE 1994a). Major program requirements are driven by the following: commitments established in the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1 Implementation Plan (DOE 1995b); corrective action plans for resolving vulnerabilities identified in the DOE Spent Fuel Working Group's Report on Health, Safety, and Environmental Vulnerabilities for Reactor Irradiated Nuclear Materials (DOE 1993); the settlement agreement between the US Department of Navy, the US Department of Energy, and the State of Idaho on the record of decision (ROD) from the DOE Programmatic SNF Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Environmental Impact Statement (DOE Programmatic SNF EIS) (Idaho, 1995)

  13. HFIR spent fuel management alternatives

    International Nuclear Information System (INIS)

    Begovich, J.M.; Green, V.M.; Shappert, L.B.; Lotts, A.L.

    1992-01-01

    The High Flux Isotope Reactor (HFIR) at Martin Marietta Energy Systems' Oak Ridge National Laboratory (ORNL) has been unable to ship its spent fuel to Savannah River Site (SRS) for reprocessing since 1985. The HFIR storage pools are expected to fill up in the February 1994 to February 1995 time frame. If a management altemative to existing HFIR pool storage is not identified and implemented before the HFIR pools are full, the HFIR will be forced to shut down. This study investigated several alternatives for managing the HFIR spent fuel, attempting to identify options that could be implemented before the HFIR pools are full. The options investigated were: installing a dedicated dry cask storage facility at ORNL, increasing HFIR pool storage capacity by clearing the HFIR pools of debris and either close-packing or stacking the spent fuel elements, storing the spent fuel at another ORNL pool, storing the spent fuel in one or more hot cells at ORNL, and shipping the spent fuel offsite for reprocessing or storage elsewhere

  14. Assessment of mercury in the Savannah River Site environment

    International Nuclear Information System (INIS)

    Kvartek, E.J.; Carlton, W.H.; Denham, M.; Eldridge, L.; Newman, M.C.

    1994-09-01

    Mercury has been valued by humans for several millennia. Its principal ore, cinnabar, was mined for its distinctive reddish-gold color and high density. Mercury and its salts were used as medicines and aphrodisiacs. At SRS, mercury originated from one of the following: as a processing aid in aluminum dissolution and chloride precipitation; as part of the tritium facilities' gas handling system; from experimental, laboratory, or process support facilities; and as a waste from site operations. Mercury is also found in Par Pond and some SRS streams as the result of discharges from a mercury-cell-type chlor-alkali plant near the city of Augusta, GA. Reactor cooling water, drawn from the Savannah River, transported mercury onto the SRS. Approximately 80,000 kg of mercury is contained in the high level waste tanks and 10,000 kg is located in the SWDF. Additional quantities are located in the various seepage basins. In 1992, 617 wells were monitored for mercury contamination, with 47 indicating contamination in excess of the 0.002-ppm EPA Primary Drinking Water Standard. More than 20 Savannah River Ecology Laboratory (SREL) reports and publications pertinent to mercury (Hg) have been generated during the last two decades. They are divided into three groupings: SRS-specific studies, basic studies of bioaccumulation, and basic studies of effect. Many studies have taken place at Par Pond and Upper Three Runs Creek. Mercury has been detected in wells monitoring the groundwater beneath SRS, but not in water supply wells in excess of the Primary Drinking Water Limit of 0.002 ppm. There has been no significant release of mercury from SRS to the Savannah River. While releases to air are likely, based on process knowledge, modeling of the releases indicates concentrations that are well below the SCDHEC ambient standard

  15. Assessment of mercury in the Savannah River Site environment

    Energy Technology Data Exchange (ETDEWEB)

    Kvartek, E.J.; Carlton, W.H.; Denham, M.; Eldridge, L.; Newman, M.C.

    1994-09-01

    Mercury has been valued by humans for several millennia. Its principal ore, cinnabar, was mined for its distinctive reddish-gold color and high density. Mercury and its salts were used as medicines and aphrodisiacs. At SRS, mercury originated from one of the following: as a processing aid in aluminum dissolution and chloride precipitation; as part of the tritium facilities` gas handling system; from experimental, laboratory, or process support facilities; and as a waste from site operations. Mercury is also found in Par Pond and some SRS streams as the result of discharges from a mercury-cell-type chlor-alkali plant near the city of Augusta, GA. Reactor cooling water, drawn from the Savannah River, transported mercury onto the SRS. Approximately 80,000 kg of mercury is contained in the high level waste tanks and 10,000 kg is located in the SWDF. Additional quantities are located in the various seepage basins. In 1992, 617 wells were monitored for mercury contamination, with 47 indicating contamination in excess of the 0.002-ppm EPA Primary Drinking Water Standard. More than 20 Savannah River Ecology Laboratory (SREL) reports and publications pertinent to mercury (Hg) have been generated during the last two decades. They are divided into three groupings: SRS-specific studies, basic studies of bioaccumulation, and basic studies of effect. Many studies have taken place at Par Pond and Upper Three Runs Creek. Mercury has been detected in wells monitoring the groundwater beneath SRS, but not in water supply wells in excess of the Primary Drinking Water Limit of 0.002 ppm. There has been no significant release of mercury from SRS to the Savannah River. While releases to air are likely, based on process knowledge, modeling of the releases indicates concentrations that are well below the SCDHEC ambient standard.

  16. Assessment of Soil Erosion Methods for Sludge Recovery, Savannah River Site

    National Research Council Canada - National Science Library

    Smith, Lawson

    1997-01-01

    ...) from selected storage tanks at the Savannah River Site (SRS) was assessed conceptually. Soil erosion methods are defined as the processes of soil detachment, entrainment, transport, and deposition...

  17. Disposal of Draeger Tubes at Savannah River Site

    International Nuclear Information System (INIS)

    Malik, N.P.

    2000-01-01

    The Savannah River Site (SRS) is a Department of Energy (DOE) facility located in Aiken, South Carolina that is operated by the Westinghouse Savannah River Company (WSRC). At SRS Draeger tubes are used to identify the amount and type of a particular chemical constituent in the atmosphere. Draeger tubes rely on a chemical reaction to identify the nature and type of a particular chemical constituent in the atmosphere. Disposal practices for these tubes were identified by performing a hazardous waste evaluation per the Resource Conservation and Recovery Act (RCRA). Additional investigations were conducted to provide guidance for their safe handling, storage and disposal. A list of Draeger tubes commonly used at SRS was first evaluated to determine if they contained any material that could render them as a RCRA hazardous waste. Disposal techniques for Draeger tubes that contained any of the toxic contaminants listed in South Carolina Hazardous Waste Management Regulations (SCHWMR) R.61-79. 261.24 (b) and/or contained an acid in the liquid form were addressed

  18. Radiological/toxicological sabotage assessments at the Savannah River Site

    International Nuclear Information System (INIS)

    Johnson, H.D.; Pascal, M.D.; Richardson, D.L.

    1995-01-01

    This paper describes the methods being employed by Westinghouse Savannah River Company (WSRC) to perform graded assessments of radiological and toxicological sabotage vulnerability at Savannah River Site (SRS) facilities. These assessments are conducted to ensure that effective measures are in place to prevent, mitigate, and respond to a potential sabotage event which may cause an airborne release of radiological/toxicological material, causing an adverse effect on the health and safety of employees, the public, and the environment. Department of Energy (DOE) Notice 5630.3A, open-quotes Protection of Departmental Facilities Against Radiological and Toxicological Sabotage,close quotes and the associated April 1993 DOE-Headquarters guidance provide the requirements and outline an eight-step process for hazardous material evaluation. The process requires the integration of information from a variety of disciplines, including safety, safeguards and security, and emergency preparedness. This paper summarizes WSRC's approach towards implementation of the DOE requirements, and explains the inter-relationships between the Radiological and Toxicological Assessments developed using this process, and facility Hazard Assessment Reports (HAs), Safety Analysis Reports (SARs), and Facility Vulnerability Assessments (VAs)

  19. Rheology of Savannah River Site Tank 51 HLW radioactive sludge

    International Nuclear Information System (INIS)

    Ha, B.C.

    1993-01-01

    Savannah River Site (SRS) Tank 51 HLW radioactive sludge represents a major portion of the first batch of sludge to be vitrified in the Defense Waste Processing Facility (DWPF) at SRS. The rheological properties of Tank 51 sludge will determine if the waste sludge can be pumped by the current DWPF process cell pump design and the homogeneity of melter feed slurries. The rheological properties of Tank 51 sludge and sludge/frit slurries at various solids concentrations were measured remotely in the Shielded Cells Operations (SCO) at the Savannah River Technology Center (SRTC) using a modified Haake Rotovisco viscometer system. Rheological properties of Tank 51 radioactive sludge/Frit 202 slurries increased drastically when the solids content was above 41 wt %. The yield stresses of Tank 51 sludge and sludge/frit slurries fall within the limits of the DWPF equipment design basis. The apparent viscosities also fall within the DWPF design basis for sludge consistency. All the results indicate that Tank 51 waste sludge and sludge/frit slurries are pumpable throughout the DWPF processes based on the current process cell pump design, and should produce homogeneous melter feed slurries

  20. Commercial integration and partnering at Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Steele, J.R. [Westinghouse Savannah River Co., Aiken, SC (United States); Babione, R.A.; Shikashio, L.A.; Wacaster, A.J.; Paterson, A.D. [SCIENTECH, Inc., Idaho Falls, ID (United States)

    1994-06-01

    Savannah River Site (SRS), particularly the Savannah River Technology Center (SRTC) with the experience from the first successful Integrated Technology Demonstration, can provide an excellent foundation for meeting DOE-EM`s objectives with the new DOE-EM five focus area approach. With this in mind, SRTC established an activity to pursue full commercialization of environmental technologies. This report is an assessment of the status of commercialization at SRS and provides recommendations for enhancement as well as some tools critical to implementation. A review was made of the current situation at SRS with regards to taking technology development to commercial fruition. This was done from the perspective of comparing it to known commercialization models and processes. It was found that SRTC already works through many of the steps in these processes. With integration and action-oriented efforts of the inclusion of business and market factors, SRTC could become an aggressive, successful developer of commercialized technologies. Commercial success criteria tools were developed with regards to integrating them with SRTC selection criteria to ensure that all critical factors are covered in technology commercialization project evaluations. Private investors are very clear that their interest lies in funding commercial enterprises, not merely technologies. Mobilizing private capital is critical to real job growth and long-term economic development. Also, potential industry partners were identified that are willing to be involved with SRS` technology applications and regional development efforts. As another important component to success, regional support organizations were reviewed and evaluated.

  1. Savannah River Site radioiodine atmospheric releases and offsite maximum doses

    International Nuclear Information System (INIS)

    Marter, W.L.

    1990-01-01

    Radioisotopes of iodine have been released to the atmosphere from the Savannah River Site since 1955. The releases, mostly from the 200-F and 200-H Chemical Separations areas, consist of the isotopes, I-129 and 1-131. Small amounts of 1-131 and 1-133 have also been released from reactor facilities and the Savannah River Laboratory. This reference memorandum was issued to summarize our current knowledge of releases of radioiodines and resultant maximum offsite doses. This memorandum supplements the reference memorandum by providing more detailed supporting technical information. Doses reported in this memorandum from consumption of the milk containing the highest I-131 concentration following the 1961 1-131 release incident are about 1% higher than reported in the reference memorandum. This is the result of using unrounded 1-131 concentrations of I-131 in milk in this memo. It is emphasized here that this technical report does not constitute a dose reconstruction in the same sense as the dose reconstruction effort currently underway at Hanford. This report uses existing published data for radioiodine releases and existing transport and dosimetry models

  2. Verification of criticality safety in on-site spent fuel storage systems

    International Nuclear Information System (INIS)

    Rasmussen, R.W.

    1989-01-01

    On February 15, 1984, Duke Power Company received approval for a two-region, burnup credit, spent fuel storage rack design at both Units 1 and 2 of the McGuire Nuclear Station. Duke also hopes to obtain approval by January of 1990 for a dry spent fuel storage system at the Oconee Nuclear Station, which will incorporate the use of burnup credit in the criticality analysis governing the design of the individual storage units. While experiences in burnup verification for criticality safety for their dry storage system at Oconee are in the future, the methods proposed for burnup verification will be similar to those currently used at the McGuire Nuclear Station in the two-region storage racks installed in both pools. In conclusion, the primary benefit of the McGuire rerack effort has obviously been the amount of storage expansion it provided. A total increase of about 2,000 storage cells was realized, 1,000 of which were the result of pursuing the two-region rather than the conventional poison rack design. Less impacting, but equally as important, however, has been the experience gained during the planning, installation, and operation of these storage racks. This experience should prove useful for future rerack efforts likely to occur at Duke's Catawba Nuclear Station as well as for the current dry storage effort underway for the Oconee Nuclear Station

  3. Environmental data management system at the Savannah River Site

    International Nuclear Information System (INIS)

    Story, C.H.; Gordon, D.E.

    1989-01-01

    The volume and complexity of data associated with escalating environmental regulations has prompted professionals at the Savannah River Site to begin taking steps necessary to better manage environmental information. This paper describes a plan to implement an integrated environmental information system at the site. Nine topic areas have been identified. They are: administrative, air, audit ampersand QA, chemical information/inventory, ecology, environmental education, groundwater, solid/hazardous waste, and surface water. Identification of environmental databases that currently exist, integration into a ''friendly environment,'' and development of new applications will all take place as a result of this effort. New applications recently completed include Groundwater Well Construction, NPDES (Surface Water) Discharge Monitoring, RCRA Quarterly Reporting, and Material Safety Data Sheet Information. Database applications are relational (Oracle RDBMS) and reside largely in DEC VMS environments. In today's regulatory and litigation climate, the site recognizes they must have knowledge of accurate environmental data at the earliest possible time. Implementation of this system will help ensure this

  4. MOX Lead Assembly Fabrication at the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Geddes, R.L. [Westinghouse Savannah River Company, AIKEN, SC (United States); Spiker, D.L.; Poon, A.P.

    1997-12-01

    The U. S. Department of Energy (DOE) announced its intent to prepare an Environmental Impact Statement (EIS) under the National Environmental Policy Act (NEPA) on the disposition of the nations weapon-usable surplus plutonium.This EIS is tiered from the Storage and Disposition of Weapons-Usable Fissile Material Programmatic Environmental Impact Statement issued in December 1996,and the associated Record of Decision issued on January, 1997. The EIS will examine reasonable alternatives and potential environmental impacts for the proposed siting, construction, and operation of three types of facilities for plutonium disposition. The three types of facilities are: a pit disassembly and conversion facility, a facility to immobilize surplus plutonium in a glass or ceramic form for disposition, and a facility to fabricate plutonium oxide into mixed oxide (MOX) fuel.As an integral part of the surplus plutonium program, Oak Ridge National Laboratory (ORNL) was tasked by the DOE Office of Fissile Material Disposition(MD) as the technical lead to organize and evaluate existing facilities in the DOE complex which may meet MD`s need for a domestic MOX fuel fabrication demonstration facility. The Lead Assembly (LA) facility is to produce 1 MT of usable test fuel per year for three years. The Savannah River Site (SRS) as the only operating plutonium processing site in the DOE complex, proposes two options to carry out the fabrication of MOX fuel lead test assemblies: an all Category I facility option and a combined Category I and non-Category I facilities option.

  5. Natural radioactivity in ground water near the Savannah River Site

    International Nuclear Information System (INIS)

    Price, V. Jr.; Michel, J.

    1990-08-01

    A study of natural radioactivity in groundwater on and adjacent to the Savannah River Site (SRS) in Aiken (SC) was conducted to determine the spatial and temporal variations in the concentration of specific radionuclides. All available measurements for gross alpha particle activity, gross beta activity, uranium, Ra-226, Ra-228, and radon were collated. Relatively few radionuclide-specific results were found. Twenty samples from drinking water supplies in the area were collected in October 1987 and analyzed for U-238, U-234, Ra-226, Ra-228, and Rn-222. The aquifer type for each public water supply system was determined, and statistical analyses were conducted to detect differences among aquifer types and geographic areas defined at the country level. For samples from the public water wells and distribution systems on and adjacent to the site, most of the gross alpha particle activity could be attributed to Ra-226. Aquifer type was an important factor in determining the level of radioactivity in groundwater. The distribution and geochemical factors affecting the distribution of each radionuclide for the different aquifer types are discussed in detail. Statistical analyses were also run to test for aerial differences, among counties and the site. For all types of measurements, there were no differences in the distribution of radioactivity among the ten counties in the vicinity of the site or the site itself. The mean value for the plant was the lowest of all geographic areas for gross alpha particle activity and radon, intermediate for gross beta activity, and in the upper ranks for Ra-226 and Ra-228. It is concluded that the drinking water quality onsite is comparable with that in the vicinity. 19 refs., 5 figs., 5 tabs

  6. Radiological criteria for the remediation of sites for spent fuel and radioactive waste storage in the Russian Northwest.

    Science.gov (United States)

    Shandala, N K; Sneve, M K; Titov, A V; Smith, G M; Novikova, N Ya; Romanov, V V; Seregin, V A

    2008-12-01

    In the 1960s, two technical bases of the Northern Fleet were created in Northwest Russia, at Andreeva Bay in the Kola Peninsula and Gremikha village on the coast of the Barents Sea. They maintained nuclear submarines, performing receipt and storage of radioactive waste and spent nuclear fuel, and are now designated sites of temporary storage (STSs). An analysis of the radiation situation at these sites demonstrates that substantial long-term remediation work will be required after the removal of the waste and spent nuclear fuel. Regulatory guidance is under development to support this work. Having in mind modern approaches to guaranteeing radiation safety, the primary regulatory focus is on a justification of dose constraints for determining acceptable residual contamination which might lead to exposure to workers and the public. For these sites, four principal options for remediation have been considered-renovation, conversion, conservation and liquidation. This paper describes a system of recommended dose constraints and derived control levels formulated for each option. The unconditional guarantee of long-term radioecological protection provides the basis for criteria development. Non-exceedance of these dose constraints and control levels implies compliance with radiological protection objectives related to the residual contamination. Dose reduction below proposed dose constraint values must also be carried out according to the optimisation principle. The developed criteria relate to the condition of the facilities and the STS areas after the termination of remediation activities. The proposed criteria for renovation, conversion, conservation and liquidation are entirely within the dose limits adopted in Russia for the management of man-made radiation sources, and are consistent with ICRP recommendations and national practice in other countries. The proposed criteria for STS remediation and new industrial (non-radiation-hazardous) facilities and buildings on

  7. Improvements MOIRA system for application to nuclear sites Spanish river

    International Nuclear Information System (INIS)

    Gallego Diaz, E.; Iglesias Ferrer, R.; Dvorzhak, A.; Hofman, D.

    2011-01-01

    Possible consequences of a nuclear accident must have radioactive contamination in the medium and long-term freshwater aquatic systems. Faced with this problem, it is essential to have a realistic assessment of the radiological impact, ecological, social and economic potential management strategies, to take the best decisions rationally. MOIRA is a system of decision support developed in the course of the European Framework Programmes with participation of the UPM, which has been improved and adapted to Spanish nuclear sites in recent years in the context ISIDRO Project, sponsored by the Council Nuclear, with the participation of CIEMAT and UPM. The paper focuses on these advances, primarily related to complex hydraulic systems such as rivers Tajo, Ebro and Jucar, which are located several Spanish plants.

  8. Beneficially reusing LLRW the Savannah River Site Stainless Steel Program

    International Nuclear Information System (INIS)

    Boettinger, W.L.

    1993-01-01

    With 68 radioactively contaminated excess Process Water Heat Exchangers the Savannah River Site launched its program to turn potential LLRW metal liabilities into assets. Each Heat Exchanger contains approximately 100 tons of 304 Stainless Steel and could be disposed as LLRW by land burial. Instead the 7000 tons of metal will be recycled into LLRW, HLW, and TRU waste containers thereby eliminating the need for near term land disposal and also eliminating the need to add more clean metal to the waste stream. Aspects of the partnership between DOE and Private Industry necessary to accomplish this new mission are described. A life cycle cost analysis associated with past practices of using carbon steel containers to indefinitely store material (contributing to the creation of today's legacy waste problems) is presented. The avoided cost calculations needed to support the economics of the ''Indifference'' decision process in assessing the Beneficial Reuse option relative to the Burial option are described

  9. Revision to flood hazard evaluation for the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Buckley, R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Werth, D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2014-08-25

    Requirements for the Natural Phenomena Hazard (NPH) mitigation for new and existing Department of Energy (DOE) facilities are outlined in DOE Order 420.1. This report examines the hazards posed by potential flooding and represents an update to two previous reports. The facility-specific probabilistic flood hazard curve is defined as the water elevation for each annual probability of precipitation occurrence (or inversely, the return period in years). New design hyetographs for both 6-hr and 24-hr precipitation distributions were used in conjunction with hydrological models of various basins within the Savannah River Site (SRS). For numerous locations of interest, peak flow discharge and flood water elevation were determined. In all cases, the probability of flooding of these facilities for a 100,000 year precipitation event is negligible.

  10. New instrument calibration facility for the DOE Savannah River Site

    International Nuclear Information System (INIS)

    Wilkie, W.H.; Polz, E.J.

    1993-01-01

    A new laboratory facility is being designed, constructed, and equipped at the Savannah River Site (SRS) as a fiscal year 1992 line item project. This facility will provide space and equipment for test, evaluation, repair, maintenance, and calibration of radiation monitoring instrumentation. The project will replace an obsolete facility and will allow implementation of program upgrades necessary to meet ANSI N323 requirements and National Voluntary Laboratory Accreditation Program (NVLAP) criteria for accreditation of federally owned secondary calibration laboratories. An outline of the project is presented including description, scope, cost, management organization, chronology, and current status. Selected design criteria and their impacts on the project are discussed. The upgraded SRS calibration program is described, and important features of the new facility and equipment that will accommodate this program are listed. The floor plan for the facility is shown, and equipment summaries and functional descriptions for each area are provided

  11. New instrument calibration facility for the DOE Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Wilkie, W.H.; Polz, E.J. [Westinghouse Savannah River Company, Aiken, SC (United States)

    1993-12-31

    A new laboratory facility is being designed, constructed, and equipped at the Savannah River Site (SRS) as a fiscal year 1992 line item project. This facility will provide space and equipment for test, evaluation, repair, maintenance, and calibration of radiation monitoring instrumentation. The project will replace an obsolete facility and will allow implementation of program upgrades necessary to meet ANSI N323 requirements and National Voluntary Laboratory Accreditation Program (NVLAP) criteria for accreditation of federally owned secondary calibration laboratories. An outline of the project is presented including description, scope, cost, management organization, chronology, and current status. Selected design criteria and their impacts on the project are discussed. The upgraded SRS calibration program is described, and important features of the new facility and equipment that will accommodate this program are listed. The floor plan for the facility is shown, and equipment summaries and functional descriptions for each area are provided.

  12. Savannah River Site waste management. Final environmental impact statement - addendum

    International Nuclear Information System (INIS)

    1995-07-01

    The purpose of this environmental impact statement is to help DOE decide how to manage over the next 30 years liquid high-level radioactive, low-level radioactive, mixed, hazardous, and transuranic wastes generated during 40 years of past operations and on-going activities (including management of wastes received from offsite) at Savannah River Site (SRS) in southwestern South Carolina. The wastes are currently stored at SRS. DOE seeks to dispose of the wastes in a cost-effective manner that protects human health and the environment. In this document, DOE assesses the cumulative environmental impacts of storing, treating, and disposing of the wastes, examines the impacts of alternatives, and identifies measures available to reduce adverse impacts. Evaluations of impacts on water quality, air quality, ecological systems, land use, geologic resources, cultural resources, socio-economics, and the health and safety of onsite workers and the public are included in the assessment

  13. Environmental ALARA Program at the Savannah River Site

    International Nuclear Information System (INIS)

    Jannik, G.T.

    1993-01-01

    The Savannah River Site (SRS) follows the ALARA (As Low As Reasonably Achievable) philosophy of keeping radiation doses to the general public as low as practical by minimizing radioactive releases to the environment. SRS accomplishes this goal by establishing challenging sitewide and area-specific Environmental ALARA Release Guides and trending radioactive releases against these guides on a monthly basis. The SRS Environmental ALARA Program, mandated by DOE Order 5400.5, is a dose-based program that has gone through many changes and improvements in recent years. A description of the SRS Environmental ALARA Program and its performance is presented in this paper. Recent SRS studies of the ''Zero Release'' option also are described

  14. Savannah River Site Waste Management Final Environmental Impact Statement Addendum

    International Nuclear Information System (INIS)

    1995-07-01

    The purpose of this environmental impact statement is to help DOE decide how to manage over the next 30 years liquid high-level radioactive, low-level radioactive, mixed, hazardous, and transuranic wastes generated during 40 years of past operations and on-going activities (including management of wastes received from offsite) at Savannah River Site (SRS) in southwestern South Carolina. The wastes are currently stored at SRS. DOE seeks to dispose of the wastes in a cost-effective manner that protects human health and the environment. In this document, DOE assesses the cumulative environmental impacts of storing, treating, and disposing of the wastes, examines the impacts of alternatives, and identifies measures available to reduce adverse impacts. Evaluations of impacts on water quality, air quality, ecological systems, land use, geologic resources, cultural resources, socio-economic, and the health and safety of onsite workers and the public are included in the assessment

  15. Savannah River Site production reactor technical specifications. K Production Reactor

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-02-01

    These technical specifications are explicit restrictions on the operation of the Savannah River Site K Production Reactor. They are designed to preserve the validity of the plant safety analysis by ensuring that the plant is operated within the required conditions bounded by the analysis, and with the operable equipment that is assumed to mitigate the consequences of an accident. Technical specifications preserve the primary success path relied upon to detect and respond to accidents. This report describes requirements on thermal-hydraulic limits; limiting conditions for operation and surveillance for the reactor, power distribution control, instrumentation, process water system, emergency cooling and emergency shutdown systems, confinement systems, plant systems, electrical systems, components handling, and special test exceptions; design features; and administrative controls.

  16. Flood Hazard Recurrence Frequencies for the Savannah River Site

    International Nuclear Information System (INIS)

    Chen, K.F.

    2001-01-01

    Department of Energy (DOE) regulations outline the requirements for Natural Phenomena Hazard (NPH) mitigation for new and existing DOE facilities. The NPH considered in this report is flooding. The facility-specific probabilistic flood hazard curve defines, as a function of water elevation, the annual probability of occurrence or the return period in years. The facility-specific probabilistic flood hazard curves provide basis to avoid unnecessary facility upgrades, to establish appropriate design criteria for new facilities, and to develop emergency preparedness plans to mitigate the consequences of floods. A method based on precipitation, basin runoff and open channel hydraulics was developed to determine probabilistic flood hazard curves for the Savannah River Site. The calculated flood hazard curves show that the probabilities of flooding existing SRS major facilities are significantly less than 1.E-05 per year

  17. The Savannah River Site's Groundwater Monitoring Program

    Energy Technology Data Exchange (ETDEWEB)

    1992-01-10

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site's (SRS) Groundwater Monitoring Program. During second quarter 1991 EPD/EMS conducted extensive sampling of monitoring wells. EPD/EMS established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead, they aid personnel in sample scheduling, interpretation of data, and trend identification. Beginning in 1991, the flagging criteria are based on EPA drinking water standards and method detection limits. A detailed explanation of the current flagging criteria is presented in the Flagging Criteria section of this document. Analytical results from second quarter 1991 are listed in this report.

  18. Waste Tank Corrosion Program at Savannah River Site

    International Nuclear Information System (INIS)

    Chandler, J.R.; Hsu, T.C.; Hobbs, D.T.; Iyer, N.C.; Marra, J.E.; Zapp, P.E.

    1993-01-01

    The Savannah River Site (SRS) has approximately 30 million gallons of high level radioactive waste stored in 51 underground tanks. SRS has maintained an active corrosion research and corrosion control and monitoring program throughout the operating history of SRS nuclear waste storage tanks. This program is largely responsible for the successful waste storage experience at SRS. The program has consisted of extensive monitoring of the tanks and surrounding environment for evidence of leaks, extensive research to understand the potential corrosion processes, and development and implementation of corrosion chemistry control. Current issues associated with waste tank corrosion are primarily focused on waste processing operations and are being addressed by a number of active programs and initiatives

  19. Sanitary landfill groundwater quality assessment plan Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Wells, D.G.; Cook, J.W.

    1990-06-01

    This assessment monitoring plan has been prepared in accordance with the guidance provided by the SCDHEC in a letter dated December 7, 1989 from Pearson to Wright and a letter dated October 9, 1989 from Keisler to Lindler. The letters are included a Appendix A, for informational purposes. Included in the plan are all of the monitoring data from the landfill monitoring wells for 1989, and a description of the present monitoring well network. The plan proposes thirty-two new wells and an extensive coring project that includes eleven soil borings. Locations of the proposed wells attempt to follow the SCDHEC guidelines and are downgradient, sidegradient and in the heart of suspected contaminant plumes. Also included in the plan is the current Savannah River Site Sampling and Analysis Plan and the well construction records for all of the existing monitoring wells around the sanitary landfill.

  20. External events analysis for the Savannah River Site K reactor

    International Nuclear Information System (INIS)

    Brandyberry, M.D.; Wingo, H.E.

    1990-01-01

    The probabilistic external events analysis performed for the Savannah River Site K-reactor PRA considered many different events which are generally perceived to be ''external'' to the reactor and its systems, such as fires, floods, seismic events, and transportation accidents (as well as many others). Events which have been shown to be significant contributors to risk include seismic events, tornados, a crane failure scenario, fires and dam failures. The total contribution to the core melt frequency from external initiators has been found to be 2.2 x 10 -4 per year, from which seismic events are the major contributor (1.2 x 10 -4 per year). Fire initiated events contribute 1.4 x 10 -7 per year, tornados 5.8 x 10 -7 per year, dam failures 1.5 x 10 -6 per year and the crane failure scenario less than 10 -4 per year to the core melt frequency. 8 refs., 3 figs., 5 tabs

  1. Savannah River Site Operating Experience with Transuranic (TRU) Waste Retrieval

    International Nuclear Information System (INIS)

    Stone, K.A.; Milner, T.N.

    2006-01-01

    Drums of TRU Waste have been stored at the Savannah River Site (SRS) on concrete pads from the 1970's through the 1980's. These drums were subsequently covered with tarpaulins and then mounded over with dirt. Between 1996 and 2000 SRS ran a successful retrieval campaign and removed some 8,800 drums, which were then available for venting and characterization for WIPP disposal. Additionally, a number of TRU Waste drums, which were higher in activity, were stored in concrete culverts, as required by the Safety Analysis for the Facility. Retrieval of drums from these culverts has been ongoing since 2002. This paper will describe the operating experience and lessons learned from the SRS retrieval activities. (authors)

  2. The Savannah River Site Waste Inventory Management Program

    International Nuclear Information System (INIS)

    Griffith, J.M.; Holmes, B.R.

    1995-01-01

    Each hazardous and radioactive waste generator that delivers waste to Savannah River Site (SRS) treatment, storage and disposal (TSD) facilities is required to implement a waste certification plan. The waste certification process ensures that waste has been properly identified, characterized, segregated, packaged, and shipped according to the receiving facilities waste acceptance criteria. In order to comply with the rigid acceptance criteria, the Reactor Division developed and implemented the Waste Inventory Management Program (WIMP) to track the generation and disposal of low level radioactive waste. The WIMP system is a relational database with integrated barcode technology designed to track the inventory radioactive waste. During the development of the WIMP several waste minimization tools were incorporated into the design of the program. The inclusion of waste minimization tools as part of the WIMP has resulted in a 40% increase in the amount of waste designated as compactible and an overall volume reduction of 5,000 cu-ft

  3. Radionuclide limits for vault disposal at the Savannah River Site

    International Nuclear Information System (INIS)

    Cook, James R.

    1992-01-01

    The Savannah River Site is developing a facility called the E-Area Vaults which will serve as the new radioactive waste disposal facility beginning early in 1992. The facility will employ engineered below-grade concrete vaults for disposal and above grade storage for certain long-lived mobile radionuclides. This report documents the determination of interim upper limits for radionuclide inventories and concentrations which should be allowed in the disposal structures. The work presented here will aid in the development of both waste acceptance criteria and operating limits for the E-Area Vaults. Disposal limits for forty isotopes which comprise the SRS waste streams were determined. The limits are based on total facility and vault inventories for those radionuclides which impact groundwater) and on waste package concentrations for those radionuclides which could affect intruders. (author)

  4. Assessment of radiocarbon in the Savannah River Site Environment

    International Nuclear Information System (INIS)

    Carlton, W.H.; Evans, A.G.; Murphy, C.E. Jr.; Tuck, D.M.

    1993-03-01

    This report is a radiological assessment of 14 C releases from the Savannah River Site. During the operation of five production reactors 14 C has been produced at SRS. Approximately 3000 curies have been released to the atmosphere but there are no recorded releases to surface waters. Once released, the 14 C joins the carbon cycle and a portion enters the food chain. The overall radiological impact of SRS releases on the offsite maximum individual can be characterized by a dose of 1.1 mrem, compared with a dose of 12,960 mrem from non-SRS sources during the same period of time. Releases of 14 C have resulted in a negligible risk to the environment and the population it supports

  5. Excavations at the Buller River Site (K29/8), January 2004

    International Nuclear Information System (INIS)

    Jacomb, C.; Tucker, B.; Walter, R.

    2004-01-01

    The Buller River Site (K29/8) is located on the south (true left) bank of the Buller, or Kawatiri, River directly across from Westport and approximately one kilometre from the present shoreline. This report describes the excavations at Buller River in February 2004, outlines the results to date and canvasses options for future research. 12 refs., 11 figs

  6. Site Selection for the Salt Disposition Facility at the Savannah River Site

    International Nuclear Information System (INIS)

    Gladden, J.B.; Rueter, K.J.; Morin, J.P.

    2000-01-01

    A site selection study was conducted to identify a suitable location for the construction and operation of a new Salt Disposition Facility (SDF) at the Savannah River Site (SRS). The facility to be sited is a single processing facility and support buildings that could house either of three technology alternatives being developed by the High Level Waste Systems Engineering Team: Small Tank Tetraphenylborate Precipitation, Crystalline Silicotitanate Non-Elutable Ion Exchange or Caustic Side Solvent Extraction. A fourth alternative, Direct Disposal in grout, is not part of the site selection study because a location has been identified that is unique to this technology (i.e., Z-Area). Facility site selection at SRS is a formal, documented process that seeks to optimize siting of new facilities with respect to facility-specific engineering requirements, sensitive environmental resources, and applicable regulatory requirements. In this manner, the prime objectives of cost minimization, environmental protection, and regulatory compliance are achieved. The results from this geotechnical characterization indicated that continued consideration be given to Site B for the proposed SDF. Suitable topography, the lack of surface hydrology and floodplain issues, no significant groundwater contamination, the presence of minor soft zones along the northeast portion of footprint, and no apparent geological structure in the Gordon Aquitard support this recommendation

  7. Functional groups of macro-benthos of selected sites of upstream of Hron River and Hnilec River

    International Nuclear Information System (INIS)

    Rufusova, A.

    2011-01-01

    The author used six functional groups of macro-benthos based on 'species traits', which are indicated with the Greek letters α to ζ. In the work authors applied this method to the macroinvertebrate communities of selected sites of upstream of the Hron River and the Hnilec River. The method appropriately captured increasing gradient of anthropogenic changes in the direction of the river continuum. Although the method was used for Slovak rivers for the first time, it seems to be promising for use in the future. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Jannik, T.

    2011-08-30

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

  9. The Savannah River Site's groundwater monitoring program

    Energy Technology Data Exchange (ETDEWEB)

    1991-05-06

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site's (SRS) Groundwater Monitoring Program. During third quarter 1990 (July through September) EPD/EMS conducted routine sampling of monitoring wells and drinking water locations. EPD/EMS established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead they aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. All analytical results from third quarter 1990 are listed in this report, which is distributed to all site custodians. One or more analytes exceeded Flag 2 in 87 monitoring well series. Analytes exceeded Flat 2 for the first since 1984 in 14 monitoring well series. In addition to groundwater monitoring, EPD/EMS collected drinking water samples from SRS drinking water systems supplied by wells. The drinking water samples were analyzed for radioactive constituents.

  10. Tritium in the Savannah River Site environment. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Murphy, C.E. Jr.; Bauer, L.R.; Hayes, D.W.; Marter, W.L.; Zeigler, C.C.; Stephenson, D.E.; Hoel, D.D.; Hamby, D.M.

    1991-05-01

    Tritium is released to the environment from many of the operations at the Savannah River Site. The releases from each facility to the atmosphere and to the soil and streams, both from normal operations and inadvertent releases, over the period of operation from the early 1950s through 1988 are presented. The fate of the tritium released is evaluated through environmental monitoring, special studies, and modeling. It is concluded that approximately 91% of the tritium remaining after decay is now in the oceans. A dose and risk assessment to the population around the site is presented. It is concluded that about 0.6 fatal cancers may be associated with the tritium released during all the years of operation to the population of about 625,000. This same population (based on the overall US cancer statistics) is expected to experience about 105,000 cancer fatalities from all types of cancer. Therefore, it is considered unlikely that a relationship between any of the cancer deaths occurring in this population and releases of tritium from the SRS will be found.

  11. Flood Hazard Assessment for the Savannah River Site

    International Nuclear Information System (INIS)

    Chen, K.F.

    2000-01-01

    A method was developed to determine the probabilistic flood elevation curves for certain Savannah River Site (SRS) facilities. This paper presents the method used to determine the probabilistic flood elevation curve for F-Area due to runoff from the Upper Three Runs basin. Department of Energy (DOE) Order 420.1, Facility Safety, outlines the requirements for Natural Phenomena Hazard (NPH) mitigation for new and existing DOE facilities. The NPH considered in this paper is flooding. The facility-specific probabilistic flood hazard curve defines as a function of water elevation the annual probability of occurrence or the return period in years. Based on facility-specific probabilistic flood hazard curves and the nature of facility operations (e.g., involving hazardous or radioactive materials), facility managers can design permanent or temporary devices to prevent the propagation of flood on site, and develop emergency preparedness plans to mitigate the consequences of floods. A method was developed to determine the probabilistic flood hazard curves for SRS facilities. The flood hazard curves for the SRS F-Area due to flooding in the Upper Three Runs basin are presented in this paper

  12. Flood hazard assessment for the Savannah River Site

    International Nuclear Information System (INIS)

    Chen, K.F.

    2000-01-01

    A method was developed to determine the probabilistic flood elevation curves for certain Savannah River Site (SRS) facilities. This paper presents the method used to determine the probabilistic flood elevation curve for F-Area due to runoff from the Upper Three Runs basin. Department of Energy (DOE) Order 420.1, Facility Safety, outlines the requirements for Natural Phenomena Hazard (NPH) mitigation for new and existing DOE facilities. The NPH considered in this paper is flooding. The facility-specific probabilistic flood hazard curve defines as a function of water elevation the annual probability of occurrence or the return period in years. Based on facility-specific probabilistic flood hazard curves and the nature of facility operations (e.g., involving hazardous or radioactive materials), facility managers can design permanent or temporary devices to prevent the propagation of flood on site, and develop emergency preparedness plans to mitigate the consequences of floods. The flood hazard curves for the SRS F-Area due to flooding in the Upper Three Runs basin are presented in this paper

  13. Evaluation of Cone Penetrometer Data for Permeability Correlation at the Savannah River Site

    International Nuclear Information System (INIS)

    Harris, M.K.

    1997-02-01

    This report documents the results of an assessment of cone penetrometer technology (CPT) use at the Savannah River Site. The study is intended to provide valuable insight into methods of increasing the utility of CPT data for site characterization

  14. Evaluation of Cone Penetrometer Data for Permeability Correlation at the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Harris, M.K. [Westinghouse Savannah River Company, AIKEN, SC (United States)

    1997-02-01

    This report documents the results of an assessment of cone penetrometer technology (CPT) use at the Savannah River Site. The study is intended to provide valuable insight into methods of increasing the utility of CPT data for site characterization.

  15. Hanford and Savannah River Site Programmatic and Technical Integration

    International Nuclear Information System (INIS)

    Ramsey, William Gene

    2013-01-01

    Abstract only. The Hanford Site and the Savannah River Site (SRS) were the primary plutonium production facilities within the U.S. nuclear weapons complex. Radioactive wastes were generated as part of these missions and are stored in similar fashion. The majority of radioactivity maintained by the two sites is located in underground carbon steel tanks in the physical form of supernatant, saltcake, or sludge. Disposition of SRS tank waste is ongoing by converting it into glass (pathway for sludge and radionuclides separated from supernatant or dissolved saltcake) or cement (pathway for the decontaminated supernatant and dissolved saltcake). Tank closure activity has also begun at SRS and will continue for the duration of mission. The Hanford tank waste inventory is roughly 2/3rds larger than SRS's by volume- but nominally half the radioactivity. The baseline disposition path includes high-level and low-activity waste vitrification with separate disposition of contact-handled transuranic tank waste. Retrieval of tank waste from aging single shell tanks (SSTs) into double-shell tanks (DSTs) is currently ongoing. As vitrification commences later this decade, Hanford will be in a similar operations mode as SRS. Site integration is increasing as the missions align. The ongoing integration is centered on key issues that impact both sites- regardless of mission timeframe. Three recent workshop exchanges have been held to improve communication with the primary intent of improving operations and technical work organization. The topics of these workshops are as follows: DST space utilization, optimization, and closure; Waste Feed Qualification; and, Cementitious Waste Forms. Key goals for these and future exchanges include aligning research and technology, preparing for joint initiatives (to maximize budgetary value for the customer), and reviewing lessons learned. Each site has played a leading role in the development of technology and operational practices that can be used

  16. Pre-shipment preparations at the Savannah River Site - WSRC's technical basis to support DOE's approval to ship

    International Nuclear Information System (INIS)

    Thomas, Jay E.; Bickley, Donald W.; Conatser, E. Ray

    2000-01-01

    In the first four years of the Foreign Research Reactor (FRR) Spent Nuclear Fuel (SNF) Return Program following resumption of the SNF return program with the DOE-EIS ROD in May 1996, 13 shipments involving 77 casks with over 2,600 assemblies have been safely received and stored at the Savannah River Site (SRS). Each fuel type has gone through a rigorous pre-shipment preparation process that includes fuel characterization, criticality safety reviews, and operational reviews, culminating in the Department of Energy's (DOE's) authorization to ship. Ideally, the authorization to ship process should begin two years in advance of the fuel receipt with an agreement between the Department of Energy - Head Quarters (DOE-HQ) and the research reactor government on the conditions and protocol for the spent nuclear fuel return, with a target of DOE shipment authorization at least two months before facility loading. A visit by representatives from the Department of Energy - Savannah River (DOE-SR) and Westinghouse Savannah River Company (WSRC), DOE's Management and Operations (M and O) Contractor for the SRS, to the research reactor facility is then scheduled for the purpose of finalizing contractual arrangements (DOE-SR), facility assessments, and initial fuel inspections. An extensive effort is initiated at this time to characterize the fuel in a standard format as identified in the Appendix A attachment to the contract. The Appendix A must be finalized in an accurate and timely manner because it serves as the base reference document for WSRC and other involved stakeholders such as the cask owners and the competent authorities throughout the approval process. With the approval of the Appendix A, criticality safety reviews are initiated to evaluate the unloading and storage configurations. Operational reviews are conducted to allow for necessary adaptation of fuel handling facilities, procedures, and training. WSRC has proceduralized this process, 'Certification to Receive and

  17. Assessment of Technetium in the Savannah River Site Environment

    International Nuclear Information System (INIS)

    Carlton, W.H.; Denham, M.; Evans, A.G.

    1993-07-01

    Assessment of Technetium in the Savannah River Site Environment is the last in a series of eight documents on individual radioisotopes released to the environment as a result of SRS operations. The earlier documents describe the environmental consequences of tritium cesium, iodine, uranium plutonium, strontium, and carbon. Technetium transport and metabolism have been studied by the nuclear industry because it is a fission product of uranium, and by the medical community because 99m Tc commonly is used as a diagnostic imaging agent in nuclear medicine. Technetium has been produced at SRS during the operation of five production reactors. The only isotope with environmental significance is 99 Tc. Because of the small activities of 99 Tc relative to other fission products, such as 90 Sr and 137 Cs, no measurements were made of releases to either the atmosphere or surface waters. Dose calculations were made in this document using conservative estimates of atmospheric releases and from a few measurements of 99 Tc concentrations in the Savannah River. Technetium in groundwater has been found principally in the vicinity of the separation areas seepage basins. Technetium is soluble in water and follows groundwater flow with little retardation. While most groundwater samples are negative or show little technetium a few samples have levels slightly above the limits set by the EPA for drinking water. The overall radiological impact of SRS 99 Tc releases on the offsite maximally exposed individual during 38 years of operations can be characterized by maximum individual doses of 0.1 mrem (atmospheric) and 0.8 mrem (liquid), compared with a dose of 13,680 mrem from non-SRS sources during the same time period. Technetium releases have resulted in a negligible risk to the environment and the population it supports

  18. Isotope hydrology of the Chalk River Laboratories site, Ontario, Canada

    Science.gov (United States)

    Peterman, Zell; Neymark, Leonid; King-Sharp, K.J.; Gascoyne, Mel

    2016-01-01

    This paper presents results of hydrochemical and isotopic analyses of groundwater (fracture water) and porewater, and physical property and water content measurements of bedrock core at the Chalk River Laboratories (CRL) site in Ontario. Density and water contents were determined and water-loss porosity values were calculated for core samples. Average and standard deviations of density and water-loss porosity of 50 core samples from four boreholes are 2.73 ± 12 g/cc and 1.32 ± 1.24 percent. Respective median values are 2.68 and 0.83 indicating a positive skewness in the distributions. Groundwater samples from four deep boreholes were analyzed for strontium (87Sr/86Sr) and uranium (234U/238U) isotope ratios. Oxygen and hydrogen isotope analyses and selected solute concentrations determined by CRL are included for comparison. Groundwater from borehole CRG-1 in a zone between approximately +60 and −240 m elevation is relatively depleted in δ18O and δ2H perhaps reflecting a slug of water recharged during colder climatic conditions. Porewater was extracted from core samples by centrifugation and analyzed for major dissolved ions and for strontium and uranium isotopes. On average, the extracted water contains 15 times larger concentration of solutes than the groundwater. 234U/238U and correlation of 87Sr/86Sr with Rb/Sr values indicate that the porewater may be substantially older than the groundwater. Results of this study show that the Precambrian gneisses at Chalk River are similar in physical properties and hydrochemical aspects to crystalline rocks being considered for the construction of nuclear waste repositories in other regions.

  19. Wetland restoration and compliance issues on the Savannah River site

    International Nuclear Information System (INIS)

    Wein, G.R.; McLeod, K.W.; Sharitz, R.R.

    1993-01-01

    Operation of the nuclear production reactors on the Savannah River Site has faced potential conflicts with wetland regulations on several occasions. This paper provides two examples in which regulatory compliance and restoration research have been meshed, providing both compliance and better knowledge to aid future regulatory needs. The decision to restart the L reactor required the mitigation of thermal effluents under Sec. 316 of the Clean Water Act. The National Pollutant Discharge Elimination System, permit for the selected mitigation alternative, a 405-ha once-through cooling reservoir, required the establishment of a balanced biological community (BBC) within the lake. To promote the development of a BBC, the reservoir was seeded with water from an existing BBC (Par Pond) and stocked with fish and had artificial reefs constructed. The US Department of Energy (DOE) also requested that the Savannah River Ecology Laboratory establish littoral/wetland vegetation along the shoreline to provide aquatic and wildlife habitat, shoreline stabilization, and a good faith effort toward the establishment of a BBC. The development of wetland vegetation was deemed important to the successful development of a BBC within L Lake. However, in a similar cooling reservoir system constructed in 1957 (Par Pond), wetland vegetation successfully developed without any planting effort. Other than the good faith effort toward a BBC, there is no reason to assume a littoral/wetland community would not develop of its own accord. However, research conducted at L Lake indicates that the planting of wetland vegetation at L Lake accelerated the process of natural selection over that of areas that were not planted

  20. Savannah River Site: Canyons and associated facilities utilization study

    International Nuclear Information System (INIS)

    Ellison, D.; Dickenson, J.

    1995-01-01

    The Westinghouse Savannah River Company was asked by the U.S. Department of Energy (DOE) to study options for utilization of Savannah River Site (SRS) Canyons and Associated Facilities to support existing and potential future material stabilization and/or disposition missions. This report is WSRC's response to that request. It includes: (1) A compilation of pending DOE material stabilization and/or disposition decisions involving utilization of SRS canyons and associated facilities, including discussion of quantities and expected availability of materials for which SRS handling and/or processing capability is a reasonable alternative under consideration. (2) A description of SRS canyons and associated facilities affected by pending DOE material stabilization and/or disposition decisions, including discussion of material handling and/or processing capabilities and capacities. (3) A comparative evaluation of three proposed scenarios for SRS canyon utilization with respect to startup and operating schedules; annual and life cycle costs; impacts on completion of commitments in the DOE Implementation Plan (IP) for Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1; SRS ability to support alternatives under consideration in pending DOE materials stabilization and/or disposition decisions; and timing for potential transition to deactivation. (4) The sensitivity of the comparative evaluation of the three canyon utilization scenarios to the effect of the selection of other alternatives for individual stabilization missions or individual new missions. Briefings on the scope of this study have been presented to key representatives of several SRS public stakeholder groups. Briefings on the major conclusions from this study have been presented to WSRC Management, DOE-SR, EM-60, EM-1, and the DNFSB

  1. Safety Assessment Document for the Spent Reactor Fuel Geologic Storage Test in the Climax Granite Stock at the Nevada Test site

    International Nuclear Information System (INIS)

    1980-01-01

    The objective of the Spent Fuel Geologic Storage Test in the Climax Granite Stock is to evaluate the response of a granitic rock mass to the underground storage of encapsulated spent reactor fuel in a geometry that simulates a module of a large-scale geologic repository. This document reports an assessment of the safety of conducting this test. Descriptions are provided of the geography, meteorology, hydrology, geology, and seismology of the Climax Site; the effects of postulated natural phenomena and other activities at the nevada Test Site on the safety of the test; and the design and operation of the test facility and associated equipment. Evaluations are made of both the radiological and nonradiological impacts of normal operations, abnormal operations, and postulated accidents. It is concluded that conduct of the spent fuel test at the Climax Site will not result in any undue risk to the public, property, environment, or site employees

  2. Spent fuel storage and isolation

    International Nuclear Information System (INIS)

    Bensky, M.S.; Kurzeka, W.J.; Bauer, A.A.; Carr, J.A.; Matthews, S.C.

    1979-02-01

    The principal spent fuel activities conducted within the commercial waste and spent fuel within the Commercial Waste and Spent Fuel Packaging Program are: simulated near-surface (drywell) storage demonstrations at Hanford and the Nevada Test Site; surface (sealed storage cask) and drywell demonstrations at the Nevada Test Site; and spent fuel receiving and packaging facility conceptual design. These investigations are described

  3. A geographic information system and multi criteria analysis method for site selection of spent nuclear fuel disposal

    International Nuclear Information System (INIS)

    Martins, Vivian Borges

    2009-01-01

    This thesis aims to develop a site selection methodology for the construction of final repository for the spent nuclear fuel disposal, by using geographic information systems (GIS) and multi-criteria decision analysis. Decision making processes of this kind are often complex, given the great number of space parameters to consider and also the typically conflicting opinions of the diverse stake holders. By using GIS, data from different space parameters can be quickly and reliably stored, treated and analyzed. Multi-criteria techniques allow for the incorporation of different stake holders' opinions. These tools, when jointly used, allow for the decision process to be more transparent, quick and reliable. The method developed was applied to the particular case of the state of Rio de Janeiro. Weights obtained from an expert panel and also by using the Hierarchical Analysis Method and cartographic data were combined in the GIS. The application showed that it is possible not only to select and classify areas as to their aptness for the proposed objective, but also to exclude those clearly inadequate areas, thus optimizing the selection process by reducing the search space and consequently minimizing costs and the time spent in the search. (author)

  4. HIGHLY ENRICHED URANIUM BLEND DOWN PROGRAM AT THE SAVANNAH RIVER SITE PRESENT AND FUTURE

    International Nuclear Information System (INIS)

    Magoulas, V; Charles Goergen, C; Ronald Oprea, R

    2008-01-01

    The Department of Energy (DOE) and Tennessee Valley Authority (TVA) entered into an Interagency Agreement to transfer approximately 40 metric tons of highly enriched uranium (HEU) to TVA for conversion to fuel for the Browns Ferry Nuclear Power Plant. Savannah River Site (SRS) inventories included a significant amount of this material, which resulted from processing spent fuel and surplus materials. The HEU is blended with natural uranium (NU) to low enriched uranium (LEU) with a 4.95% 235U isotopic content and shipped as solution to the TVA vendor. The HEU Blend Down Project provided the upgrades needed to achieve the product throughput and purity required and provided loading facilities. The first blending to low enriched uranium (LEU) took place in March 2003 with the initial shipment to the TVA vendor in July 2003. The SRS Shipments have continued on a regular schedule without any major issues for the past 5 years and are due to complete in September 2008. The HEU Blend program is now looking to continue its success by dispositioning an additional approximately 21 MTU of HEU material as part of the SRS Enriched Uranium Disposition Project

  5. Final disposal of spent fuel in the Finnish bedrock. Scope and requirements for site-specific safety analysis

    International Nuclear Information System (INIS)

    1996-12-01

    The report is a summary of the research conducted in the period 1993 to 1996 into safety of spent fuel final disposal. The principal goal of the research in this period, as set in 1993, was to develop a strategy for site-specific safety analysis. At the same time efforts were to be continued to gather data and validate the technical approach for the analysis. The work aimed at having the data needed for the analysis available at the end of year 1998. A safety assessment update, TILA-96, prepared by VTT Energy, is published as a separate report. The assessment is based on the TVO-92 safety analysis, but takes into account the knowledge acquired after 1992 on safety aspects of the disposal system and the data gathered from the site investigations made by TVO and from the beginning of 1996, by Posiva. Since the site investigations are still ongoing and much of the data gathered still pending interpretation, only limited amount of new site-specific information has been available for the present assessment. (172 refs.)

  6. The Savannah River Site`s Groundwater Monitoring Program: Fourth quarter 1991

    Energy Technology Data Exchange (ETDEWEB)

    Rogers, C.D. [Westinghouse Savannah River Co., Aiken, SC (United States)

    1992-06-02

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During fourth quarter 1991, EPD/EMS conducted extensive sampling of monitoring wells. EPD/EMS established two sets of criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead, they aid personnel in sample scheduling, interpretation of data, and trend identification. Beginning in 1991, the flagging criteria are based on EPA drinking water standards and method detection limits. A detailed explanation of the current flagging criteria is presented in the Flagging Criteria section of this document. Analytical results from fourth quarter 1991 are listed in this report.

  7. The Savannah River Site`s Groundwater Monitoring Program: Second quarter 1992

    Energy Technology Data Exchange (ETDEWEB)

    Rogers, C.D. [Westinghouse Savannah River Co., Aiken, SC (United States)

    1992-10-07

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During second quarter 1992, EPD/EMS conducted extensive sampling of monitoring wells. EPD/EMS established two sets of criteria to assist in the management of sample results. The flagging criteria do not define contamination levels; instead, they aid personnel in sample scheduling, interpretation of data, and trend identification. Since 1991, the flagging criteria have been based on the federal Environmental Protection Agency (EPA) drinking water standards and on method detection limits. A detailed explanation of the current flagging criteria is presented in the Flagging Criteria section of this document. Analytical results from second quarter 1992 are listed in this report.

  8. The Savannah River Site`s Groundwater Monitoring Program, second quarter 1990

    Energy Technology Data Exchange (ETDEWEB)

    1991-02-07

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During second quarter 1990 (April through June) EPD/EMS conducted routine sampling of monitoring wells and drinking water locations. EPD/EMS established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. An explanation of flagging criteria for the second quarter is presented in the Flagging Criteria section of this document. All analytical results from second quarter 1990 are listed in this report.

  9. The Savannah River Site`s Groundwater Monitoring Program. Fourth quarter, 1990

    Energy Technology Data Exchange (ETDEWEB)

    1991-06-18

    This report summarizes the Savannah River Site (SRS) groundwater monitoring program conducted in the fourth quarter of 1990. It includes the analytical data, field data, well activity data, and other documentation for this program, provides a record of the program`s activities and rationale, and serves as an official document of the analytical results. The groundwater monitoring program includes the following activities: installation, maintenance, and abandonment of monitoring wells, environmental soil borings, development of the sampling and analytical schedule, collection and analyses of groundwater samples, review of analytical and other data, maintenance of the databases containing groundwater monitoring data, quality assurance (QA) evaluations of laboratory performance, and reports of results to waste-site facility custodians and to the Environmental Protection Section (EPS) of EPD.

  10. The Savannah River Site`s Groundwater Monitoring Program. Second quarter, 1991

    Energy Technology Data Exchange (ETDEWEB)

    1992-01-10

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During second quarter 1991 EPD/EMS conducted extensive sampling of monitoring wells. EPD/EMS established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead, they aid personnel in sample scheduling, interpretation of data, and trend identification. Beginning in 1991, the flagging criteria are based on EPA drinking water standards and method detection limits. A detailed explanation of the current flagging criteria is presented in the Flagging Criteria section of this document. Analytical results from second quarter 1991 are listed in this report.

  11. Spent Nuclear Fuel Alternative Technology Decision Analysis

    International Nuclear Information System (INIS)

    Shedrow, C.B.

    1999-01-01

    The Westinghouse Savannah River Company (WSRC) made a FY98 commitment to the Department of Energy (DOE) to recommend a technology for the disposal of aluminum-based spent nuclear fuel (SNF) at the Savannah River Site (SRS). The two technologies being considered, direct co-disposal and melt and dilute, had been previously selected from a group of eleven potential SNF management technologies by the Research Reactor Spent Nuclear Fuel Task Team chartered by the DOE''s Office of Spent Fuel Management. To meet this commitment, WSRC organized the SNF Alternative Technology Program to further develop the direct co-disposal and melt and dilute technologies and ultimately provide a WSRC recommendation to DOE on a preferred SNF alternative management technology

  12. Spent Nuclear Fuel Alternative Technology Decision Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Shedrow, C.B.

    1999-11-29

    The Westinghouse Savannah River Company (WSRC) made a FY98 commitment to the Department of Energy (DOE) to recommend a technology for the disposal of aluminum-based spent nuclear fuel (SNF) at the Savannah River Site (SRS). The two technologies being considered, direct co-disposal and melt and dilute, had been previously selected from a group of eleven potential SNF management technologies by the Research Reactor Spent Nuclear Fuel Task Team chartered by the DOE''s Office of Spent Fuel Management. To meet this commitment, WSRC organized the SNF Alternative Technology Program to further develop the direct co-disposal and melt and dilute technologies and ultimately provide a WSRC recommendation to DOE on a preferred SNF alternative management technology.

  13. Savannah River Site FY 2001 Spent Nuclear Fuel Integrated Management Plan

    International Nuclear Information System (INIS)

    Dunsmuir, M.D.

    2000-01-01

    This document presents the SRS integrated near and long-term plans (FY 2001 through 2035) for the safe life cycle management of SNF inventories and other SFSD legacy material programs/projects that impact this mission until final disposition has been implemented

  14. Savannah River Site Approved Site Treatment Plan, 1998 Annual Update (U)

    International Nuclear Information System (INIS)

    Lawrence, B.; Berry, M.

    1998-03-01

    The U.S. Department of Energy, Savannah River Operations Office (DOE- SR),has prepared the Site Treatment Plan (STP) for Savannah River Site (SRS) mixed wastes in accordance with RCRA Section 3021(b), and SCDHEC has approved the STP (except for certain offsite wastes) and issued an order enforcing the STP commitments in Volume I. DOE-SR and SCDHEC agree that this STP fulfills the requirements contained in the FFCAct, RCRA Section 3021, and therefore,pursuant to Section 105(a) of the FFCAct (RCRA Section 3021(b)(5)), DOE's requirements are to implement the plan for the development of treatment capacities and technologies pursuant to RCRA Section 3021.Emerging and new technologies not yet considered may be identified to manage waste more safely, effectively, and at lower cost than technologies currently identified in the plan. DOE will continue to evaluate and develop technologies that offer potential advantages in public acceptance, privatization, consolidation, risk abatement, performance, and life-cycle cost. Should technologies that offer such advantages be identified, DOE may request a revision/modification of the STP in accordance with the provisions of Consent Order 95-22-HW.The Compliance Plan Volume (Volume I) identifies project activity schedule milestones for achieving compliance with Land Disposal Restrictions (LDR). Information regarding the technical evaluation of treatment options for SRS mixed wastes is contained in the Background Volume (Volume II) and is provided for information

  15. Seismic stability of the survey areas of potential sites for the deep geological repository of the spent nuclear fuel

    Directory of Open Access Journals (Sweden)

    Kaláb Zdeněk

    2017-07-01

    Full Text Available This paper deals with the seismic stability of the survey areas of potential sites for the deep geological repository of the spent nuclear fuel in the Czech Republic. The basic source of data for historical earthquakes up to 1990 was the seismic website [10]. The most intense earthquake described occurred on September 15, 1590 in the Niederroesterreich region (Austria in the historical period; its reported intensity is Io = 8-9. The source of the contemporary seismic data for the period since 1991 to the end of 2014 was the website [11]. It may be stated based on the databases and literature review that in the period from 1900, no earthquake exceeding magnitude 5.1 originated in the territory of the Czech Republic.

  16. Probabilistic Risk Assessment of Cask Drop Accident during On-site Spent Nuclear Fuel Transportation

    Energy Technology Data Exchange (ETDEWEB)

    Ham, Jae Hyun; Christian, Robby; Momani, Belal Al; Kang, Hyun Gook [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    There are two ways to transfer the SNF from a site to other site, one is land transportation and the other is maritime transportation. Maritime transportation might be used because this way uses more safe route which is far from populated area. The whole transportation process can be divided in two parts: transferring the SNF between SNP and wharf in-Nuclear Power Plant (NPP) site by truck, and transferring the SNF from the wharf to the other wharf by ship. In this research, on-site SNF transportation between SNP and wharf was considered. Two kinds of single accident can occur during this type of SNF transportation, impact and fire, caused by internal events and external events. In this research, PRA of cask drop accident during onsite SNF transportation was done, risk to a person (mSv/person) from a case with specific conditions was calculated. In every 11 FEM simulation drop cases, FDR is 1 even the fuel assemblies are located inside of the cask. It is a quite larger value for all cases than the results with similar drop condition from the reports which covers the PRA on cask storage system. Because different from previous reports, subsequent impact was considered. Like in figure 8, accelerations which are used to calculate the FDR has extremely higher values in subsequent impact than the first impact for all SNF assemblies.

  17. Experiences of risk in connection with site selection for a repository for spent nuclear fuel

    International Nuclear Information System (INIS)

    Biel, A.; Dahlstrand, U.

    1991-03-01

    Describes an investigation of the experiences of risks the the Swedish inhabitants have in connection with site selection for a repository for radioactive waste. The attitudes show a rather complicated picture. It is influenced by such factors as: sex, education and distance to the facility. (KAE)

  18. Design basis flood for nuclear power plants on river sites

    International Nuclear Information System (INIS)

    1983-01-01

    The Guide presents techniques for determining the design basis flood (DBF) to be used for siting nuclear power plants at or near non-tidal reaches of rivers and for protecting nuclear power plants against floods. Since flooding of a nuclear power plant can have repercussions on safety, the DBF is always chosen to have a very low probability of exceedance per annum. The DBF may result from one or more of the following causes: (1) Precipitation, snowmelt; (2) Failure of water control structures, either from seismic or hydrological causes or from faulty operation of these structures; (3) Channel obstruction such as landslide, ice effects, log or debris jams, and effects of vulcanism. Normally the DBF is not less than any recorded or historical flood occurrence. For flood evaluation two types of methods are discussed in this Guide: probabilistic and deterministic. Simple probabilistic methods to determine floods of such low exceedance probability have a great degree of uncertainty and are presented for use only during the site survey. However, the more sophisticated probabilistic methods, the so-called stochastic methods, may give an acceptable result, as outlined in this Guide. The preferred method of evaluating the component of the DBF due to precipitation, as described in this Guide, is the deterministic one, based on the concept of a limit to the probable maximum precipitation (PMP) and on the unit hydrograph technique. Dam failures may generate a flood substantially more severe than that due to precipitation. The methodology for evaluating these types of floods is therefore presented in this Guide. Making allowance for the possible simultaneous occurrence of two or more important flood-producing events is also discussed here. The Guide does not deal with floods caused by sabotage

  19. THE COLD AND DARK PROCESS AT THE SAVANNAH RIVER SITE

    International Nuclear Information System (INIS)

    Gilmour, J; William Austin, W; Cathy Sizemore, C

    2007-01-01

    The deactivation and decommissioning (D and D) of a facility exposes D and D workers to numerous hazards. One of the more serious hazards is coming into contact to hazardous energy sources (e.g. electrical, pressurized steam). At the Savannah River Site (SRS) a formal process for identifying and eliminating sources of hazardous energy was developed and is called ''Cold and Dark''. Several ''near miss'' events involving cutting of energized conductors during D and D work in buildings thought to be isolated identified the need to have a formal process to identify and isolate these potentially hazardous systems. This process was developed using lessons learned from D and D activities at the Rocky Flats Environmental Technology Site (Rocky Flats) in Colorado. The Cold and Dark process defines an isolation boundary (usually a building perimeter) and then systematically identifies all of the penetrations through this boundary. All penetrations that involve hazardous energy sources are then physically air-gapped. The final product is a documented declaration of isolation performed by a team involving operations, engineering, and project management. Once the Cold and Dark declaration is made for a building work can proceed without the usual controls used in an operational facility (e.g. lockout/tagout, arc flash PPE). It is important to note that the Cold and Dark process does not remove all hazards from a facility. Work planning and controls still need to address hazards that can be present from such things as chemicals, radiological contamination, residual liquids, etc., as well as standard industrial hazards

  20. Integrated account of method, site selection and programme prior to the site investigation phase[Planning for a Swedish repository for spent nuclear fuels

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-12-01

    In order to dispose of the spent nuclear fuel in a safe manner, SKB plans to site a deep repository and an encapsulation plant with associated canister fabrication and transportation system. After an integrated evaluation of feasibility studies and other material, SKB will proceed with investigations of the rock and studies regarding establishment of the deep disposal system in the municipality of Oskarshamn or in Northern Uppland. The plans also include further study of the prospects for a deep repository in the municipality of Nykoeping. In the municipality of Oskarshamn, SKB plans further studies of a siting of the deep repository at Simpevarp. There SKB wants to initiate site investigations with test drilling. For the encapsulation plant, SKB wants to continue studying a siting at CLAB. In Northern Uppland, SKB plans to study two siting alternatives for the deep repository. One is Forsmark in the municipality of Oesthammar, where SKB wants to initiate a site investigation with test drilling. The other is Tierp north of Skutskaer, where SKB intends to start test drilling in an area north of Tierp. First, however, a suitable drilling area with possible transport solutions needs to be defined. This alternative requires the participation of the municipalities of both Tierp and Aelvkarleby. A siting of the encapsulation plant in Northern Uppland will also be studied. For the municipality of Nykoeping, SKB plans to conduct a new safety assessment for the Fjaellveden area, based on data from previous investigations as well as additional studies of how a deep repository could be arranged. SKB will thereby gather data from yet another geographic and geological region beyond those that are prioritized. No test drilling is planned in Nykoeping. The goal of the site investigation phase is to obtain all permits needed to build the planned facilities. It will take an estimated 7 - 8 years to assemble the requisite supporting material, carry out consultations, compile siting

  1. Law enforcement tools available at the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Hofstetter, K.J.

    2000-03-29

    A number of nuclear technologies developed and applied at the Savannah River Site in support of nuclear weapons material production and environmental remediation can be applied to problems in law enforcement. Techniques and equipment for high-sensitivity analyses of samples are available to identify and quantify trace elements and establish origins and histories of forensic evidence removed from crime scenes. While some of theses capabilities are available at local crime laboratories, state-of-the-art equipment and breakthroughs in analytical techniques are continually being developed at DOE laboratories. Extensive experience with the handling of radioactive samples at the DOE labs minimizes the chances of cross-contamination of evidence received from law enforcement. In addition to high-sensitivity analyses, many of the field techniques developed for use in a nuclear facility can assist law enforcement personnel in detecting illicit materials and operations, in retrieving of pertinent evidence and in surveying crime scenes. Some of these tools include chemical sniffers, hand-held detectors, thermal imaging, etc. In addition, mobile laboratories can be deployed to a crime scene to provide field screening of potential evidence. A variety of portable sensors can be deployed on vehicle, aerial, surface or submersible platforms to assist in the location of pertinent evidence or illicit operations. Several specific nuclear technologies available to law enforcement and their potential uses are discussed.

  2. Savannah River Site reactor hardware design modification study

    International Nuclear Information System (INIS)

    Fisher, J.E.

    1990-01-01

    A study was undertaken to assess the merits of proposed design modifications to the Savannah River Site (SRS) reactors. The evaluation was based on the responses calculated by the RELAP5 systems code to double-ended guillotine break loss-of-coolant-accidents (DEGB LOCAs). The three concepts evaluated were (a) elevated plenum inlet piping with a guard vessel and clamshell enclosures, (b) closure of both rotovalves in the affected loop, and (c) closure of the pump suction valve in the affected loop. Each concept included a fast reactor shutdown (to 65% power in 100 ms) and a 2-s ac pump trip. System recovery potential was evaluated for break locations at the pump suction, the pump discharge, and the plenum inlet. The code version used was RELAP5/MOD2.5 version 3d3, a preliminary version of RELAP5/MOD3. The model was a three-dimensional representation of the K-Reactor water plenum and moderator tank. It included explicit representations of all six loops, which were based on the configuration of L-Reactor. A combination of features is recommended to ensure liquid inventory recovery for all break locations. Valve closure design performance for a break location in the short section of piping between the reactor concrete shield and the pump suction valve would benefit from the clamshell enclosing that section of piping. 7 refs., 10 figs., 2 tabs

  3. Savannah River Site delayed neutron instruments for safeguards measurements

    International Nuclear Information System (INIS)

    Studley, R.V.

    1992-01-01

    The Savannah River Site (SRS) includes a variety of nuclear production facilities that, since 1953, have processed special nuclear materials (SNM) including highly-enriched uranium (>90% 235 U), recycled enriched uranium (∼50% 235 U + 40% 236 U), low burnup plutonium (> 90% 239 Pu + 240 Pu ) and several other nuclear materials such as heat source plutonium ( 238 Pu). DOE Orders, primarily 5633.3, require all nuclear materials to be safeguarded through accountability and material control. Accountability measurements determine the total amount of material in a facility, balancing inventory changes against receipts and shipments, to provide assurance (delayed) that all material was present. Material control immediately detects or deters theft or diversion by assuring materials remain in assigned locations or by impeding unplanned movement of materials within or from a material access area. Goals for accountability or material control, and, therefore, the design of measurement systems, are distinctly different. Accountability measurements are optimized for maximum precision and accuracy, usually for large amounts of special nuclear material. Material control measurements are oriented more toward security features and often must be optimized for sensitivity, to detect small amounts of materials where none should be

  4. Mathematical model of the Savannah River Site waste tank farm

    International Nuclear Information System (INIS)

    Smith, F.G. III.

    1991-01-01

    A mathematical model has been developed to simulate operation of the waste tank farm and the associated evaporator systems at the Savannah River Site. The model solves material balance equations to predict the volumes of liquid waste, salt, and sludge for all of the tanks within each of the evaporator systems. Additional logic is included to model the behavior of waste tanks not directly associated with the evaporators. Input parameters include the Material Management Plan forecast of canyon operations, specification of other waste sources for the evaporator systems, evaporator operating characteristics, and salt and sludge removal schedules. The model determines how the evaporators will operate, when waste transfers can be made, and waste accumulation rates. Output from the model includes waste tank contents, summaries of systems operations, and reports of space gain and the remaining capacity to store waste materials within the tank farm. Model simulations can be made to predict waste tank capacities on a daily basis for up to 20 years. The model is coded as a set of three computer programs designed to run on either IBM compatible or Apple Macintosh II personal computers

  5. Hydrogen isotope separation experience at the Savannah River Site

    International Nuclear Information System (INIS)

    Lee, M.W.

    1993-01-01

    Savannah River Site (SRS) is a sole producer of tritium for US Weapons Program. SRS has built Facilities, developed the tritium handling processes, and operated safely for the last forty years. Tritium is extracted from the irradiated reactor target, purified, mixed with deuterium, and loaded to the booster gas bottle in the weapon system for limited lifetime. Tritium is recovered from the retired bottle and recycled. Newly produced tritium is branded into the recycled tritium. One of the key process is the hydrogen isotope separation that tritium is separated from deuterium and protium. Several processes have been used for the hydrogen isotope separation at SRS: Thermal Diffusion Column (TD), Batch Cryogenic Still (CS), and Batch Chromatography called Fractional Sorption (FS). TD and CS requires straight vertical columns. The overall system separation factor depends on the length of the column. These are three story building high and difficult to put in glove box. FS is a batch process and slow operation. An improved continuous chromatographic process called Thermal Cycling Absorption Process (TCAP) has been developed. It is small enough to be about to put in a glove box yet high capacity comparable to CS. The SRS tritium purification processes can be directly applicable to the Fusion Fuel Cycle System of the fusion reactor

  6. Assessment of strontium in the Savannah River Site environment

    International Nuclear Information System (INIS)

    Carlton, W.H.; Evans, A.G.; Geary, L.A.; Murphy, C.E. Jr.; Strom, R.N.

    1992-01-01

    This document on strontium is published as a part of the Radiological Assessment Program (RAP). It is the sixth in a series of eight documents on individual radioisotopes released to the environment as a result of SRS (Savannah River Site) operations. Strontium exists in the environment as a result of above-ground nuclear weapons tests, the Chernobyl accident, the destruction of satellite Cosmos 954, small releases from reactors and reprocessing plants, and the operation of industrial, medical, and educational facilities. Strontium has been produced at SRS during the operation of 5 production reactors. About 300 curies of radiostrontium were released into streams in the late 50s and 60s, primarily from leaking fuel elements in reactor storage basins. Smaller quantities were released from the fuel reprocessing operations. About 400 Ci were released to seepage basins. A much smaller quantity, about 2 Ci, was released to the atmosphere. The overall radiological impact of SRS releases on the offsite maximum individual can be characterized by total doses of 6.2 mrem (atmospheric) and 1.4 mrem (liquid), compared with a dose of 12,960 mrem from non-SRS sources during the same period of time. Radiostrontium releases have resulted in a negligible risk to the environment and the population it supports

  7. Assessment of strontium in the Savannah River Site environment

    Energy Technology Data Exchange (ETDEWEB)

    Carlton, W.H.; Evans, A.G.; Geary, L.A.; Murphy, C.E. Jr.; Strom, R.N.

    1992-12-31

    This document on strontium is published as a part of the Radiological Assessment Program (RAP). It is the sixth in a series of eight documents on individual radioisotopes released to the environment as a result of SRS (Savannah River Site) operations. Strontium exists in the environment as a result of above-ground nuclear weapons tests, the Chernobyl accident, the destruction of satellite Cosmos 954, small releases from reactors and reprocessing plants, and the operation of industrial, medical, and educational facilities. Strontium has been produced at SRS during the operation of 5 production reactors. About 300 curies of radiostrontium were released into streams in the late 50s and 60s, primarily from leaking fuel elements in reactor storage basins. Smaller quantities were released from the fuel reprocessing operations. About 400 Ci were released to seepage basins. A much smaller quantity, about 2 Ci, was released to the atmosphere. The overall radiological impact of SRS releases on the offsite maximum individual can be characterized by total doses of 6.2 mrem (atmospheric) and 1.4 mrem (liquid), compared with a dose of 12,960 mrem from non-SRS sources during the same period of time. Radiostrontium releases have resulted in a negligible risk to the environment and the population it supports.

  8. Law enforcement tools available at the Savannah River Site

    International Nuclear Information System (INIS)

    Hofstetter, K.J.; Beals, D.M.; Halverson, J.E.; Villa-Aleman, E.; Hayes, D.W.

    2001-01-01

    A number of nuclear technologies developed and applied at the Savannah River Site in support of nuclear weapons material production and environmental remediation can be applied to problems in law enforcement. Techniques and equipment for high-sensitivity analyses of samples are available to identify and quantify trace elements and establish origins and histories of forensic evidence removed from crime scenes. While some of these capabilities are available at local crime laboratories, state-of-the-art equipment and breakthroughs in analytical techniques are continually being developed at DOE laboratories. Extensive experience with the handling of radioactive samples at the DOE labs minimizes the chances of cross-contamination of evidence received from law enforcement. In addition to high-sensitivity analyses, many of the field techniques developed for use in a nuclear facility can assist law enforcement personnel in detecting illicit materials and operations, in retrieving of pertinent evidence and in surveying crime sciences. Some of these tools include chemical sniffers, hand-held detectors, thermal imaging, etc. In addition, mobile laboratories can be deployed to a crime scene to provide field screening of potential evidence. A variety of portable sensors can be deployed on vehicle, aerial, surface of submersible platforms to assist in the location of pertinent evidence or illicit operations. Several specific nuclear technologies available to law enforcement and their potential uses are discussed. (author)

  9. Final disposal of spent nuclear fuel-geological, hydrogeological and geophysical methods for site characterization

    International Nuclear Information System (INIS)

    Ahlbom, K.; Carlsson, L.; Olsson, O.

    1983-05-01

    Investigations for the siting of a final repository for high-level radioactive waste are currently being conducted in crystalline rock formations in Sweden. A repository will be located at a depth of about 500 m, and investigations are being carried out in drill holes to below that level. A standard program has been established for the site investigations, comprising a number of phases: 1. General reconnaissance for selection of study site 2. Detailed investigation on the ground surface 3. Depth investigation in drill holes 4. Evaluation and modelling 1. Includes geological and geophysical reconnaissance measurements and drilling of one deep drill hole 2. includes surface and depth investigation within an area of approximately 4-8 km 2 . The surface investigations consist of geophysical measurements including electrical resistivity, magnetization, induced polarization and seismic measurements, and yeild informatin on the composition and fracturing of the bedrock in the superficial parts of the study sites. Mapping of the superficial parts of the bedrock are concluded with short percussion and core drillholes down to 150-250 metres in order to determine the dip and character of fracture zones and rock boundaries. 3. Comprises core drilling to vertical depths of about 600 m, core mapping geophysical well-logging and different hydraulic downhole measurements. In core mapping, the emphasis is placed on fracture characterization of the core. The geophysical logging includes three resistivity methods, natural gamma, induced polarization, spontaneous potential and temperature, salinity, pH and Eh of the drill hole fluid. The hydraulic measurements include: measurements of hydraulic conductivity by single-hole and cross-hole testing, determination of the hydraulic fracture frequency and determination of groundwater head at different levels in the bedrock. (G.B.)

  10. Effects of AFR storage location on spent fuel transportation

    International Nuclear Information System (INIS)

    Joy, D.S.; Shappert, L.B.

    1979-01-01

    In order to assess the impact of Away-From-Reactor (AFR) siting on the spent fuel transportation system, five different sites were studied: Argonne, Oak Ridge, Savannah River, Idaho Falls, and Richland. Transportation costs, cask fleet sizes, and radiation exposures received by transportation workers and the general public were calculated for each site. Results show that the eastern three sites are best. 5 figures, 5 tables

  11. Reconnaissance survey of site 7 of the proposed Three Rivers Regional Landfill and Technology Center, Savannah River Site, Aiken County, South Carolina

    Energy Technology Data Exchange (ETDEWEB)

    Cabak, M.A.; Beck, M.L.; Gillam, C.; Sassaman, K.E.

    1996-02-01

    This report documents the archaeological investigation of Site 7 of the proposed Three Rivers Regional Landfill and Technology Center in Aiken County on the United States Department of Energy`s Savannah River Site (SRS) in Aiken and Barnwell Counties, South Carolina. Pedestrian and subsurface survey techniques were used to investigate the 1,403-acre project area. Survey resulted in the discovery of 23 previously unrecorded sites and 11 occurrences; six previously recorded sites were also investigated. These sites consist of six prehistoric sites, nine historic sites, and 14 sites with both prehistoric and historic components. Sites locations and project area boundaries are provided on a facsimile of a USGS 7.5 topographic map. The prehistoric components consist of very small, low-density lithic and ceramic scatters; most contain less than 10 artifacts. Six of the prehistoric components are of unknown cultural affiliation, the remaining prehistoric sites were occupied predominately in the Woodland period. The historic sites are dominated by postbellum/modem home places of tenant and yeoman farmers but four historic sites were locations of antebellum house sites (38AK136, 38AK613, 38AK660, and 38AK674). The historic sites also include an African-American school (38AK677).

  12. A New Hydrogeological Research Site in the Willamette River Floodplain

    Science.gov (United States)

    The Willamette River is a ninth-order tributary of the Columbia which passes through a productive and populous region in northwest Oregon. Where unconstrained by shoreline revetments, the floodplain of this river is a high-energy, dynamic system which supports a variety of ripari...

  13. Occupational radiation dose assessment for a non site specific spent fuel storage facility

    International Nuclear Information System (INIS)

    Hadley, J.; Eble, R.G. Jr.

    1997-01-01

    To expedite the licensing process of the non site specific Centralized Interim Storage Facility (CISF) the Department of Energy has completed a phase I CISF Topical Safety Analysis Report (TSAR). The TSAR will be used in licensing the phase I CISF if a site is designated. An occupational radiation does assessment of the facility operations is performed as part of the phase I CISF design. The first phase of the CISF has the capability to receive, transfer, and store SNF in dual-purpose cask/canister systems (DPC's). Currently there are five vendor technologies under consideration. The preliminary dose assessment is based on estimated occupational exposures using traditional power plant ISFSI and transport cask handling processes. The second step in the process is to recommend ALARA techniques to reduce potential exposures. A final dose assessment is completed implementing the ALARA techniques and a review is performed to ensure that the design is in compliance with regulatory criteria. The dose assessment and ALARA evaluation are determined using the following input information: Dose estimates from vendor SAR's; ISFSI experience with similar systems; Traditional methods of operations; Expected CISF cask receipt rates; and feasible ALARA techniques. 5 refs., 1 tab

  14. Demonstration of Eastman Christensen horizontal drilling system -- Integrated Demonstration Site, Savannah River Site

    International Nuclear Information System (INIS)

    1992-12-01

    An innovative horizontal drilling system was used to install two horizontal wells as part of an integrated demonstration project at the Savannah River Site (SRS), Aiken, South Carolina. The SRS is located in south-central South Carolina in the upper Coastal Plain physiographic province. The demonstration site is located near the A/M Area, and is currently known as the Integated Demonstration Site. The Department of Energy's Office of Technology Development initiated an integrated demonstration of innovative technologies for cleanup of volatile organic compounds (VOCS) in soils and groundwater at the SRS in 1989. The overall goal of the program is to demonstrate, at a single location, multiple technologies in the fields of drilling, characterization, monitoring, and remediation. Innovative technologies are compared to one another and to baseline technologies in terms of technical performance and cost effectiveness. Transfer of successfully demonstrated technologies and systems to DOE environmental restoration organizations, to other government agencies, and to industry is a critical part of the program

  15. The Savannah River Site`s groundwater monitoring program. Third quarter 1990

    Energy Technology Data Exchange (ETDEWEB)

    1991-05-06

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During third quarter 1990 (July through September) EPD/EMS conducted routine sampling of monitoring wells and drinking water locations. EPD/EMS established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead they aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. All analytical results from third quarter 1990 are listed in this report, which is distributed to all site custodians. One or more analytes exceeded Flag 2 in 87 monitoring well series. Analytes exceeded Flat 2 for the first since 1984 in 14 monitoring well series. In addition to groundwater monitoring, EPD/EMS collected drinking water samples from SRS drinking water systems supplied by wells. The drinking water samples were analyzed for radioactive constituents.

  16. Development of a site-wide accident management center for the Savannah River Site

    International Nuclear Information System (INIS)

    Heal, D.W.; Britt, T.E.

    1992-01-01

    In 1990, the Safety Analysis Group at the Savannah River Site (SRS) began development of an Accident Management program. The program was designed to provide a total system which would meet the Department of Energy (DOE) Safety Performance Criteria, in regard to severe accident management, in the most effective manner. This paper will present two significant changes in the current SRS Accident Management program which will be used to meet these expanded needs. The first and most significant change will be to expand the diversity of the groups involved in the Accident Management process. In the future, organizations such as Environmental Safety, Health ampersand Quality Assurance, Emergency Planning, Site Management, Human Factors, Risk Assessment, and many others will work as an integrated team to solve facility problems. Organizations such as Materials Technology, Equipment Engineering and many of the laboratories on site will be utilized as support groups to increase the technical capability for specific accident analyses. This phase of the program is currently being structured, and should be operational by January of 1993

  17. Geological site selection studies for the final disposal of spent nuclear fuel in Finland

    International Nuclear Information System (INIS)

    Salmi, M.; Vuorela, P.; Kuivamaeki, A.

    1985-10-01

    In the work of selecting at the areas, heed has been taken of international geological recommendations, which have been adapted to local conditions prevailing in this country. At the present stage, the studies are largely based on the available information about the bedrock of Finland, as contained in, for example, geological maps, various geophysical maps covering the country as a whole and the maps of ore deposits and indications as well as of groundwater areas. The regional investigations of the structure of the Finnish bedrock has taken as its point of departure the study of satellite photos. These pictures best show the mosaiclike block structure of the Finnish bedrock, where the fracture zones surrounding the blocks are involved in the movements of the bedrock resulting mainly from land uplift. From the interpretation of satellite photos, attention has switched over to the interpretation of large-scale maps and stereoscopic aerial photographs. The investigation areas selected by the interpretation of aerial photos have also been studied tentatively on the ground to obtain a more accurate comparative estimation of the different localities. Of the areas chosen for study, the majority consist of granites, which best meet the geological site selection recommendations. The investigation areas have been classified into four categories according to how well they are suited to further study. One important criterion in the classification has been the amount of information obtainable from the bedrock. The areas included in the first category have well exposed and solid bedrock. The areas chosen for inclusion in the second category contain fewer outcrops and are not so easy to study with respect to the structure of the bedrock. The areas included in the third category are generally blanketed under surficial deposits with the result that obtaining reliable information about the bedrock calls for further investigation. The fourth category represents areas where features

  18. Field testing at the Climax Stock on the Nevada Test Site: spent fuel test and radionuclide migration experiments

    International Nuclear Information System (INIS)

    Ballou, L.B.; Isherwood, D.J.; Patrick, W.C.

    1982-01-01

    Two field tests in the Climax Stock are being conducted. The Climax Stock, a granitic instrusive, has been administratively excluded from consideration as a full-scale repository site. However, it provides a readily available facility for field testing with high-level radioactive materials at a depth (420 m) approaching that of a repository. The major test activity in the 1980 fiscal year has been initiation of the Spent Fuel Test-Climax (SFT-C). This test, which was authorized in June 1978, is designed to evaluate the generic feasibility of geologic storage and retrievability of commercial power reactor spent fuel assemblies in a granitic medium. In addition, the test is configured and instrumented to provide thermal and thermomechanical response data that will be relevant to the design of a repository in hard crystalline rock. The other field activity in the Climax Stock is a radionuclide migration test. It combines a series of field and laboratory migration experiments with the use of existing hydrologic models for pretest predictions and data interpretation. Goals of this project are to develop: (1) field measurement techniques for radionuclide migration studies in a hydrologic regime where the controlling mechanism is fracture permeability; (2) field test data on radionuclide migration; and (3) a comparison of laboratory- and field-measured retardation factors. This radionuclide migration test, which was authorized in the middle of the 1980 fiscal year, is in the preliminary design phase. The detailed program plan was prepared and subjected to formal peer review in August. In September/October researchers conducted preliminary flow tests with water in selected near-vertical fractures intersected by small horizontal boreholes. These tests were needed to establish the range of pressures, flow rates, and other operating parameters to be used in conducting the nuclide migration tests. 21 references, 14 figures, 1 table

  19. Learning and education on environmental radioactivity by residents of Rokkasho Site for the spent fuel recycling facilities

    International Nuclear Information System (INIS)

    Kawauchi, Kiye; Itoh, Natsuko; Ishikawa, Tomiye; Nihonyanagi, Haruko; Aratani, Michi

    2005-01-01

    The neutron criticality accident at the JCO, a private company for nuclear fuel processing facilities in Tokai has drastically changed minds and attitudes of residents toward environmental radioactivity. The accident happened on September 30, 1999. Before the accident the residents of the Rokkasho Site were not anxious about environmental radioactivity, because they thought the facilities were safe enough concerning containment policy of the radioactivity inside the facilities. Residents, however, had not been taught on a neutron. It is an unfamiliar radiation for them. So, they promptly learnt on neutrons, and some of them began the fixed point measurement of neutrons at the nearest site of the Spent Fuel Recycling Facilities of Rokkasho by the help of Prof. Kazuhisa. Komura, Kanazawa University. Members of the Reading Cicle, Rokkasho Culture Society, mainly women, learnt measurements of environmental radioactivity using simplified counters for alpha-, beta-, and gamma-ray from natural radioactive elements and prepared various kinds of environmental samples. After learning of environmental radioactivity, they began educational activities on the environmental radioactivity for boys and girls in the region. Monitoring of environmental radioactivity is performed by different institutions and with their purposes. Here is reported learning of environmental radioactivity by the residents and education of environmental radioactivity toward the young. Even with the simplest counters, we think that the monitoring of environmental radioactivity by the residents themselves is the royal road to the safety of the regional society. (author)

  20. Site Outcomes Baseline Multi Year Work Plan Volume 1, River Corridor Restoration Baseline

    International Nuclear Information System (INIS)

    Wintczak, T.M.

    2001-01-01

    The River Corridor Restoration volume is a compilation of Hanford Site scope, which excludes the approximately 194 km 2 Central Plateau. The River Corridor scope is currently contractually assigned to Fluor Hanford, Bechtel Hanford, inc., DynCorp, and Pacific Northwest National Laboratory, and others. The purpose of this project specification is to provide an overall scoping document for the River Corridor Restoration volume, and to provide a link with the overall Hanford Site River Corridor scope. Additionally, this specification provides an integrated and consolidated source of information for the various scopes, by current contract, for the River Corridor Restoration Baseline. It identifies the vision, mission, and goals, as well as the operational history of the Hanford Site, along with environmental setting and hazards

  1. Data Summary Report for teh Remedial Investigation of Hanford Site Releases to the Columbia River, Hanford Site, Washington

    Energy Technology Data Exchange (ETDEWEB)

    Hulstrom, L.

    2011-02-07

    This data summary report summarizes the investigation results to evaluate the nature and distribution of Hanford Site-related contaminants present in the Columbia River. As detailed in DOE/RL-2008-11, more than 2,000 environmental samples were collected from the Columbia River between 2008 and 2010. These samples consisted of island soil, sediment, surface water, groundwater upwelling (pore water, surface water, and sediment), and fish tissue.

  2. Nuclear Waste Risk Perceptions and Attitudes in Siting a Final Repository for Spent Nuclear Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Sjoeberg, Lennart [Stockholm School of Economics (Sweden). Center for Risk Research

    2006-09-15

    The paper does the following: Describes the time trends between 2001 and 2005 in terms of policy intention, perceived risk, trust and attitude Analyzes the relationships between policy attitude - the major dependent variable - and the explanatory variables of perceived risk, trust and attitude. Determines whether policy attitude variation across time, municipalities and genders can be accounted for by variation in perceived risk, trust and attitude. Random samples of 2000 persons living in Oesthammar and Oskarshamn were approached with a mailed questionnaire in 2005 (as was done in 2005). After two reminders, 888 had returned filled out questionnaires, yielding a total response rate of 50 percent, taking into account that some persons had moved without giving a forwarding address to the post office, and that some were unable to answer due to illness or old age. (1). There was a substantially more positive attitude to a local SNF repository in 2005 than in 2001, after an intervening period of phase 2 site investigation. This was true for men and women, both municipalities and with all the response measures analyzed. Men were more positive than women, and had developed more strongly in the positive direction than women had. The attitude in Oskarshamn was somewhat more positive than in Oesthammar. (2). Policy intention was well accounted for by the explanatory variables used here, close to 64 percent of the variance. The most important explanatory variables were epistemic trust, attitude to the repository and social trust, in that order. The differences among these three variables were small with regard to explanatory power. (3) Variation in policy attitude across time, municipalities and gender was reduced in an analysis of covariance with risk, trust and attitude as controlling factors. Hence, these factors explain a large fraction of the variation in policy attitude as observed here. Yet, the time trend was not fully explained and gender variability remained to

  3. Nuclear Waste Risk Perceptions and Attitudes in Siting a Final Repository for Spent Nuclear Fuel

    International Nuclear Information System (INIS)

    Sjoeberg, Lennart

    2006-01-01

    The paper does the following: Describes the time trends between 2001 and 2005 in terms of policy intention, perceived risk, trust and attitude Analyzes the relationships between policy attitude - the major dependent variable - and the explanatory variables of perceived risk, trust and attitude. Determines whether policy attitude variation across time, municipalities and genders can be accounted for by variation in perceived risk, trust and attitude. Random samples of 2000 persons living in Oesthammar and Oskarshamn were approached with a mailed questionnaire in 2005 (as was done in 2005). After two reminders, 888 had returned filled out questionnaires, yielding a total response rate of 50 percent, taking into account that some persons had moved without giving a forwarding address to the post office, and that some were unable to answer due to illness or old age. (1). There was a substantially more positive attitude to a local SNF repository in 2005 than in 2001, after an intervening period of phase 2 site investigation. This was true for men and women, both municipalities and with all the response measures analyzed. Men were more positive than women, and had developed more strongly in the positive direction than women had. The attitude in Oskarshamn was somewhat more positive than in Oesthammar. (2). Policy intention was well accounted for by the explanatory variables used here, close to 64 percent of the variance. The most important explanatory variables were epistemic trust, attitude to the repository and social trust, in that order. The differences among these three variables were small with regard to explanatory power. (3) Variation in policy attitude across time, municipalities and gender was reduced in an analysis of covariance with risk, trust and attitude as controlling factors. Hence, these factors explain a large fraction of the variation in policy attitude as observed here. Yet, the time trend was not fully explained and gender variability remained to

  4. Radioecological condition assessment and remediation criteria for sites of spent fuel and radioactive waste storage in the russian northwest

    International Nuclear Information System (INIS)

    Shandala, Nataliya; Titov, Alex; Novikova, Natalia; Kiselev, Mikhail; Romanov, Vladimir; Sneve, Malgorzata; Smith, Graham

    2008-01-01

    The Norwegian Radiation Protection Authority and the Federal Medical-Biological Agency of the Russian Federation have a regulatory cooperation programme which is concerned with management of the nuclear legacy in northwest Russia, and, in particular, the remediation of facilities for spent fuel and radioactive waste management at the former Shore Technical Bases at Andreeva Bay and Gremikha Village. New regulatory guidance documents have been developed, necessary because of the special abnormal situation at these sites, now designated as Sites of Temporary Storage, but also because of the transition from military to civilian regulatory supervision and the evolving regulatory system in the Russian Federation. This paper presents the progress made and on-going projects in 2008 which involve development of the radio-ecological basis for identifying radiation supervision area boundaries and a system of recommended dose constraints and derived control levels for protection of workers and the public. Unconditional guarantee of long-term radioecological protection serves as the basis for criteria development. Non-exceedance of these dose constraints and control levels implies compliance with radiological protection objectives related to the residual contamination. Dose reduction below proposed dose constraint values must also be carried out according to the optimization principle. A number of remediation strategies are considered, corresponding to different future land use assumptions, including interim continued use in a nuclear context. The developed criteria relate to conditions of facilities and surrounding areas at the sites of temporary storage after completion of their remediation, and during the interim stages of remediation, depending upon the remediation strategy adopted. (author)

  5. Carbon-14 geochemistry at the Savannah River Site

    International Nuclear Information System (INIS)

    Roberts, Kimberly A.; Kaplan, Daniel I.

    2013-01-01

    Carbon-14 is among the key radionuclides driving risk at the E-Area Low-Level Waste Disposal Facility on the Savannah River Site (SRS). Much of this calculated risk is believed to be the result of having to make conservative assumptions in risk calculations because of the lack of site-specific data. The original geochemical data package (Kaplan 2006) recommended that performance assessments and composite analyses for the SRS assume that 14 C did not sorbed to sediments or cementitious materials, i.e., that C-14 K d value (solid:liquid concentration ratio) be set to 0 mL/g (Kaplan 2006). This recommendation was based primarily on the fact that no site-specific experimental work was available and the assumption that the interaction of anionic 14 C as CO 2 2- ) with similarly charged sediments or cementitious materials would be minimal. When used in reactive transport equations, the 0 mL/g Kd value results in 14 C not interacting with the solid phase and moving quickly through the porous media at the same rate as water. The objective of this study was to quantify and understand how aqueous 14 C, as dissolved carbonate, sorbs to and desorbs from SRS sediments and cementitious materials. Laboratory studies measuring the sorption of 14 C, added as a carbonate, showed unequivocally that 14 C-carbonate K d values were not equal to 0 mL/g for any of the solid phases tested, but they required several months to come to steady state. After six months of contact, the apparent K d values for a clayey sediment was 3,000 mL/g, for a sandy sediment was 10 mL/g, for a 36-year-old concrete was 30,000 mL/g, and for a reducing grout was 40 mL/g. Furthermore, it was demonstrated that (ad)sorption rates were appreciably faster than desorption rates, indicating that a kinetic sorption model, as opposed to the steady-state K d model, may be a more accurate description of the 14 C-carbonate sorption process. A second study demonstrated that the 14 C-carbonate sorbed very strongly onto the

  6. Title V Operating Permit: XTO Energy, Inc. - River Bend Dehydration Site

    Science.gov (United States)

    Initial Title V Operating Permit (Permit Number: V-UO-000026-2011.00) and the Administrative Permit Record for the XTO Energy, Inc., River Bend Dehydration Site, located on the Uintah and Ouray Indian Reservation.

  7. Sensitivity of Coastal Environments and Wildlife to Spilled Oil: Hudson River: STAGING (Staging Site Points)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — This data set contains human-use resource data for staging sites along the Hudson River. Vector points in this data set represent locations of possible staging areas...

  8. Savannah River Site Experiences in In Situ Field Measurements of Radioactive Materials

    International Nuclear Information System (INIS)

    Moore, F.S.

    1999-01-01

    This paper discusses some of the field gamma-ray measurements made at the Savannah River Site, the equipment used for the measurements, and lessons learned during in situ identification and characterization of radioactive materials

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

    Energy Technology Data Exchange (ETDEWEB)

    Blanchard, A.

    1999-03-26

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

  10. Ecological studies related to construction of the Defense Waste Processing Facility on the Savannah River Site

    International Nuclear Information System (INIS)

    Scott, D.E.; Pechmann, J.H.K.; Knox, J.N.; Estes, R.A.; McGregor, J.H.; Bailey, K.

    1988-12-01

    The Savannah River Ecology Laboratory has completed 10 years of ecological studies related to the construction of the Defense Waste Processing Facility (DWPF) on the Savannah River Site. This progress report examines water quality studies on streams peripheral to the DWPF construction site and examines the effectiveness of ''refuge ponds'' in ameliorating the effects of construction on local amphibians. Individual papers on these topics are indexed separately. 93 refs., 15 figs., 15 tabs

  11. Ecological studies related to construction of the Defense Waste Processing Facility on the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Scott, D.E.; Pechmann, J.H.K.; Knox, J.N.; Estes, R.A.; McGregor, J.H.; Bailey, K. (ed.)

    1988-12-01

    The Savannah River Ecology Laboratory has completed 10 years of ecological studies related to the construction of the Defense Waste Processing Facility (DWPF) on the Savannah River Site. This progress report examines water quality studies on streams peripheral to the DWPF construction site and examines the effectiveness of refuge ponds'' in ameliorating the effects of construction on local amphibians. Individual papers on these topics are indexed separately. 93 refs., 15 figs., 15 tabs. (MHB)

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

    International Nuclear Information System (INIS)

    Blanchard, A.

    1999-01-01

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

  13. SAVANNAH RIVER SITE R REACTOR DISASSEMBLY BASIN IN SITU DECOMMISSIONING

    Energy Technology Data Exchange (ETDEWEB)

    Langton, C.; Blankenship, J.; Griffin, W.; Serrato, M.

    2009-12-03

    The US DOE concept for facility in-situ decommissioning (ISD) is to physically stabilize and isolate in tact, structurally sound facilities that are no longer needed for their original purpose of, i.e., generating (reactor facilities), processing(isotope separation facilities) or storing radioactive materials. The 105-R Disassembly Basin is the first SRS reactor facility to undergo the in-situ decommissioning (ISD) process. This ISD process complies with the105-R Disassembly Basin project strategy as outlined in the Engineering Evaluation/Cost Analysis for the Grouting of the R-Reactor Disassembly Basin at the Savannah River Site and includes: (1) Managing residual water by solidification in-place or evaporation at another facility; (2) Filling the below grade portion of the basin with cementitious materials to physically stabilize the basin and prevent collapse of the final cap - Sludge and debris in the bottom few feet of the basin will be encapsulated between the basin floor and overlying fill material to isolate if from the environment; (3) Demolishing the above grade portion of the structure and relocating the resulting debris to another location or disposing of the debris in-place; and (4) Capping the basin area with a concrete slab which is part of an engineered cap to prevent inadvertent intrusion. The estimated total grout volume to fill the 105-R Reactor Disassembly Basin is 24,424 cubic meters or 31,945 cubic yards. Portland cement-based structural fill materials were design and tested for the reactor ISD project and a placement strategy for stabilizing the basin was developed. Based on structural engineering analyses and work flow considerations, the recommended maximum lift height is 5 feet with 24 hours between lifts. Pertinent data and information related to the SRS 105-R-Reactor Disassembly Basin in-situ decommissioning include: regulatory documentation, residual water management, area preparation activities, technology needs, fill material designs

  14. Tritium in the burial ground of the Savannah River Site

    International Nuclear Information System (INIS)

    Hyder, M.L.

    1993-06-01

    This memorandum reviews the available information on tritium-contaminated material discarded to burial grounds. Tritium was the first isotope studied because it represents the most immediate concern with regard to release to the environment. Substantial amounts of tritium are known to be present in the ground water underneath the area, and outcropping of this ground water in springs and seeps has been observed. The response to this release of tritium from the burial ground is a current concern. The amount of tritium emplaced in the burial ground facilities is very uncertain, however, some general conclusions can be made. In particular, most of the tritium buried is associated with spent equipment and other waste, rather than spent melts. Correspondingly, most of the tritium in the ground water seems to be associated with burials of this type, rather than the spent melts. Maps are presented showing the location of burials of tritiated waste by type, and the location of the largest individual burials according to COBRA records

  15. Seismic stability of the survey areas of potential sites for the deep geological repository of the spent nuclear fuel

    Science.gov (United States)

    Kaláb, Zdeněk; Šílený, Jan; Lednická, Markéta

    2017-07-01

    This paper deals with the seismic stability of the survey areas of potential sites for the deep geological repository of the spent nuclear fuel in the Czech Republic. The basic source of data for historical earthquakes up to 1990 was the seismic website [1-]. The most intense earthquake described occurred on September 15, 1590 in the Niederroesterreich region (Austria) in the historical period; its reported intensity is Io = 8-9. The source of the contemporary seismic data for the period since 1991 to the end of 2014 was the website [11]. It may be stated based on the databases and literature review that in the period from 1900, no earthquake exceeding magnitude 5.1 originated in the territory of the Czech Republic. In order to evaluate seismicity and to assess the impact of seismic effects at depths of hypothetical deep geological repository for the next time period, the neo-deterministic method was selected as an extension of the probabilistic method. Each one out of the seven survey areas were assessed by the neo-deterministic evaluation of the seismic wave-field excited by selected individual events and determining the maximum loading. Results of seismological databases studies and neo-deterministic analysis of Čihadlo locality are presented.

  16. Heat transfer analysis of consolidated dry storage system for CANDU spent fuel considering environmental conditions of Wolsong site

    International Nuclear Information System (INIS)

    Lee, K. H.; Yoon, J. H.; Choi, B. I.; Lee, H. Y.

    2004-01-01

    The purpose of the present paper is to perform heat transfer analysis of the MACSTOR/KN-400 dry storage system for CANDU spent fuel in order to predict maximum concrete temperatures and temperature gradients. This module has twice the capacity of the existing MACSTOR-200, which is in operation at Gentilly-2. In the thermal design of the MACSTOR/KN-400, Thermal Insulation Panels(TIP) were introduced to reduce concrete temperatures and temperature gradients in the module caused by the high fuel heat loads. Environmental factors such as solar heat, daily temperature variations and ambient temperatures in summer and winter at Wolsong site and the assumed presence of hot baskets were taken into consideration in the simulations. Two cases were performed for the MACSTOR/KN-400: Off-normal cases in summer and winter. The maximum local concrete temperatures were predicted to be 63 .deg. C for the off-normal case. The temperature gradients in the concrete walls and roof are predicted to be 28C and 25C for off-normal operation in summer, incorporating a 3C uncertainty. In conclusion, this paper shows that the maximum temperature for the module is expected to meet the temperature limitations of ACI 349

  17. Monitoring and Evaluation of Environmental Flow Prescriptions for Five Demonstration Sites of the Sustainable Rivers Project

    Science.gov (United States)

    Konrad, Christopher P.

    2010-01-01

    The Nature Conservancy has been working with U.S. Army Corps of Engineers (Corps) through the Sustainable Rivers Project (SRP) to modify operations of dams to achieve ecological objectives in addition to meeting the authorized purposes of the dams. Modifications to dam operations are specified in terms of environmental flow prescriptions that quantify the magnitude, duration, frequency, and seasonal timing of releases to achieve specific ecological outcomes. Outcomes of environmental flow prescriptions implemented from 2002 to 2008 have been monitored and evaluated at demonstration sites in five rivers: Green River, Kentucky; Savannah River, Georgia/South Carolina; Bill Williams River, Arizona; Big Cypress Creek, Texas; and Middle Fork Willamette River, Oregon. Monitoring and evaluation have been accomplished through collaborative partnerships of federal and state agencies, universities, and nongovernmental organizations.

  18. Analysis on the use of engineered barriers for geologic isolation of spent fuel in a reference salt site repository

    International Nuclear Information System (INIS)

    Cloninger, M.O.; Cole, C.R.; Washburn, J.F.

    1980-12-01

    A perspective on the potential durability and effectiveness requirements for the waste form, container and other engineered barriers for geologic disposal of spent nuclear fuel has been developed. This perspective is based on calculated potential doses to individuals who may be exposed to radioactivity released from a repository via a groundwater transport pathway. These potential dose commitments were calculated with an integrated geosphere transport and bioshpere transport model. A sensitivity analysis was accomplished by varying four important system parameters, namely the waste radionuclide release rate from the repository, the delay prior to groundwater contact with the waste (leach initiation), aquifer flow velocity and flow path length. The nuclide retarding capacity of the geologic media, a major determinant of the isolation effectiveness, was not varied as a parameter but was held constant for a particular reference site. This analysis is limited to looking only at engineered barriers whose net effect is either to delay groundwater contact with the waste form or to limit the rate of release of radionuclides into the groundwater once contact has occurred. The analysis considers only leach incident scenarios, including a water well intrusion into the groundwater near a repository, but does not consider other human intrusion events or catastrophic events. The analysis has so far been applied to a reference salt site repository system and conclusions are presented.Basically, in nearly all cases, the regional geology is the most effective barrier to release of radionuclides to the biosphere; however, for long-lived isotopes of carbon, technetium and iodine, which were poorly sorbed on the geologic media, the geology is not very effective once a leach incident is initiated

  19. Hydrogeological investigations of river bed clogging at a river bank filtration site along the River Warta, Poland

    Directory of Open Access Journals (Sweden)

    Przybyłek Jan

    2017-12-01

    Full Text Available River bank filtration (RBF is a system that enriches groundwater resources by induced infiltration of river water to an aquifer. Problematic during operation of RBF systems is the deterioration of infiltration effectiveness caused by river bed clogging. This situation was observed in the Krajkowo well field which supplies fresh water to the city of Poznań (Poland during and after the long hydrological drought between the years 1989 and 1992. The present note discusses results of specific hydrogeological research which included drilling of a net of boreholes to a depth of 10 m below river bottom (for sediment sampling as well as for hydrogeological measurements, analyses of grain size distribution and relative density studies. The results obtained have allowed the recognition of the origin of the clogging processes, as well as the documentation of the clogged parts of the river bottom designated for unclogging activities.

  20. Environmental Assessment for the construction and operation of the Health Physics Site Support Facility on the Savannah River Site

    International Nuclear Information System (INIS)

    1995-07-01

    DOE has prepared an environmental assessment for the proposed construction and operation of the Health Physics Site Support Facility on the Savannah River Site. This (new) facility would meet requirements of the site radiological protection program and would ensure site compliance with regulations. It was determined that the proposed action is not a major Federal action significantly affecting the quality of the environment within the meaning of NEPA. Therefore, a finding of no significant impact is made, and no environmental impact statement is needed

  1. Presentation of safety after closure of the repository for spent nuclear fuel. Main report of the project SR-Site. Part III

    International Nuclear Information System (INIS)

    2011-01-01

    The purpose of the safety assessment SR-Site is to investigate whether a safe repository for spent nuclear fuel by KBS-3 type can be constructed at Forsmark in Oesthammar in Sweden. The location of the Forsmark has been selected based on results of several surveys from surface conditions at depth in Forsmark and in Laxemar in Oskarshamn. The choice of location is not justified in SR-Site Report, but in other attachments to SKB's permit applications. SR-Site Report is an important part of SKB's permit applications to construct and operate a repository for spent nuclear fuel at Forsmark in Oesthammar. The purpose of the report in the applications is to show that a repository at Forsmark is safe after closure

  2. Presentation of safety after closure of the repository for spent nuclear fuel. Main report of the project SR-Site. Part I

    International Nuclear Information System (INIS)

    2011-01-01

    The purpose of the safety assessment SR-Site is to investigate whether a safe repository for spent nuclear fuel by KBS-3 type can be constructed at Forsmark in Oesthammar in Sweden. The location of the Forsmark has been selected based on results of several surveys from surface conditions at depth in Forsmark and in Laxemar in Oskarshamn. The choice of location is not justified in SR-Site Report, but in other attachments to SKB's permit applications. SR-Site Report is an important part of SKB's permit applications to construct and operate a repository for spent nuclear fuel at Forsmark in Oesthammar. The purpose of the report in the applications is to show that a repository at Forsmark is safe after closure

  3. Characterization and risk assessment of spent pot lining at Valco’s landfill site at Tema, Ghana

    International Nuclear Information System (INIS)

    Arthur, E.

    2015-01-01

    Spent Pot Lining (SPL) is a waste material generated in the Primary Aluminium Smelting Industry. Globally, aluminium smelters produce in excess of about 500,000 tons of SPL annually, and safely disposing of this unavoidable but hazardous waste product is a challenge faced by the Aluminium Smelting Industry. In many cases, SPL is disposed of in a landfill. SPL contains toxic fluoride and cyanide compounds that are leachable in water. SPL is corrosive (exhibiting high pH due to alkali metals and oxides). In addition, SPL is reactive with water (producing inflammable, toxic and explosive gases). The toxic, corrosive and reactive nature of SPL means that utmost care must be taken in its handling, transportation and storage. SPL is becoming one of the aluminium industry’s major environmental concerns. The concerns stems from the environmental impact of dissolved fluorides and cyanide from SPL landfill leachate. SPL is known to have high energy value ranging from 4444 cal/g to about 5000 cal/g or more as determined in this study. It is therefore being used as a direct fuel in foundries. The high fluoride content in SPL is of immense benefit to the Cement Industry (speeds up the clinkering reaction thereby lowering operating temperatures). In view of the economic importance of SPL, there is intense mining of SPL at VALCO’s SPL landfill site at Tema. Considering the toxic nature of SPL, mining of SPL raises health concerns. In this Study, a conceptual model was developed to help understand the interrelationship between CN - and F - release mechanisms, exposure medium and pathways at the landfill site. In addition, human health risk assessment was conducted to assess possible human health risks posed to scavengers mining the waste. Also, characteristics such as the calorific value and sulphur content in the SPL which are important parameters to consider if the waste is to be used as alternate fuels were determined. Hazard Quotients of 0.73 and 0.72 for F - in soils

  4. Summary of the Phase II, Title I engineering assessment of inactive uranium mill tailings, Green River Site, Green River, Utah

    International Nuclear Information System (INIS)

    1977-12-01

    An engineering assessment was performed of the problems resulting from the existence of radioactive uranium mill tailings at the Green River site, Utah. The services include the preparation of topographic maps, the performance of core drillings and radiometric measurements sufficient to determine areas and volumes of tailings and other radium-contaminated materials, the evaluation of resulting radiation exposures of individuals and nearby populations, the investigation of site hydrology and meteorology and the evaluation and costing of alternative corrective actions. Radon gas release from the 123 thousand tons of tailings at the Green River site constitutes the most significant environmental impact, although windblown tailings and external gamma radiation are also factors. The three alternative actions presented are dike stabilization, fencing, on- and off-site decontamination and maintenance; improvements in the stabilization cover and diking plus cleanup of the site and Browns Wash, and realignment of Browns Wash; and addition of stabilization cover to a total of 2 ft, realignment of Browns Wash and placement of additional riprap, on-site cleanup and drainage improvements. All options include remedial action at off-site structures. Cost estimates for the three options range from $700,000 to $926,000

  5. Phase II, Title I engineering assessment of inactive uranium mill tailings, Green River Site, Green River, Utah

    International Nuclear Information System (INIS)

    1977-12-01

    An engineering assessment was performed of the problems resulting from the existence of radioactive uranium mill tailings at the Green River site, Utah. Services included the preparation of topographic maps, the performance of core drillings and radiometric measurements sufficient to determine areas and volumes of tailings and other radium-contaminated materials, the evaluation of resulting radiation exposures of individuals and nearby populations , the investigation of site hydrology and meteorology and the evaluation and costing of alternative corrective actions. Radon gas release from the 123 thousand tons of tailings at the Green River site constitutes the most significant environmental impact, although windblown tailings and external gamma radiation are also factors. The three alternative actions presented are dike stabilization, fencing, on- and off-site decontamination and maintenance (Option I); improvements in the stabilization cover and diking plus cleanup of the site and Browns Wash, and realignment of Browns Wash (Option II); and addition of stabilization cover to a total of 2 ft, realignment of Browns Wash and placement of additional riprap, on-site cleanup and drainage improvements (Option III). All options include remedial action at off-site structures. Cost estimates for the three options range from $700,000 to $926,000

  6. SITE SPECIFIC REFERENCE PERSON PARAMETERS AND DERIVED CONCENTRATION STANDARDS FOR THE SAVANNAH RIVER SITE

    Energy Technology Data Exchange (ETDEWEB)

    Jannik, T.

    2013-03-14

    The purpose of this report is twofold. The first is to develop a set of behavioral parameters for a reference person specific for the Savannah River Site (SRS) such that the parameters can be used to determine dose to members of the public in compliance with Department of Energy (DOE) Order 458.1 “Radiation Protection of the Public and the Environment.” A reference person is a hypothetical, gender and age aggregation of human physical and physiological characteristics arrived at by international consensus for the purpose of standardizing radiation dose calculations. DOE O 458.1 states that compliance with the annual dose limit of 100 mrem (1 mSv) to a member of the public may be demonstrated by calculating the dose to the maximally exposed individual (MEI) or to a representative person. Historically, for dose compliance, SRS has used the MEI concept, which uses adult dose coefficients and adult male usage parameters. Beginning with the 2012 annual site environmental report, SRS will be using the representative person concept for dose compliance. The dose to a representative person will be based on 1) the SRS-specific reference person usage parameters at the 95th percentile of appropriate national or regional data, which are documented in this report, 2) the reference person (gender and age averaged) ingestion and inhalation dose coefficients provided in DOE Derived Concentration Technical Standard (DOE-STD-1196-2011), and 3) the external dose coefficients provided in the DC_PAK3 toolbox. The second purpose of this report is to develop SRS-specific derived concentration standards (DCSs) for all applicable food ingestion pathways, ground shine, and water submersion. The DCS is the concentration of a particular radionuclide in water, in air, or on the ground that results in a member of the public receiving 100 mrem (1 mSv) effective dose following continuous exposure for one year. In DOE-STD-1196-2011, DCSs were developed for the ingestion of water, inhalation of

  7. Recovery of thermophilic Campylobacter by three sampling methods from classified river sites in Northeast Georgia, USA

    Science.gov (United States)

    It is not clear how best to sample streams for the detection of Campylobacter which may be introduced from agricultural or community land use. Fifteen sites in the watershed of the South Fork of the Broad River (SFBR) in Northeastern Georgia, USA, were sampled in three seasons. Seven sites were cl...

  8. Test program for closure activities at a mixed waste disposal site at the Savannah River Plant

    International Nuclear Information System (INIS)

    Cook, J.R.; Harley, J.P. Jr.

    1988-01-01

    A 58-acre site at the Savannah River Plant which was used for disposal of low-level radioactive waste and quantities of the hazardous materials lead, cadmium, scintillation fluid, and oil will be the first large waste site at the Savannah River Plant to be permanently closed. The actions leading to closure of the facility will include surface stabilization and capping of the site. Test programs have been conducted to evaluate the effectiveness of dynamic compaction as a stabilization technique and the feasibility of using locally derived clay as a capping material

  9. Critical Radionuclide and Pathway Analysis for the Savannah River Site, 2016 Update

    Energy Technology Data Exchange (ETDEWEB)

    Jannik, Tim [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hartman, Larry [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2016-09-08

    During the operational history of Savannah River Site, many different radionuclides have been released from site facilities. However, as shown in this analysis, only a relatively small number of the released radionuclides have been significant contributors to doses to the offsite public. This report is an update to the 2011 analysis, Critical Radionuclide and Pathway Analysis for the Savannah River Site. SRS-based Performance Assessments for E-Area, Saltstone, F-Tank Farm, H-Tank Farm, and a Comprehensive SRS Composite Analysis have been completed. The critical radionuclides and pathways identified in those extensive reports are also detailed and included in this analysis.

  10. US EPA record of decision review for landfills: Sanitary landfill (740-G), Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    1993-06-01

    This report presents the results of a review of the US Environmental Protection Agency (EPA) Record of Decision System (RODS) database search conducted to identify Superfund landfill sites where a Record of Decision (ROD) has been prepared by EPA, the States or the US Army Corps of Engineers describing the selected remedy at the site. ROD abstracts from the database were reviewed to identify site information including site type, contaminants of concern, components of the selected remedy, and cleanup goals. Only RODs from landfill sites were evaluated so that the results of the analysis can be used to support the remedy selection process for the Sanitary Landfill at the Savannah River Site (SRS).

  11. US EPA record of decision review for landfills: Sanitary landfill (740-G), Savannah River Site

    International Nuclear Information System (INIS)

    1993-06-01

    This report presents the results of a review of the US Environmental Protection Agency (EPA) Record of Decision System (RODS) database search conducted to identify Superfund landfill sites where a Record of Decision (ROD) has been prepared by EPA, the States or the US Army Corps of Engineers describing the selected remedy at the site. ROD abstracts from the database were reviewed to identify site information including site type, contaminants of concern, components of the selected remedy, and cleanup goals. Only RODs from landfill sites were evaluated so that the results of the analysis can be used to support the remedy selection process for the Sanitary Landfill at the Savannah River Site (SRS)

  12. A summary of INSITE activities in tracking SKB's spent fuel repository site investigations from 2002-2009 and of advice provided to the regulatory authorities on the status of site understanding at the end of the surface-based investigations

    International Nuclear Information System (INIS)

    Chapman, Neil; Bath, Adrian; Geier, Joel; Ove Stephansson; Tiren, Sven; Tsang, Chin-Fu

    2010-11-01

    SSM and its predecessor SKI employed a team of earth scientists who followed and reviewed SKB's investigations of the potential spent nuclear fuel repository sites at Forsmark and Laxemar. This group was named INSITE (INdependent Site Investigation Tracking and Evaluation) and began its work in 2002 and completed its task with the review of the final versions SKB's site descriptive models, SDM-Site, in 2009. This report is a summary of INSITE's work over the eight-and-a-half year period of the site investigations and the lead-in and the wind-down to the work. It is intended to provide an outline and a record of how INSITE has worked and how its advice was generated and provided to SKI and, latterly, to SSM. Together with all the other documentation generated by INSITE, this report is intended to support the regulatory review of SKB's licence application for a spent nuclear fuel repository

  13. Savannah River Site integrated stabilization management plan. Revision 3

    International Nuclear Information System (INIS)

    Geddes, R.L.; Barone, A.; Shook, H.E.; Varner, C.E.; Rollins, R.

    1996-01-01

    On May 26, 1994, the Defense Nuclear Facilities Safety Board (DNFSB) issued Recommendation 94-1. The concern is that the halt in production of materials to be used in nuclear weapons froze the manufacturing pipeline in a state that, for safety reasons, should not be allowed to persist unremediated. This recommendation had eight specific sub-recommendations that dealt with the potential problems. Specifically, the Board expressed concern about certain liquids and solids containing fissile materials and other radioactive substances located in spent fuel storage pools, reactor basins, reprocessing canyons; and various other facilities once used for processing and weapons manufacture. The WSRC and DOE-SR acknowledges and shares the Board's concerns and has developed this Integrated Stabilization Management Plan (ISMP) to aggressively address these urgent problems in a systems engineering approach

  14. Westinghouse Savannah River Site Supplier Environmental Restoration and Waste Management Information Exchange Forum

    International Nuclear Information System (INIS)

    Sturm, H.F. Jr.; Hottel, R.E.; Christoper, N.

    1994-01-01

    The Savannah River Site conducted its first Supplier Information Exchange in September 1993. The intent of the conference was to inform potential suppliers of the Savannah River Sites mission and research and development program objectives in the areas of environmental restoration and waste management, and to solicit proposals for innovative research in those areas. Major areas addressed were Solid Waste, Environmental Restoration, Environmental Monitoring, Transition/Decontamination and Decommissioning, and the Savannah River Technology Center. A total of 1062 proposals were received addressing the 89 abstracts presented. This paper will describe the forum the process for solicitation, the process for proposal review and selection, and review the overall results and benefits to Savannah River

  15. Instream biological assessment of NPDES point source discharges at the Savannah River Site, 1997-1998

    International Nuclear Information System (INIS)

    Specht, W.L.

    2000-01-01

    The Savannah River Site currently has 33 permitted NPDES outfalls that have been permitted by the South Carolina Department of Health an Environmental Control to discharge to SRS streams and the Savannah River. In order to determine the cumulative impacts of these discharges to the receiving streams, a study plan was developed to perform in-stream assessments of the fish assemblages, macroinvertebrate assemblages, and habitats of the receiving streams

  16. Instream biological assessment of NPDES point source discharges at the Savannah River Site, 1997-1998

    Energy Technology Data Exchange (ETDEWEB)

    Specht, W.L.

    2000-02-28

    The Savannah River Site currently has 33 permitted NPDES outfalls that have been permitted by the South Carolina Department of Health an Environmental Control to discharge to SRS streams and the Savannah River. In order to determine the cumulative impacts of these discharges to the receiving streams, a study plan was developed to perform in-stream assessments of the fish assemblages, macroinvertebrate assemblages, and habitats of the receiving streams.

  17. Environmental Assessment for the off-site commercial cleaning of lead and asbestos contaminated laundry from the Savannah River Site

    International Nuclear Information System (INIS)

    1995-12-01

    This Environmental Assessment (EA) has been prepared by the Department of Energy (DOE) to assess the potential environmental impacts of off-site commercial cleaning of lead and asbestos contaminated laundry generated at the Savannah River Site (SRS), located near Aiken, South Carolina. The proposed action constitutes an addition to the already-implemented action of sending controlled and routine SRS laundry to an off-site commercial facility for cleaning. This already-implemented action was evaluated in a previous EA (i.e., DOE/EA-0990; DOE, 1994) prepared under the National Environmental Policy Act of 1969 (NEPA)

  18. Mixed Waste Management Facility closure at the Savannah River Site

    International Nuclear Information System (INIS)

    Bittner, M.F.

    1991-08-01

    The Mixed Waste Management Facility of the Savannah River Plant received hazardous and solid low level radioactive wastes from 1972 until 1986. Because this facility did not have a permit to receive hazardous wastes, a Resource Conservation and Recovery Act closure was performed between 1987 and 1990. This closure consisted of dynamic compaction of the waste trenches and placement of a 3-foot clay cap, a 2-foot soil cover, and a vegetative layer. Operations of the waste disposal facility, tests performed to complete the closure design, and the construction of the closure cap are discussed herein

  19. Remedial Investigation of Hanford Site Releases to the Columbia River - 13603

    Energy Technology Data Exchange (ETDEWEB)

    Lerch, J.A.; Hulstrom, L.C. [Washington Closure Hanford, LLC, Richland, Washington 99354 (United States); Sands, J.P. [U.S Department of Energy, Richland Operations Office, Richland, Washington 99352 (United States)

    2013-07-01

    In south-central Washington State, the Columbia River flows through the U.S. Department of Energy Hanford Site. A primary objective of the Hanford Site cleanup mission is protection of the Columbia River, through remediation of contaminated soil and groundwater that resulted from its weapons production mission. Within the Columbia River system, surface water, sediment, and biota samples related to potential Hanford Site hazardous substance releases have been collected since the start of Hanford operations. The impacts from release of Hanford Site radioactive substances to the Columbia River in areas upstream, within, and downstream of the Hanford Site boundary have been previously investigated as mandated by the U.S. Department of Energy requirements under the Atomic Energy Act. The Remedial Investigation Work Plan for Hanford Site Releases to the Columbia River [1] was issued in 2008 to initiate assessment of the impacts under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 [2]. The work plan established a phased approach to characterize contaminants, assess current risks, and determine whether or not there is a need for any cleanup actions. Field investigation activities over a 120-mile stretch of the Columbia River began in October 2008 and were completed in 2010. Sampled media included surface water, pore water, surface and core sediment, island soil, and fish (carp, walleye, whitefish, sucker, small-mouth bass, and sturgeon). Information and sample results from the field investigation were used to characterize current conditions within the Columbia River and assess whether current conditions posed a risk to ecological or human receptors that would merit additional study or response actions under CERCLA. The human health and ecological risk assessments are documented in reports that were published in 2012 [3, 4]. Conclusions from the risk assessment reports are being summarized and integrated with remedial investigation

  20. Safety assessment document for spent fuel handling, packaging, and storage demonstrations at the E-MAD facility on the Nevada Test Site

    International Nuclear Information System (INIS)

    1985-04-01

    The objectives for spent fuel handling and packaging demonstration are to develop the capability to satisfactorily encapsulate typical commercial nuclear reactor spent fuel assemblies and to establish the suitability of interim dry surface and near surface storage concepts. To accomplish these objectives, spent fuel assemblies from a pressurized water reactor have been received, encapsulated in steel canisters, and emplaced in on-site storage facilities and subjected to other tests. As an essential element of these demonstrations, a thorough safety assessment of the demonstration activities conducted at the E-MAD facility has been completed. This document describes the site location and characteristics, the existing E-MAD facility, and the facility modifications and equipment additions made specifically for the demonstrations. The document also summarizes the Quality Assurance Program utilized, and specifies the principal design criteria applicable to the facility modifications, equipment additions, and process operations. Evaluations have been made of the radiological impacts of normal operations, abnormal operations, and postulated accidents. Analyses have been performed to determine the affects on nuclear criticality safety of postulated accidents and credible natural phenomena. The consequences of postulated accidents resulting in fission product gas release have also been estimated. This document identifies the engineered safety features, procedures, and site characteristics that (1) prevent the occurrence of potential accidents or (2) assure that the consequences of postulated accidents are either insignificant or adequately mitigated

  1. HANFORD SITE RIVER PROTECTION PROJECT (RPP) TANK FARM CLOSURE

    International Nuclear Information System (INIS)

    JARAYSI, M.N.; SMITH, Z.; QUINTERO, R.; BURANDT, M.B.; HEWITT, W.

    2006-01-01

    The U. S. Department of Energy, Office of River Protection and the CH2M HILL Hanford Group, Inc. are responsible for the operations, cleanup, and closure activities at the Hanford Tank Farms. There are 177 tanks overall in the tank farms, 149 single-shell tanks (see Figure 1), and 28 double-shell tanks (see Figure 2). The single-shell tanks were constructed 40 to 60 years ago and all have exceeded their design life. The single-shell tanks do not meet Resource Conservation and Recovery Act of 1976 [1] requirements. Accordingly, radioactive waste is being retrieved from the single-shell tanks and transferred to double-shell tanks for storage prior to treatment through vitrification and disposal. Following retrieval of as much waste as is technically possible from the single-shell tanks, the Office of River Protection plans to close the single-shell tanks in accordance with the Hanford Federal Facility Agreement and Consent Order [2] and the Atomic Energy Act of 1954 [3] requirements. The double-shell tanks will remain in operation through much of the cleanup mission until sufficient waste has been treated such that the Office of River Protection can commence closing the double-shell tanks. At the current time, however, the focus is on retrieving waste and closing the single-shell tanks. The single-shell tanks are being managed and will be closed in accordance with the pertinent requirements in: Resource Conservation and Recovery Act of 1976 and its Washington State-authorized Dangerous Waste Regulations [4], US DOE Order 435.1 Radioactive Waste Management [5], the National Environmental Policy Act of 1969 [6], and the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 [7]. The Hanford Federal Facility Agreement and Consent Order, which is commonly referred to as the Tri-Party Agreement or TPA, was originally signed by Department of Energy, the State of Washington, and the U. S. Environmental Protection Agency in 1989. Meanwhile, the

  2. Land cover mapping and GIS processing for the Savannah River Site Database

    International Nuclear Information System (INIS)

    Christel, L.M.; Guber, A.L.

    1994-07-01

    The Savannah River Site (SRS) is owned by the U.S. Department of Energy and operated by Westinghouse Savannah River Company. Located in Barnwell, Aiken, and Allendale counties in South Carolina, SRS covers an area of approximately 77,700 hectares. Land cover information for SRS was interpreted from color and color infrared aerial photography acquired between 1980 and 1989. The data were then used as the source of the land cover data layer for the SRS sitewide Geographic Information System database. This database provides SRS managers with recent land use information and has been successfully used to support cost-effective site characterization and reclamation

  3. Audit of the Uranium Solidification Facility at the Savannah River Site

    International Nuclear Information System (INIS)

    1994-01-01

    In the late 1980s, DOE decided to construct a Uranium Solidification Facility at the Savannah River Site to process liquid uranyl nitrate into powder. Since the need for weapons materials has been reduced, an audit was conducted to assess the need for this facility. The audit disclosed that DOE continued to construct the facility, because DOE's procedures did not ensure that projects of this type were periodically reassessed when significant program changes occurred. The audit identified more economical alternatives for processing existing quantities of liquid uranyl nitrate at the Savannah River Site

  4. Water Quality Sampling Locations Along the Shoreline of the Columbia River, Hanford Site, Washington

    Energy Technology Data Exchange (ETDEWEB)

    Peterson, Robert E.; Patton, Gregory W.

    2009-12-14

    As environmental monitoring evolved on the Hanford Site, several different conventions were used to name or describe location information for various sampling sites along the Hanford Reach of the Columbia River. These methods range from handwritten descriptions in field notebooks to the use of modern electronic surveying equipment, such as Global Positioning System receivers. These diverse methods resulted in inconsistent archiving of analytical results in various electronic databases and published reports because of multiple names being used for the same site and inaccurate position data. This document provides listings of sampling sites that are associated with groundwater and river water sampling. The report identifies names and locations for sites associated with sampling: (a) near-river groundwater using aquifer sampling tubes; (b) riverbank springs and springs areas; (c) pore water collected from riverbed sediment; and (d) Columbia River water. Included in the listings are historical names used for a particular site and the best available geographic coordinates for the site, as of 2009. In an effort to create more consistency in the descriptive names used for water quality sampling sites, a naming convention is proposed in this document. The convention assumes that a unique identifier is assigned to each site that is monitored and that this identifier serves electronic database management requirements. The descriptive name is assigned for the convenience of the subsequent data user. As the historical database is used more intensively, this document may be revised as a consequence of discovering potential errors and also because of a need to gain consensus on the proposed naming convention for some water quality monitoring sites.

  5. WHite paper on the proposed design, development, and implementation of a monitored retrievable storage module and the siting criteria for spent nuclear fuel

    International Nuclear Information System (INIS)

    Villarreal, B.; Knobeloch, D.

    1996-01-01

    Congress enacted the Nuclear Waste Policy (NWP) Act in 1982 as comprehensive legislation for the DOE to locate, build, and operate repositories to permanently dispose of spent nuclear fuel and other high-level wastes. In 1987, Congress amended the NWP Act and authorized the DOE to site, construct, and operate one Monitored Retrievable Storage (MRS) facility. The MRS facility was planned as a means to enhance the flexibility and reliability of the overall waste management system. This white paper presents a broad prospectus of the scientific and regulatory capabilities at Los Alamos National Laboratory and outlines the methodology to design and implement an MRS test module. This proposed module will incorporate the flexibility to store all types of spent nuclear fuel above or below ground level and will be fully monitored for the residence time of the spent fuel in the MRS module. The purpose of this test module is to define the parameters necessary to build a simple and economical MRS system. Demonstration of the proposed MRS test module will be important because it will form the basis for an integrated MRS site model

  6. Environmental assessment for the off-site volume reduction of low-level radioactive waste from the Savannah River Site

    International Nuclear Information System (INIS)

    1995-07-01

    The Department of Energy (DOE) has prepared an environmental assessment (EA) (DOE/EA-1061) for the proposed off-site volume reduction of low-level radioactive wastes (LLW) generated at the Savannah River Site (SRS), near Aiken, South Carolina. 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 human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969. Therefore, the preparation of an environmental impact statement (EIS) is not required, and DOE is issuing this Finding of No Significant Impact (FONSI)

  7. Presentation of safety after closure of the repository for spent nuclear fuel. Main report of the project SR-Site. Part I; Redovisning av saekerhet efter foerslutning av slutfoervaret foer anvaent kaernbraensle. Huvudrapport fraan projekt SR-Site. Del I

    Energy Technology Data Exchange (ETDEWEB)

    2011-07-01

    The purpose of the safety assessment SR-Site is to investigate whether a safe repository for spent nuclear fuel by KBS-3 type can be constructed at Forsmark in Oesthammar in Sweden. The location of the Forsmark has been selected based on results of several surveys from surface conditions at depth in Forsmark and in Laxemar in Oskarshamn. The choice of location is not justified in SR-Site Report, but in other attachments to SKB's permit applications. SR-Site Report is an important part of SKB's permit applications to construct and operate a repository for spent nuclear fuel at Forsmark in Oesthammar. The purpose of the report in the applications is to show that a repository at Forsmark is safe after closure

  8. Presentation of safety after closure of the repository for spent nuclear fuel. Main report of the project SR-Site. Part II; Redovisning av saekerhet efter foerslutning av slutfoervaret foer anvaent kaernbraensle. Huvudrapport fraan projekt SR-Site. Del II

    Energy Technology Data Exchange (ETDEWEB)

    2011-07-01

    The purpose of the safety assessment SR-Site is to investigate whether a safe repository for spent nuclear fuel by KBS-3 type can be constructed at Forsmark in Oesthammar in Sweden. The location of the Forsmark has been selected based on results of several surveys from surface conditions at depth in Forsmark and in Laxemar in Oskarshamn. The choice of location is not justified in SR-Site Report, but in other attachments to SKB's permit applications. SR-Site Report is an important part of SKB's permit applications to construct and operate a repository for spent nuclear fuel at Forsmark in Oesthammar. The purpose of the report in the applications is to show that a repository at Forsmark is safe after closure

  9. Presentation of safety after closure of the repository for spent nuclear fuel. Main report of the project SR-Site. Part III; Redovisning av saekerhet efter foerslutning av slutfoervaret foer anvaent kaernbraensle. Huvudrapport fraan projekt SR-Site. Del III

    Energy Technology Data Exchange (ETDEWEB)

    2011-07-01

    The purpose of the safety assessment SR-Site is to investigate whether a safe repository for spent nuclear fuel by KBS-3 type can be constructed at Forsmark in Oesthammar in Sweden. The location of the Forsmark has been selected based on results of several surveys from surface conditions at depth in Forsmark and in Laxemar in Oskarshamn. The choice of location is not justified in SR-Site Report, but in other attachments to SKB's permit applications. SR-Site Report is an important part of SKB's permit applications to construct and operate a repository for spent nuclear fuel at Forsmark in Oesthammar. The purpose of the report in the applications is to show that a repository at Forsmark is safe after closure

  10. SAVANNAH RIVER SITE ENVIRONMENTAL REPORT SUMMARY FOR 2012

    Energy Technology Data Exchange (ETDEWEB)

    Griffith, M.; Meyer, A.

    2013-09-12

    This report's purpose is to: Present summary environmental data that characterize Site environmental management performance, Describe compliance status with respect to environmental standards and requirements, and Highlight significant programs and efforts. Environmental monitoring is conducted extensively with a 2,000-square-mile network extending 25 miles from SRS, with some monitoring performed as far as 100 miles from the Site. The area includes neighboring cities, towns, and counties in Georgia (GA) and South Carolina (SC). Thousands of samples of air, rainwater, surface water, drinking water, groundwater, food products, wildlife, soil, sediment, and vegetation are collected by SRS and analyzed for the presence of radioactive and nonradioactive contaminants. During 2012, SRS accomplished several significant milestones while maintaining its record of environmental excellence, as its operations continued to result in minimal impact to the public and the environment. The Site's radioactive and chemical discharges to air and water were well below regulatory standards for environmental and public health protection; its air and water quality met applicable requirements; and the potential radiation dose to the public was well below the DOE public dose limit.

  11. Long-term surveillance plan for the Green River, Utah, disposal site

    International Nuclear Information System (INIS)

    1997-06-01

    The long-term surveillance plan (LTSP) for the Green River, Utah, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Green River disposal cell. The U.S. Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This final LTSP was prepared as a requirement for acceptance under the U.S. Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials (RRM). This LTSP documents whether the land and interests are owned by the United States or an Indian tribe and details how the long-term care of the disposal site will be carried out. The Green River, Utah, LTSP is based on the DOE's Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992a)

  12. Rheology of Savannah River Site Tank 42 radioactive sludges. Revision 1

    International Nuclear Information System (INIS)

    Ha, B.C.; Bibler, N.E.

    1995-01-01

    Knowledge of the rheology of the radioactive sludge slurries at the Savannah River Site (SRS) is necessary in order to ensure that they can be retrieved from waste tanks and processed for final disposal. At Savannah River Site (SRS), Tank 42 sludge represents one of the first HLW radioactive sludges to be vitrified in the Defense Waste Processing Facility (DWPF). The rheological properties of unwashed Tank 42 sludge slurries at various solids concentrations were measured remotely in the Shielded Cells at the Savannah River Technology Center (SRTC) using a modified Haake Rotovisco viscometer. Rheological properties of Tank 42 radioactive sludge were measured as a function of weight percent total solids to ensure that the first DWPF radioactive sludge batch can be pumped and processed in the DWPF with the current design bases. The yield stress and consistency of the sludge slurries were determined by assuming a Bingham plastic fluid model

  13. Long-term surveillance plan for the Green River, Utah disposal site. Revision 1

    International Nuclear Information System (INIS)

    1994-08-01

    The long-term surveillance plan (LTSP) for the Green River, Utah, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Green River disposal cell. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This final LTSP was prepared as a requirement for acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials (RRM). This LTSP documents whether the land and interests are owned by the United States or an Indian tribe and details how the long-term care of the disposal site will be carried out. The Green River, Utah, LTSP is based on the DOE's Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992a)

  14. Investigation of nonlinear dynamic soil property at the Savannah River Site

    International Nuclear Information System (INIS)

    Lee, R.C.

    2000-01-01

    This document summarizes laboratory dynamic soil testing investigations conducted by the University of Texas at Austin (UTA) for the Savannah River Site (SRS) (Stokoe et al., 1995a, Stokoe et al., 1995b, Sponseller and Stokoe, 1995). The purpose of the investigation is to provide an evaluation of past testing results in the context of new test data and the development of consistent site wide models of material strain dependencies based upon geologic formation, depth, and relevant index properties

  15. Initial Operation of the Savannah River Site Advanced Storage Monitoring Facility

    International Nuclear Information System (INIS)

    McCurry, D.R.

    2001-01-01

    An advanced storage monitoring facility has been constructed at the Savannah River Site capable of storing sensitive nuclear materials (SNM) with access to monitoring information available over the Internet. This system will also have monitoring information available over the Internet to appropriate users. The programs will ultimately supply authenticated and encrypted data from the storage sites to certified users to demonstrate the capability of using the Internet as a safe and secure communications medium for remote monitoring of sensitive items

  16. Analysis of Removal Alternatives for the Heavy Water Components Test Reactor at the Savannah River Site

    International Nuclear Information System (INIS)

    Owen, M.B.

    1996-08-01

    This engineering study was developed to evaluate different options for decommissioning of the Heavy Water Components Test Reactor (HWCTR) at the Savannah River Site. This document will be placed in the DOE-SRS Area reading rooms for a period of 30 days in order to obtain public input to plans for the demolition of HWCTR

  17. Savannah River Site TIER TWO report 1992: Emergency and Hazardous Chemical Inventory report

    International Nuclear Information System (INIS)

    Still, G.O.

    1993-03-01

    This report is a compilation of data on emergency and hazardous chemicals stored at the Savannah River Site. The report lists quantities of materials, general types of storage containment, types of storage conditions (pressure and temperature), and other information of relevance for particular materials

  18. The Savannah River Site's Groundwater Monitoring Program, third quarter 1991

    Energy Technology Data Exchange (ETDEWEB)

    1992-02-17

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site's (SRS) Groundwater Monitoring Program. During third quarter 1991, EPD/EMS conducted extensive sampling of monitoring wells. Analytical results from third quarter 1991 are listed in this report.

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

    Energy Technology Data Exchange (ETDEWEB)

    Vincent, A.W. III

    2001-01-03

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

  20. The Savannah River Site's Groundwater Monitoring Program second quarter 1999 (April through June 1999)

    International Nuclear Information System (INIS)

    Hutchison, J.B.

    1999-01-01

    This report summarizes the Groundwater Monitoring Program conducted by Savannah River Site during first quarter 1999. It includes the analytical data, field data, data review, quality control, and other documentation for this program; provides a record of the program's activities; and serves as an official record of the analytical results

  1. Hanford Site River Protection Project (RPP) High-Level Waste Storage

    International Nuclear Information System (INIS)

    KRISTOFZSKI, J.G.

    2000-01-01

    The CH2M HILL Hanford Group (CHG) conducts business to achieve the goals of the U.S. Department of Energy's (DOE) Office of River Protection at the Hanford Site. The CHG is organized to manage and perform work to safely store, retrieve, etc

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

    Energy Technology Data Exchange (ETDEWEB)

    Hamby, D.M.

    1991-03-01

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

  3. Cost benefit of caustic recycle for tank waste remediation at the Hanford and Savannah River Sites

    International Nuclear Information System (INIS)

    DeMuth, S.

    1998-01-01

    The potential cost savings due to the use of caustic recycle used in conjunction with remediation of radioactive underground storage tank waste, is shown in a figure for the Hanford and Savannah River sites. Two cost savings estimates for each case have been made for Hanford, and one cost savings estimate for each case have been made for Hanford, and one cost savings estimate for each case has been made for the Savannah River site. This is due to the Hanford site remediation effort being less mature than that of Savannah River; and consequently, a range of cost savings being more appropriate for Hanford. This range of cost savings (rather than a ingle value) for each case at Hanford is due to cost uncertainties related to the LAW immobilization operation. Caustic recycle Case-1 has been defined as the sodium required to meet al identified caustic needs for the entire Site. Case-2 has been defined as the maximum sodium which can be separated from the low activity waste without precipitation of Al(OH) 3 . It has been determined that the potential cost savings at Hanford ranges from $194 M to $215 M for Case-1, and $293 M to $324 M for Case-2. The potential cost savings at Savannah River are $186 M for Case-1 and $281 M for Case-2. A discussion of the uncertainty associated with these cost savings estimates can be found in the Discussion and Conclusions section

  4. Basement Surface Faulting and Topography for Savannah River Site and Vicinity

    International Nuclear Information System (INIS)

    Cumbest, R.J.

    1998-01-01

    This report integrates the data from more than 60 basement borings and over 100 miles of seismic reflection profiling acquired on the Savannah River Site to map the topography of the basement (unweathered rock) surface and faulting recorded on this surface

  5. Innovative in situ treatment approach for DOE Savannah River Site Sanitary Landfill

    International Nuclear Information System (INIS)

    Knapp, J.; Suer, A.

    1994-01-01

    Pursuant to a settlement agreement reached between the US Department of Energy (DOE) and the South Carolina Department of Health and Environmental Control (SCDHEC), the Sanitary Landfill at the Savannah River Site will be closed. This paper addresses the approach used to select the innovative in situ treatment alternative for the groundwater and the vadose zone associated with the landfill

  6. 76 FR 7835 - Great River Hydropower, LLC; Notice of Scoping Meetings and Environmental Site Review and...

    Science.gov (United States)

    2011-02-11

    ... Hydropower, LLC; Notice of Scoping Meetings and Environmental Site Review and Soliciting Scoping Comments.... c. Date filed: July 12, 2010. d. Applicant: Great River Hydropower, LLC. e. Name of Project: Upper... 796-foot-long by 46-foot-wide by 25-foot-high concrete hydropower structure consisting of 30 turbine...

  7. The Savannah River Site's Groundwater Monitoring Program 1991 well installation report

    International Nuclear Information System (INIS)

    1992-06-01

    This report is a summary of the well and environmental soil boring information compiled for the groundwater monitoring program of the Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) at the Savannah River Site (SRS) during 1991. It includes discussion of environmental soil borings, surveying, well installations, abandonments, maintenance, and stabilization

  8. The seasonal factor at the prehistoric site of Shag River Mouth, New Zealand

    International Nuclear Information System (INIS)

    Higham, T.F.G.

    1997-01-01

    This paper addresses moa hunters' seasonality at the Shag River Mouth site. A two meters section in layer 4 of the SM/C: Dune site was left as a baulk in 1988 to enable the stratigraphic profile (∼2m) to be more carefully investigated. Within the baulk, detailed lensing and microstrata could be identified. Claassen (1991) has suggested that one of the most important variables in determining seasonal and prehistoric shell-bearing site formation more accurately is emphasizing finer stratigraphic resolution and more rigorous attention to retrieving midden components. At Shag River Mouth, seven sub-layers, or spits, were excavated within the 2m baulk to refine the precision of subsequent seasonal analyses and enable a detailed assessment of the components of each and their season of deposition. A variety of seasonal methods were utilised including 18 O analysis of blue mussel shell carbonate and growth ring analysis of estuarine bivalves. In addition, sagital otoliths of red cod excavated from the site were sectioned and the annual and seasonal growth rings formed during the fishes' life were analysed for seasonal information. This has enabled a detailed analysis of the seasonality of this discrete area of the Shag River Mouth site. The significance of the results for understanding the prehistoric seasonal round of activities within the site and its wider orbit is presented

  9. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement; Volume 1, Appendix F, Nevada Test Site and Oak Ridge Reservation Spent Nuclear Fuel Management Programs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-06-01

    This volume addresses the interim storage of spent nuclear fuel (SNF) at two US Department of Energy sites, the Nevada Test Site (NTS) and the Oak Ridge Reservation (ORR). These sites are being considered to provide a reasonable range of alternative settings at which future SNF management activities could be conducted. These locations are not currently involved in management of large quantities of SNF; NTS has none, and ORR has only small quantities. But NTS and ORR do offer experience and infrastructure for the handling, processing and storage of radioactive materials, and they do exemplify a broad spectrum of environmental parameters. This broad spectrum of environmental parameters will provide, a perspective on whether and how such location attributes may relate to potential environmental impacts. Consideration of these two sites will permit a programmatic decision to be based upon an assessment of the feasible options without bias, to the current storage sites. This volume is divided into four parts. Part One is the volume introduction. Part Two contains chapters one through five for the NTS, as well as references contained in chapter six. Part Three contains chapters one through five for the ORR, as well as references contained in chapter six. Part Four is summary information including the list of preparers, organizations contacted, acronyms, and abbreviations for both the NTS and the ORR. A Table of Contents, List of Figures, and List of Tables are included in parts Two, Three, and Four. This approach permitted the inclusion of both sites in one volume while maintaining consistent chapter numbering.

  10. Assessment of tritium in the Savannah River Site environment

    International Nuclear Information System (INIS)

    Carlton, W.H.; Murphy, C.E. Jr.; Bauer, L.R.

    1993-10-01

    This report is the first revision to a series of reports on radionuclides inn the SRS environment. Tritium was chosen as the first radionuclide in the series because the calculations used to assess the dose to the offsite population from SRS releases indicate that the dose due to tritium, through of small consequence, is one of the most important the radionuclides. This was recognized early in the site operation, and extensive measurements of tritium in the atmosphere, surface water, and ground water exist due to the effort of the Environmental Monitoring Section. In addition, research into the transport and fate of tritium in the environment has been supported at the SRS by both the local Department of Energy (DOE) Office and DOE's Office of Health and Environmental Research

  11. Assessment of tritium in the Savannah River Site environment

    Energy Technology Data Exchange (ETDEWEB)

    Carlton, W.H.; Murphy, C.E. Jr.; Bauer, L.R. [and others

    1993-10-01

    This report is the first revision to a series of reports on radionuclides inn the SRS environment. Tritium was chosen as the first radionuclide in the series because the calculations used to assess the dose to the offsite population from SRS releases indicate that the dose due to tritium, through of small consequence, is one of the most important the radionuclides. This was recognized early in the site operation, and extensive measurements of tritium in the atmosphere, surface water, and ground water exist due to the effort of the Environmental Monitoring Section. In addition, research into the transport and fate of tritium in the environment has been supported at the SRS by both the local Department of Energy (DOE) Office and DOE`s Office of Health and Environmental Research.

  12. DEVELOPMENT OF REMOTE HANFORD CONNECTOR GASKET REPLACEMENT TOOLING FOR THE SAVANNAH RIVER SITE'S DEFENSE WASTE PROCESSING FACILITY

    International Nuclear Information System (INIS)

    Krementz, D

    2007-01-01

    The Savannah River Site's (SRS) Defense Waste Processing Facility (DWPF) requested development of tooling for remote replacement of gaskets in mechanical Hanford connectors. The facility has compressed air supply, two master-slave manipulators (MSM's) and a lightweight robotic arm for operation of the remote tools. The Savannah River National Laboratory (SRNL) developed and tested multiple tools to perform the gasket replacement tasks. Separate pneumatic snap-ring removal tools that use the connector skirt as a reaction surface were developed for removal of the snap ring and spent gasket on both vertical and horizontal Hanford connectors. A pneumatic tool that clamps and centers on the jumper pipe ID was developed to simultaneously install the new gasket and snap ring. A pneumatic snap-ring-loading tool was developed that compresses the snap ring and places it in a groove in the installation tool. All of the tools are located on a custom work table with a pneumatic valve station that directs compressed air to the desired tool and vents the tools as needed. The entire system has been successfully tested using MSM's to manipulate the various tools. Deployment of the entire system is expected during FY08. The Hanford connector gasket replacement tooling has been successfully tested using MSM's to manipulate the various tools. Nitric acid is used in many of the decontamination processes performed in the REDC, where the tooling will be deployed. Although most of the tool components were fabricated/purchased with nitric acid and radioactive service in mind, some of the prototype parts must be replaced with parts that are more compatible with nitric acid/radioactive service. Several modifications to the various tools are needed to facilitate maintenance and replacement of failed components. Development of installation tools for replacement of 1-inch, 2-inch and multi-hole gaskets is being considered. Deployment of the existing system in the DWPF REDC is expected during FY

  13. The Savannah River Site's Groundwater Monitoring Program, third quarter 1989

    Energy Technology Data Exchange (ETDEWEB)

    1989-01-01

    The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site's Groundwater Monitoring Program. During third quarter 1989 (July--September), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead they aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. An explanation of flagging criteria for the third quarter is presented in the Flagging Criteria section of this document. All analytical results from third quarter 1989 are listed in this report, which is distributed to all waste-site custodians.

  14. The Savannah River Site's Groundwater Monitoring Program, second quarter 1989

    Energy Technology Data Exchange (ETDEWEB)

    1989-01-01

    The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site's Groundwater Monitoring Program. During second quarter 1989 (April--June), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. An explanation of flagging criteria for the second quarter is presented in the Flagging Criteria section of this document. All analytical results from second quarter 1989 are listed in this report, which is distributed to all waste-site custodians.

  15. Radiological bioconcentration factors for aquatic, terrestrial, and wetland ecosystems at the Savannah River Site

    International Nuclear Information System (INIS)

    Cummins, C.L.

    1994-09-01

    As a result of operations at the Savannah River Site (SRS), over 50 radionuclides have been released to the atmosphere and to onsite streams and seepage basins. Now, many of these radionuclides are available to aquatic and/or terrestrial organisms for uptake and cycling through the food chain. Knowledge about the uptake and cycling of these radionuclides is now crucial in evaluating waste management and clean-up alternatives for the site. Numerous studies have been conducted at the SRS over the past forty years to study the uptake and distribution of radionuclides in the Savannah River Site environment. In many instances, bioconcentration factors have been calculated to quantify the uptake of a radionuclide by an organism from the surrounding medium (i.e., soil or water). In the past, it has been common practice to use bioconcentration factors from the literature because site-specific data were not readily available. However, because of the variability of bioconcentration factors due to experimental or environmental conditions, site-specific data should be used when available. This report compiles and summarizes site-specific bioconcentration factors for selected radionuclides released at the Savannah River Site (SRS). An extensive literature search yielded site-specific bioconcentration factors for cesium, strontium, cobalt, plutonium, americium, curium, and tritium. These eight radionuclides have been the primary radionuclides studied at SRS because of their long half lives or because they are major contributors to radiological dose from exposure. For most radionuclides, it was determined that the site-specific bioconcentration factors were higher than those reported in literature. This report also summarizes some conditions that affect radionuclide bioavailability to and bioconcentration by aquatic and terrestrial organisms

  16. SAVANNAH RIVER SITE CAPABILITIES FOR CONDUCTING INGESTION PATHWAY CONSEQUENCE ASSESSMENTS FOR EMERGENCY RESPONSE

    Energy Technology Data Exchange (ETDEWEB)

    Hunter, C

    2007-12-11

    Potential airborne releases of radioactivity from facilities operated for the U. S. Department of Energy at the Savannah River Site could pose significant consequences to the public through the ingestion pathway. The Savannah River National Laboratory has developed a suite of technologies needed to conduct assessments of ingestion dose during emergency response, enabling emergency manager at SRS to develop initial protective action recommendation for state agencies early in the response and to make informed decisions on activation of additional Federal assets that would be needed to support long-term monitoring and assessment activities.

  17. Criticality safety engineering at the Savannah River Site - the 1990s

    International Nuclear Information System (INIS)

    Chandler, J.R.; Apperson, C.E. Jr.

    1996-01-01

    The privatization and downsizing effort that is ongoing within the U.S. Department of Energy (DOE) is requiring a change in the management of criticality safety engineering resources at the Savannah River Site (SRS). Downsizing affects the number of criticality engineers employed by the prime contractor, Westinghouse Savannah River Company (WSRC), and privatization affects the manner in which business is conducted. In the past, criticality engineers at the SRS have been part of the engineering organizations that support each facility handling fissile material. This practice led to different criticality safety engineering organizations dedicated to fuel fabrication activities, reactor loading and unloading activities, separation and waste management operations, and research and development

  18. Demonstration of Caustic-Side Solvent Extraction with Savannah River Site High Level Waste

    International Nuclear Information System (INIS)

    Walker, D.D.

    2001-01-01

    Researchers successfully demonstrated the chemistry and process equipment of the Caustic-Side Solvent Extraction (CSSX) flowsheet for the decontamination of high level waste using a 33-stage, 2-cm centrifugal contactor apparatus at the Savannah River Technology Center. This represents the first CSSX process demonstration using Savannah River Site (SRS) high level waste. Three tests lasting 6, 12, and 48 hours processed simulated average SRS waste, simulated Tank 37H/44F composite waste, and Tank 37H/44F high level waste, respectively

  19. Using Geoscience and Geostatistics to Optimize Groundwater Monitoring Networks at the Savannah River Site

    International Nuclear Information System (INIS)

    Tuckfield, R.C.

    2001-01-01

    A team of scientists, engineers, and statisticians was assembled to review the operation efficiency of groundwater monitoring networks at US Department of Energy Savannah River Site (SRS). Subsequent to a feasibility study, this team selected and conducted an analysis of the A/M area groundwater monitoring well network. The purpose was to optimize the number of groundwater wells requisite for monitoring the plumes of the principal constituent of concern, viz., trichloroethylene (TCE). The project gathered technical expertise from the Savannah River Technology Center (SRTC), the Environmental Restoration Division (ERD), and the Environmental Protection Department (EPD) of SRS

  20. Wetlands for Industrial Wastewater Treatment at the Savannah River Site

    International Nuclear Information System (INIS)

    Gladden, J.B.

    2002-01-01

    The A-01 effluent outfall, which collects both normal daily process flow and stormwater runoff from a industrial park area, did not meet the South Carolina Department of Health and Environmental Control (SCDHEC) National Pollutant Discharge Elimination System (NPDES) permit limits for metals, toxicity, and total residual chlorine at the outfall sampling point. Copper was the constituent of primary concern and the effluent consistently failed to meet that NPDES limit. Installation of a constructed wetland system including a basin to manage stormwater surges was required to reduce the problematic constituent concentrations to below the NPDES permit limits before the effluent reaches the sampling point. Both bench-scale and on-site pilot scale physical models were constructed to refine and optimize the preliminary design as well as demonstrate the effectiveness of this approach prior to construction, which was completed in October 2000. The constructed treatment wetlands system has prov en its ability to treat industrial wastewaters containing metals with low O and M costs since there are no mechanical parts. With an anticipated life of over 50 years, this system is exceptionally cost effective

  1. Department of Energy Plutonium ES ampersand H Vulnerability Assessment Savannah River Site interim compensatory measures

    International Nuclear Information System (INIS)

    Bickford, W.E.

    1994-01-01

    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 ampersand 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 ampersand H has requested this status for all vulnerabilities ranked medium or higher with respect to potential consequences to workers, environment, and the public

  2. Geochemical Data Package for Performance Assessment Calculations Related to the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Kaplan, Daniel I. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2010-03-15

    The Savannah River Site disposes of low-activity radioactive waste within subsurface-engineered facilities. One of the tools used to establish the capacity of a given site to safely store radioactive waste (i.e., that a site does not exceed its Waste Acceptance Criteria) is the Performance Assessment (PA). The objective of this document is to provide the geochemical values for the PA calculations. This work is being conducted as part of the on-going maintenance program that permits the PA to periodically update existing calculations when new data become available.

  3. SRP baseline hydrogeologic investigation: Aquifer characterization. Groundwater geochemistry of the Savannah River Site and vicinity

    Energy Technology Data Exchange (ETDEWEB)

    Strom, R.N.; Kaback, D.S.

    1992-03-31

    An investigation of the mineralogy and chemistry of the principal hydrogeologic units and the geochemistry of the water in the principal aquifers at Savannah River Site (SRS) was undertaken as part of the Baseline Hydrogeologic Investigation. This investigation was conducted to provide background data for future site studies and reports and to provide a site-wide interpretation of the geology and geochemistry of the Coastal Plain Hydrostratigraphic province. Ground water samples were analyzed for major cations and anions, minor and trace elements, gross alpha and beta, tritium, stable isotopes of hydrogen, oxygen, and carbon, and carbon-14. Sediments from the well borings were analyzed for mineralogy and major and minor elements.

  4. Radiation situation dynamics at the Andreeva Bay site for temporary storage of spent nuclear fuel and radioactive waste over the period 2002-2016.

    Science.gov (United States)

    Chizhov, K; Sneve, M K; Shandala, N; Siegien-Iwaniuk, K; Smith, G M; Krasnoschekov, A; Kosnikov, A; Grigoriev, A; Simakov, A; Kemsky, I; Kryuchkov, V

    2018-02-01

    The Coastal Technical Base (CTB) №569 at Andreeva Bay was established in the early 1960s and intended for the refueling of nuclear submarine reactors and temporary storage of spent nuclear fuel (SNF) and radioactive waste (RW). In 2001, the base was transferred to the Russian Ministry for Atomic Energy and the site remediation began. The paper describes in detail the radiation situation change at the technical site in Andreeva Bay from 2002-2016, the period of preparation for the most critical phase of remedial work: removal of spent fuel assemblies. The analysis of aggregated indicators and data mining were used. The article suggests the best number and location of checkpoints needed to ensure sufficient accuracy of the radiation situation description. The fractal properties of the radiation field are studied using the Hurst index. The relationship between checkpoints was assessed using the method of searching for checkpoint communities. The decrease in the integral of the ambient dose equivalent rate (ADER) at the technical site was evaluated by the method of time series decomposition. Three components of time series were identified: trend, seasonal and residual. The trend of the ADER integral over the technical site is a monotonic decreasing function, where the initial and final values differ tenfold. Taking into account that 137 Cs dominates the radiation situation on-site, it is clear that the ADER due to the radionuclide decay will have decreased by 1.4 times. It is estimated that only a small proportion of 137 Cs has migrated off-site. Therefore, approximately a sevenfold decrease in dose rate is mainly due to remediation activities of personnel. During the year, the seasonal component varies the ADER integral by a factor of two, due to snowfall. The residual component reflects the uncertainty of the ADER integral calculation and phases of active SNF and RW management. The methods developed are used to support the optimization of remediation work as well

  5. Evaluation of Mineral Deposits Along the Little Wind River, Riverton, WY, Processing Site

    Energy Technology Data Exchange (ETDEWEB)

    Campbell, Sam [Navarro Research and Engineering, Oak Ridge, TN (United States); Dam, Wiliam [US Department of Energy, Washington, DC (United States). Office of Legacy Management

    2014-12-01

    In 2012, the U.S.Department of Energy (DOE) began reassessing the former Riverton, Wyoming, Processing Site area for potential contaminant sources impacting groundwater. A flood in 2010 along the Little Wind River resulted in increases in groundwater contamination (DOE 2013).This investigation is a small part of continued efforts by DOE and other stakeholders to update human health and ecological risk assessments, to make a comprehensive examination of all exposure pathways to ensure that the site remains protective through established institutional controls. During field inspections at the Riverton Site in 2013, a white evaporitic mineral deposit was identified along the bank of the Little Wind River within the discharge zone of the groundwater contamination plume. In December 2013, Savannah River National Laboratory (SRNL) personnel collected a sample for analysis by X-ray fluorescence (Figure 1 shows the type of material sampled). The sample had a uranium concentration of approximately 64 to 73 parts per million. Although the uranium in this mineral deposit is within the expected range for evaporatic minerals in the western United States (SRNL 2014), DOE determined that additional assessment of the mineral deposit was warranted. In response to the initial collection and analysis of a sample of the mineral deposit, DOE developed a work plan (Work Plan to Sample Mineral Deposits Along the Little Wind River, Riverton, Wyoming, Processing Site [DOE 2014]) to further define the extent of these mineral deposits and the concentration of the associated contaminants (Appendix A). The work plan addressed field reconnaissance, mapping, sampling, and the assessment of risk associated with the mineral deposits adjacent to the Little Wind River.

  6. Intervention in independent spent fuel storage facility license application proceedings for storage on the power plant site

    International Nuclear Information System (INIS)

    Jordan, J.

    1992-01-01

    This presentation summarizes the intervention in the Nuclear Regulatory Commission (NRC) licensing process for currently operating Independent Spent fuel Storage Installation (ISFSI) projects at Carolina Power and Light's Company's H.B. Robinson, Duke Power Company's Oconee, and Virginia Power Company's Surry. In addition, intervention at dry storage facilities that are currently under development are also described. The utilities and reactors include Baltimore Gas and Electric Company's Calvert Cliffs, Public Service Company of Colorado's Fort St. Vrain plant, Northern States Power Company's Prairie Island, Wisconsin Electric Power Company's Point Beach, and Consumers Power Company's Palisades

  7. Site Selection for Surplus Plutonium Disposition Facilities at the Savannah River Site

    International Nuclear Information System (INIS)

    Wike, L.D.

    2000-01-01

    A site selection study was conducted to evaluate locations for the proposed Surplus Plutonium Disposition Facilities. Facilities to be located include the Mixed Oxide (MOX) Fuel Fabrication Facility, the Pit Disassembly and Conversion Facility (PDCF), and the Plutonium Immobilization Project (PIP) facility. Objectives of the study include: (1) Confirm that the Department of Energy (DOE) selected locations for the MOX and PDCF were suitable based on selected siting criteria, (2) Recommend a site in the vicinity of F Area that is suitable for the PIP, and (3) Identify alternative suitable sites for one or more of these facilities in the event that further geotechnical characterization or other considerations result in disqualification of a currently proposed site

  8. Pilot study risk assessment for selected problems at the Savannah River Site (SRS)

    International Nuclear Information System (INIS)

    Hamilton, L.D.; Holtzman, S.; Meinhold, A.; Morris, S.C.; Pardi, R.; Sun, C.; Daniels, J.I.; Layton, D.; McKone, T.E.; Straume, T.; Anspaugh, L.

    1993-03-01

    An assessment of the health risks was made for releases of tritium and 137 Cs from the Savannah River Site (SRS) at water-receptor locations downriver. Although reactor operations were shut down at the SRS in 1989, liquid wastes continue to be released to the Savannah River either by direct discharges into onsite surface waters or by groundwater transport into surface waters from waste facilities. Existing state mandates will cause the liquid waste streams from future operations to go directly into surface waters. Two drinking water processing plants take water from the river approximately 129 km downriver from the SRS. Potential incremental risks of cancer fatality to individuals and each population were analyzed for either no further reactor operations or resumption of operation of one specific reactor

  9. Pilot study risk assessment for selected problems at the Savannah River Site (SRS)

    Energy Technology Data Exchange (ETDEWEB)

    Hamilton, L.D.; Holtzman, S.; Meinhold, A.; Morris, S.C.; Pardi, R.; Sun, C. [Brookhaven National Lab., Upton, NY (United States); Daniels, J.I.; Layton, D.; McKone, T.E.; Straume, T.; Anspaugh, L. [Lawrence Livermore National Lab., CA (United States)

    1993-03-01

    An assessment of the health risks was made for releases of tritium and {sup 137}Cs from the Savannah River Site (SRS) at water-receptor locations downriver. Although reactor operations were shut down at the SRS in 1989, liquid wastes continue to be released to the Savannah River either by direct discharges into onsite surface waters or by groundwater transport into surface waters from waste facilities. Existing state mandates will cause the liquid waste streams from future operations to go directly into surface waters. Two drinking water processing plants take water from the river approximately 129 km downriver from the SRS. Potential incremental risks of cancer fatality to individuals and each population were analyzed for either no further reactor operations or resumption of operation of one specific reactor.

  10. Pilot study risk assessment for selected problems at the Savannah River Site (SRS)

    Energy Technology Data Exchange (ETDEWEB)

    Hamilton, L.D.; Holtzman, S.; Meinhold, A.; Morris, S.C.; Pardi, R.; Sun, C. (Brookhaven National Lab., Upton, NY (United States)); Daniels, J.I.; Layton, D.; McKone, T.E.; Straume, T.; Anspaugh, L. (Lawrence Livermore National Lab., CA (United States))

    1993-03-01

    An assessment of the health risks was made for releases of tritium and [sup 137]Cs from the Savannah River Site (SRS) at water-receptor locations downriver. Although reactor operations were shut down at the SRS in 1989, liquid wastes continue to be released to the Savannah River either by direct discharges into onsite surface waters or by groundwater transport into surface waters from waste facilities. Existing state mandates will cause the liquid waste streams from future operations to go directly into surface waters. Two drinking water processing plants take water from the river approximately 129 km downriver from the SRS. Potential incremental risks of cancer fatality to individuals and each population were analyzed for either no further reactor operations or resumption of operation of one specific reactor.

  11. Reliability Centered Maintenance for Savannah River Site`s interim waste management facilities. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Hauer, K.A. [Westinghouse Savannah River Co., Aiken, SC (United States); Wilson, J.F. [PRC, Inc. (US)

    1992-06-01

    The application of Reliability Centered Maintenance (RCM) has been shown to be an effective means to optimize maintenance programs or to establish new programs. The key to success of any RCM program is to customize the methodology to meet the specific needs of the implementing organization. This paper discusses how RCM is being used to establish the preventive maintenance program and how the resulting system data is being used to support the Technical Baseline reconstitution effort for the interim Waste Management Division of Westinghouse Savannah River Company (WSRC).

  12. Technical summary of groundwater quality protection program at the Savannah River Site, 1952--1986. Volume 1, Site geohydrology and waste sites

    Energy Technology Data Exchange (ETDEWEB)

    Heffner, J.D. [ed.] [Exploration Resources, Inc., Athens, GA (United States)

    1991-11-01

    This report provides information regarding the status of and groundwater quality at the waste sites at the Department of Energy`s (DOE) Savannah River Site (SRS). Specific information provided for each waste site at SRS includes its location, size, inventory (when known), and history. Many waste sites at SRS are considered to be of little environmental concern because they contain nontoxic or inert material such as construction rubble and debris. Other waste sites, however, either are known to have had an effect on groundwater quality or are suspected of having the potential to affect groundwater. Monitoring wells have been installed at most of these sites; monitoring wells are scheduled for installation at the remaining sites. Results of the groundwater analyses from these monitoring wells, presented in the appendices, are used in the report to help identify potential contaminants of concern, if any, at each waste site. The list of actions proposed for each waste site in Christensen and Gordon`s 1983 report are summarized, and an update is provided for each site. Planned actions for the future are also outlined.

  13. The Fall River Long-Term Site Productivity study in coastal Washington: site characteristics, methods, and biomass and carbon and nitrogen stores before and after harvest.

    Science.gov (United States)

    Adrian Ares; Thomas A. Terry; Kathryn B. Piatek; Robert B. Harrison; Richard E. Miller; Barry L. Flaming; ChristopherW Licata; Brian D. Strahm; Constance A. Harrington; Rodney Meade; Harry W. Anderson; Leslie C. Brodie; Joseph M. Kraft

    2007-01-01

    The Fall River research site in coastal Washington is an affiliate installation of the North American Long-Term Soil Productivity (LTSP) network, which constitutes one of the world’s largest coordinated research programs addressing forest management impacts on sustained productivity. Overall goals of the Fall River study are to assess effects of biomass removals, soil...

  14. Geomorphology and geologic characteristics of the Savannah River floodplain in the vicinity of the Savannah River Site, South Carolina and Georgia

    International Nuclear Information System (INIS)

    Leeth, D.C.; Nagle, D.D.

    1994-01-01

    The potential for migration of contaminated ground water from the US Department of Energy Savannah River Site (SRS) beneath the Savannah River into Georgia (trans-river flow) is a subject of recent environmental concern. The degree of incision of the ancestral Savannah River into the local hydrogeologic framework is a significant consideration in the assessment of trans-river flow. The objective of this investigation is to identify the geologic formations which subcrop beneath the alluvium and the extent to which the river has incised regional confining beds. To meet this objective 18 boreholes were drilled to depths of 25 to 100 feet along three transects across the present floodplain. These borings provided data on the hydrogeologic character of the strata that fill the alluvial valley. The profiles from the borehole transects were compared with electrical conductivity (EM-34) data to ascertain the applicability of this geophysical technique to future investigations

  15. DOE Research Set-Aside Areas of the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Davis, C.E.; Janecek, L.L.

    1997-08-31

    Designated as the first of seven National Environmental Research Parks (NERPs) by the Atomic Energy Commission (now the Department of Energy), the Savannah River Site (SRS) is an important ecological component of the Southeastern Mixed Forest Ecoregion located along the Savannah River south of Aiken, South Carolina. Integral to the Savannah River Site NERP are the DOE Research Set-Aside Areas. Scattered across the SRS, these thirty tracts of land have been set aside for ecological research and are protected from public access and most routine Site maintenance and forest management activities. Ranging in size from 8.5 acres (3.44 ha) to 7,364 acres (2,980 ha), the thirty Set-Aside Areas total 14,005 acres (5,668 ha) and comprise approximately 7% of the Site`s total area. This system of Set-Aside Areas originally was established to represent the major plant communities and habitat types indigenous to the SRS (old-fields, sandhills, upland hardwood, mixed pine/hardwood, bottomland forests, swamp forests, Carolina bays, and fresh water streams and impoundments), as well as to preserve habitats for endangered, threatened, or rare plant and animal populations. Many long-term ecological studies are conducted in the Set-Asides, which also serve as control areas in evaluations of the potential impacts of SRS operations on other regions of the Site. The purpose of this document is to give an historical account of the SRS Set-Aside Program and to provide a descriptive profile of each of the Set-Aside Areas. These descriptions include a narrative for each Area, information on the plant communities and soil types found there, lists of sensitive plants and animals documented from each Area, an account of the ecological research conducted in each Area, locator and resource composition maps, and a list of Site-Use permits and publications associated with each Set-Aside.

  16. The ArcSDE GIS Dynamic Population Model Tool for Savannah River Site Emergency Response

    International Nuclear Information System (INIS)

    MCLANE, TRACY; JONES, DWIGHT

    2005-01-01

    The Savannah River Site (SRS) is a 310-square-mile Department of Energy site located near Aiken, South Carolina. With a workforce of over 10,000 employees and subcontractors, SRS emergency personnel must be able to respond to an emergency event in a timely and effective manner, in order to ensure the safety and security of the Site. Geographic Information Systems (GIS) provides the technology needed to give managers and emergency personnel the information they need to make quick and effective decisions. In the event of a site evacuation, knowing the number of on-site personnel to evacuate from a given area is an essential piece of information for emergency staff. SRS has developed a GIS Dynamic Population Model Tool to quickly communicate real-time information that summarizes employee populations by facility area and building and then generates dynamic maps that illustrate output statistics

  17. Site Management and Monitoring Plan (SMMP) for the Mouth of Columbia River- Deep and Shallow Water Ocean Dredged Material Disposal Sites, OR/WA

    Science.gov (United States)

    This SMMP is intended to provide management and monitoring strategies for disposal in the Mouth of Columbia River- Deep and Shallow Ocean Dredged Material Disposal Sites on the border of Oregon and Washington.

  18. Breeding bird populations and habitat associations within the Savannah River Site (SRS).

    Energy Technology Data Exchange (ETDEWEB)

    Gauthreaux, Sidney, A.; Steven J. Wagner.

    2005-06-29

    Gauthreaux, Sidney, A., and Steven J. Wagner. 2005. Breeding bird populations and habitat associations within the Savannah River Site (SRS). Final Report. USDA Forest Service, Savannah River, Aiken, SC. 48 pp. Abstract: During the 1970's and 1980's a dramatic decline occurred in the populations of Neotropical migratory birds, species that breed in North America and winter south of the border in Central and South America and in the Caribbean. In 1991 an international initiative was mounted by U. S. governmental land management agencies, nongovernmental conservation agencies, and the academic and lay ornithological communities to understand the decline of Neotropical migratory birds in the Americas. In cooperation with the USDA Forest Service - Savannah River (FS - SR) we began 1992 a project directed to monitoring population densities of breeding birds using the Breeding Bird Census (BBC) methodology in selected habitats within the Savannah River Site SRS. In addition we related point count data on the occurrence of breeding Neotropical migrants and other bird species to the habitat data gathered by the Forest Inventory and Analysis (FIA) program of the USDA Forest Service and data on habitat treatments within forest stands.

  19. Intensive archaeological survey of the proposed Savannah River Ecology Laboratory Conference Center and Educational Facility, Savannah River Site, Aiken County, South Carolina

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-02-01

    Documented in this report are the methods and results of an intensive archaeological survey for the proposed University of Georgia Savannah River Ecology Laboratory (SREL) Conference Center and Educational Facility on the DOE Savannah River Site (SRS). Archaeological investigations conducted by the Savannah River Archaeological Research Program (SRARP) on the 70-acre project area and associated rights-of-way consisted of subsurface testing at two previously recorded sites and the discovery of one previously unrecorded site. The results show that 2 sites contain archaeological remains that may yield significant information about human occupations in the Aiken Plateau and are therefore considered eligible for nomination to the National Register of Historic Places. Adverse impacts to these sites can be mitigated through avoidance.

  20. Laboratory QA/QC improvements for small drinking water systems at Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Turner, R.D.

    1995-12-01

    The Savannah River Site (SRS), a 310 square mile facility located near Aiken, S.C., is operated by Westinghouse Savannah River Company for the US Department of Energy. SRS has 28 separate drinking water systems with average daily demands ranging from 0.0002 to 0.5 MGD. All systems utilize treated groundwater. Until recently, the water laboratories for each system operated independently. As a result, equipment, reagents, chemicals, procedures, personnel, and quality control practices differed from location to location. Due to this inconsistency, and a lack of extensive laboratory OA/QC practices at some locations, SRS auditors were not confident in the accuracy of daily water quality analyses results. The Site`s Water Services Department addressed these concerns by developing and implementing a practical laboratory QA/QC program. Basic changes were made which can be readily adopted by most small drinking water systems. Key features of the program include: Standardized and upgraded laboratory instrumentation and equipment; standardized analytical procedures based on vendor manuals and site requirements; periodic accuracy checks for all instrumentation; creation of a centralized laboratory to perform metals digestions and chlorine colorimeter accuracy checks; off-site and on-site operator training; proper storage, inventory and shelf life monitoring for reagents and chemicals. This program has enhanced the credibility and accuracy of SRS drinking water system analyses results.

  1. Ecological studies related to construction of the Defense Waste Processing Facility on the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Pechmann, J.H.K.; Scott, D.E.; McGregor, J.H.; Estes, R.A.; Chazal, A.C.

    1993-02-01

    The Defense Waste Processing Facility (DWPF) was built on the Savannah River Site (SRS) during the mid-1980's. The Savannah River Ecology Laboratory (SREL) has completed 12 years of ecological studies related to the construction of the DWPF complex. Prior to construction, the 600-acre site (S-Area) contained a Carolina bay and the headwaters of a stream. Research conducted by the SREL has focused primarily on four questions related to these wetlands: (1) Prior to construction, what fauna and flora were present at the DWPF site and at similar, yet undisturbed, alternative sites (2) By comparing the Carolina bay at the DWPF site (Sun Bay) with an undisturbed control Carolina bay (Rainbow Bay), what effect is construction having on the organisms that inhabited the DWPF site (3) By comparing control streams with streams on the periphery of the DWPF site, what effect is construction having on the peripheral streams (4) How effective have efforts been to lessen the impacts of construction, both with respect to erosion control measures and the construction of refuge ponds'' as alternative breeding sites for amphibians that formerly bred at Sun Bay Through the long-term census-taking of biota at the DWPF site and Rainbow Bay, SREL has begun to evaluate the impact of construction on the biota and the effectiveness of mitigation efforts. Similarly, the effects of erosion from the DWPF site on the water quality of S-Area peripheral streams are being assessed. This research provides supporting data relevant to the National Environmental Policy Act (NEPA) of 1969, the Endangered Species Act of 1973, Executive Orders 11988 (Floodplain Management) and 11990 (Protection of Wetlands), and United States Department of Energy (DOE) Guidelines for Compliance with Floodplain/Wetland Environmental Review Requirements (10CFR1022).

  2. Corrosion surveillance in spent fuel storage pools

    International Nuclear Information System (INIS)

    Howell, J.P.

    1996-01-01

    In mid-1991, corrosion of aluminum-clad spent nuclear fuel was observed in the light-water filled basins at the Savannah River site. A corrosion surveillance program was initiated in the P, K, L-Reactor basins and in the Receiving Basin for Offsite Fuels (RBOF). This program verified the aggressive nature of the pitting corrosion and provided recommendations for changes in basin operations to permit extended longer term interim storage. The changes were implemented during 1994--1996 and have resulted in significantly improved basin water quality with conductivity in the 1--3 microS/cm range. Under these improved conditions, no new pitting has been observed over the last three years. This paper describes the corrosion surveillance program at SRS and what has been learned about the corrosion of aluminum-clad in spent fuel storage pools

  3. Control of safety and risk management software at the Savannah River Site

    International Nuclear Information System (INIS)

    Ades, M.J.; Toffer, H.; Crowe, R.D.

    1992-01-01

    As a part of its Reactor Operations Improvement Program at the Savannah River Site (SRS), Westinghouse Savannah River Company (WSRC), in cooperation with the Westinghouse Hanford Company, has developed and implemented software quality assurance (SQA) for computer codes essential to the safety and reliability of reactor operations. This effort includes the use of quality standards and attendant procedures developed for and applied to computer codes used in safety and risk management analyses. The certification process that was recently implemented is in compliance with site wide and departmental SQA requirements. Certification consists of preparing a specific verification and validation (V and V) plan, a configuration control plan, and user qualifications. Applicable documentation is reviewed to determine compliance with V and V and configuration control action items. The results of this review are documented and serve as a baseline for additional certification activities. Resource commitment and schedules are drawn up for each individual code to complete certification in accordance with SQA requirements

  4. Long-term surveillance plan for the Green River, Utah disposal site. Revision 2

    International Nuclear Information System (INIS)

    1998-07-01

    The long-term surveillance plan (LTSP) for the Green River, Utah, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Green River disposal cell. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This final LTSP was prepared as a requirement for acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials (RRM). This LTSP documents whether the land and interests are owned by the United States or an Indian tribe and details how the long-term care of the disposal site will be carried out

  5. Comprehensive strategy for corrective actions at the Savannah River Site General Separations Area

    International Nuclear Information System (INIS)

    Ebra, M.A.; Lewis, C.M.; Amidon, M.B.; McClain, L.K.

    1991-01-01

    The Savannah River Site (SRS), operated by the Westinghouse Savannah River Company for the United States Department of Energy, contains a number of waste disposal units that are currently in various stages of corrective action investigations, closures, and postclosure corrective actions. Many of these sites are located within a 40-square-kilometer area called the General Separations Area (GSA). The SRS has proposed to the regulatory agencies, the United States Environmental Protection Agency (EPA) and the South Carolina Department of Health and Environmental Control (SCDHEC), that groundwater investigations and corrective actions in this area be conducted under a comprehensive plan. The proposed plan would address the continuous nature of the hydrogeologic regime below the GSA and the potential for multiple sources of contamination. This paper describes the proposed approach

  6. Habitat preferences of foraging red-cockaded woodpeckers at the Savannah River Site, South Carolina.

    Energy Technology Data Exchange (ETDEWEB)

    Franzreb, Kathleen, E.

    2004-12-31

    Franzreb, Kathleen, E. 2004. Habitat preferences of foraging red-cockaded woodpeckers at the Savannah River Site, South Carolina. In: Red-cockaded woodpecker; Road to Recovery. Proceedings of the 4th Red-cockaded woodpecker Symposium. Ralph Costa and Susan J. Daniels, eds. Savannah, Georgia. January, 2003. Chapter 9. Habitat Management and Habitat Relationships. Pp 553-561. Abstract: I constructed a foraging study to examine habitat use of red-cockaded woodpeckers at the Savannah River Site, South Carolina. Because much of the land had been harvested in the late 1940s and early 1950s prior to being sold to the Department of Energy, the available habitat largely consisted of younger trees (e.g., less than 40 years old). From 1992 to 1995, I examined the foraging behavior and reproductive success of 7 groups of red-cockaded woodpeckers.

  7. Technical summary of groundwater quality protection program at the Savannah River Site, 1952--1986

    International Nuclear Information System (INIS)

    Heffner, J.D.

    1991-01-01

    This report provides information regarding the status of and groundwater quality at the waste sites at the Department of Energy's (DOE) Savannah River Site (SRS). Specific information provided for each waste site at SRS includes its location, size, inventory (when known), and history. Many waste sites at SRS are considered to be of little environmental concern because they contain nontoxic or inert material such as construction rubble and debris. Other waste sites, however, either are known to have had an effect on groundwater quality or are suspected of having the potential to affect groundwater. Monitoring wells have been installed at most of these sites; monitoring wells are scheduled for installation at the remaining sites. Results of the groundwater analyses from these monitoring wells, presented in the appendices, are used in the report to help identify potential contaminants of concern, if any, at each waste site. The list of actions proposed for each waste site in Christensen and Gordon's 1983 report are summarized, and an update is provided for each site. Planned actions for the future are also outlined

  8. Characterization of the geology, geochemistry, and microbiology of the radio frequency heating demonstration site at the Savannah River Site

    International Nuclear Information System (INIS)

    Eddy Dilek, C.A.; Jarosch, T.R.; Fliermans, C.B.; Looney, B.B.; Parker, W.H.

    1993-08-01

    The overall objective of the Integrated Demonstration Project for the Remediation of Organics at Nonarid Sites at the Savannah River Site (SRS) is to evaluate innovative remediation, characterization, and monitoring systems to facilitate restoration of contaminated sites. The first phase of the demonstration focused on the application and development of in situ air stripping technologies to remediate sediments and groundwater contaminated with volatile organic compounds (VOCs). The second phase focused on the enhancement of the in situ air stripping process by adding selected nutrients to stimulate naturally occurring microorganisms that degrade VOCs. The purpose of the third phase was to evaluate the use of heating technologies [radio frequency (rf) and ohmic heating] to enhance the removal of contamination from clay layers where mass transfer is limited. The objective of this report is to document pretest and post-test data collected in support of the rf heating demonstration. The following data are discussed in this report: (1) a general description of the site including piezometers and sensors installed to monitor the remedial process; (2) stratigraphy, lithology, and a detailed geologic cross section of the study site; (3) tabulations of pretest and post-test moisture and VOC content of the sediments; (4) sampling and analysis procedures for sediment samples; (5) microbial abundance and diversity; (6) three-dimensional images of pretest and post-test contaminant distribution; (7) volumetric calculations

  9. Spent Nuclear Fuel project, project management plan

    International Nuclear Information System (INIS)

    Fuquay, B.J.

    1995-01-01

    The Hanford Spent Nuclear Fuel Project has been established to safely store spent nuclear fuel at the Hanford Site. This Project Management Plan sets forth the management basis for the Spent Nuclear Fuel Project. The plan applies to all fabrication and construction projects, operation of the Spent Nuclear Fuel Project facilities, and necessary engineering and management functions within the scope of the project

  10. Savannah River Site RCRA/CERCLA/NEPA integrated investigation case study

    International Nuclear Information System (INIS)

    Clark, D.R.; Thomas, R.; Wilson, M.P.

    1992-01-01

    The Savannah River Site (SRS) is a US Department of Energy facility placed on the Superfund National Priority List in 1989. Numerous past disposal facilities and contaminated areas are undergoing the integrated regulatory remediation process detailed in the draft SRS Federal Facility Agreement. This paper will discuss the integration of these requirements by highlighting the investigation of the D-Area Burning/Rubble Pits, a typical waste unit at SRS

  11. 2003 Savannah River Site Annual Illness and Injury Surveillance Report, Revised September 2007

    Energy Technology Data Exchange (ETDEWEB)

    U.S. Department of Energy, Office of Health, Safety and Security, Office of Illness and Injury Prevention Programs

    2007-10-05

    Annual Illness and Injury Surveillance Program report for 2003 for the Savannah River Site. DOE is commitment to assuring the health and safety of its workers includes the conduct of epidemiologic surveillance activities that provide an early warning system for health problems among workers. The report monitors illnesses and health conditions that result in an absence of workdays, occupational injuries and illnesses, and disabilities and deaths among current workers.

  12. Discussion about design basis flood of site of research reactors by river

    International Nuclear Information System (INIS)

    Rong Feng; Zhao Jianjun; Du Qiaomin; Zhang Lingyan

    2006-01-01

    This paper presents the well-defined standard in relation to design the basis flood of the sites of research reactors by river. It is based on the concept of some relational standards, analysis of hydrological calculation technology and methods, and analysis of accident dangerous degrees of research reactor, as well as in combination with the engineering practices. The flood preventing standard for research reactors with higher power should be the same with that of the nuclear power plants. (authors)

  13. DOE Research Set-Aside Areas of the Savannah River Site

    International Nuclear Information System (INIS)

    Davis, C.E.; Janecek, L.L.

    1997-01-01

    Designated as the first of seven National Environmental Research Parks (NERPs) by the Atomic Energy Commission (now the Department of Energy), the Savannah River Site (SRS) is an important ecological component of the Southeastern Mixed Forest Ecoregion located along the Savannah River south of Aiken, South Carolina. Integral to the Savannah River Site NERP are the DOE Research Set-Aside Areas. Scattered across the SRS, these thirty tracts of land have been set aside for ecological research and are protected from public access and most routine Site maintenance and forest management activities. Ranging in size from 8.5 acres (3.44 ha) to 7,364 acres (2,980 ha), the thirty Set-Aside Areas total 14,005 acres (5,668 ha) and comprise approximately 7% of the Site's total area. This system of Set-Aside Areas originally was established to represent the major plant communities and habitat types indigenous to the SRS (old-fields, sandhills, upland hardwood, mixed pine/hardwood, bottomland forests, swamp forests, Carolina bays, and fresh water streams and impoundments), as well as to preserve habitats for endangered, threatened, or rare plant and animal populations. Many long-term ecological studies are conducted in the Set-Asides, which also serve as control areas in evaluations of the potential impacts of SRS operations on other regions of the Site. The purpose of this document is to give an historical account of the SRS Set-Aside Program and to provide a descriptive profile of each of the Set-Aside Areas. These descriptions include a narrative for each Area, information on the plant communities and soil types found there, lists of sensitive plants and animals documented from each Area, an account of the ecological research conducted in each Area, locator and resource composition maps, and a list of Site-Use permits and publications associated with each Set-Aside

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

    International Nuclear Information System (INIS)

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

    1993-09-01

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

  15. A review of geophysical investigations at the site of Chalk River Nuclear Laboratories, Ontario

    International Nuclear Information System (INIS)

    Thomas, M.D.; Hayles, J.G.

    1988-01-01

    The site of the Chalk River Nuclear Laboratories was one of the first research areas located on crystalline rocks to be extensively investigated under the Canadian Nuclear Fuel Waste Management Program. A large contribution to meeting the geoscientific objectives of the program has been made using a suite of geophysical techniques. Many of them are standard, though sometimes modified in terms of instrumentation and/or experimental and/or analytical procedures, to meet the particular needs of the waste management program. Relatively new techniques have also been employed. Much of the early evaluation and development of the various techniques took place at the Chalk River site. Standard methods such as gravity, magnetics and seismic sounding have been used to investigate bedrock structure, and the seismic method has also been used to estimate overburden thickness. Standard geophysical borehole logging has been used to obtain in situ estimates of physical properties, to locate fracture zones and to make hole to hole correlations that have helped define local structure. Several standard electrical (e.g. resitivity) and electromagnetic (e.g. VLF-EM) techniques have proven successful in identifying water-filled fractures and faults. Relatively new techniques introduced into the geophysics at Chalk River were: ground probing radar; to investigate overburden; borehole TV and acoustic televiewer and VLF-EM, to locate fractures; studies of seismic tube-waves, well tides and temperature logs, to investigate fracture location and permeability. Most of these methods have been successful and are now routinely employed at other research sites

  16. Nuclear incident monitor criticality alarm instrument for the Savannah River Site: Technical manual

    International Nuclear Information System (INIS)

    Jenkins, J.B.

    1996-01-01

    The Savannah River Site is a Department of Energy facility. The facility stores, processes, and works with fissionable material at a number of locations. Technical standards and US Department of Energy orders, require these locations to be monitored by criticality alarm systems under certain circumstances. The Savannah River Site calls such instruments Nuclear Incident Monitors or NIMs. The Sole purpose of the Nuclear Incident Monitor is to provide an immediate evacuation signal in the case of an accidental criticality in order to minimize personnel exposure to radiation. The new unit is the third generation Nuclear Incident Monitor at the Savannah River Site. The second generation unit was developed in 1979. It was designed to eliminate vacuum-tube circuits, and was the first solid state NIM at SRS. The major design objectives of the second generation NIM were to improve reliability and reduce maintenance costs. Ten prototype units have been built and tested. This report describes the design of the new NIM and the testing that took place to verify its acceptability

  17. Effect of Hydrologic Alteration on the Community Succession of Macrophytes at Xiangyang Site, Hanjiang River, China.

    Science.gov (United States)

    Yang, Na; Zhang, Yehui; Duan, Kai

    2017-01-01

    With the intensification of human activities over the past three decades in China, adverse effects on river ecosystem become more serious especially in the Hanjiang River. Xiangyang site is an important spawn ground for four domestic fishes in the downstream region of Hanjiang River. Based on the field survey results of macrophytes during 1997-2000 and 2013-2014, community succession of aquatic macrophytes at Xiangyang site was evaluated and discussed. Two-key ecologic-related hydrologic characteristics, flow regime and water level, were identified as the main influence factors. The EFC (environmental flow components) parameters were adopted to evaluate the alteration of flow regimes at Xiangyang site during 1941-2013. Evaluation results demonstrate a highly altered flow process after being regulated by reservoir. The flow patterns tend to be an attenuation process with no large floods occurring but a higher monthly low flow. Furthermore, the water level decreased and fluctuation reduced after the dam was built, which caused the decrease of biomass but favored the submerged macrophytes during 1995-2009. However, with the water level increasing after 2010 and gently fluctuating, due to uplift by the hydraulic projects downstream as well as the flow attenuation, the dominant position of submerged macrophytes will be weakened.

  18. Radiological bioconcentration factors for aquatic, terrestrial, and wetland ecosystems at the Savannah River site

    International Nuclear Information System (INIS)

    Friday, G.P.; Cummins, C.L.; Schwartzman, A.L.

    1996-01-01

    Since the early 1950s, the Savannah River Site (SRS) released over 50 radionuclides into the environment while producing nuclear defense materials. These releases directly exposed aquatic and terrestrial biota to ionizing radiation from surface water, soil, and sediment, and also indirectly by the ingestion of items in the food chain. As part of new missions to develop waste management strategies and identify cost-effective environmental restoration options, knowledge concerning the uptake and distribution of these radionuclides is essential. This report compiles and summarizes site-specific bioconcentration factors for selected radionuclides released at SRS

  19. ASME N510 test results for Savannah River Site AACS filter compartments

    Energy Technology Data Exchange (ETDEWEB)

    Paul, J.D.; Punch, T.M. [Westinghouse Savannah River Company, Aiken, SC (United States)

    1995-02-01

    The K-Reactor at the Savannah River Site recently implemented design improvements for the Airborne Activity Confinement System (AACS) by procuring, installing, and testing new Air Cleaning Units, or filter compartments, to ASME AG-11, N509, and N510 requirements. Specifically, these new units provide documentable seismic resistance to a Design Basis Accident earthquake, provide 2 inch adsorber beds with 0.25 second residence time, and meet all AG-1, N509, and N510 requirements for testability and maintainability. This paper presents the results of the Site acceptance testing and discusses an issue associated with sample manifold qualification testing.

  20. 50 years of excellence in science and engineering at the Savannah River Site

    International Nuclear Information System (INIS)

    Phillips, A.G.

    2000-01-01

    This is a collection of papers including abstracts about the celebration of 50 years of excellence in science and engineering at the Savannah River Site. The Symposium Committee invited current and former employees to nominate the innovations to be recognized. Several selection panels of experts in various technical fields reviewed 190 nominations and selected the achievements included in this proceedings. Neither the Symposium Committee nor the selection panels claim that these accomplishments are the best of the best. Instead, they believe that they typify the outstanding quality of science and engineering at the Site during its first half-century

  1. Upgrade of the Department of Energy's Savannah River Site's reactor operations and maintenance procedures

    International Nuclear Information System (INIS)

    Walsh, T.E.

    1991-01-01

    This paper describes the program in progress at the Savannah River Site (SRS) to upgrade the existing reactor operating and maintenance procedures to current commercial nuclear industry standards. In order to meet this goal, the following elements were established: administrative procedures to govern the upgrade process, tracking system to provide status and accountability; and procedure writing guides. The goal is to establish a benchmark of excellence by which other Department of Energy (DOE) sites will measure themselves. The above three elements are addressed in detail in this paper

  2. Radiological bioconcentration factors for aquatic, terrestrial, and wetland ecosystems at the Savannah River site

    Energy Technology Data Exchange (ETDEWEB)

    Friday, G.P.; Cummins, C.L.; Schwartzman, A.L.

    1996-12-31

    Since the early 1950s, the Savannah River Site (SRS) released over 50 radionuclides into the environment while producing nuclear defense materials. These releases directly exposed aquatic and terrestrial biota to ionizing radiation from surface water, soil, and sediment, and also indirectly by the ingestion of items in the food chain. As part of new missions to develop waste management strategies and identify cost-effective environmental restoration options, knowledge concerning the uptake and distribution of these radionuclides is essential. This report compiles and summarizes site-specific bioconcentration factors for selected radionuclides released at SRS.

  3. The operational and logistic experience on transportation of Brazilian spent fuel to USA

    International Nuclear Information System (INIS)

    Maiorino, Jose Rubens; Frajndlich, Roberto; Mandlae, Martin; Bensberg, Werner; Renger, August; Grabow, Karsten

    2000-01-01

    A shipment of 127 spent MTR fuel assemblies was made from IEA-R1 Research Reactor located at the Instituto de Pesquisas Energeticas e Nucleares (IPEN-CNEN/SP), Sao Paulo, Brazil to Savannah River Site Laboratory in the United States. This paper describes the operational and logistic experience on this transportation made by IPEN staff and the Consortium NCS/GNS. (author)

  4. Feasibility determination of low head hydroelectric power development at existing sites: Mousam River Project

    Energy Technology Data Exchange (ETDEWEB)

    1979-06-01

    The technical and economic feasibility of low head hydroelectric power development at existing sites along the Mousam River in southeastern Maine was studied. The following areas were investigated: determination of available energy; development of restoration concepts; environmental studies; historical and archeological studies; assessment of civil construction requirements; geotechnical and geologic assessment of existing dams; assessment of turbine alternatives; assessment of generator and utility interface alternatives; economic analysis; and restoration concept evaluation and selection. The results of the hydropower evaluation showed that: of the seven sites evaluated, only four can be considered economically feasible for refurbishment at this time; the use of used and/or rebuilt equipment is more economically attractive than new equipment; the cost of equipment at each site was of the same order as the cost of the dam reconstruction; and the cost of fuel prices will be the determining feature of whether the sites should be reconstructed.

  5. Pesticides in surface water measured at select sites in the Sacramento River basin, California, 1996-1998

    Science.gov (United States)

    Domagalski, Joseph L.

    2000-01-01

    Pesticides were measured in one urban stream, one agricultural stream, one site on the Sacramento River, and one large flood control channel over a period of 18 months during 1996-1998. All sites were located within the Sacramento River Basin of California. Measurements were made on 83 pesticides or pesticide transformation products by either gas chromatography/mass spectrometry or by high performance liquid chromatography with ultraviolet light spectrometry. Some pesticides were detected frequently at the agricultural stream and downstream in the Sacramento River and at the flood control channel of the Sacramento River. These were pesticides related to rice farming (molinate, carbofuran, thiobencarb, and bentazon); herbicides used both agriculturally or for roadside maintenance (diuron, simazine, and metolachlor); or insecticides used on orchards and row corps (diazinon and chlorpyrifos). No pesticide concen-trations above enforceable water quality criteria were measured at either the agricultural site or the Sacramento River sites. In contrast to the agricul-tural site, insecticides used for household, lawn, or garden maintenance were the most frequently detected pesticides at the urban site. Diazinon, an organophosphate insecticide, exceeded recom-mended criteria for the protection of aquatic life, and the diazinon levels were frequently above known toxic levels for certain zooplankton species at the urban site. Because of the low discharge of the urban stream, pesticide concentrations were greatly diluted upon mixing with Sacramento River water.

  6. Savannah River Site nuclear materials management plan FY 2017-2031

    Energy Technology Data Exchange (ETDEWEB)

    Magoulas, V. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-06-22

    The purpose of the Nuclear Materials Management Plan (herein referred to as “this Plan”) is to integrate and document the activities required to disposition the legacy and/or surplus Enriched Uranium (EU) and Plutonium (Pu) and other nuclear materials already stored or anticipated to be received by facilities at the Department of Energy (DOE) Savannah River Site (SRS) as well as the activities to support the DOE Tritium mission. It establishes a planning basis for EU and Pu processing operations in Environmental Management Operations (EMO) facilities through the end of their program missions and for the tritium through the National Nuclear Security Administration (NNSA) Defense Programs (DP) facilities. Its development is a joint effort among the Department of Energy - Savannah River (DOE-SR), DOE – Environmental Management (EM), NNSA Office of Material Management and Minimization (M3), NNSA Savannah River Field Office (SRFO), and the Management and Operations (M&O) contractor, Savannah River Nuclear Solutions, LLC (SRNS). Life-cycle program planning for Nuclear Materials Stabilization and Disposition and the Tritium Enterprise may use this Plan as a basis for the development of the nuclear materials disposition scope and schedule. This Plan assumes full funding to accomplish the required project and operations activities. It is recognized that some aspects of this Plan are pre decisional with regard to National Environmental Policy Act (NEPA); in such cases new NEPA actions will be required.

  7. Demonstration of innovative monitoring technologies at the Savannah River Integrated Demonstration Site

    Energy Technology Data Exchange (ETDEWEB)

    Rossabi, J. [Westinghouse Savannah River Co., Aiken, SC (United States); Jenkins, R.A.; Wise, M.B. [Oak Ridge National Lab., TN (United States)] [and others

    1993-12-31

    The Department of Energy`s Office of Technology Development initiated an Integrated Demonstration Program at the Savannah River Site in 1989. The objective of this program is to develop, demonstrate, and evaluate innovative technologies that can improve present-day environmental restoration methods. The Integrated Demonstration Program at SRS is entitled ``Cleanup of Organics in Soils and Groundwater at Non-Arid Sites.`` New technologies in the areas of drilling, characterization, monitoring, and remediation are being demonstrated and evaluated for their technical performance and cost effectiveness in comparison with baseline technologies. Present site characterization and monitoring methods are costly, time-consuming, overly invasive, and often imprecise. Better technologies are required to accurately describe the subsurface geophysical and geochemical features of a site and the nature and extent of contamination. More efficient, nonintrusive characterization and monitoring techniques are necessary for understanding and predicting subsurface transport. More reliable procedures are also needed for interpreting monitoring and characterization data. Site characterization and monitoring are key elements in preventing, identifying, and restoring contaminated sites. The remediation of a site cannot be determined without characterization data, and monitoring may be required for 30 years after site closure.

  8. Demonstration of innovative monitoring technologies at the Savannah River Integrated Demonstration Site

    International Nuclear Information System (INIS)

    Rossabi, J.; Jenkins, R.A.; Wise, M.B.

    1993-01-01

    The Department of Energy's Office of Technology Development initiated an Integrated Demonstration Program at the Savannah River Site in 1989. The objective of this program is to develop, demonstrate, and evaluate innovative technologies that can improve present-day environmental restoration methods. The Integrated Demonstration Program at SRS is entitled ''Cleanup of Organics in Soils and Groundwater at Non-Arid Sites.'' New technologies in the areas of drilling, characterization, monitoring, and remediation are being demonstrated and evaluated for their technical performance and cost effectiveness in comparison with baseline technologies. Present site characterization and monitoring methods are costly, time-consuming, overly invasive, and often imprecise. Better technologies are required to accurately describe the subsurface geophysical and geochemical features of a site and the nature and extent of contamination. More efficient, nonintrusive characterization and monitoring techniques are necessary for understanding and predicting subsurface transport. More reliable procedures are also needed for interpreting monitoring and characterization data. Site characterization and monitoring are key elements in preventing, identifying, and restoring contaminated sites. The remediation of a site cannot be determined without characterization data, and monitoring may be required for 30 years after site closure

  9. Non-Operational Property Evaluation for the Hanford Site River Corridor - 12409

    Energy Technology Data Exchange (ETDEWEB)

    Lowe, John [CH2M HILL, Richland, Washington 99354 (United States); Aly, Alaa [CH2M HILL Plateau Remediation Company and INTERA Incorporated, Richland, Washington 99354 (United States)

    2012-07-01

    The Hanford Site River Corridor consists of the former reactor areas of the 100 Areas and the former industrial (fuel processing) area in the 300 Area. Most of the waste sites are located close to the decommissioned reactors or former industrial facilities along the Columbia River. Most of the surface area of the River Corridor consists of land with little or no subsurface infrastructure or indication of past or present releases of hazardous constituents, and is referred to as non-operational property or non-operational area. Multiple lines of evidence have been developed to assess identified fate and transport mechanisms and to evaluate the potential magnitude and significance of waste site-related contaminants in the non-operational area. Predictive modeling was used for determining the likelihood of locating waste sites and evaluating the distribution of radionuclides in soil based on available soil concentration data and aerial radiological surveys. The results of this evaluation indicated: 1) With the exception of stack emissions, transport pathways associated with waste site contaminants are unlikely to result in dispersion of contaminants in soil away from operational areas, 2) Stack emissions that may have been associated with Hanford Site operations generally emitted short-lived and/or gaseous radionuclides, and (3) the likelihood of detecting elevated radionuclide concentrations or other waste sites in non-operational area soils is very small. The overall conclusions from the NPE evaluation of the River Corridor are: - With the exception of stack emissions to the air, transport pathways associated with waste site contaminants are unlikely to result in dispersion of contaminants in soil away from operational areas. While pathways such as windblown dust, overland transport and biointrusion have the potential for dispersing waste site contaminants, the resulting transport is unlikely to result in substantial contamination in non-operational areas. - Stack

  10. Thermal and physical property determination for IONSIV/256 IE-911 crystalline silicotitanate and Savannah River Site waste simulant solutions

    International Nuclear Information System (INIS)

    Canada, C.C.

    1999-01-01

    This document describes physical and thermophysical property determinations that were made in order to resolve questions associated with the decontamination of Savannah River Site waste streams using ion exchange on crystalline silicotitanate

  11. Ecosystem description of a drainage area - a strategy in biosphere descriptions during site investigations for a repository of spent nuclear fuel

    International Nuclear Information System (INIS)

    Lindborg, T.; Lofgren, A.

    2004-01-01

    During the next few years the Swedish Nuclear Fuel and Waste Management Co. (SKB) performs site investigations at two sites in Sweden for a future repository of spent nuclear fuel. Novel methods based on systems and landscape ecology are developed to understand and model the radionuclide flow in the biosphere using site specific data for a safety assessment. This work describes the strategy for development of a descriptive ecosystem model for the surface ecosystem. The site description is needed to: a) perform a safety assessment that describes and analyzes different scenarios for radionuclide releases into the ecosystem and possible pathways for dispersal or accumulation radionuclides in the ecosystem, b) detect changes caused by the construction of a repository, c) establish a baseline for detecting long-term effects of the repository. The description adopts a site-specific approach focusing on the quantification of the properties that will constitute the descriptive model. The aim is also to present the methodology for determining the properties, to describe the development of the framework for the descriptive ecosystem models by integrating use of different properties, and finally, to present vital data from other site descriptive models such as those for geology or hydrogeology. The safety assessment will use an approach, among other methods, where transport and accumulation of radionuclides will be modelled by quantifying biogeochemical pathways of matter. The descriptive ecosystem model applied to the site was therefore built to describe and quantify processes affecting i.e. turnover of matter in a drainage area. The conclusions from applying this approach was that by have estimating the flow of matter the ecological and physical constrains on the system reduces the potential variations in outcome of future states of the ecosystem and thus also reduces the uncertainties in estimating radionuclide flow and consequences to humans and the environment. (author)

  12. Effects of post-disposal gas generation in a repository for spent fuel, high-level waste and long-lived intermediate level waste sited in opalinus clay

    International Nuclear Information System (INIS)

    Johnson, L.; Marschall, P.; Zuidema, P.; Gribi, P.

    2004-07-01

    This comprehensive report issued by the Swiss National Cooperative for the Disposal of Radioactive Waste NAGRA takes a look at post-disposal gas generation in a repository for spent fuel and highly radioactive wastes in Opalinus clay strata. This study provides a comprehensive treatment of the issue of gas generation in a repository for spent fuel (SF), vitrified high-level waste (HLW) and long-lived intermediate-level waste (ILW), sited in the Opalinus clay of the Zuercher Weinland in northern Switzerland. The issue of how gas generation in and transport from waste repositories may influence disposal system performance has been under study for many years, both at Nagra and internationally. The report consists of three main parts: (i) A synthesis of basic information on the host rock and on details of repository construction; (ii) A discussion on gas transport characteristics of the engineered barrier system and the geosphere; (iii) A discussion on the effects of gas on system performance, based on the available information on gas generation, gas transport properties and gas pathways provided in the previous parts of the report. Simplified model calculations based on a mass balance approach for the gas generated within the repository are presented and discussed

  13. Loads imposed on dual purpose casks in German on-site-storage facilities for long term intermediate storage of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Wetzel, N.; Rabe, O. [TUeV NORD EnSys Hannover GmbH und Co. KG, Hanover (Germany)

    2004-07-01

    In accordance with recent changes of the atomic energy act and in order to secure reliable removal of spent fuel from the nuclear power plants' fuel storage ponds the German utilities filed license applications for a total of 12 onsite- storage facilities for spent fuel assemblies. By the end of 2003 the last of these storage facilities were licensed and are currently under construction. The first on-site-storage facility of that line became operational in late 2002. There are several design lines of storage facilities with different handling procedures or possible accident conditions. Short term interim storage facilities for a few casks are characterized by individual concrete hoods shielding the casks in horizontal position whereas long term intermediate storage facilities currently erected for large numbers of casks typically feature a condensed pattern of casks stored in upright position and massive structures of reinforced concrete. TUeV Hannover/Sachsen-Anhalt e. V. (now TUeV NORD EnSys Hannover GmbH and Co. KG) has been contracted as a body of independent experts for the assessment of all related safety requirements on behalf of the national licensing authority, the federal office for radiation protection (BfS).

  14. Local decision-making facing issues of national interest experiences from the swedish siting process for a spent nuclear fuel repository

    International Nuclear Information System (INIS)

    Soderberg, O.

    1998-01-01

    It is common knowledge that there are difficulties in convincing the general public and their democratically elected representatives that final disposal of spent nuclear fuel can be made in safe way. Special problems for the decision-makers are created by the demands put on today's generations to make a responsible risk assessment in a area with genuine uncertainties and characterised by any expressions of lack of confidence in social institutions. The current Swedish process for siting a deep repository for spent nuclear fuel has evolved during a period of many years, through inputs by the industry, Government, regulatory authorities and concerned municipalities. It is clear that the nuclear industry, represented by the Swedish Nuclear Fuel and Waste Management CO (SKB), has the full responsibility to find a solution to the waste management problem and to implement the solution - and to for this under the supervision of Government and regulating authorities. But, given the strong tradition of local self-government, the concerned municipalities, the local population in this process. this is simply the following fact: For people who have engaged themselves in local politics - and are prepared to take their responsibility for the well-being and development of their local community - the issue of a possible nuclear repository in the neighbourhood is difficult to handle. A relevant question is: Why should the nation as a whole expect these locally elected representatives to feel a responsibility for an issue of national importance? (author)

  15. Loads imposed on dual purpose casks in German on-site-storage facilities for long term intermediate storage of spent nuclear fuel

    International Nuclear Information System (INIS)

    Wetzel, N.; Rabe, O.

    2004-01-01

    In accordance with recent changes of the atomic energy act and in order to secure reliable removal of spent fuel from the nuclear power plants' fuel storage ponds the German utilities filed license applications for a total of 12 onsite- storage facilities for spent fuel assemblies. By the end of 2003 the last of these storage facilities were licensed and are currently under construction. The first on-site-storage facility of that line became operational in late 2002. There are several design lines of storage facilities with different handling procedures or possible accident conditions. Short term interim storage facilities for a few casks are characterized by individual concrete hoods shielding the casks in horizontal position whereas long term intermediate storage facilities currently erected for large numbers of casks typically feature a condensed pattern of casks stored in upright position and massive structures of reinforced concrete. TUeV Hannover/Sachsen-Anhalt e. V. (now TUeV NORD EnSys Hannover GmbH and Co. KG) has been contracted as a body of independent experts for the assessment of all related safety requirements on behalf of the national licensing authority, the federal office for radiation protection (BfS)

  16. Final disposal of spent fuel in the Finnish bedrock. Scope and requirements for site-specific safety analysis; Kaeytetyn polttoaineen loppusijoitus Suomen kallioperaeaen. Paikkakohtaisen turvallisuusanalyysin edellytykset ja mahdollisuudet

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-01

    The report is a summary of the research conducted in the period 1993 to 1996 into safety of spent fuel final disposal. The principal goal of the research in this period, as set in 1993, was to develop a strategy for site-specific safety analysis. At the same time efforts were to be continued to gather data and validate the technical approach for the analysis. The work aimed at having the data needed for the analysis available at the end of year 1998. A safety assessment update, TILA-96, prepared by VTT Energy, is published as a separate report. The assessment is based on the TVO-92 safety analysis, but takes into account the knowledge acquired after 1992 on safety aspects of the disposal system and the data gathered from the site investigations made by TVO and from the beginning of 1996, by Posiva. Since the site investigations are still ongoing and much of the data gathered still pending interpretation, only limited amount of new site-specific information has been available for the present assessment. (172 refs.).

  17. Spent fuel receipt and lag storage facility for the spent fuel handling and packaging program

    International Nuclear Information System (INIS)

    Black, J.E.; King, F.D.

    1979-01-01

    Savannah River Laboratory (SRL) is participating in the Spent Fuel Handling and Packaging Program for retrievable, near-surface storage of spent light water reactor (LWR) fuel. One of SRL's responsibilities is to provide a technical description of the wet fuel receipt and lag storage part of the Spent Fuel Handling and Packaging (SFHP) facility. This document is the required technical description

  18. Applications of high transition temperature superconductors at the Savannah River Site

    International Nuclear Information System (INIS)

    Payne, J.E.; Payne, L.L.

    1993-04-01

    The first year of the research program involved evaluating the applications of high transition temperature superconducting devices at the Savannah River Site and initiating the development of high T c circuit elements that might be of use in programs at the site. Although during the course of this year there were major changes in the direction of and areas of interest at the Savannah River Site, it has been possible to accomplish the first year goals. The technology required to produce a useful nitrogen temperature SQUID for applications such as those that might be encountered at the site has developed more rapidly than was anticipated. This has made it possible to begin the initial studies with a high T c device as opposed to starting with the helium temperature SQUID. This will have an important impact on the outcome of the project by allowing for a more complete evaluation of a device that can be used in an industrial situation. The goals of the first year of the project are listed and will be addressed in this report

  19. Independent technical review of Savannah River Site Defense Waste Processing Facility technical issues

    International Nuclear Information System (INIS)

    1992-07-01

    The Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) will vitrify high-level radioactive waste that is presently stored as liquid, salt-cake, and sludge in 51 waste-storage tanks. Construction of the DWPF began in 1984, and the Westinghouse Savannah Company (WSRC) considers the plant to be 100% turned over from construction and 91% complete. Cold-chemical runs are scheduled to begin in November 1992, and hot start up is projected for June 1994. It is estimated that the plant lifetime must exceed 15 years to complete the vitrification of the current, high-level tank waste. In a memo to the Assistant Secretary for Defense Programs (DP-1), the Assistant Secretary for Environmental Restoration and Waste management (EM-1) established the need for an Independent Technical Review (ITR), or the Red Team, to ''review process technology issues preventing start up of the DWPF.'' This report documents the findings of an Independent Technical Review (ITR) conducted by the Department of Energy (DOE), Office of Environmental Restoration and Waste Management (EM), at the request of the Assistant Secretary for Environmental Restoration and Waste Management, of specified aspects of Defense Waste Process Facility (DWPF) process technology. Information for the assessment was drawn from documents provided to the ITR Team by the Westinghouse Savannah River Company (WSRC), and presentations, discussions, interviews, and tours held at the Savannah River Site (SRS) during the weeks of February and March 9, 1992

  20. Specification of requirements to get a license for an Independent Spent Fuel Dry Storage Installation (ISFSI) at the site of the NPP-LV

    International Nuclear Information System (INIS)

    Serrano R, M. L.

    2015-09-01

    This article describes some of the work done in the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) to define specifically the requirements that the Federal Electricity Commission (CFE) shall meet to submit for consideration of CNSNS an operation request of an Independent Spent Fuel Dry Storage Installation (ISFSI). The project of a facility of this type arose from the need to provide storage capacity for spent nuclear fuel in the nuclear power plant of Laguna Verde (NPP-LV) and to continue the operation at the same facility in a safe manner. The licensing of these facilities in the United States of America has two modes: specific license or general license. The characteristics of these licenses are described in this article. However, in Mexico the existing national legislation is not designed for such license types, in fact there is a lack of standards or regulations in this regard. The regulatory law of Article 27 of the Constitution in the nuclear matter, only generally establishes that this type of facility requires an authorization from the Ministry of Energy. For this reason and because there is not a national legislation, was necessary to use the legislation that provides the Nuclear Regulatory Commission of USA, the US NRC. However, it cannot be applied as is established, so was necessary that the CNSNS analyze one by one the requirements of both types of license and determine what would be required to NPP-LV to submit its operating license of ISFSI. The American regulatory applicable to an ISFSI, the 10-Cfr-72 of the US NRC, establishes the requirements for both types of licenses. Chapter 10-Cfr was analyzed in all its clauses and coupled to the laws, regulations and standards as well as to the requirements established by CNSNS, all associated with a store spent fuel on site; the respective certification of containers for spent fuel dry storage was not included in this article, even though the CNSNS also performed that activity under the