Sample records for miamisburg closure project

  1. INDEPENDENT VERIFICATION SURVEY REPORT FOR THE OPERABLE UNIT-1 LANDFILL TRENCHES, MIAMISBURG CLOSURE PROJECT

    SciTech Connect (OSTI)

    W.C. Adams

    2010-05-24T23:59:59.000Z

    INDEPENDENT VERIFICATION SURVEY REPORT FOR THE OPERABLE UNIT-1 LANDFILL TRENCHES, MIAMISBURG CLOSURE PROJECT, MIAMISBURG, OHIO DCN: 0468-SR-02-0

  2. INDEPENDENT VERIFICATION SURVEY REPORT OPERABLE UNIT-1 LANDFILL TRENCHES, MIAMISBURG CLOSURE PROJECT

    SciTech Connect (OSTI)

    W.C. Adams

    2010-07-21T23:59:59.000Z

    INDEPENDENT VERIFICATION SURVEY REPORT FOR THE OPERABLE UNIT-1 LANDFILL TRENCHES, MIAMISBURG CLOSURE PROJECT, MIAMISBURG, OHIO DCN: 0468-SR-03-0

  3. Miamisburg Environmental Management Project Archived Soil & Groundwate...

    Office of Environmental Management (EM)

    Miamisburg Environmental Management Project Archived Soil & Groundwater Master Reports Miamisburg Environmental Management Project Archived Soil & Groundwater Master Reports...

  4. Miamisburg Environmental Management Project Archived Soil & Groundwater

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2 OPAM Flash2011-12Approvedof6,Projects38,R&D Methane

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

    SciTech Connect (OSTI)

    Weaver, P.

    2008-03-17T23:59:59.000Z

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

  6. EA-1239: Disposition of Mound Plant's South Property, Miamisburg, Ohio

    Broader source: Energy.gov [DOE]

    DOE prepared an EA for the proposed title transfer of 123 acres of land referred to as the “South Property” at the Miamisburg Environmental Management Project Mound Plant in Miamisburg, Ohio.

  7. Independent Verification Survey Report for the Offsite Portion of the Potential Release Site-7 Abandoned Sanitary Line, Miamisburg Closure Project, Miamisburg, Ohio

    SciTech Connect (OSTI)

    P.C. Weaver

    2008-08-15T23:59:59.000Z

    The ORISE objective was to confirm that the remedial action process implemented by the contractor was in accordance with the PRS-7 Work Package. Following removal of the sanitary line, the soil beneath the line would be sampled to determine if remediation was required (ARC 2007a).

  8. EIS-0014: Mound Facility, Miamisburg, Ohio

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy prepared this EIS to assess the environmental implications of its continuing and future programs at the Mound Facility (formerly designated Mound Laboratory), located in Miamisburg, Ohio.

  9. Tools for Closure Project and Contract Management: Development of the Rocky Flats Integrated Closure Project Baseline

    SciTech Connect (OSTI)

    Gelles, C. M.; Sheppard, F. R.

    2002-02-26T23:59:59.000Z

    This paper details the development of the Rocky Flats Integrated Closure Project Baseline - an innovative project management effort undertaken to ensure proactive management of the Rocky Flats Closure Contract in support of the Department's goal for achieving the safe closure of the Rocky Flats Environmental Technology Site (RFETS) in December 2006. The accelerated closure of RFETS is one of the most prominent projects within the Department of Energy (DOE) Environmental Management program. As the first major former weapons plant to be remediated and closed, it is a first-of-kind effort requiring the resolution of multiple complex technical and institutional challenges. Most significantly, the closure of RFETS is dependent upon the shipment of all special nuclear material and wastes to other DOE sites. The Department is actively working to strengthen project management across programs, and there is increasing external interest in this progress. The development of the Rocky Flats Integrated Closure Project Baseline represents a groundbreaking and cooperative effort to formalize the management of such a complex project across multiple sites and organizations. It is original in both scope and process, however it provides a useful precedent for the other ongoing project management efforts within the Environmental Management program.

  10. Environmental Assessment for the Accelerated Tank Closure Demonstration Project

    SciTech Connect (OSTI)

    N /A

    2003-06-16T23:59:59.000Z

    The U.S. Department of Energy's (DOE) Office of River Protection (ORP) needs to collect engineering and technical information on (1) the physical response and behavior of a Phase I grout fill in an actual tank, (2) field deployment of grout production equipment and (3) the conduct of component closure activities for single-shell tank (SST) 241-C-106 (C-106). Activities associated with this Accelerated Tank Closure Demonstration (ATCD) project include placement of grout in C-106 following retrieval, and associated component closure activities. The activities will provide information that will be used in determining future closure actions for the remaining SSTs and tank farms at the Hanford Site. This information may also support preparation of the Environmental Impact Statement (EIS) for Retrieval, Treatment, and Disposal of Tank Waste and Closure of Single-Shell Tanks at the Hanford Site, Richland, Washington (Tank Closure EIS). Information will be obtained from the various activities associated with the component closure activities for C-106 located in the 241-C tank farm (C tank farm) under the ''Resource Conservation and Recovery Act of 1976'' (RCRA) and the Hanford Federal Facility Agreement and Consent Order (HFFACO) (Ecology et al. 1989). The impacts of retrieving waste from C-106 are bounded by the analysis in the Tank Waste Remediation System (TWRS) EIS (DOE/EIS-0189), hereinafter referred to as the TWRS EIS. DOE has conducted and continues to conduct retrieval activities at C-106 in preparation for the ATCD Project. For major federal actions significantly affecting the quality of the human environment, the ''National Environmental Policy Act of 1969'' (NEPA) requires that federal agencies evaluate the environmental effects of their proposed and alternative actions before making decisions to take action. The President's Council on Environmental Quality (CEQ) has developed regulations for implementing NEPA. These regulations are found in Title 40 of the Code of Federal Regulations (CFR), Parts 1500-1508. They require the preparation of an Environmental Assessment (EA) that includes an evaluation of alternative means of addressing the problem and a discussion of the potential environmental impacts of a proposed federal action. An EA provides analysis to determine whether an EIS or a finding of no significant impact should be prepared.

  11. Miamisburg Mound Community Improvement Corp | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere I Geothermal Pwer Plant JumpMarysville, Ohio:Menomonee| Open Energy InformationGardens,Springs,Miamisburg

  12. Voluntary Protection Program Onsite Review, Plutonium Finishing Plant Closure Project- May 2007

    Broader source: Energy.gov [DOE]

    Evaluation to determine whether Plutonium Finishing Plant Closure Project is continuing to perform at a level deserving DOE-VPP Star recognition.

  13. STATUS OF MECHANICAL SLUDGE REMOVAL AND COOLING COILS CLOSURE AT THE SAVANNAH RIVER SITE - F TANK FARM CLOSURE PROJECT - 9225

    SciTech Connect (OSTI)

    Jolly, R

    2009-01-06T23:59:59.000Z

    The Savannah River Site F-Tank Farm Closure project has successfully performed Mechanical Sludge Removal using the Waste on Wheels (WOW) system within two of its storage tanks. The Waste on Wheels (WOW) system is designed to be relatively mobile with the ability for many components to be redeployed to multiple tanks. It is primarily comprised of Submersible Mixer Pumps (SMPs), Submersible Transfer Pumps (STPs), and a mobile control room with a control panel and variable speed drives. These tanks, designated as Tank 6 and Tank 5 respectively, are Type I waste tanks located in F-Tank Farm (FTF) with a capacity of 2839 cubic meters (750,000 gallons) each. In addition, Type I tanks have 34 vertically oriented cooling coils and two horizontal cooling coil circuits along the tank floor. DOE intends to remove from service and operationally close Tank 5 and Tank 6 and other HLW tanks that do not meet current containment standards. After obtaining regulatory approval, the tanks and cooling coils will be isolated and filled with grout for long term stabilization. Mechanical Sludge Removal of the remaining sludge waste within Tank 6 removed {approx} 75% of the original 25,000 gallons in August 2007. Utilizing lessons learned from Tank 6, Tank 5 Mechanical Sludge Removal completed removal of {approx} 90% of the original 125 cubic meters (33,000 gallons) of sludge material in May 2008. The successful removal of sludge material meets the requirement of approximately 19 to 28 cubic meters (5,000 to 7,500 gallons) remaining prior to the Chemical Cleaning process. The Chemical Cleaning Process will utilize 8 wt% oxalic acid to dissolve the remaining sludge heel. The flow sheet for Chemical Cleaning planned a 20:1 volume ratio of acid to sludge for the first strike with mixing provided by the submersible mixer pumps. The subsequent strikes will utilize a 13:1 volume ratio of acid to sludge with no mixing. The results of the Chemical Cleaning Process are detailed in the 'Status of Chemical Cleaning of Waste Tanks at the Savannah River Site--F Tank Farm Closure Project--Abstract 9114'. To support Tank 5 and Tank 6 cooling coil closure, cooling coil isolation and full scale cooling coil grout testing was completed to develop a strategy for grouting the horizontal and vertical cooling coils. This paper describes in detail the performance of the Mechanical Sludge Removal activities and SMP operational strategies within Tank 5. In addition, it will discuss the current status of Tank 5 & 6 cooling coil isolation activities and the results from the cooling coil grout fill tests.

  14. How the Lean Management System is Working on a Closure Project - 13242

    SciTech Connect (OSTI)

    Mowery, Carol [Washington Closure Hanford, 2620 Fermi, Richland, Washington, 99354 (United States)] [Washington Closure Hanford, 2620 Fermi, Richland, Washington, 99354 (United States)

    2013-07-01T23:59:59.000Z

    Washington Closure Hanford, LLC (WCH) manages the River Corridor Closure Project (RCCP), a 10-year contract, in which WCH will clean up 220 mi{sup 2} of contaminated land at the Hanford Site in Richland, Washington. Strategic planning sessions in 2009 identified key performance areas that were essential to closure and in which focused change could result in dramatic performance improvement. Lean Management Systems (Lean) was selected as the methodology to achieve the desired results. The Lean Process is built upon the fundamentals of the power of respect for people and the practice of continuous process improvement. Lean uses week-long, focused sessions that teach a selected team the techniques to recognize waste within their own work processes, propose potential solutions, and then conduct experiments during the week to test their solutions. In 2011, the Lean process was implemented in the Waste Operations organization. From there it was expanded to closure documents, field remediation, and decommissioning and demolition. WCH identified the following Lean focus areas: 1) closure document processes that required extensive internal preparation, and lengthy external review and approval cycles; 2) allocation of limited transportation and waste disposal resources to meet aggressive remediation schedules; 3) effective start-of-the-day routines in field operations; 4) improved excavation and load-out processes; and 5) approaches to strengthen safety culture and support disciplined operations. Since the introduction of Lean, RCCP has realized many successes and also gained some unexpected benefits. (authors)

  15. HANFORD SITE RIVER PROTECTION PROJECT (RPP) TANK FARM CLOSURE

    SciTech Connect (OSTI)

    JARAYSI, M.N.; SMITH, Z.; QUINTERO, R.; BURANDT, M.B.; HEWITT, W.

    2006-01-30T23:59:59.000Z

    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 retrieval of the waste is under way and is being conducted to achieve the completion criteria established in the Hanford Federal Facility Agreement and Consent Order.

  16. HIGH LEVEL WASTE TANK CLOSURE PROJECT AT THE IDAHO NATIONAL ENGINEERING AND ENVIRONMENTAL LABORATORY

    SciTech Connect (OSTI)

    Quigley, K.D.; Wessman, D

    2003-02-27T23:59:59.000Z

    The Department of Energy, Idaho Operations Office (DOE-ID) is in the process of closing two underground high-level waste (HLW) storage tanks at the Idaho National Engineering and Environmental Laboratory (INEEL) to meet Resource Conservation and Recovery Act (RCRA) regulations and Department of Energy orders. Closure of these two tanks is scheduled for 2004 as the first phase in closure of the eleven 1.14 million liter (300,000 gallon) tanks currently in service at the Idaho Nuclear Technology and Engineering Center (INTEC). The INTEC Tank Farm Facility (TFF) Closure sequence consists of multiple steps to be accomplished through the existing tank riser access points. Currently, the tank risers contain steam and process waste lines associated with the steam jets, corrosion coupons, and liquid level indicators. As necessary, this equipment will be removed from the risers to allow adequate space for closure equipment and activities. The basic tank closure sequence is as follows: Empty the tank to the residual heel using the existing jets; Video and sample the heel; Replace steam jets with new jet at a lower position in the tank, and remove additional material; Flush tank, piping and secondary containment with demineralized water; Video and sample the heel; Evaluate decontamination effectiveness; Displace the residual heel with multiple placements of grout; and Grout piping, vaults and remaining tank volume. Design, development, and deployment of a remotely operated tank cleaning system were completed in June 2002. The system incorporates many commercially available components, which have been adapted for application in cleaning high-level waste tanks. The system is cost-effective since it also utilizes existing waste transfer technology (steam jets), to remove tank heel solids from the tank bottoms during the cleaning operations. Remotely operated directional spray nozzles, automatic rotating wash balls, video monitoring equipment, decontamination spray-rings, and tank -specific access interface devices have been integrated to provide a system that efficiently cleans tank walls and heel solids in an acidic, radioactive environment. Through the deployment of the tank cleaning system, the INEEL High Level Waste Program has cleaned tanks to meet RCRA clean closure standards and DOE closure performance measures. Design, development, and testing of tank grouting delivery equipment were completed in October 2002. The system incorporates lessons learned from closures at other DOE facilities. The grout will be used to displace the tank residuals remaining after the cleaning is complete. To maximize heel displacement to the discharge pump, grout was placed in a sequence of five positions utilizing two riser locations. The project is evaluating the use of six positions to optimize the residuals removed. After the heel has been removed and the residuals stabilized, the tank, piping, and secondary containment will be grouted.

  17. The River Corridor Closure Contract How Washington Closure Hanford is Closing A Unique Department of Energy Project - 12425

    SciTech Connect (OSTI)

    Feist, E.T. [Washington Closure Hanford, 2620 Fermi Avenue, Richland, WA 99354 (United States)

    2012-07-01T23:59:59.000Z

    Cleanup of the Hanford River Corridor has been one of Hanford Site's top priorities since the early 1990's. This urgency is due to the proximity of hundreds of waste sites to the Columbia River and the groundwater that continues to threaten the Columbia River. In April 2005, the U.S. Department of Energy, Richland Operations Office (DOE-RL) awarded the Hanford River Corridor Closure Contract (RCCC), a cost-plus incentive-fee closure contract with a 2015 end date and first of its kind at Hanford Site, to Washington Closure Hanford (WCH), a limited-liability company owned by URS, Bechtel National, and CH2M HILL. WCH is a single-purpose company whose goal is to safely, compliantly, and efficiently accelerate cleanup in the Hanford River Corridor and reduce or eliminate future obligations to DOE-RL for maintaining long-term stewardship over the site. Accelerated performance of the work-scope while keeping a perspective on contract completion presents challenges that require proactive strategies to support the remaining work-scope through the end of the RCCC. This paper outlines the processes to address the challenges of completing work-scope while planning for contract termination. WCH is responsible for cleanup of the River Corridor 569.8 km{sup 2} (220 mi{sup 2}) of the 1,517.7 km{sup 2} (586 mi{sup 2}) Hanford Site's footprint reduction. At the end of calendar year 2011, WCH's closure implementation is well underway. Fieldwork is complete in three of the largest areas within the RCCC scope (Segments 1, 2, and 3), approximately 44.5% of the River Corridor (Figure 3). Working together, DOE-RL and WCH are in the process of completing the 'paper work' that will document the completion of the work-scope and allow DOE-RL to relieve WCH of contractual responsibilities and transition the completed areas to the Long-Term Stewardship Program, pending final action RODs. Within the next 4 years, WCH will continue to complete cleanup of the River Corridor following the completion goals. As field work-scope is completed, progressive reductions of business processes, physical facilities, and staff will occur. Organizations will collapse and flatten commensurate with workload. WCH employees will move on to new endeavors, proud of their accomplishments and the legacy they are leaving behind as being the first and largest environmental cleanup closure contract at Hanford. (authors)

  18. Quality Assurance Project Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System - 1997 Notice of Violation Consent Order

    SciTech Connect (OSTI)

    Evans, S.K.

    2002-01-31T23:59:59.000Z

    This Quality Assurance Project Plan for the HWMA/RCRA Closure Certification of the TRA- 731 Caustic and Acid Storage Tank System is one of two documents that comprise the Sampling and Analysis Plan for the HWMA/RCRA closure certification of the TRA-731 caustic and acid storage tank system at the Idaho National Engineering and Environmental Laboratory. This plan, which provides information about the project description, project organization, and quality assurance and quality control procedures, is to be used in conjunction with the Field Sampling Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System. This Quality Assurance Project Plan specifies the procedures for obtaining the data of known quality required by the closure activities for the TRA-731 caustic and acid storage tank system.

  19. Quality Assurance Project Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System - 1997 Notice of Violation Consent Order

    SciTech Connect (OSTI)

    Evans, Susan Kay; Orchard, B. J.

    2002-01-01T23:59:59.000Z

    This Quality Assurance Project Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System is one of two documents that comprise the Sampling and Analysis Plan for the HWMA/RCRA closure certification of the TRA-731 caustic and acid storage tank system at the Idaho National Engineering and Environmental Laboratory. This plan, which provides information about the project description, project organization, and quality assurance and quality control procedures, is to be used in conjunction with the Field Sampling Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System. This Quality Assurance Project Plan specifies the procedures for obtaining the data of known quality required by the closure activities for the TRA-731 caustic and acid storage tank system.

  20. High Level Waste Tank Closure Project at the Idaho National Engineering and Environmental Laboratory

    SciTech Connect (OSTI)

    Wessman, D. L.; Quigley, K. D.

    2002-02-27T23:59:59.000Z

    The Department of Energy, Idaho Operations Office (DOE-ID) is making preparations to close two underground high-level waste (HLW) storage tanks at the Idaho National Engineering and Environmental Laboratory (INEEL) to meet Resource Conservation and Recovery Act (RCRA) regulations and Department of Energy orders. Closure of these two tanks is scheduled for 2004 as the first phase in closure of the eleven 300,000 gallon tanks currently in service at the Idaho Nuclear Technology and Engineering Center (INTEC). The INTEC Tank Farm Facility (TFF) Closure sequence consists of multiple steps to be accomplished through the existing tank riser access points. Currently, the tank risers contain steam and process waste lines associated with the steam jets, corrosion coupons, and liquid level indicators. As necessary, this equipment will be removed from the risers to allow adequate space for closure equipment and activities.

  1. HIGH LEVEL WASTE MECHANCIAL SLUDGE REMOVAL AT THE SAVANNAH RIVER SITE F TANK FARM CLOSURE PROJECT

    SciTech Connect (OSTI)

    Jolly, R; Bruce Martin, B

    2008-01-15T23:59:59.000Z

    The Savannah River Site F-Tank Farm Closure project has successfully performed Mechanical Sludge Removal (MSR) using the Waste on Wheels (WOW) system for the first time within one of its storage tanks. The WOW system is designed to be relatively mobile with the ability for many components to be redeployed to multiple waste tanks. It is primarily comprised of Submersible Mixer Pumps (SMPs), Submersible Transfer Pumps (STPs), and a mobile control room with a control panel and variable speed drives. In addition, the project is currently preparing another waste tank for MSR utilizing lessons learned from this previous operational activity. These tanks, designated as Tank 6 and Tank 5 respectively, are Type I waste tanks located in F-Tank Farm (FTF) with a capacity of 2,840 cubic meters (750,000 gallons) each. The construction of these tanks was completed in 1953, and they were placed into waste storage service in 1959. The tank's primary shell is 23 meters (75 feet) in diameter, and 7.5 meters (24.5 feet) in height. Type I tanks have 34 vertically oriented cooling coils and two horizontal cooling coil circuits along the tank floor. Both Tank 5 and Tank 6 received and stored F-PUREX waste during their operating service time before sludge removal was performed. DOE intends to remove from service and operationally close (fill with grout) Tank 5 and Tank 6 and other HLW tanks that do not meet current containment standards. Mechanical Sludge Removal, the first step in the tank closure process, will be followed by chemical cleaning. After obtaining regulatory approval, the tanks will be isolated and filled with grout for long-term stabilization. Mechanical Sludge Removal operations within Tank 6 removed approximately 75% of the original 95,000 liters (25,000 gallons). This sludge material was transferred in batches to an interim storage tank to prepare for vitrification. This operation consisted of eleven (11) Submersible Mixer Pump(s) mixing campaigns and multiple intraarea transfers utilizing STPs from July 2006 to August 2007. This operation and successful removal of sludge material meets requirement of approximately 19,000 to 28,000 liters (5,000 to 7,500 gallons) remaining prior to the Chemical Cleaning process. Removal of the last 35% of sludge was exponentially more difficult, as less and less sludge was available to mobilize and the lighter sludge particles were likely removed during the early mixing campaigns. The removal of the 72,000 liters (19,000 gallons) of sludge was challenging due to a number factors. One primary factor was the complex internal cooling coil array within Tank 6 that obstructed mixer discharge jets and impacted the Effective Cleaning Radius (ECR) of the Submersible Mixer Pumps. Minimal access locations into the tank through tank openings (risers) presented a challenge because the available options for equipment locations were very limited. Mechanical Sludge Removal activities using SMPs caused the sludge to migrate to areas of the tank that were outside of the SMP ECR. Various SMP operational strategies were used to address the challenge of moving sludge from remote areas of the tank to the transfer pump. This paper describes in detail the Mechanical Sludge Removal activities and mitigative solutions to cooling coil obstructions and other challenges. The performance of the WOW system and SMP operational strategies were evaluated and the resulting lessons learned are described for application to future Mechanical Sludge Removal operations.

  2. Vendor Assessment for the Waste Package Closure System (Yucca Mtn. Project)

    SciTech Connect (OSTI)

    Colleen Shelton-Davis

    2003-09-01T23:59:59.000Z

    The Idaho National Engineering and Environmental Laboratory (INEEL) has been tasked with developing, designing, constructing, and operating a full-scale prototype of the work package closure system. As a precursor to developing the conceptual design, all commercially available equipment was assessed to identify any existing technology gaps. This report presents the results of that assessment for all major equipment.

  3. Vendor Assessment for the Waste Package Closure System (Yucca Mountain Project)

    SciTech Connect (OSTI)

    Shelton-Davis, C.V.

    2003-09-26T23:59:59.000Z

    The Idaho National Engineering and Environmental Laboratory (INEEL) has been tasked with developing, designing, constructing, and operating a full-scale prototype of the work package closure system. As a precursor to developing the conceptual design, all commercially available equipment was assessed to identify any existing technology gaps. This report presents the results of that assessment for all major equipment.

  4. Controlling landfill closure costs

    SciTech Connect (OSTI)

    Millspaugh, M.P.; Ammerman, T.A. [Spectra Engineering, Latham, NY (United States)

    1995-05-01T23:59:59.000Z

    Landfill closure projects are significant undertakings typically costing well over $100,000/acre. Innovative designs, use of alternative grading and cover materials, and strong project management will substantially reduce the financial impact of a landfill closure project. This paper examines and evaluates the various elements of landfill closure projects and presents various measures which can be employed to reduce costs. Control measures evaluated include: the beneficial utilization of alternative materials such as coal ash, cement kiln dust, paper mill by-product, construction surplus soils, construction debris, and waste water treatment sludge; the appropriate application of Mandate Relief Variances to municipal landfill closures for reduced cover system requirements and reduced long-term post closure monitoring requirements; equivalent design opportunities; procurement of consulting and contractor services to maximize project value; long-term monitoring strategies; and grant loan programs. An analysis of closure costs under differing assumed closure designs based upon recently obtained bid data in New York State, is also provided as a means for presenting the potential savings which can be realized.

  5. The Effect of the Recovery Act on the River Corridor Closure Project: Lessons Learned

    SciTech Connect (OSTI)

    Mackay, S. M.

    2012-07-31T23:59:59.000Z

    This summary report provides a high-level lessons learned by WCH of the impact to its project performance. The context is limited to the WCH project alone.

  6. [hal-00529816, v2] On optimizing over lift-and-project closures

    E-Print Network [OSTI]

    Bonami, Pierre

    2010-10-27T23:59:59.000Z

    Oct 27, 2010 ... Page 1 ... lift-and-project cuts from the initial formulation of a mixed integer linear pro ..... Now the last quantity is non-negative since u ? 0, A?x?b, ?T x>?0 ...... procedure such as ours could be used, and what issues should be dealt with. ... branch-and-cut algorithm (we don't use dynamic search since it is ...

  7. Sulimar Queen environmental restoration project closure package Sandia environmental stewardship exemplar.

    SciTech Connect (OSTI)

    Tillman, Jack B.

    2008-09-01T23:59:59.000Z

    In March 2008, Sandia National Laboratories (Sandia), in partnership with the Bureau of Land Management, Roswell Field Office, completed its responsibilities to plug and abandon wells and restore the surface conditions for the Sulimar Queens Unit, a 2,500 acre oil field, in Chaves County, Southeast New Mexico. Sandia assumed this liability in an agreement to obtain property to create a field laboratory to perform extensive testing and experimentation on enhanced oil recovery techniques for shallow oil fields. In addition to plugging and abandoning 28 wells, the project included the removal of surface structures and surface reclamation of disturbed lands associated with all plugged and abandoned wells, access roads, and other auxiliary facilities within unit boundaries. A contracting strategy was implemented to mitigate risk and reduce cost. As the unit is an important wildlife habitat for prairie chickens, sand dune lizards, and mule deer, the criteria for the restoration and construction process were designed to protect and enhance the wildlife habitat. Lessons learned from this project include: (1) extreme caution should be exercised when entering agreements that include future liabilities, (2) partnering with the regulator has huge benefits, and (3) working with industry experts, who were familiar with the work, and subcontractors, who provided the network to complete the project cost effectively.

  8. Structural analysis of closure cap barriers: A pre-test study for the Bentonite Mat Demonstration Project

    SciTech Connect (OSTI)

    Gong, Chung

    1993-10-01T23:59:59.000Z

    According to the EPA-recommended closure cap design a waste site can either be covered with a single layer cap made of 36 inches of compacted soil (clay) or with a multilayer cap consisting of an upper vegetative layer underlain by a drainage layer over a low permeability layer. The Bentonite Mat Demonstration Project (BMDP) is a field demonstration study to determine the construction/installation requirements, permeability, and subsidence performance characteristics of a composite barrier. The composite barrier will consist of on-site sandy-clay blanketed by a bentonite mat and a flexible High Density Polyethylene (HDPE) liner (also called flexible membrane liner). Construction of one control test pad and three bentonite test pads are planned. The control test pad will be used to establish baseline data. Underneath the composite clay cap is a four-foot loose sand layer in which cavities will be created by evacuation of sand. The present work provides a mathematical model for the BMDP. The mathematical model will be used to simulate the mechanical and structural responses of the composite clay cap during the testing processes. Based upon engineering experience and technical references, a set of nominal soil parameters have been selected. Currently, detailed soil test data and cavity configuration data are not available to validate the mathematical model. Since the configuration of the cavities created in the testing process is irregular and unpredictable, two extreme configurations are considered in this mathematical model, viz., the circular cavity and the infinitely long trench in the sand underneath the cap. This approach will provide bounds for the testing results.

  9. Fiscal Year 2006 Washington Closure Hanford Science & Technology Plan

    SciTech Connect (OSTI)

    K.J. Kroegler, M. Truex, D.J. McBride

    2006-01-19T23:59:59.000Z

    This Washington Closure Hanford science and technology (S&T) plan documents the activities associated with providing S&T support to the River Corridor Closure Project for fiscal year 2006.

  10. Post-Closure Benefits: DOE Complex vs Closure Sites | Department...

    Office of Environmental Management (EM)

    Post-Closure Benefits: DOE Complex vs Closure Sites Status of Contractor Pension and PRB Benefit Programs - September 30, 2013 DOE Wide Closure Sites Defined Benefit Pension...

  11. EA-1239: Final Environmental Assessment | Department of Energy

    Energy Savers [EERE]

    Property" at the Miamisburg Environmental Management Project Mound Plant in Miamisburg, Ohio. EA-1239-FEA-1999.pdf More Documents & Publications EA-1239: Finding of No...

  12. Structural analysis of closure cap barriers: A pre-test study for the Bentonite Mat Demonstration Project. Revision 1

    SciTech Connect (OSTI)

    Gong, Chung; Pelfrey, J.R.

    1993-12-01T23:59:59.000Z

    The Bentonite Mat Demonstration Project (BMDP) is a field demonstration study to determine the construction/installation requirements, permeability, and subsidence performance characteristics of a composite barrier. The composite barrier will consist of on-site sandy-clay blanketed by a bentonite mat and a flexible High Density Polyethylene (HDPE) liner (also called flexible membrane liner). Construction of one control test pad and three bentonite test pads are planned. The control test pad will be used to establish baseline data. Underneath the composite clay cap is a four feet thick loose sand layer in which cavities will be created by evacuation of sand. The present work provides a mathematical model for the BMDP. The mathematical model will be used to simulate the mechanical and structural responses of the composite clay cap during the testing processes. Based upon engineering experience and technical references, a set of nominal soil parameters have been selected.

  13. Object Closure Conversion * Neal Glew

    E-Print Network [OSTI]

    Glew, Neal

    of closure conversion. This paper argues that a direct formulation of object closure conversio* *n Object Closure Conversion * Neal into closed code and auxiliary data* * structures. Closure conversion has been extensively studied

  14. Closure for Jason Frank

    E-Print Network [OSTI]

    Wirosoetisno, Djoko

    Closure for HPM Onno Bokhove & Jason Frank Introduction Hamiltonian Parcel Vlasov Dynamics.leeds.ac.uk/~obokhove/ & http://www.staff.science.uu.nl/~frank011/ December 9, 2013 #12;Closure for HPM Onno Bokhove & Jason References #12;Closure for HPM Onno Bokhove & Jason Frank Introduction Hamiltonian Parcel Vlasov Dynamics

  15. Taking Closure to the Next Level - 13030

    SciTech Connect (OSTI)

    Feist, E.T. [Washington Closure Hanford, 2620 Fermi Avenue, Richland, WA, 99354 (United States)] [Washington Closure Hanford, 2620 Fermi Avenue, Richland, WA, 99354 (United States)

    2013-07-01T23:59:59.000Z

    The River Corridor Closure Project (RCCP) is the Hanford Site's first closure project and when it is complete, in 2015, it will have cleaned up 220 mi{sup 2} of contaminated land adjacent to the Columbia River. Washington Closure Hanford (WCH) was selected by the DOE to manage the removal and cleanup of Hanford's nuclear legacy along the River Corridor. Work began in 2005 and is now more than 85% complete with more than 2 years left in the contract. A Closure Team was commissioned in December 2009 and has since issued a closure strategy and a disciplined three-phase approach to transition land parcels to DOE, Richland Operations Office (DOE-RL) as cleanup is completed. This process supports DOE-RL objectives for progressive footprint reduction based on the division of the River Corridor into geographical land parcels. It also allows for incremental area-by-area transition and turnover to the Long-Term Stewardship program. Several important milestones stand between now and the successful end of the RCCP. They include overall funding impacts, working with DOE-RL on new scope additions, meeting regulatory milestones, and maintaining a strong safety performance. (authors)

  16. What's the Damage? Assessing the Costs of Spatial Closures to Protect Corals and

    E-Print Network [OSTI]

    What's the Damage? Assessing the Costs of Spatial Closures to Protect Corals and Sponges from.: 588 Title of Project: What's the damage? Assessing the costs of spatial closures to protect corals for protecting corals and sponges from potential damage by bottom trawling. However, closures can be challenging

  17. Post-Closure Benefits | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's Possible forPortsmouth/Paducah Project Office Press ReleasesPost-Closure Benefits Post-Closure

  18. Tank closure reducing grout

    SciTech Connect (OSTI)

    Caldwell, T.B.

    1997-04-18T23:59:59.000Z

    A reducing grout has been developed for closing high level waste tanks at the Savannah River Site in Aiken, South Carolina. The grout has a low redox potential, which minimizes the mobility of Sr{sup 90}, the radionuclide with the highest dose potential after closure. The grout also has a high pH which reduces the solubility of the plutonium isotopes. The grout has a high compressive strength and low permeability, which enhances its ability to limit the migration of contaminants after closure. The grout was designed and tested by Construction Technology Laboratories, Inc. Placement methods were developed by the Savannah River Site personnel.

  19. Object Closure Conversion Cornell University

    E-Print Network [OSTI]

    Glew, Neal

    that a direct formulation of object closure conversion is interesting and gives further insight into generalObject Closure Conversion Neal Glew Cornell University 24 August 1999 Abstract An integral part of implementing functional languages is closure conversion--the process of converting code with free variables

  20. New Construction Road Closures

    E-Print Network [OSTI]

    New Construction Remodel Utility Road Closures 11 Keiss 12 Keiss 13 Stoddard 14 Stoddard Scott? Martha Coleman: 491-0101 Colorado State University - Fall 2013 Major Construction BRT Mason Corridor Facilitites Management Haberecht Haberecht Construction Work Zones 13 12 14 21 23 22 32 Ća #12;

  1. Accelerated Tank Closure Demonstrations at the Hanford Site

    SciTech Connect (OSTI)

    Sams, Terry L.; Riess, Mark J.; Cammann, Jerry W.; Lee, Timothy A.; Nichols, David

    2003-02-27T23:59:59.000Z

    Among the highest priorities for action under the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1989a), hereafter referred to as the Tri-Party Agreement, is the retrieval, treatment and disposal of Hanford Site tank waste. Tank waste is recognized as one of the primary threats to the Columbia River and one of the most complex technical challenges. Progress has been made in resolving safety issues, characterizing tank waste and past tank leaks, enhancing double-shell tank waste transfer and operations systems, retrieving single-shell tank waste, deploying waste treatment facilities, and planning for the disposal of immobilized waste product. However, limited progress has been made in developing technologies and providing a sound technical basis for tank system closure. To address this limitation the Accelerated Tank Closure Demonstration Project was created to develop information through technology demonstrations in support of waste retrieval and closure decisions. To complete its mission the Accelerated Tank Closure Demonstration Project has adopted performance objectives that include: Protecting human health and the environment; Minimizing/eliminating potential waste releases to the soil and groundwater; Preventing water infiltration into the tank; Maintaining accessibility of surrounding tanks for future closure; Maintaining tank structural integrity; Complying with applicable waste retrieval, disposal, and closure regulations; Maintaining flexibility for final closure options in the future. This paper provides an overview of the Hanford Site tank waste mission with emphasis on the Accelerated Tank Closure Demonstration Project. Included are discussions of single-shell tank waste retrieval and closure challenges, progress made to date, lessons learned, regulatory approach, data acquisition, near-term retrieval opportunities, schedule, and cost.

  2. RECENT PROGRESS IN DOE WASTE TANK CLOSURE

    SciTech Connect (OSTI)

    Langton, C

    2008-02-01T23:59:59.000Z

    The USDOE complex currently has over 330 underground storage tanks that have been used to process and store radioactive waste generated from the production of weapons materials. These tanks contain over 380 million liters of high-level and low-level radioactive waste. The waste consists of radioactively contaminated sludge, supernate, salt cake or calcine. Most of the waste exists at four USDOE locations, the Hanford Site, the Savannah River Site, the Idaho Nuclear Technology and Engineering Center and the West Valley Demonstration Project. A summary of the DOE tank closure activities was first issued in 2001. Since then, regulatory changes have taken place that affect some of the sites and considerable progress has been made in closing tanks. This paper presents an overview of the current regulatory changes and drivers and a summary of the progress in tank closures at the various sites over the intervening six years. A number of areas are addressed including closure strategies, characterization of bulk waste and residual heel material, waste removal technologies for bulk waste, heel residuals and annuli, tank fill materials, closure system modeling and performance assessment programs, lessons learned, and external reviews.

  3. Rulison Site Surface Closure Report

    SciTech Connect (OSTI)

    NONE

    1998-07-01T23:59:59.000Z

    This Closure Report provides documentation for closure of the Rulison Site surface and summarizes the data from groundwater monitoring conducted quarterly in 1996 and 1997. The quarterly groundwater monitoring was conducted to demonstrate that no contaminants are migrating from the pond after completion of the pond remediation activities. The Rulison Site is located in the North 1/2 of the Southwest 1/4 of Section 25, Township 7 South, Range 95 West of the 6` Principal Meridian, Garfield County, Colorado, approximately 19 kilometers (km) (12 miles [mi]) southwest of Rifle, Colorado, and approximately 65 km (40 mi) northeast of Grand Junction, Colorado (Figure I - 1). The site is situated on the north slope of Battlement Mesa on the upper reaches of Battlement Creek at an elevation of approximately 2,500 meters (m) (8,200 feet [ft]). The valley is open to the north-northwest and is bounded on the other three sides by steep mountain slopes that rise to elevations above 2,927 m (9,600 ft). Project Rulison was a joint U.S. Atomic Energy Commission (AEC) and Austral Oil Company (Austral) experiment. It was conducted under the AEC`s Plowshare Program to evaluate the feasibility of using a nuclear device to stimulate natural gas production in low- permeability, gas-producing geologic formations. The experiment consisted of detonating a 40-kiloton nuclear device at a depth of 2, 568 m (8,426 ft) below ground surface on September 10, 1969, followed by natural gas production testing in 1970 and 1971 (AEC, 1973).

  4. Technical assistance to Ohio closure sites; Technologies to address leachate from the on-site disposal facility at Fernald Environmental Management Project, Ohio

    SciTech Connect (OSTI)

    Hazen, Terry

    2002-08-26T23:59:59.000Z

    On August 6-7, 2002, a Technical Assistance Team (''Team'') from the U.S. Department of Energy (DOE) Subsurface Contaminants Focus Area (SCFA) met with Fernald Environmental Management Project (FEMP) personnel in Ohio to assess approaches to remediating uranium-contaminated leachate from the On-Site Disposal Facility (OSDF). The Team was composed of technical experts from national labs, technology centers, and industry and was assembled in response to a request from the FEMP Aquifer Restoration Project. Dave Brettschneider of Fluor Fernald, Inc., requested that a Team of experts be convened to review technologies for the removal of uranium in both brine ion exchange regeneration solution from the Advanced Wastewater Treatment facility and in the leachate from the OSDF. The Team was asked to identify one or more technologies for bench-scale testing as a cost effective alternative to remove uranium so that the brine regeneration solution from the Advanced Waste Water Treatment facility and the leachate from the OSDF can be discharged without further treatment. The Team was also requested to prepare a recommended development and demonstration plan for the alternative technologies. Finally, the Team was asked to make recommendations on the optimal technical solution for field implementation. The Site's expected outcomes for this effort are schedule acceleration, cost reduction, and better long-term stewardship implementation. To facilitate consideration of the most appropriate technologies, the Team was divided into two groups to consider the brine and the leachate separately, since they represent different sources with different constraints on solutions, e.g., short-term versus very long-term and concentrated versus dilute contaminant matrices. This report focuses on the technologies that are most appropriate for the leachate from the OSDF. Upon arriving at FEMP, project personnel asked the Team to concentrate its efforts on evaluating potential technologies and strategies to reduce uranium concentration in the leachate.

  5. System for closure of a physical anomaly

    SciTech Connect (OSTI)

    Bearinger, Jane P; Maitland, Duncan J; Schumann, Daniel L; Wilson, Thomas S

    2014-11-11T23:59:59.000Z

    Systems for closure of a physical anomaly. Closure is accomplished by a closure body with an exterior surface. The exterior surface contacts the opening of the anomaly and closes the anomaly. The closure body has a primary shape for closing the anomaly and a secondary shape for being positioned in the physical anomaly. The closure body preferably comprises a shape memory polymer.

  6. Accelerating cleanup: Paths to closure

    SciTech Connect (OSTI)

    NONE

    1998-06-01T23:59:59.000Z

    This report describes the status of Environmental Management`s (EM`s) cleanup program and a direction forward to complete achievement of the 2006 vision. Achieving the 2006 vision results in significant benefits related to accomplishing EM program objectives. As DOE sites accelerate cleanup activities, risks to public health, the environment, and worker safety and health are all reduced. Finding more efficient ways to conduct work can result in making compliance with applicable environmental requirements easier to achieve. Finally, as cleanup activities at sites are completed, the EM program can focus attention and resources on the small number of sites with more complex cleanup challenges. Chapter 1 describes the process by which this report has been developed and what it hopes to accomplish, its relationship to the EM decision-making process, and a general background of the EM mission and program. Chapter 2 describes how the site-by-site projections were constructed, and summarizes, for each of DOE`s 11 Operations/Field Offices, the projected costs and schedules for completing the cleanup mission. Chapter 3 presents summaries of the detailed cleanup projections from three of the 11 Operations/Field Offices: Rocky Flats (Colorado), Richland (Washington), and Savannah River (South Carolina). The remaining eight Operations/Field Office summaries are in Appendix E. Chapter 4 reviews the cost drivers, budgetary constraints, and performance enhancements underlying the detailed analysis of the 353 projects that comprise EM`s accelerated cleanup and closure effort. Chapter 5 describes a management system to support the EM program. Chapter 6 provides responses to the general comments received on the February draft of this document.

  7. Decontamination and inspection plan for Phase 3 closure of the 300 area waste acid treatment system

    SciTech Connect (OSTI)

    LUKE, S.N.

    1999-02-01T23:59:59.000Z

    This decontamination and inspection plan (DIP) describes decontamination and verification activities in support of Phase 3 closure of the 300 Area Waste Acid Treatment System (WATS). Phase 3 is the third phase of three WATS closure phases. Phase 3 attains clean closure conditions for WATS portions of the 334 and 311 Tank Farms (TF) and the 333 and 303-F Buildings. This DIP also describes designation and management of waste and debris generated during Phase 3 closure activities. Information regarding Phase 1 and Phase 2 for decontamination and verification activities closure can be found in WHC-SD-ENV-AP-001 and HNF-1784, respectively. This DIP is provided as a supplement to the closure plan (DOE/RL-90-11). This DIP provides the documentation for Ecology concurrence with Phase 3 closure methods and activities. This DIP is intended to provide greater detail than is contained in the closure plan to satisfy Ecology Dangerous Waste Regulations, Washington Administrative Code (WAC) 173-303-610 requirement that closure documents describe the methods for removing, transporting, storing, and disposing of all dangerous waste at the unit. The decontamination and verification activities described in this DIP are based on the closure plan and on agreements reached between Ecology and the U.S. Department of Energy, Richland Operations Office (DOE-RL) during Phase 3 closure activity workshops and/or project manager meetings (PMMs).

  8. HOOTS99 Preliminary Version Object Closure Conversion

    E-Print Network [OSTI]

    Glew, Neal

    classes is an exam* *ple of closure conversion. This paper argues that a direct formulation of object HOOTS99 Preliminary Version Object Closure Conversion __________________________________________________________________________ Abstract An integral part of implementing functional languages is closure conversion_the process

  9. Project Transition/Closeout (CD-4)

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

    2008-09-24T23:59:59.000Z

    This Guide is written for the federal project director ensuring that processes progress smoothly and that projects meet asset management goals and financial closure requirements of DOE.

  10. Closure report for N Reactor

    SciTech Connect (OSTI)

    Not Available

    1994-01-01T23:59:59.000Z

    This report has been prepared to satisfy Section 3156(b) of Public Law 101-189 (Reports in Connection with Permanent Closures of Department of Energy Defense Nuclear Facilities), which requires submittal of a Closure Report to Congress by the Secretary of Energy upon the permanent cessation of production operations at a US Department of Energy (DOE) defense nuclear facility (Watkins 1991). This closure report provides: (1) A complete survey of the environmental problems at the facility; (2) Budget quality data indicating the cost of environmental restoration and other remediation and cleanup efforts at the facility; (3) A proposed cleanup schedule.

  11. Ohio Closure Projects Ceremony | Department of Energy

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed offOCHCO2:Introduction toManagementOPAM PolicyOf EnvironmentalGuide, JulyIssueOffshore WindOh,Ohio

  12. River Corridor Closure Project Partnering Performance Agreement |

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2 OPAM615_CostNSAR -DepartmentRetail DemandEnergyRisk Management

  13. River Corridor Closure Project Partnering Performance Agreement

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently AskedEnergy SmallImplementing theFinancing » Financing StructuresA l i cKerryRita

  14. Commencement Activities & Facility Maintenance Closures Updated Monday 4/29

    E-Print Network [OSTI]

    von der Heydt, RĂĽdiger

    · Fitness Center & Weight Room equipment cleaning, preventive maintenance, and layout changes #12;Commencement Activities & Facility Maintenance Closures Updated Monday 4/29 Spring Semester Normal Maintenance projects. · The Rec Center will be closed Monday 5/20 ­ Sunday 6/9. · The Rec Center reopens

  15. Kinetic Modeling and Thermodynamic Closure Approximation of ...

    E-Print Network [OSTI]

    2007-10-03T23:59:59.000Z

    Oct 5, 2007 ... Kinetic Modeling and Thermodynamic Closure. Approximation of Liquid Crystal Polymers. Haijun Yu. Program in Applied and Computational ...

  16. HOOTS99 Preliminary Version Object Closure Conversion

    E-Print Network [OSTI]

    Glew, Neal

    is an example of closure conversion. This paper argues that a direct formulation of object closure conversionHOOTS99 Preliminary Version Object Closure Conversion Neal Glew 1 Department of Computer Science conversion--the process of converting code with free variables into closed code and auxiliary data structures

  17. HOOTS99 Preliminary Version Object Closure Conversion

    E-Print Network [OSTI]

    Glew, Neal

    classes is an example of closure conversion. This paper argues that a direct formulation of object closureHOOTS99 Preliminary Version Object Closure Conversion Neal Glew 1 Department of Computer Science conversion---the process of converting code with free variables into closed code and auxiliary data

  18. Fourier's Law from Closure Equations

    E-Print Network [OSTI]

    Jean Bricmont; Antti Kupiainen

    2006-09-01T23:59:59.000Z

    We give a rigorous derivation of Fourier's law from a system of closure equations for a nonequilibrium stationary state of a Hamiltonian system of coupled oscillators subjected to heat baths on the boundary. The local heat flux is proportional to the temperature gradient with a temperature dependent heat conductivity and the stationary temperature exhibits a nonlinear profile.

  19. Small Site Closures

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2Uranium Transfer toSensor TechnologiesProjects | Department ofEnergySite

  20. Miamisburg, Ohio: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere I Geothermal Pwer Plant JumpMarysville, Ohio:Menomonee| Open Energy

  1. IDENTIFICATION OF DOE'S POST-CLOSURE MONITORING NEEDS AND REQUIREMENTS

    SciTech Connect (OSTI)

    M.A. Ebadian, Ph.D.

    1999-01-01T23:59:59.000Z

    The 2006 plan sets an ambitious agenda for the U.S. Department of Energy (DOE), Office of Environmental Management (EM) and the remediation of sites contaminated by decades of nuclear weapons production activities. The plan's primary objective is to reduce overall clean up costs by first eliminating the environmental problems that are most expensive to control and safely maintain. In the context of the 2006 Plan, closure refers to the completion of area or facility specific cleanup projects. The cleanup levels are determined by the planned future use of the site or facility. Use restrictions are still undecided for most sites but are highly probable to exclude residential or agricultural activities. Most of the land will be remediated to ''industrial use'' levels with access restrictions and some areas will be closed-off through containment. Portions of the site will be reserved for waste disposal, either as a waste repository or the in-situ immobilization of contaminated soil and groundwater, and land use will be restricted to waste disposal only. The land used for waste disposal will require monitoring and maintenance activities after closure. Most of the land used for industrial use may also require such postclosure activities. The required postclosure monitoring and maintenance activities will be imposed by regulators and stakeholders. Regulators will not approve closure plans without clearly defined monitoring methods using approved technologies. Therefore, among all other more costly and labor-intensive closure-related activities, inadequate planning for monitoring and lack of appropriate monitoring technologies can prevent closure. The purpose of this project is to determine, document, and track the current and evolving postclosure monitoring requirements at DOE-EM sites. This information will aid CMST-CP in guiding its postclosure technology development and deployment efforts.

  2. 324 Building REC and HLV Tank Closure Plan

    SciTech Connect (OSTI)

    Becker-Khaleel, B; Schlick, K. [Scienfific Ecology Group, Inc. Richland, WA (United States)

    1995-12-01T23:59:59.000Z

    This closure plan describes the activities necessary to close the 324 Radiochemical Engineering Cells (REC) and High-Level Vault (HLV) in accordance with the Washington State Dangerous Waste regulations. To provide a complete description of the activities required, the closure plan relies on information contained in the 324 Building B-Cell Safety Cleanout Project (BCCP) plans, the 324 Building REC HLV Interim Waste Management Plan (IWMP), the Project Management Plan for Nuclear Facilities Management 300 Area Compliance Program, and the 324 High Level Vault Interim Removal Action Project (project management plan [PMP]). The IWMP addresses the management of mixed waste in accordance with state and federal hazardous waste regulations. It provides a strategy for managing high-activity mixed waste in compliance with Resource Conservation and Recovery Act (RCRA) requirements or provides for an alternative management approach for the waste. The BCCP outlines the past, present, and future activities necessary for removing from B-Cell the solid waste, including mixed waste generated as a result of historical research and development (R&D) activities conducted in the cell. The BCCP also includes all records and project files associated with the B-Cell cleanout. This information is referenced throughout the closure plan. The PMP sets forth the plans, organization, and systems that Pacific Northwest National Laboratory (PNNL) will use to direct and control the 324 High-Level Vault Interim Removal Action Project. This project will develop and implement a treatment strategy that will remove and stabilize the inventory of liquid waste from the 324 HLV tanks. The PMP also provides for flushing and sampling the flush solution.

  3. Multi-canister overpack closure operations location study

    SciTech Connect (OSTI)

    Goldmann, L.H.

    1996-04-15T23:59:59.000Z

    The Spent Nuclear Fuel Path Forward Project (SNF Project) has been established to develop engineered methods for the expedited removal of the irradiated uranium fuel from the K East (KE) and K West (KW) Basins. As specified by the SNF Project, the SNF will be removed from the K Basins, conditioned for dry storage and placed in a long term interim storage facility located in the 200 East Area. The SNF primarily consists of Zircaloy-2 clad uranium fuel discharged from the N-Reactor. A small portion of the SNF is Single Pass Reactor (SPR) Fuel, which is aluminum clad uranium fuel. The SNF will be loaded into Multi-Canister Overpacks (MCOs) at the K Basins, transferred to the Cold Vacuum Drying (CVD) facility for initial fuel conditioning, and transported to the Canister Storage Building (CSB) for staging, final fuel conditioning, and dry storage. The MCO is a transportation, conditioning, and storage vessel. The MCO consists of a 24 inch pipe with a welded bottom closure and a top closure that is field welded after the MCO is loaded with SNF. The MCO is handled and transported in the vertical orientation during all operations. Except for operations within the CSB, the MCO is always within the transportation cask which primarily provides radiological shielding and structural protection of the MCO. The MCO closure operations location study provides a relative evaluation of location options at the K Basins and the CVD Facility and recommends that the MCO closure weld be performed, inspected, and repaired at the CVD Facility.

  4. ICPP tank farm closure study. Volume 2: Engineering design files

    SciTech Connect (OSTI)

    NONE

    1998-02-01T23:59:59.000Z

    Volume 2 contains the following topical sections: Tank farm heel flushing/pH adjustment; Grouting experiments for immobilization of tank farm heel; Savannah River high level waste tank 20 closure; Tank farm closure information; Clean closure of tank farm; Remediation issues; Remote demolition techniques; Decision concerning EIS for debris treatment facility; CERCLA/RCRA issues; Area of contamination determination; Containment building of debris treatment facility; Double containment issues; Characterization costs; Packaging and disposal options for the waste resulting from the total removal of the tank farm; Take-off calculations for the total removal of soils and structures at the tank farm; Vessel off-gas systems; Jet-grouted polymer and subsurface walls; Exposure calculations for total removal of tank farm; Recommended instrumentation during retrieval operations; High level waste tank concrete encasement evaluation; Recommended heavy equipment and sizing equipment for total removal activities; Tank buoyancy constraints; Grout and concrete formulas for tank heel solidification; Tank heel pH requirements; Tank cooling water; Evaluation of conservatism of vehicle loading on vaults; Typical vault dimensions and approximately tank and vault void volumes; Radiological concerns for temporary vessel off-gas system; Flushing calculations for tank heels; Grout lift depth analysis; Decontamination solution for waste transfer piping; Grout lift determination for filling tank and vault voids; sprung structure vendor data; Grout flow properties through a 2--4 inch pipe; Tank farm load limitations; NRC low level waste grout; Project data sheet calculations; Dose rates for tank farm closure tasks; Exposure and shielding calculations for grout lines; TFF radionuclide release rates; Documentation of the clean closure of a system with listed waste discharge; and Documentation of the ORNL method of radionuclide concentrations in tanks.

  5. 100-D Ponds closure plan. Revision 1

    SciTech Connect (OSTI)

    Petersen, S.W.

    1997-09-01T23:59:59.000Z

    The 100-D Ponds is a Treatment, Storage, and Disposal (TSD) unit on the Hanford Facility that received both dangerous and nonregulated waste. This Closure Plan (Rev. 1) for the 100-D Ponds TSD unit consists of a RCRA Part A Dangerous Waste Permit Application (Rev. 3), a RCRA Closure Plan, and supporting information contained in the appendices to the plan. The closure plan consists of eight chapters containing facility description, process information, waste characteristics, and groundwater monitoring data. There are also chapters containing the closure strategy and performance standards. The strategy for the closure of the 100-D Ponds TSD unit is clean closure. Appendices A and B of the closure plan demonstrate that soil and groundwater beneath 100-D Ponds are below cleanup limits. All dangerous wastes or dangerous waste constituents or residues associated with the operation of the ponds have been removed, therefore, human health and the environment are protected. Discharges to the 100-D Ponds, which are located in the 100-DR-1 operable unit, were discontinued in June 1994. Contaminated sediment was removed from the ponds in August 1996. Subsequent sampling and analysis demonstrated that there is no contamination remaining in the ponds, therefore, this closure plan is a demonstration of clean closure.

  6. Summative Mass Closure: Laboratory Analytical Procedure (LAP...

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

    the appropriate combinations of LAPs allows for the summative mass closure of biomass feedstocks and process intermediates. By combining the appropriate LAPs, the goal is to...

  7. Preliminary Notice of Violation, Washington Closure Hanford,...

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

    Notice of Violation, Savannah River Nuclear Solutions, LLC - WEA-2012-04 Type B Accident Investigation At Washington Closure Hanford, LLC, Employee Fall Injury on July 1,...

  8. Clamshell closure for metal drum

    DOE Patents [OSTI]

    Blanton, Paul S

    2014-09-30T23:59:59.000Z

    Closure ring to retain a lid in contact with a metal drum in central C-section conforming to the contact area between a lid and the rim of a drum and further having a radially inwardly directed flange and a vertically downwardly directed flange attached to the opposite ends of the C-section. The additional flanges reinforce the top of the drum by reducing deformation when the drum is dropped and maintain the lid in contact with the drum. The invention is particularly valuable in transportation and storage of fissile material.

  9. Closure Sites | Department of Energy

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed offOCHCO OverviewAttachments4 Chairs Meeting - AprilEvents CleanSeattle, WAClosingClosure Sites

  10. Transitional nuclei near shell closures

    SciTech Connect (OSTI)

    Mukherjee, G. [Variable Energy Cyclotron Centre, 1/AF Bidhan Nagar, Kolkata 700064 (India); Pai, H. [Variable Energy Cyclotron Centre, 1/AF Bidhan Nagar, Kolkata 700064, India and Present Address: Institut für Kernphysik, Technische Universität Darmstadt, Schlossgartenstrasse 9, 64289 Darmstadt (Germany)

    2014-08-14T23:59:59.000Z

    High spin states in Bismuth and Thallium nuclei near the Z = 82 shell closure and Cesium nuclei near the N = 82 shell closure in A = 190 and A = 130 regions, respectively, have been experimentally investigated using heavy-ion fusion evaporation reaction and by detecting the gamma rays using the Indian National Gamma Array (INGA). Interesting shape properties in these transitional nuclei have been observed. The results were compared with the neighboring nuclei in these two regions. The total Routhian surface (TRS) calculations have been performed for a better understanding of the observed properties. In mass region A = 190, a change in shape from spherical to deformed has been observd around neutron number N = 112 for the Bi (Z = 83) isotopes with proton number above the magic gap Z = 82, whereas, the shape of Tl (Z = 81) isotopes with proton number below the magic gap Z = 82 remains stable as a function of neutron number. An important transition from aplanar to planar configuration of angular momentum vectors leading to the occurance of nuclar chirality and magnetic rotation, respectively, has been proposed for the unique parity ?h{sub 11/2}??h{sub 11/2} configuration in Cs isotopes in the mass region A ? 130 around neutron number N = 79. These results are in commensurate with the TRS calculations.

  11. Using closures for code generation Marc Feeley

    E-Print Network [OSTI]

    Feeley, Marc

    which offers the advantages of an interpreter with the speed of compiled code. Code generation relies - environment (i.e. the set of current variable bindings). This operation is called closure. We speakUsing closures for code generation Marc Feeley Guy Lapalme D´epartement d'informatique et de

  12. Utilizing Divers in Support of Spent Fuel Basin Closure Subproject

    SciTech Connect (OSTI)

    Allen Nellesen

    2005-01-01T23:59:59.000Z

    A number of nuclear facilities in the world are aging and with this comes the fact that we have to either keep repairing them or decommission them. At the Department of Energy Idaho Site (DOEID) there are a number of facilities that are being decommissioned, but the facilities that pose the highest risk to the large aquifer that flows under the site are given highest priorities. Aging spent nuclear fuel pools at DOE-ID are among the facilities that pose the highest risk, therefore four pools were targeted for decommissioning in Fiscal Year 2004. To accomplish this task the Idaho Completion Project (ICP) of Bechtel BWXT Idaho, LLC, put together an integrated Basin Closure Subproject team. The team was assigned a goal to look beyond traditional practices at the Idaho National Engineering and Environmental Laboratory (INEEL) to find ways to get the basin closure work done safer and more efficiently. The Idaho Completion Project (ICP) was faced with a major challenge – cleaning and preparing aging spent nuclear fuel basins for closure by removing sludge and debris, as necessary, and removing water to eliminate a potential risk to the Snake River Plain Aquifer. The project included cleaning and removing water from four basins. Two of the main challenges to a project like this is the risk of contamination from the basin walls and floors becoming airborne as the water is removed and keeping personnel exposures ALARA. ICP’s baseline plan had workers standing at the edges of the basins and on rafts or bridge cranes and then using long-handled tools to manually scrub the walls of basin surfaces. This plan had significant risk of skin contamination events, workers falling into the water, or workers sustaining injuries from the awkward working position. Analysis of the safety and radiation dose risks presented by this approach drove the team to look for smarter ways to get the work done.

  13. Closure models for turbulent reacting flows

    SciTech Connect (OSTI)

    Dutta, A.; Tarbell, J.M. (Pennsylvania State Univ., University Park, PA (USA). Dept. of Chemical Engineering)

    1989-12-01T23:59:59.000Z

    In this paper, a simple procedure based on fast and slow reaction asymptotics has been employed to drive first-order closure models for the nonlinear reaction terms in turbulent mass balances from mechanistic models of turbulent mixing and reaction. The coalescence-redispersion (CRD) model, the interaction by exchange with the mean (IEM) model, the three-environment (3E) model, and the four-environment (4E) model have been used to develop closure equations. The closure models have been tested extensively against experimental data for both single and multiple reactions. The closures based on slow asymptotics for the CRD, 3E and 4E models provide very good predictions of all of the experimental data, while other models available either in the literature or derived here are not adequate. The simple new closure equations developed in this paper may be useful in modeling systems involving turbulent mixing and complex chemical reactions.

  14. CFD Combustion Modeling with Conditional Moment Closure using...

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

    Combustion Modeling with Conditional Moment Closure using Tabulated Chemistry CFD Combustion Modeling with Conditional Moment Closure using Tabulated Chemistry A method is...

  15. approaching site closure: Topics by E-print Network

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

    Summary: Cloudy sky shortwave radiative closure for a Baseline Surface Radiation Network site Ping Wang,1 2011; published 16 April 2011. 1 A shortwave radiative closure analysis...

  16. Closure for the Seventh Generation - A Report from the Stewardship...

    Energy Savers [EERE]

    Closure for the Seventh Generation - A Report from the Stewardship Committee of the State and Tribal Government Working Group (February 1999) Closure for the Seventh Generation - A...

  17. Applying Lean Concepts to Waste Site Closure - 13137

    SciTech Connect (OSTI)

    Proctor, M.L. [Washington Closure Hanford, 2620 Fermi, Richland, Washington 99354 (United States)] [Washington Closure Hanford, 2620 Fermi, Richland, Washington 99354 (United States)

    2013-07-01T23:59:59.000Z

    Washington Closure Hanford (WCH) was selected by the U.S. Department of Energy, Richland Operations Office to manage the River Corridor Closure Project, a 10-year contract in which WCH will clean up 220 mi{sup 2} of contaminated land at the Hanford Site in Richland, Washington. In the summer of 2011, with Tri-Party (DOE-RL, Environmental Protection Agency and Washington State Department of Ecology) Agreement Milestones due at the end of the calendar year, standard work practices were challenged in regards to closure documentation development. The Lean process, a concept that maximizes customer value while minimizing waste, was introduced to WCH's Sample Design and Cleanup Verification organization with the intention of eliminating waste and maximizing efficiencies. The outcome of implementing Lean processes and concepts was impressive. It was determined that the number of non-value added steps far outnumbered the value added steps. Internal processing time, document size, and review times were all reduced significantly; relationships with the customer and the regulators were also improved; and collaborative working relationships with the Tri Parties have been strengthened by working together on Lean initiatives. (authors)

  18. Closure for milliliter scale bioreactor

    DOE Patents [OSTI]

    Klein, David L. (Palo Alto, CA); Laidlaw, Robert D. (Albany, CA); Andronaco, Gregory (Palo Alto, CA); Boyer, Stephen G. (Moss Beach, CA)

    2010-12-14T23:59:59.000Z

    A closure for a microreactor includes a cap that is configured to be inserted into a well of the microreactor. The cap, or at least a portion of the cap, is compliant so as to form a seal with the well when the cap is inserted. The cap includes an aperture that provides an airway between the inside of the well to the external environment when the cap is inserted into the well. A porous plug is inserted in the aperture, e.g., either directly or in tube that extends through the aperture. The porous plug permits gas within the well to pass through the aperture while preventing liquids from passing through to reduce evaporation and preventing microbes from passing through to provide a sterile environment. A one-way valve may also be used to help control the environment in the well.

  19. Challenges for Lithuania: Ignalina NPP Early Closure

    SciTech Connect (OSTI)

    Teskeviciene, Birute [Ministry of Economy, Gedimino pr. 38/2, Vilnius, LT-01104 (Lithuania); Harrison, Peter [Central Project Management Agency, S. Konarskio 13, Vilnius, LT-03109 (Lithuania)

    2008-01-15T23:59:59.000Z

    As a condition of accession into the European Union (EU), Lithuania is committed to the closure and decommissioning of Ignalina NPP comprising two RBMK-1500 reactor units (Fig. 1). It was agreed in a special protocol to the Accession Treaty that, in return for adequate EU financial assistance, Unit 1 would be closed before 2005 and Unit 2 by the end of 2009. The first unit was duly shut down on December 31, 2004. Lithuania, which has borders with Russia (Kaliningrad territory), Poland, Latvia and Belarus, spent fifty years as part of the Soviet Union and was deeply integrated into its economy and electrical infrastructure. At the break-up of the USSR, Lithuania inherited electricity generating capacity designed to supply the north-west region including ownership of Ignalina NPP located in the north-east of the country. Ignalina NPP Unit 1 was commissioned in 1983, Unit 2 in 1987; the planned lifespan of each unit was 30 years. Construction of a third unit was started but never completed. Since Lithuania became independent in 1990, Ignalina NPP has typically contributed more than 70% of national power supply. The town of Visaginas (population approx. 30,000) was purpose built to serve the plant and staff were brought in from throughout the USSR. With 3200 direct employees, Ignalina NPP remains by far the largest employer. Although there are pockets of Russian-language speakers in communities throughout Lithuania, Visaginas is the only example on a whole-town scale. Thus closure of Ignalina NPP within the restricted timescale required by the EU Accession Treaty commitment set an exceptional challenge to Lithuania. However, since the preparatory phase of decommissioning started in 2000, notable progress has been made, experience gained and lessons learnt. At present Unit 1 remains partially fueled in a state of care and maintenance. Partly burnt fuel is being transferred from Unit 1 to Unit 2 for further irradiation in order to minimize the commitment of new fuel thereby reducing operating costs and the final quantity of spent fuel. Design and construction of the facilities for spent fuel storage, waste processing and free-release is ongoing. The siting of the Near Surface Repository is now in the final stages of approval and construction of the landfill facility is under tendering. In order to facilitate the approval process and minimize the transport of waste, both disposal facilities will be within the boundary of the NPP site. Approximately 450 staff are employed at the shutdown Unit 1 for the safe maintenance of essential systems. The total staffing level at the plant is currently being reduced by around 200 each year, with a larger release to take place at the closure of Unit 2. It is envisaged that 2000 staff will be required for the dismantling operations. Although Ignalina NPP is still in the early stages of closure and decommissioning, some important lessons have already been learnt: Firstly, the importance considering social and financial issues as well as technical factors in deciding the decommissioning strategy. This should be done before the preparation is started of the FDP. The same broad consideration should also be given to the economic restructuring of the local area. Consultation is necessary with local and national authorities, and other stakeholders up to ensure a common vision. At Ignalina NPP it was considered essential to staff morale and the maintenance of a strong safety culture to guarantee the special social and employment benefits to dismissed staff in law [9]. At the same time, measures were also adopted to encourage certain key personnel to remain at the plant until closure. The case of Lithuania, which at independence had no legislative framework or management infrastructure for radioactive waste, may be exceptional; however, for all decommissioning projects it is necessary to have, from the outset, a clear strategy on waste storage and disposal. Finally, coordination at all levels must be assured, especially with the involvement of the nuclear regulators and other regulatory authorities, t

  20. MODIFICATIONS TO THE WIPP PANEL CLOSURE

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

    panel closure design. FLAC3D implements the Callahan and DeVries (1991) crushed salt creep constitutive model. This model is based on Sjaardema and Krieg (1987) and was...

  1. Extender for securing a closure

    DOE Patents [OSTI]

    Thomas, II, Patrick A.

    2012-10-02T23:59:59.000Z

    An apparatus for securing a closure such as door or a window that opens and closes by movement relative to a fixed structure such as a wall or a floor. Many embodiments provide a device for relocating a padlock from its normal location where it secures a fastener (such as a hasp) to a location for the padlock that is more accessible for locking and unlocking the padlock. Typically an extender is provided, where the extender has a hook at a first end that is disposed through the eye of the staple of the hasp, and at an opposing second end the extender has an annulus, such as a hole in the extender or a loop or ring affixed to the extender. The shackle of the padlock may be disposed through the annulus and may be disposed through the eye of a second staple to secure the door or window in a closed or open position. Some embodiments employ a rigid sheath to enclose at least a portion of the extender. Typically the rigid sheath has an open state where the hook is exposed outside the sheath and a closed state where the hook is disposed within the sheath.

  2. 488-4D ASH LANDFILL CLOSURE CAP HELP MODELING

    SciTech Connect (OSTI)

    Phifer, M.

    2014-11-17T23:59:59.000Z

    At the request of Area Completion Projects (ACP) in support of the 488-4D Landfill closure, the Savannah River National Laboratory (SRNL) has performed Hydrologic Evaluation of Landfill Performance (HELP) modeling of the planned 488-4D Ash Landfill closure cap to ensure that the South Carolina Department of Health and Environmental Control (SCDHEC) limit of no more than 12 inches of head on top of the barrier layer (saturated hydraulic conductivity of no more than 1.0E-05 cm/s) in association with a 25-year, 24-hour storm event is not projected to be exceeded. Based upon Weber 1998 a 25-year, 24-hour storm event at the Savannah River Site (SRS) is 6.1 inches. The results of the HELP modeling indicate that the greatest peak daily head on top of the barrier layer (i.e. geosynthetic clay liner (GCL) or high density polyethylene (HDPE) geomembrane) for any of the runs made was 0.079 inches associated with a peak daily precipitation of 6.16 inches. This is well below the SCDHEC limit of 12 inches.

  3. 216-B-3 expansion ponds closure plan

    SciTech Connect (OSTI)

    Not Available

    1994-10-01T23:59:59.000Z

    This document describes the activities for clean closure under the Resource Conservation and Recovery Act of 1976 (RCRA) of the 216-B-3 Expansion Ponds. The 216-B-3 Expansion Ponds are operated by the US Department of Energy, Richland Operations Office (DOE-RL) and co-operated by Westinghouse Hanford Company (Westinghouse Hanford). The 216-B-3 Expansion Ponds consists of a series of three earthen, unlined, interconnected ponds that receive waste water from various 200 East Area operating facilities. The 3A, 3B, and 3C ponds are referred to as Expansion Ponds because they expanded the capability of the B Pond System. Waste water (primarily cooling water, steam condensate, and sanitary water) from various 200 East Area facilities is discharged to the Bypass pipe (Project X-009). Water discharged to the Bypass pipe flows directly into the 216-B-3C Pond. The ponds were operated in a cascade mode, where the Main Pond overflowed into the 3A Pond and the 3A Pond overflowed into the 3C Pond. The 3B Pond has not received waste water since May 1985; however, when in operation, the 3B Pond received overflow from the 3A Pond. In the past, waste water discharges to the Expansion Ponds had the potential to have contained mixed waste (radioactive waste and dangerous waste). The radioactive portion of mixed waste has been interpreted by the US Department of Energy (DOE) to be regulated under the Atomic Energy Act of 1954; the dangerous waste portion of mixed waste is regulated under RCRA.

  4. An eddy closure for potential vorticity

    SciTech Connect (OSTI)

    Ringler, Todd D [Los Alamos National Laboratory

    2009-01-01T23:59:59.000Z

    The Gent-McWilliams (GM) parameterization is extended to include a direct influence in the momentum equation. The extension is carried out in two stages; an analysis of the inviscid system is followed by an analysis of the viscous system. In the inviscid analysis the momentum equation is modified such that potential vorticity is conserved along particle trajectories following a transport velocity that includes the Bolus velocity in a manner exactly analogous to the continuity and tracer equations. In addition (and in contrast to traditional GM closures), the new formulation of the inviscid momentum equation results in a conservative exchange between potential and kinetic forms of energy. The inviscid form of the eddy closure conserves total energy to within an error proportional to the time derivative of the Bolus velocity. The hypothesis that the viscous term in the momentum equation should give rise to potential vorticity being diffused along isopycnals in a manner analogous to other tracers is examined in detail. While the form of the momentum closure that follows from a strict adherence to this hypothesis is not immediately interpretable within the constructs of traditional momentum closures, three approximations to this hypothesis results in a form of dissipation that is consistent with traditional Laplacian diffusion. The first two approximations are that relative vorticity, not potential vorticity, is diffused along isopyncals and that the flow is in approximate geostrophic balance. An additional approximation to the Jacobian term is required when the dissipation coefficient varies in space. More importantly, the critique of this hypothesis results in the conclusion that the viscosity parameter in the momentum equation should be identical to the tradition GM closure parameter {Kappa}. Overall, we deem the viscous form of the eddy closure for potential vorticity as a viable closure for use in ocean circulation models.

  5. RCRA/UST, superfund, and EPCRA hotline training module. Introduction to: Closure/post-closure (40 CFR parts 264/265, subpart G) updated as of July 1995

    SciTech Connect (OSTI)

    NONE

    1995-11-01T23:59:59.000Z

    The module explains the difference between closure and post-closure and lists the types of facilities that are subject to closure/post-closure. It defines the difference between partial and final closure. It specifies who submits a closure plan and when a closure plan must be submitted, listed the steps in the process, states the time frame for submittal and identifies when and how a closure must be amended. It explains the time frame for notification of closure and the deadlines for beginning and completing closure. It specifies which facilities need contingent post-closure plans, lists the elements of post-closure, and cites the requirements. It specifies the conditions and timing for amending a post-closure plan, and states who must certify closure/post-closure.

  6. RCRA, superfund and EPCRA hotline training module. Introduction to: Closure/post-closure (40 cfr parts 264/265, subpart g) updated July 1996

    SciTech Connect (OSTI)

    NONE

    1996-07-01T23:59:59.000Z

    The module explains the difference between closure and post-closure. It lists the types of facilities that are subject to closure/post-closures and defines the difference between partial and final closure. It specifies who submits a closure plan and when a closure plan must be submitted, lists the steps in the process, and states the time frame for submittal. It identifies when and how a closure must be amended. It explains the time frame for notification of closure and the deadlines for beginning and completing closure. It specifies which facilities need contingent post-closure plans and lists and the elements of post-closure and cites the requirements. It specifies the conditions and timing for amending a post-closure plan and states who must certify closure/post-closure.

  7. Adapting MARSSIM for FUSRAP site closure.

    SciTech Connect (OSTI)

    Johnson, R.; Durham, L.; Rieman, C.; Hoover, R.

    2001-12-21T23:59:59.000Z

    The Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) provides a coherent, technically defensible process for establishing that exposed surfaces satisfy site cleanup requirements. Unfortunately, many sites have complications that challenge a direct application of MARSSIM. Example complications include Record of Decision (ROD) requirements that are not MARSSIM-friendly, the potential for subsurface contamination, and incomplete characterization information. These types of complications are typically the rule, rather than the exception, for sites undergoing radiologically-driven remediation and closure. One such site is the Formerly Utilized Sites Remedial Action Program (FUSRAP) Linde site in Tonawanda, New York. Cleanup of the site is currently underway. The Linde site presented a number of challenges to designing and implementing a closure strategy consistent with MARSSIM. This paper discusses some of the closure issues confronted by the U.S. Army Corps of Engineers Buffalo District at the Linde site, and describes how MARSSIM protocols were adapted to address these issues.

  8. Closure device for lead-acid batteries

    DOE Patents [OSTI]

    Ledjeff, Konstantin (Schwalbach, DE)

    1983-01-01T23:59:59.000Z

    A closure device for lead-acid batteries includes a filter of granulated activated carbon treated to be hydrophobic combined with means for preventing explosion of emitted hydrogen and oxygen gas. The explosion prevention means includes a vertical open-end tube within the closure housing for maintaining a liquid level above side wall openings in an adjacent closed end tube. Gases vent from the battery through a nozzle directed inside the closed end tube against an impingement surface to remove acid droplets. The gases then flow through the side wall openings and the liquid level to quench any possible ignition prior to entering the activated carbon filter. A wick in the activated carbon filter conducts condensed liquid back to the closure housing to replenish the liquid level limited by the open-end tube.

  9. Hanford Patrol Academy demolition sites closure plan

    SciTech Connect (OSTI)

    Not Available

    1993-09-30T23:59:59.000Z

    The Hanford Site is owned by the U.S. Government and operated by the U.S. Department of Energy, Richland Operations Office. Westinghouse Hanford Company is a major contractor to the U.S. Department of Energy, Richland Operations Office and serves as co-operator of the Hanford Patrol Academy Demolition Sites, the unit addressed in this paper. This document consists of a Hanford Facility Dangerous Waste Part A Permit Application, Form 3 (Revision 4), and a closure plan for the site. An explanation of the Part A Form 3 submitted with this closure plan is provided at the beginning of the Part A section. This Hanford Patrol Academy Demolition Sites Closure Plan submittal contains information current as of December 15, 1994.

  10. 2401-W Waste storage building closure plan

    SciTech Connect (OSTI)

    LUKE, S.M.

    1999-07-15T23:59:59.000Z

    This plan describes the performance standards met and closure activities conducted to achieve clean closure of the 2401-W Waste Storage Building (2401-W) (Figure I). In August 1998, after the last waste container was removed from 2401-W, the U.S. Department of Energy, Richland Operations Office (DOE-RL) notified Washington State Department of Ecology (Ecology) in writing that the 2401-W would no longer receive waste and would be closed as a Resource Conservation and Recovery Act (RCRA) of 1976 treatment, storage, and/or disposal (TSD) unit (98-EAP-475). Pursuant to this notification, closure activities were conducted, as described in this plan, in accordance with Washington Administrative Code (WAC) 173-303-610 and completed on February 9, 1999. Ecology witnessed the closure activities. Consistent with clean closure, no postclosure activities will be necessary. Because 2401-W is a portion of the Central Waste Complex (CWC), these closure activities become the basis for removing this building from the CWC TSD unit boundary. The 2401-W is a pre-engineered steel building with a sealed concrete floor and a 15.2-centimeter concrete curb around the perimeter of the floor. This building operated from April 1988 until August 1998 storing non-liquid containerized mixed waste. All waste storage occurred indoors. No potential existed for 2401-W operations to have impacted soil. A review of operating records and interviews with cognizant operations personnel indicated that no waste spills occurred in this building (Appendix A). After all waste containers were removed, a radiation survey of the 2401-W floor for radiological release of the building was performed December 17, 1998, which identified no radiological contamination (Appendix B).

  11. Permanent Closure of the TAN-664 Underground Storage Tank

    SciTech Connect (OSTI)

    Bradley K. Griffith

    2011-12-01T23:59:59.000Z

    This closure package documents the site assessment and permanent closure of the TAN-664 gasoline underground storage tank in accordance with the regulatory requirements established in 40 CFR 280.71, 'Technical Standards and Corrective Action Requirements for Owners and Operators of Underground Storage Tanks: Out-of-Service UST Systems and Closure.'

  12. MAE Seminar Series Boundary Closures for

    E-Print Network [OSTI]

    Krovi, Venkat

    ) boundary layer stability and transition. 206 Furnas Hall Thursday, April 8th, 2010 11:00 am ­ 12:00 pmMAE Seminar Series Boundary Closures for ESWENO Schemes Mark H. Carpenter, Ph.D. Computational AeroSciences Branch NASA Langley Research Center Abstract Energy Stable Weighted Essentially Non--Oscillatory (ESWENO

  13. Field Sampling Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System - 1997 Notice of Violation Consent Order

    SciTech Connect (OSTI)

    Evans, S.K.

    2002-01-31T23:59:59.000Z

    This Field Sampling Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System is one of two documents that comprise the Sampling and Analysis Plan for the HWMA/RCRA closure certification of the TRA-731 caustic and acid storage tank system at the Idaho National Engineering and Environmental Laboratory. This plan, which provides information about sampling design, required analyses, and sample collection and handling procedures, is to be used in conjunction with the Quality Assurance Project Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System.

  14. Field Sampling Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System - 1997 Notice of Violation Consent Order

    SciTech Connect (OSTI)

    Evans, Susan Kay; Orchard, B. J.

    2002-01-01T23:59:59.000Z

    This Field Sampling Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System is one of two documents that comprise the Sampling and Analysis Plan for the HWMA/RCRA closure certification of the TRA-731 caustic and acid storage tank system at the Idaho National Engineering and Environmental Laboratory. This plan, which provides information about sampling design, required analyses, and sample collection and handling procedures, is to be used in conjunction with the Quality Assurance Project Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System.

  15. Title I conceptual design for Pit 6 landfill closure at Lawrence Livermore National Laboratory Site 300

    SciTech Connect (OSTI)

    MacDonnell, B.A.; Obenauf, K.S. [Golder Associates, Inc., Alameda, CA (United States)

    1996-08-01T23:59:59.000Z

    The objective of this design project is to evaluate and prepare design and construction documents for a closure cover cap for the Pit 6 Landfill located at Lawrence Livermore National Laboratory Site 300. This submittal constitutes the Title I Design (Conceptual Design) for the closure cover of the Pit 6 Landfill. A Title I Design is generally 30 percent of the design effort. Title H Design takes the design to 100 percent complete. Comments and edits to this Title I Design will be addressed in the Title II design submittal. Contents of this report are as follows: project background; design issues and engineering approach; design drawings; calculation packages; construction specifications outline; and construction quality assurance plan outline.

  16. Independent Oversight Special Review, Rocky Flats Closure Project...

    Energy Savers [EERE]

    The review focused on two areas of concern: (1) implementation of the integrated work control process and line management oversight and (2) internal radiation doses received by...

  17. Contract and Project Management Improvement (CPMI) Closure Report -- April

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative FuelsNovember 13, 2014 BuildingEnergyEnergyConsortiumContacts Contacts2012 |

  18. DOE, Washington Closure complete recycling project at Hanford | Department

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011AT&T,Office of Policy, OAPM |TRUJuly 29,of Energyof EnergyDepartment of|of

  19. DOE, Washington Closure complete recycling project at Hanford | Department

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny: Theof"WaveInteractionsMaterialsDevelopEnergyof

  20. ROCKY FLATS CLOSURE PROJECT EM, AUG 2006 | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently20,000 RussianBy: ThomasDepartment ofThisHiTek logo HiTekLoans |DTEFrequency |Rocky

  1. Voluntary Protection Program Onsite Review, River Corridor Closure Project

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently20,000 Russian Nuclear Warheads| DepartmentVictor Kane AboutContract -Energy - February-

  2. Independent Oversight Special Review, Rocky Flats Closure Project Site -

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently Asked Questions for DOEthe RankingReform atSolar2014 || DepartmentMarch 2013|2011

  3. Calcined solids storage facility closure study

    SciTech Connect (OSTI)

    Dahlmeir, M.M.; Tuott, L.C.; Spaulding, B.C. [and others] [and others

    1998-02-01T23:59:59.000Z

    The disposal of radioactive wastes now stored at the Idaho National Engineering and Environmental Laboratory is currently mandated under a {open_quotes}Settlement Agreement{close_quotes} (or {open_quotes}Batt Agreement{close_quotes}) between the Department of Energy and the State of Idaho. Under this agreement, all high-level waste must be treated as necessary to meet the disposal criteria and disposed of or made road ready to ship from the INEEL by 2035. In order to comply with this agreement, all calcined waste produced in the New Waste Calcining Facility and stored in the Calcined Solids Facility must be treated and disposed of by 2035. Several treatment options for the calcined waste have been studied in support of the High-Level Waste Environmental Impact Statement. Two treatment methods studied, referred to as the TRU Waste Separations Options, involve the separation of the high-level waste (calcine) into TRU waste and low-level waste (Class A or Class C). Following treatment, the TRU waste would be sent to the Waste Isolation Pilot Plant (WIPP) for final storage. It has been proposed that the low-level waste be disposed of in the Tank Farm Facility and/or the Calcined Solids Storage Facility following Resource Conservation and Recovery Act closure. In order to use the seven Bin Sets making up the Calcined Solids Storage Facility as a low-level waste landfill, the facility must first be closed to Resource Conservation and Recovery Act (RCRA) standards. This study identifies and discusses two basic methods available to close the Calcined Solids Storage Facility under the RCRA - Risk-Based Clean Closure and Closure to Landfill Standards. In addition to the closure methods, the regulatory requirements and issues associated with turning the Calcined Solids Storage Facility into an NRC low-level waste landfill or filling the bin voids with clean grout are discussed.

  4. Relationship Between Flowability And Tank Closure Grout Quality

    SciTech Connect (OSTI)

    Langton, C. A.; Stefanko, D. B.; Hay, M. S.

    2012-10-08T23:59:59.000Z

    After completion of waste removal and chemical cleaning operations, Tanks 5-F and 6-F await final closure. The project will proceed with completing operational closure by stabilizing the tanks with grout. Savannah River Remediation's (SRR) experience with grouting Tanks 18-F and 19-F showed that slump-flow values were correlated with flow/spread inside these tanks. Less mounding was observed when using grouts with higher slump-flow. Therefore, SRNL was requested to evaluate the relationship between flowability and cured properties to determine whether the slump-flow maximum spread of Mix LP#8-16 could be increased from 28 inches to 30 inches without impacting the grout quality. A request was also made to evaluate increasing the drop height from 5 feet to 10 feet with the objective of enhancing the flow inside the tank by imparting more kinetic energy to the placement. Based on a review of the grout property data for Mix LP#8-16 collected from Tank 18-F and 19-F quality control samples, the upper limit for slump-flow measured per ASTM C 1611 can be increased from 28 to 30 inches without affecting grout quality. However, testing should be performed prior to increasing the drop height from 5 to 10 feet or observations should be made during initial filling operations to determine whether segregation occurs as a function of drop heights between 5 and 10 feet. Segregation will negatively impact grout quality. Additionally, increasing the delivery rate of grout into Tanks 5-F and 6-F by using a higher capacity concrete/grout pump will result in better grout spread/flow inside the tanks.

  5. Post-closure permit application for the Kerr Hollow Quarry at the Y-12 plant

    SciTech Connect (OSTI)

    NONE

    1995-06-01T23:59:59.000Z

    The Kerr Hollow Quarry (KHQ) is located on U.S. Department of Energy (DOE) property at the Y-12 Plant, Oak Ridge, Tennessee. The Oak Ridge Y-12 Plant was built by the U.S. Army Corps of Engineers in 1943 as part of the Manhattan Project. Until 1992, the primary mission of the Y-12 Plant was the production and fabrication of nuclear weapons components. Activities associated with these functions included production of lithium compounds, recovery of enriched uranium from scrap material, and fabrication of uranium and other materials into finished parts for assemblies. The Kerr Hollow Quarry was used for waste disposal of a variety of materials including water-reactive and shock-sensitive chemicals and compressed gas cylinders. These materials were packaged in various containers and sank under the water in the quarry due to their great weight. Disposal activities were terminated in November, 1988 due to a determination by the Tennessee Department of Environment and Conservation that the quarry was subject to regulations under the Resource Conservation and Recovery Act of 1993. Methods of closure for the quarry were reviewed, and actions were initiated to close the quarry in accordance with closure requirements for interim status surface impoundments specified in Tennessee Rules 1200-1-11-.05(7) and 1200-1-11-.05(11). As part of these actions, efforts were made to characterize the physical and chemical nature of wastes that had been disposed of in the quarry, and to remove any containers or debris that were put into the quarry during waste disposal activities. Closure certification reports (Fraser et al. 1993 and Dames and Moore 1993) document closure activities in detail. This report contains the post-closure permit application for the Kerr Hollow Quarry site.

  6. 3718-F Alkali Metal Treatment and Storage Facility Closure Plan

    SciTech Connect (OSTI)

    none,

    1991-12-01T23:59:59.000Z

    Since 1987, Westinghouse Hanford Company has been a major contractor to the U.S. Department of Energy-Richland Operations Office and has served as co-operator of the 3718-F Alkali Metal Treatment and Storage Facility, the waste management unit addressed in this closure plan. The closure plan consists of a Part A Dangerous waste Permit Application and a RCRA Closure Plan. An explanation of the Part A Revision (Revision 1) submitted with this document is provided at the beginning of the Part A section. The closure plan consists of 9 chapters and 5 appendices. The chapters cover: introduction; facility description; process information; waste characteristics; groundwater; closure strategy and performance standards; closure activities; postclosure; and references.

  7. Bat Surveys of Retired Facilitiies Scheduled for Demolition by Washington Closure Hanford

    SciTech Connect (OSTI)

    Gano, K. A.; Lucas, J. G.; Lindsey, C. T.

    2011-06-30T23:59:59.000Z

    This project was conducted to evaluate buildings and facilities remaining in the Washington Closure Hanford (WCH) deactivation, decontamination, decommissioning, and demolition schedule for bat roost sites. The project began in spring of 2009 and was concluded in spring of 2011. A total of 196 buildings and facilities were evaluated for the presence of bat roosting sites. The schedule for the project was prioritized to accommodate the demolition schedule. As the surveys were completed, the results were provided to the project managers to facilitate planning and project completion. The surveys took place in the 300 Area, 400 Area, 100-H, 100-D, 100-N, and 100-B/C Area. This report is the culmination of all the bat surveys and summarizes the findings by area and includes recommended mitigation actions where bat roosts were found.

  8. PERFORMANCE OF A CONTAINMENT VESSEL CLOSURE FOR RADIOACTIVE GAS CONTENTS

    SciTech Connect (OSTI)

    Blanton, P.; Eberl, K.

    2010-07-09T23:59:59.000Z

    This paper presents a summary of the design and testing of the containment vessel closure for the Bulk Tritium Shipping Package (BTSP). This package is a replacement for a package that has been used to ship tritium in a variety of content configurations and forms since the early 1970s. The containment vessel closure incorporates features specifically designed for the containment of tritium when subjected to the normal and hypothetical conditions required of Type B radioactive material shipping Packages. The paper discusses functional performance of the containment vessel closure of the BTSP prototype packages and separate testing that evaluated the performance of the metallic C-Rings used in a mock BTSP closure.

  9. The Chvátal-Gomory Closure of a Strictly Convex Body

    E-Print Network [OSTI]

    Megiddo

    2010-05-02T23:59:59.000Z

    Key words: nonlinear integer programming; cutting planes; Chvatal-Gomory closure. MSC2000 ... OR/MS subject classification: Primary: Integer - Nonlinear. 1

  10. Tank Closure and Waste Management Environmental Impact Statement...

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

    describes the public comment process for the Draft Tank Closure and Waste Management Environmental Impact Statement for the Hanford Site, Richland, Washington (Draft TC & WM...

  11. News Release Closure of Russian Nuclear Plant.PDF

    National Nuclear Security Administration (NNSA)

    CONTACTS: FOR IMMEDIATE RELEASE Jonathan Kiell, 202586-7371 September 27, 2001 Date Set for Closure of Russian Nuclear Weapons Plant U.S. National Nuclear Security Administration...

  12. Date Set for Closure of Russian Nuclear Weapons Plant - NNSA...

    National Nuclear Security Administration (NNSA)

    Date Set for Closure of Russian Nuclear Weapons Plant - NNSA Is Helping Make It Happen | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission...

  13. LABORATORY NEW HIRE NOTICE: LABORATORY DELAYED OPENING OR CLOSURE...

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

    LABORATORY NEW HIRE NOTICE: LABORATORY DELAYED OPENING OR CLOSURE DUE TO INCLEAMENT WEATHER During the winter months, the Los Alamos National Laboratory (LANL) may at times...

  14. Type B Accident Investigation At Washington Closure Hanford,...

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

    Fall Injury on July 1, 2009, At The 336 Building, Hanford Site, Washington Type B Accident Investigation At Washington Closure Hanford, LLC, Employee Fall Injury on July 1,...

  15. Closures for Course-Grid Simulation of Fluidized Gas-Particle Flows

    SciTech Connect (OSTI)

    Sankaran Sundaresan

    2010-02-14T23:59:59.000Z

    Gas-particle flows in fluidized beds and riser reactors are inherently unstable, and they manifest fluctuations over a wide range of length and time scales. Two-fluid models for such flows reveal unstable modes whose length scale is as small as ten particle diameters. Yet, because of limited computational resources, gas-particle flows in large fluidized beds are invariably simulated by solving discretized versions of the two-fluid model equations over a coarse spatial grid. Such coarse-grid simulations do not resolve the small-scale spatial structures which are known to affect the macroscale flow structures both qualitatively and quantitatively. Thus there is a need to develop filtered two-fluid models which are suitable for coarse-grid simulations and capturing the effect of the small-scale structures through closures in terms of the filtered variables. The overall objective of the project is to develop validated closures for filtered two-fluid models for gas-particle flows, with the transport gasifier as a primary, motivating example. In this project, highly resolved three-dimensional simulations of a kinetic theory based two-fluid model for gas-particle flows have been performed and the statistical information on structures in the 100-1000 particle diameters length scale has been extracted. Based on these results, closures for filtered two-fluid models have been constructed. The filtered model equations and closures have been validated against experimental data and the results obtained in highly resolved simulations of gas-particle flows. The proposed project enables more accurate simulations of not only the transport gasifier, but also many other non-reacting and reacting gas-particle flows in a variety of chemical reactors. The results of this study are in the form of closures which can readily be incorporated into existing multi-phase flow codes such as MFIX (www.mfix.org). Therefore, the benefits of this study can be realized quickly. The training provided by this project has prepared a PhD student to enter research and development careers in DOE laboratories or chemicals/energy-related industries.

  16. 100-N Area underground storage tank closures

    SciTech Connect (OSTI)

    Rowley, C.A.

    1993-08-01T23:59:59.000Z

    This report describes the removal/characterization actions concerning underground storage tanks (UST) at the 100-N Area. Included are 105-N-LFT, 182-N-1-DT, 182-N-2-DT, 182-N-3-DT, 100-N-SS-27, and 100-N-SS-28. The text of this report gives a summary of remedial activities. In addition, correspondence relating to UST closures can be found in Appendix B. Appendix C contains copies of Unusual Occurrence Reports, and validated sampling data results comprise Appendix D.

  17. Closure End States for Facilities, Waste Sites, and Subsurface Contamination

    SciTech Connect (OSTI)

    Gerdes, Kurt D.; Chamberlain, Grover S.; Wellman, Dawn M.; Deeb, Rula A.; Hawley, Elizabeth L.; Whitehurst, Latrincy; Marble, Justin

    2012-11-21T23:59:59.000Z

    The United States (U.S.) Department of Energy (DOE) manages the largest groundwater and soil cleanup effort in the world. DOE’s Office of Environmental Management (EM) has made significant progress in its restoration efforts at sites such as Fernald and Rocky Flats. However, remaining sites, such as Savannah River Site, Oak Ridge Site, Hanford Site, Los Alamos, Paducah Gaseous Diffusion Plant, Portsmouth Gaseous Diffusion Plant, and West Valley Demonstration Project possess the most complex challenges ever encountered by the technical community and represent a challenge that will face DOE for the next decade. Closure of the remaining 18 sites in the DOE EM Program requires remediation of 75 million cubic yards of contaminated soil and 1.7 trillion gallons of contaminated groundwater, deactivation & decommissioning (D&D) of over 3000 contaminated facilities and thousands of miles of contaminated piping, removal and disposition of millions of cubic yards of legacy materials, treatment of millions of gallons of high level tank waste and disposition of hundreds of contaminated tanks. The financial obligation required to remediate this volume of contaminated environment is estimated to cost more than 7% of the to-go life-cycle cost. Critical in meeting this goal within the current life-cycle cost projections is defining technically achievable end states that formally acknowledge that remedial goals will not be achieved for a long time and that residual contamination will be managed in the interim in ways that are protective of human health and environment. Formally acknowledging the long timeframe needed for remediation can be a basis for establishing common expectations for remedy performance, thereby minimizing the risk of re-evaluating the selected remedy at a later time. Once the expectations for long-term management are in place, remedial efforts can be directed towards near-term objectives (e.g., reducing the risk of exposure to residual contamination) instead of focusing on long-term cleanup requirements. An acknowledgement of the long timeframe for complete restoration and the need for long-term management can also help a site transition from the process of pilot testing different remedial strategies to selecting a final remedy and establishing a long-term management and monitoring approach. This approach has led to cost savings and the more efficient use of resources across the Department of Defense complex and at numerous industrial sites across the U.S. Defensible end states provide numerous benefits for the DOE environmental remediation programs including cost-effective, sustainable long-term monitoring strategies, remediation and site transition decision support, and long-term management of closure sites.

  18. Remote controlled vacuum joint closure mechanism

    DOE Patents [OSTI]

    Doll, David W. (San Diego, CA); Hager, E. Randolph (La Jolla, CA)

    1986-01-01T23:59:59.000Z

    A remotely operable and maintainable vacuum joint closure mechanism for a noncircular aperture is disclosed. The closure mechanism includes an extendible bellows coupled at one end to a noncircular duct and at its other end to a flange assembly having sealed grooves for establishing a high vacuum seal with the abutting surface of a facing flange which includes an aperture forming part of the system to be evacuated. A plurality of generally linear arrangements of pivotally coupled linkages and piston combinations are mounted around the outer surface of the duct and aligned along the length thereof. Each of the piston/linkage assemblies is adapted to engage the flange assembly by means of a respective piston and is further coupled to a remote controlled piston drive shaft to permit each of the linkages positioned on a respective flat outer surface of the duct to simultaneously and uniformly displace a corresponding piston and the flange assembly with which it is in contact along the length of the duct in extending the bellows to provide a high vacuum seal between the movable flange and the facing flange. A plurality of latch mechanisms are also pivotally mounted on the outside of the duct. A first end of each of the latch mechanisms is coupled to a remotely controlled latch control shaft for displacing the latch mechanism about its pivot point. In response to the pivoting displacement of the latch mechanism, a second end thereof is displaced so as to securely engage the facing flange.

  19. CLOSURE WELD DEVELOPMENT FOR 3013 OUTER CONTAINERS

    SciTech Connect (OSTI)

    Daugherty, W.; Howard, S.; Peterson, K.; Stokes, M.

    2009-11-10T23:59:59.000Z

    Excess plutonium materials in the DOE complex are packaged and stored in accordance with DOE-STD-3013. This standard specifies requirements for the stabilization of such materials and subsequent packaging in dual nested seal-welded containers. Austenitic stainless steels have been selected for container fabrication. The inner 3013 container provides contamination control while the outer 3013 container is the primary containment vessel and is the focus of this paper. Each packaging site chose a process for seal welding the outer 3013 containers in accordance with its needs and expertise. The two processes chosen for weld closure were laser beam welding (LBW) and gas tungsten arc welding (GTAW). Following development efforts, each system was qualified in accordance with DOE-STD-3013 prior to production use. The 3013 outer container closure weld joint was designed to accommodate the characteristics of a laser weld. This aspect of the joint design necessitated some innovative process and equipment considerations in the application of the GTAW process. Details of the weld requirements and the development processes are presented and several potential enhancements for the GTAW system are described.

  20. WASTE PACKAGE OPERATIONS FY99 CLOSURE METHODS REPORT

    SciTech Connect (OSTI)

    M. C. Knapp

    1999-09-23T23:59:59.000Z

    The waste package (WP) closure weld development task is part of a larger engineering development program to develop waste package designs. The purpose of the larger waste package engineering development program is to develop nuclear waste package fabrication and closure methods that the Nuclear Regulatory Commission will find acceptable and will license for disposal of spent nuclear fuel (SNF), non-fuel components, and vitrified high-level waste within a Monitored Geologic Repository (MGR). Within the WP closure development program are several major development tasks, which, in turn, are divided into subtasks. The major tasks include: WP fabrication development, WP closure weld development, nondestructive examination (NDE) development, and remote in-service inspection development. The purpose of this report is to present the objectives, technical information, and work scope relating to the WP closure weld development.and NDE tasks and subtasks and to report results of the closure weld and NDE development programs for fiscal year 1999 (FY-99). The objective of the FY-99 WP closure weld development task was to develop requirements for closure weld surface and volumetric NDE performance demonstrations, investigate alternative NDE inspection techniques, and develop specifications for welding, NDE, and handling system integration. In addition, objectives included fabricating several flat plate mock-ups that could be used for NDE development, stress relief peening, corrosion testing, and residual stress testing.

  1. Construction quality assurance for Pit 6 landfill closure, Lawrence Livermore National Laboratory, Site 300

    SciTech Connect (OSTI)

    NONE

    1997-10-30T23:59:59.000Z

    Golder Construction Services, Inc. (GCS), under contract to the Regents of the University of California, Lawrence Livermore National Laboratory (LLNL), provided the construction quality assurance (CQA) observation and testing during the construction of the Site 300, Pit 6 landfill closure cover. The cap construction was performed as a CERCLA non-time-critical removal action from June 2 to August 29, 1997. the project site is located 18 miles east of Livermore on Tesla Road and approximately 10 miles southwest of Tracy on Corral Hollow Road in San Joaquin County, California. This report certifies that the LLNL, Site 300, Pit 6, Landfill Closure was constructed in accordance with the construction specifications and design drawings. This report documents construction activities and CQA monitoring and testing for construction of the Pit 6 Landfill Closure. Golder Associates, Inc. of Oakland, California was the design engineering firm responsible for preparation of the drawings and specifications. CQA services were provided by GCS, of Roseville, California, under supervision of a California registered civil Engineer.

  2. Regulatory issues associated with closure of the Hanford AX Tank Farm ancillary equipment

    SciTech Connect (OSTI)

    Becker, D.L.

    1998-09-02T23:59:59.000Z

    Liquid mixed, high-level radioactive waste has been stored in underground single-shell tanks at the US Department of Energy`s (DOE`s) Hanford Site. After retrieval of the waste from the single-shell tanks, the DOE will proceed with closure of the tank farm. The 241-AX Tank Farm includes four one-million gallon single-shell tanks in addition to sluice lines, transfer lines, ventilation headers, risers, pits, cribs, catch tanks, buildings, well and associated buried piping. This equipment is classified as ancillary equipment. This document addresses the requirements for regulatory close of the ancillary equipment in the Hanford Site 241-AX Tank Farm. The options identified for physical closure of the ancillary equipment include disposal in place, disposal in place after treatment, excavation and disposal on site in an empty single-shell tank, and excavation and disposal outside the AX Tank Farm. The document addresses the background of the Hanford Site and ancillary equipment in the AX Tank Farm, regulations for decontamination and decommissioning of radioactively contaminated equipment, requirements for the cleanup and disposal of radioactive wastes, cleanup and disposal requirements governing hazardous and mixed waste, and regulatory requirements and issues associated with each of the four physical closure options. This investigation was conducted by the Sandia National Laboratories, Albuquerque, New Mexico, during Fiscal Year 1998 for the Hanford Tanks Initiative Project.

  3. TECHNICAL PEER REVIEW REPORT - YUCCA MOUNTAIN: WASTE PACKAGE CLOSURE CONTROL SYSTEM

    SciTech Connect (OSTI)

    NA

    2005-10-25T23:59:59.000Z

    The objective of the Waste Package Closure System (WPCS) project is to assist in the disposal of spent nuclear fuel (SNF) and associated high-level wastes (HLW) at the Yucca Mountain site in Nevada. Materials will be transferred from the casks into a waste package (WP), sealed, and placed into the underground facility. The SNF/HLW transfer and closure operations will be performed in an aboveground facility. The objective of the Control System is to bring together major components of the entire WPCS ensuring that unit operations correctly receive, and respond to, commands and requests for data. Integrated control systems will be provided to ensure that all operations can be performed remotely. Maintenance on equipment may be done using hands-on or remote methods, depending on complexity, exposure, and ease of access. Operating parameters and nondestructive examination results will be collected and stored as permanent electronic records. Minor weld repairs must be performed within the closure cell if the welds do not meet the inspection acceptance requirements. Any WP with extensive weld defects that require lids to be removed will be moved to the remediation facility for repair.

  4. 2101-M pond closure plan. Volume 1, Revision 2

    SciTech Connect (OSTI)

    Izatt, R. D.; Lerch, R. E.

    1993-06-01T23:59:59.000Z

    This document describes activities for the closure of a surface impoundment (2101-M Pond) at the Hanford Site. The 2101-H Pond was initially constructed in 1953 to serve as a drainage collection area for the 2101-H Building. (Until the Basalt Waste Isolation Project (BWIP) Laboratory was constructed in the 2101-M Building in 1979--1981, the only source contributing discharge to the pond was condensate water from the 2101-H Building heating, ventilation, and air conditioning (HVAC) system. The drains for the BWIP Laboratory rooms were plumbed into a 4-in., cast-iron, low-pressure drain pipe that carries waste water from the HVAC system to the pond. During the active life of the BWIP Laboratory, solutions of dissolved barium in groundwater samples were discharged to the 2101-M Pond via the laboratory drains. As a result of the discharges, a Part A permit application was initially submitted to the Washington State Department of Ecology (Ecology) in August 1986 which designates the 2101-M Pond as a surface impoundment.

  5. Closure head for a nuclear reactor

    DOE Patents [OSTI]

    Wade, Elman E. (South Huntingdon, PA)

    1980-01-01T23:59:59.000Z

    A closure head for a nuclear reactor includes a stationary outer ring integral with the reactor vessel with a first rotatable plug disposed within the stationary outer ring and supported from the stationary outer ring by a bearing assembly. A sealing system is associated with the bearing assembly to seal the annulus defined between the first rotatable plug and the stationary outer ring. The sealing system comprises tubular seal elements disposed in the annulus with load springs contacting the tubular seal elements so as to force the tubular seal elements against the annulus in a manner to seal the annulus. The sealing system also comprises a sealing fluid which is pumped through the annulus and over the tubular seal elements causing the load springs to compress thereby reducing the friction between the tubular seal elements and the rotatable components while maintaining a gas-tight seal therebetween.

  6. Remote controlled vacuum joint closure mechanism

    DOE Patents [OSTI]

    Doll, D.W.; Hager, E.R.

    1984-02-22T23:59:59.000Z

    A remotely operable and maintainable vacuum joint closure mechanism for a noncircular aperture is disclosed. The closure mechanism includes an extendible bellows coupled at one end to a noncircular duct and at its other end to a flange assembly having sealed grooves for establishing a high vacuum seal with the abutting surface of a facing flange which includes an aperture forming part of the system to be evacuated. A plurality of generally linear arrangements of pivotally coupled linkages and piston combinations are mounted around the outer surface of the duct and aligned along the length thereof. Each of the piston/linkage assemblies is adapted to engage the flange assembly by means of a respective piston and is further coupled to a remote controlled piston drive shaft to permit each of the linkages positioned on a respective flat outer surface of the duct to simultaneously and uniformly displace a corresponding piston and the flange assembly with which it is in contact along the length of the duct in extending the bellows to provide a high vacuum seal between the movable flange and the facing flange. A plurality of latch mechanisms are also pivotally mounted on the outside of the duct. A first end of each of the latch mechanisms is coupled to a remotely controlled latch control shaft for displacing the latch mechanism about its pivot point. In response to the pivoting displacement of the latch mechanism, a second end thereof is displaced so as to securely engage the facing flange and maintain the high vacuum seal established by the displacement of the flange assembly and extension of the bellows without displacing the entire duct.

  7. ICPP tank farm closure study. Volume 1

    SciTech Connect (OSTI)

    Spaulding, B.C.; Gavalya, R.A.; Dahlmeir, M.M. [and others

    1998-02-01T23:59:59.000Z

    The disposition of INEEL radioactive wastes is now under a Settlement Agreement between the DOE and the State of Idaho. The Settlement Agreement requires that existing liquid sodium bearing waste (SBW), and other liquid waste inventories be treated by December 31, 2012. This agreement also requires that all HLW, including calcined waste, be disposed or made road ready to ship from the INEEL by 2035. Sodium bearing waste (SBW) is produced from decontamination operations and HLW from reprocessing of SNF. SBW and HLW are radioactive and hazardous mixed waste; the radioactive constituents are regulated by DOE and the hazardous constituents are regulated by the Resource Conservation and Recovery Act (RCRA). Calcined waste, a dry granular material, is produced in the New Waste Calcining Facility (NWCF). Two primary waste tank storage locations exist at the ICPP: Tank Farm Facility (TFF) and the Calcined Solids Storage Facility (CSSF). The TFF has the following underground storage tanks: four 18,400-gallon tanks (WM 100-102, WL 101); four 30,000-gallon tanks (WM 103-106); and eleven 300,000+ gallon tanks. This includes nine 300,000-gallon tanks (WM 182-190) and two 318,000 gallon tanks (WM 180-181). This study analyzes the closure and subsequent use of the eleven 300,000+ gallon tanks. The 18,400 and 30,000-gallon tanks were not included in the work scope and will be closed as a separate activity. This study was conducted to support the HLW Environmental Impact Statement (EIS) waste separations options and addresses closure of the 300,000-gallon liquid waste storage tanks and subsequent tank void uses. A figure provides a diagram estimating how the TFF could be used as part of the separations options. Other possible TFF uses are also discussed in this study.

  8. Laboratory testing of closure cap repair techniques

    SciTech Connect (OSTI)

    Persoff, P.; Moridis, G. [Lawrence Berkeley National Lab., CA (United States); Tuck, D.M. [Westinghouse Savannah River Company, Aiken, SC (United States)] [and others

    1996-10-01T23:59:59.000Z

    Landfill design requires a low permeability closure cap as well as a low permeability liner. The Savannah River Site, in South Carolina, has approximately 85 acres of mixed waste landfills covered with compacted kaolin clay. Maintaining low permeability of the clay cap requires both that the permeability of the compacted clay itself remain low and that the integrity of the barrier be maintained. Barrier breaches typically result from penetration by roots or animals, and especially cracks caused by uneven settling or desiccation. In this study, clay layers, 0.81 m in diameter and 7.6 cm thick, were compacted in 7 lysimeters to simulate closure caps. The hydraulic conductivity of each layer was measured, and the compacted clay layers (CCL`s) were cracked by drying. Then various repair techniques were applied and the effectiveness of each repair was assessed by remeasuring the hydraulic conductivity. Finally the repaired CCL was again dried and measured to determine how the repair responded to the conditions that caused the original failure. For a full report of this investigation see Persoff et al. Six repair techniques have been tested, four of which involve the use of injectable barrier liquids colloidal silica (CS) and polysiloxane (PSX) described below: (I) covering the crack with a bentonite geosynthetic clay liner (GCL), (ii) recompaction of new kaolinite at STD+3 moisture content joined to existing kaolinite that had dried and shrunk, (iii) direct injection of colloidal silica to a crack, (iv) injection of colloidal silica (CS) to wells in an overlying sand layer, (v) direct injection of polysiloxane to a crack, and (vi), injection of polysiloxane (PSX) to wells in an overlying soil layer.

  9. Spurious Shell Closures in the Relativistic Mean Field Model

    E-Print Network [OSTI]

    L. S. Geng; J. Meng; H. Toki; W. H. Long; G. Shen

    2006-03-10T23:59:59.000Z

    Following a systematic theoretical study of the ground-state properties of over 7000 nuclei from the proton drip line to the neutron drip line in the relativistic mean field model [Prog. Theor. Phys. 113 (2005) 785], which is in fair agreement with existing experimental data, we observe a few spurious shell closures, i.e. proton shell closures at Z=58 and Z=92. These spurious shell closures are found to persist in all the effective forces of the relativistic mean field model, e.g. TMA, NL3, PKDD and DD-ME2.

  10. CLOSURE REPORT FOR CORRECTIVE ACTION UNIT 214: BUNKERS AND STORAGE AREAS NEVADA TEST SITE, NEVADA

    SciTech Connect (OSTI)

    NONE

    2006-09-01T23:59:59.000Z

    The purpose of this Closure Report is to document that the closure of CAU 214 complied with the Nevada Division of Environmental Protection-approved Corrective Action Plan closure requirements. The closure activities specified in the Corrective Action Plan were based on the approved corrective action alternatives presented in the CAU 214 Corrective Action Decision Document.

  11. Economic evaluation of closure cap barrier materials study

    SciTech Connect (OSTI)

    Serrato, M.G.; Bhutani, J.S.; Mead, S.M.

    1993-09-01T23:59:59.000Z

    Volume II of the Economic Evaluation of the Closure Cap Barrier Materials, Revision I contains detailed cost estimates for closure cap barrier materials. The cost estimates incorporate the life cycle costs for a generic hazardous waste seepage basin closure cap under the RCRA Post Closure Period of thirty years. The economic evaluation assessed six barrier material categories. Each of these categories consists of several composite cover system configurations, which were used to develop individual cost estimates. The information contained in this report is not intended to be used as a cost estimating manual. This information provides the decision makers with the ability to screen barrier materials, cover system configurations, and identify cost-effective materials for further consideration.

  12. Nonlinear closures for scale separation in supersonic magnetohydrodynamic turbulence

    E-Print Network [OSTI]

    Grete, Philipp; Schmidt, Wolfram; Schleicher, Dominik R G; Federrath, Christoph

    2015-01-01T23:59:59.000Z

    Turbulence in compressible plasma plays a key role in many areas of astrophysics and engineering. The extreme plasma parameters in these environments, e.g. high Reynolds numbers, supersonic and super-Alfvenic flows, however, make direct numerical simulations computationally intractable even for the simplest treatment -- magnetohydrodynamics (MHD). To overcome this problem one can use subgrid-scale (SGS) closures -- models for the influence of unresolved, subgrid-scales on the resolved ones. In this work we propose and validate a set of constant coefficient closures for the resolved, compressible, ideal MHD equations. The subgrid-scale energies are modeled by Smagorinsky-like equilibrium closures. The turbulent stresses and the electromotive force (EMF) are described by expressions that are nonlinear in terms of large scale velocity and magnetic field gradients. To verify the closures we conduct a priori tests over 137 simulation snapshots from two different codes with varying ratios of thermal to magnetic pre...

  13. Stress analysis of closure bolts for shipping casks

    SciTech Connect (OSTI)

    Mok, G.C.; Fischer, L.E. (Lawrence Livermore National Lab., CA (United States)); Hsu, S.T. (Kaiser Engineers, Oakland, CA (United States))

    1993-01-01T23:59:59.000Z

    This report specifies the requirements and criteria for stress analysis of closure bolts for shipping casks containing nuclear spent fuels or high level radioactive materials. The specification is based on existing information conceming the structural behavior, analysis, and design of bolted joints. The approach taken was to extend the ASME Boiler and Pressure Vessel Code requirements and criteria for bolting analysis of nuclear piping and pressure vessels to include the appropriate design and load characteristics of the shipping cask. The characteristics considered are large, flat, closure lids with metal-to-metal contact within the bolted joint; significant temperature and impact loads; and possible prying and bending effects. Specific formulas and procedures developed apply to the bolt stress analysis of a circular, flat, bolted closure. The report also includes critical load cases and desirable design practices for the bolted closure, an in-depth review of the structural behavior of bolted joints, and a comprehensive bibliography of current information on bolted joints.

  14. On freeway traffic control by a lane closure

    E-Print Network [OSTI]

    Henderson, Donald Manson

    1971-01-01T23:59:59.000Z

    ON PREENAY TRAPPIC CONTROL BY. A LANE CLOSURE A Thesis by DONALD MANSON HENDERSON Submitted to the. Graduate College of Texas A&M University in partial fulfillment of the requirement. for the degree of MASTER OP SCIENCE Ma)or Suh]ect: Civil... Engineering August 1971 ON FREEWAY TRAFFIC CONTROL BY A LANE CLOSURE A Thesis by DONALD MANSON HENDERSON Approved as to style and content by: (Chairman of ommittee) (Head of Departmen (Member) (Member) (Member) ember) (Member) August 1971 ABSTRACT...

  15. Design Alternative Evaluation No. 3: Post-Closure Ventilation

    SciTech Connect (OSTI)

    Logan, R.C.

    1999-06-22T23:59:59.000Z

    The objective of this study is to provide input to the Enhanced Design Alternatives (EDA) for License Application Design Selection (LADS). Its purpose is to develop and evaluate conceptual designs for post-closure ventilation alternatives that enhance repository performance. Post-closure ventilation is expected to enhance repository performance by limiting the amount of water contacting the waste packages. Limiting the amount of water contacting the waste packages will reduce corrosion.

  16. CLOSURE REPORT FOR CORRECTIVE ACTION UNIT 528: POLYCHLORINATED BIPHENYLS CONTAMINATION NEVADA TEST SITE, NEVADA

    SciTech Connect (OSTI)

    BECHTEL NEVADA

    2006-09-01T23:59:59.000Z

    This Closure Report (CR) describes the closure activities performed at CAU 528, Polychlorinated Biphenyls Contamination, as presented in the Nevada Division of Environmental Protection (NDEP)-approved Corrective Action Plan (CAP) (US. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSAINSO], 2005). The approved closure alternative was closure in place with administrative controls. This CR provides a summary of the completed closure activities, documentation of waste disposal, and analytical data to confirm that the remediation goals were met.

  17. ICPP calcined solids storage facility closure study. Volume III: Engineering design files

    SciTech Connect (OSTI)

    NONE

    1998-02-01T23:59:59.000Z

    The following information was calculated to support cost estimates and radiation exposure calculations for closure activities at the Calcined Solids Storage Facility (CSSF). Within the estimate, volumes were calculated to determine the required amount of grout to be used during closure activities. The remaining calcine on the bin walls, supports, piping, and floor was also calculated to approximate the remaining residual calcine volumes at different stages of the removal process. The estimates for remaining calcine and vault void volume are higher than what would actually be experienced in the field, but are necessary for bounding purposes. The residual calcine in the bins may be higher than was is experienced in the field as it was assumed that the entire bin volume is full of calcine before removal activities commence. The vault void volumes are higher as the vault roof beam volumes were neglected. The estimations that follow should be considered rough order of magnitude, due to the time constraints as dictated by the project`s scope of work. Should more accurate numbers be required, a new analysis would be necessary.

  18. Remedial Action Work Plan Amchitka Island Mud Pit Closures

    SciTech Connect (OSTI)

    DOE/NV

    2001-04-05T23:59:59.000Z

    This remedial action work plan presents the project organization and construction procedures developed for the performance of the remedial actions at U.S. Department of Energy (DOE's) sites on Amchitka Island, Alaska. During the late1960s and early 1970s, the U.S. Department of Defense and the U.S. Atomic Energy Commission (the predecessor agency to DOE) used Amchitka Island as a site for underground nuclear tests. A total of nine sites on the Island were considered for nuclear testing; however, tests were only conducted at three sites (i.e., Long Shot in 1965, Milrow in 1969, and Cannikin in 1971). In addition to these three sites, large diameter emplacement holes were drilled in two other locations (Sites D and F) and an exploratory hole was in a third location (Site E). It was estimated that approximately 195 acres were disturbed by drilling or preparation for drilling in conjunction with these activities. The disturbed areas include access roads, spoil-disposal areas, mud pits which have impacted the environment, and an underground storage tank at the hot mix plant which was used to support asphalt-paving operations on the island. The remedial action objective for Amchitka Island is to eliminate human and ecological exposure to contaminants by capping drilling mud pits, removing the tank contents, and closing the tank in place. The remedial actions will meet State of Alaska regulations, U.S. Fish and Wildlife Service refuge management goals, address stakeholder concerns, and address the cultural beliefs and practices of the native people. The U.S. Department of Energy, Nevada Operations Office will conduct work on Amchitka Island under the authority of the Comprehensive Emergency Response, Compensation, and Liability Act. Field activities are scheduled to take place May through September 2001. The results of these activities will be presented in a subsequent Closure Report.

  19. Single-shell tank closure work plan. Revision A

    SciTech Connect (OSTI)

    NONE

    1995-06-01T23:59:59.000Z

    In January 1994, the Hanford Federal Facility Agreement and Conset Order (Tri-Party Agreement) was amended to reflect a revised strategy for remediation of radioactive waste in underground storage tanks. These amendments include milestones for closure of the single-shell tank (SST) operable units, to be initiated by March 2012 and completed by September 2024. This SST-CWP has been prepared to address the principal topical areas identified in Tri-Party Agreement Milestone M-45-06 (i.e., regulatory pathway, operable unit characterization, waste retrieval, technology development, and a strategy for achieving closure). Chapter 2.0 of this SST-CWP provides a brief description of the environmental setting, SST System, the origin and characteristics of SST waste, and ancillary equipment that will be remediated as part of SST operable unit closure. Appendix 2A provides a description of the hydrogeology of the Hanford Site, including information on the unsaturated sediments (vadose zone) beneath the 200 Areas Plateau. Chapter 3.0 provides a discussion of the laws and regulations applicable to closure of the SST farm operable units. Chapter 4.0 provides a summary description of the ongoing characterization activities that best align with the proposed regulatory pathway for closure. Chapter 5.0 describes aspects of the SST waste retrieval program, including retrieval strategy, technology, and sequence, potential tank leakage during retrieval, and considerations of deployment of subsurface barriers. Chapter 6.0 outlines a proposed strategy for closure. Chapter 7.0 provides a summary of the programs underway or planned to develop technologies to support closure. Ca. 325 refs.

  20. Simplifying documentation while approaching site closure: integrated health & safety plans as documented safety analysis

    SciTech Connect (OSTI)

    Brown, Tulanda

    2003-06-01T23:59:59.000Z

    At the Fernald Closure Project (FCP) near Cincinnati, Ohio, environmental restoration activities are supported by Documented Safety Analyses (DSAs) that combine the required project-specific Health and Safety Plans, Safety Basis Requirements (SBRs), and Process Requirements (PRs) into single Integrated Health and Safety Plans (I-HASPs). By isolating any remediation activities that deal with Enriched Restricted Materials, the SBRs and PRs assure that the hazard categories of former nuclear facilities undergoing remediation remain less than Nuclear. These integrated DSAs employ Integrated Safety Management methodology in support of simplified restoration and remediation activities that, so far, have resulted in the decontamination and demolition (D&D) of over 150 structures, including six major nuclear production plants. This paper presents the FCP method for maintaining safety basis documentation, using the D&D I-HASP as an example.

  1. Preliminary technique assessment for nondestructive evaluation certification of the NNWSI [Nevada Nuclear Waste Storage Investigations] disposal container closure

    SciTech Connect (OSTI)

    Day, R.A.

    1988-12-31T23:59:59.000Z

    Under the direction of the Department of Energy`s (DOE) Office of Civilian Radioactive Waste Management (OCRWM) program, the Nevada Nuclear Waste Storage Investigations (NNWSI) project is evaluating a candidate repository site at Yucca Mountain, Nevada, for permanent disposal of high-level nuclear waste. The Lawrence Livermore National Laboratory (LLNL), a participant in the NNWSI project, is developing waste package designs to meet the NRC requirements. One aspect of this waste package is the nondestructive testing of the final closure of the waste container. The container closure weld can best be nondestructively examined (NDE) by a combination of ultrasonics and liquid penetrants. This combination can be applied remotely and can meet stringent quality control requirements common to nuclear applications. Further development in remote systems and inspection will be required to meet anticipated requirements for flaw detection reliability and sensitivity. New research is not required but might reduce cost or inspection time. Ultrasonic and liquid penetrant methods can examine all closure methods currently being considered, which include fusion welding and inertial welding, among others. These NDE methods also have a history of application in high radiation environments and a well developed technology base for remote operation that can be used to reduce development and design costs. 43 refs., 23 figs., 3 tabs.

  2. Closure development for high-level nuclear waste containers for the tuff repository; Phase 1, Final report

    SciTech Connect (OSTI)

    Robitz, E.S. Jr.; McAninch, M.D. Jr.; Edmonds, D.P. [Babcock and Wilcox Co., Lynchburg, VA (USA). Nuclear Power Div.]|[Babcock and Wilcox Co., Alliance, OH (USA). Research and Development Div.

    1990-09-01T23:59:59.000Z

    This report summarizes Phase 1 activities for closure development of the high-level nuclear waste package task for the tuff repository. Work was conducted under U.S. Department of Energy (DOE) Contract 9172105, administered through the Lawrence Livermore National Laboratory (LLNL), as part of the Yucca Mountain Project (YMP), funded through the DOE Office of Civilian Radioactive Waste Management (OCRWM). The goal of this phase was to select five closure processes for further evaluation in later phases of the program. A decision tree methodology was utilized to perform an objective evaluation of 15 potential closure processes. Information was gathered via a literature survey, industrial contacts, and discussions with project team members, other experts in the field, and the LLNL waste package task staff. The five processes selected were friction welding, electron beam welding, laser beam welding, gas tungsten arc welding, and plasma arc welding. These are felt to represent the best combination of weldment material properties and process performance in a remote, radioactive environment. Conceptual designs have been generated for these processes to illustrate how they would be implemented in practice. Homopolar resistance welding was included in the Phase 1 analysis, and developments in this process will be monitored via literature in Phases 2 and 3. Work was conducted in accordance with the YMP Quality Assurance Program. 223 refs., 20 figs., 9 tabs.

  3. Moment Closure Approximations in a Genetic Negative Feedback Circuit

    E-Print Network [OSTI]

    Mohammad Soltani; Cesar Vargas; Niraj Kumar; Rahul Kulkarni; Abhyudai Singh

    2014-05-15T23:59:59.000Z

    Auto-regulation, a process wherein a protein negatively regulates its own production, is a common motif in gene expression networks. Negative feedback in gene expression plays a critical role in buffering intracellular fluctuations in protein concentrations around optimal value. Due to the nonlinearities present in these feedbacks, moment dynamics are typically not closed, in the sense that the time derivative of the lower-order statistical moments of the protein copy number depends on high-order moments. Moment equations are closed by expressing higher-order moments as nonlinear functions of lower-order moments, a technique commonly referred to as moment closure. Here, we compare the performance of different moment closure techniques. Our results show that the commonly used closure method, which assumes a priori that the protein population counts are normally distributed, performs poorly. In contrast, conditional derivative matching, a novel closure scheme proposed here provides a good approximation to the exact moments across different parameter regimes. In summary our study provides a new moment closure method for studying stochastic dynamics of genetic negative feedback circuits, and can be extended to probe noise in more complex gene networks.

  4. INTEC CPP-603 Basin Water Treatment System Closure: Process Design

    SciTech Connect (OSTI)

    Kimmitt, Raymond Rodney; Faultersack, Wendell Gale; Foster, Jonathan Kay; Berry, Stephen Michael

    2002-09-01T23:59:59.000Z

    This document describes the engineering activities that have been completed in support of the closure plan for the Idaho Nuclear Technology and Engineering Center (INTEC) CPP-603 Basin Water Treatment System. This effort includes detailed assessments of methods and equipment for performing work in four areas: 1. A cold (nonradioactive) mockup system for testing equipment and procedures for vessel cleanout and vessel demolition. 2. Cleanout of process vessels to meet standards identified in the closure plan. 3. Dismantlement and removal of vessels, should it not be possible to clean them to required standards in the closure plan. 4. Cleanout or removal of pipelines and pumps associated with the CPP-603 basin water treatment system. Cleanout standards for the pipes will be the same as those used for the process vessels.

  5. Certification report for final closure of Y-12 Centralized Sanitary Landfill II, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    NONE

    1995-12-31T23:59:59.000Z

    This report represents the Geotek Engineering Company, Inc., (Geotek) record of activities to support certification of final closure Of the subject Y-12 Centralized Sanitary Landfill II. Ex as noted herein, final closure of the landfill was completed in accordance with the Y-12 Centralized Sanitary Landfill 11 Closure/Post Closure Plan, Revision 2, submitted by the US Department of Energy (DOE) to the Tennessee Department of Environment and Conservation (TDEC) on April 14, 1992, and approved by TDEC on May 27, 1994 (the ``Closure Plan``). minor modification to the Closure Plan allowing partial closure of the Y-12 Centralized Sanitary Landfill II (Phase 1) was approved by TDEC on August 3, 1994. The Phase I portion of the closure for the subject landfill was completed on March 25, 1995. A closure certification report entitled Certification Report for Partial Closure of Y-12 Centralized Sanitary Landfill II was submitted to Lockheed Martin Energy Systems, Inc., (LMES) on March 28, 1995. The final closure represents the completion of the closure activities for the entire Y-12 Centralized Sanitary Landfill II Site. The contents of this report and accompanying certification are based on observations by Geotek engineers and geologists during closure activities and on review of reports, records, laboratory test results, and other information furnished to Geotek by LMES.

  6. Closure mechanism and method for spent nuclear fuel canisters

    DOE Patents [OSTI]

    Doman, Marvin J. (Monroeville, PA)

    2004-11-23T23:59:59.000Z

    A canister is provided for storing, transporting, and/or disposing of spent nuclear fuel. The canister includes a canister shell, a top shield plug disposed within the canister, and a leak-tight closure arrangement. The closure arrangement includes a shear ring which forms a containment boundary of the canister, and which is welded to the canister shell and top shield plug. An outer seal plate, forming an outer seal, is disposed above the shear ring and is welded to the shield plug and the canister.

  7. Closure Plan for Active Low Level Burial Grounds

    SciTech Connect (OSTI)

    SKELLY, W.A.

    2000-11-16T23:59:59.000Z

    This plan has been prepared in response to direction from the U.S. Department of Energy. The purpose of the plan is to define approaches that will be implemented to ensure protection of the public and the environment when active Low-Level Burial Grounds (LLBGs) at the Hanford Site are closed. Performance assessments for active burial grounds in the 200 East and West 200 Areas provide current estimates of potential environmental contamination and doses to the ''maximum exposed individual'' from burial ground operation and closure and compare dose estimates to performance objective dose limits for the facilities. This is an Operational Closure Plan. The intent of the guidance in DOE Order 435.1 is that this plan will be a living document, like the facility performance assessments, and will be revised periodically through the operational life of the LLBGs to reflect updated information on waste inventory. management practices, facility transition planning, schedule dates, assessments of post-closure performance, and environmental consequences. Out year dates identified in this plan are tentative. A Final Closure Plan will be prepared in the future when the timing and extent of closure-related activities for LLBGs can be established with greater certainty. After current operations at the LLBGs are concluded, this plan proposes transitioning of these facilities to the Environmental Restoration Program. This action will enable the Environmental Restoration Program to design and implement consistent and coordinated final remedial actions for active and inactive LLBGs. Active and inactive burial grounds in the 200 West and 200 East Areas are commingled. This plan describes approaches that will be implemented during Interim Closure, Final Closure, and Institutional Control Periods to prepare LLBGs for surface barriers, and the construction of barriers, as well as the scope of inspection, monitoring and maintenance practices that will be performed during and after closure. Environmental monitoring is briefly discussed in this plan. However, a more comprehensive discussion of monitoring issues is provided in a separate performance assessment monitoring plan for LLBGs. Supporting information is provided regarding the geography, climate, hydrogeology, geochemistry and land-use practices of adjacent land areas.

  8. TANK FARM REMEDIATION TECHNOLOGY DEVELOPMENT PROJECT AN EXERCISE IN TECHNICAL & REGULATORY COLLABORATION

    SciTech Connect (OSTI)

    JARAYSI, M.N.

    2007-01-08T23:59:59.000Z

    The Tank Farm Remediation Technology Development Project at the Hanford Site focuses on waste storage tanks, pipelines and associated ancillary equipment that are part of the C-200 single-shell tank (SST) farm system located in the C Tank Farm. The purpose of the project is to obtain information on the implementation of a variety of closure activities and to answer questions on technical, operational and regulatory issues associated with closure.

  9. A Fruit of Yucca Mountain: The Remote Waste Package Closure System

    SciTech Connect (OSTI)

    Kevin Skinner; Greg Housley; Colleen Shelton-Davis

    2011-11-01T23:59:59.000Z

    Was the death of the Yucca Mountain repository the fate of a technical lemon or a political lemon? Without caution, this debate could lure us away from capitalizing on the fruits of the project. In March 2009, Idaho National Laboratory (INL) successfully demonstrated the Waste Package Closure System, a full-scale prototype system for closing waste packages that were to be entombed in the now abandoned Yucca Mountain repository. This article describes the system, which INL designed and built, to weld the closure lids on the waste packages, nondestructively examine the welds using four different techniques, repair the welds if necessary, mitigate crack initiating stresses in the surfaces of the welds, evacuate and backfill the packages with an inert gas, and perform all of these tasks remotely. As a nation, we now have a proven method for securely sealing nuclear waste packages for long term storage—regardless of whether or not the future destination for these packages will be an underground repository. Additionally, many of the system’s features and concepts may benefit other remote nuclear applications.

  10. Calendar Year 1999 | Department of Energy

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

    March 15, 1999 Audit Report: ER-B-99-04 Credit Card Usage at the Ohio Field Office and the Fernald and Miamisburg Environmental Management Projects March 11, 1999 Audit Report:...

  11. Permanent Closure of MFC Biodiesel Underground Storage Tank 99ANL00013

    SciTech Connect (OSTI)

    Kerry L. Nisson

    2012-10-01T23:59:59.000Z

    This closure package documents the site assessment and permanent closure of the Materials and Fuels Complex biodiesel underground storage tank 99ANL00013 in accordance with the regulatory requirements established in 40 CFR 280.71, “Technical Standards and Corrective Action Requirements for Owners and Operators of Underground Storage Tanks: Out-of-Service UST Systems and Closure.”

  12. PNW Coal Closure Study Resource Adequacy Advisory Committee

    E-Print Network [OSTI]

    PNW Coal Closure Study 1 y Resource Adequacy Advisory Committee Steering Committee Meeting outage calculations)100 MW (for forced outage calculations) #12;Coal Replacement Plans 4 Coal Replacement Plans · Boardman ­ 601 MW · The 2016 PGE IRP process will include the Boardman coal plant replacement

  13. DISCUSSIONS AND CLOSURES Discussion of "1907 Static Liquefaction

    E-Print Network [OSTI]

    from the north dike failure of the Wachu sett Dam by force matching the postfailure geometry. The post-------------- DISCUSSIONS AND CLOSURES Discussion of "1907 Static Liquefaction Flow Failure of North Dike of Wachusett Dam" by Scott M. Olson, Timothy D. Stark, William H. Walton, and Gonzalo Castro

  14. Underground storage tank 511-D1U1 closure plan

    SciTech Connect (OSTI)

    Mancieri, S.; Giuntoli, N.

    1993-09-01T23:59:59.000Z

    This document contains the closure plan for diesel fuel underground storage tank 511-D1U1 and appendices containing supplemental information such as staff training certification and task summaries. Precision tank test data, a site health and safety plan, and material safety data sheets are also included.

  15. SWAIN LIBRARY -INTERSESSION AND WINTER CLOSURE HOURS DECEMBER 14TH

    E-Print Network [OSTI]

    Straight, Aaron

    Green Library will be open December 22-23, 26, 29-31, and January 2, 8 a.m.-5 p.m. with limited servicesSWAIN LIBRARY - INTERSESSION AND WINTER CLOSURE HOURS DECEMBER 14TH , 2008 ­ JANUARY 5TH , 2009. Branch Libraries that are open, circulation desks will be open for borrowing only. All other services

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

    SciTech Connect (OSTI)

    SIMMONS, F.M.

    2000-12-01T23:59:59.000Z

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

  17. Data-driven non-Markovian closure models

    E-Print Network [OSTI]

    Dmitri Kondrashov; Mickaël D. Chekroun; Michael Ghil

    2014-11-18T23:59:59.000Z

    This paper has two interrelated foci: (i) obtaining stable and efficient data-driven closure models by using a multivariate time series of partial observations from a large-dimensional system; and (ii) comparing these closure models with the optimal closures predicted by the Mori-Zwanzig (MZ) formalism of statistical physics. Multilayer stochastic models (MSMs) are introduced as both a generalization and a time-continuous limit of existing multilevel, regression-based approaches to closure in a data-driven setting; these approaches include empirical model reduction (EMR), as well as more recent multi-layer modeling. It is shown that the multilayer structure of MSMs can provide a natural Markov approximation to the generalized Langevin equation (GLE) of the MZ formalism. A simple correlation-based stopping criterion for an EMR-MSM model is derived to assess how well it approximates the GLE solution. Sufficient conditions are derived on the structure of the nonlinear cross-interactions between the constitutive layers of a given MSM to guarantee the existence of a global random attractor. This existence ensures that no blow-up can occur for a very broad class of MSM applications, a class that includes non-polynomial predictors and nonlinearities that do not necessarily preserve quadratic energy invariants. The approach is applied to conceptual nonlinear models borrowed from climate dynamics and population dynamics. In both cases, it is shown that the resulting closure models are able to capture the main statistical features of the dynamics, even in presence of weak time-scale separation.

  18. Reusing Property Resulting from Analytical Laboratory Closure

    SciTech Connect (OSTI)

    Elmer, J. [S.M. Stoller Corporation, Grand Junction, CO 81503 (United States); DePinho, D.; Wetherstein, P. [Battelle Memorial Institute, Grand Junction, CO 81503 (United States)

    2006-07-01T23:59:59.000Z

    The U.S. Department of Energy Office of Legacy Management (DOE-LM) site in Grand Junction, Colorado, faced the problem of reusing an extensive assortment of laboratory equipment and supplies when its on-site analytical chemistry laboratory closed. This challenge, undertaken as part of the Grand Junction site's pollution prevention program, prioritized reuse of as much of the laboratory equipment and supplies as possible during a 9-month period in fiscal year 2004. Reuse remedies were found for approximately $3 million worth of instrumentation, equipment, chemicals, precious metals, and other laboratory items through other Grand Junction site projects, Federal Government databases, and extensive contact with other DOE facilities, universities, and colleges. In 2005, the DOE-LM Grand Junction site received two prestigious DOE pollution prevention awards for reuse of the laboratory's equipment and supplies. (authors)

  19. CLOSING IN ON CLOSURE PERSPECTIVES FROM HANFORD & FERNALD AN UPDATE

    SciTech Connect (OSTI)

    CONNELL, J.D.

    2004-12-22T23:59:59.000Z

    In World War II, the arms dramatically changed from machine guns and incendiary bombs to nuclear weapons. Hanford and Fernald, two government-run sites, were part of the infrastructure established for producing the fissile material for making these weapons, as well as building a nuclear arsenal to deter future aggression by other nations. This paper compares and contrasts, from a communications point of view, these two Department of Energy (DOE) closure sites, each with Fluor as a prime contractor. The major differences between the two sites--Hanford in Washington state and Fernald in Ohio--includes the following: size of the site and the workforce, timing of closure, definition of end state, DOE oversight, proximity to population centers, readiness of local population for closure, and dependence of the local economy on the site's budget. All of these elements affect how the sites' communication professionals provide information even though the objectives are the same: build public acceptance and support for DOE's mission to accelerate cleanup, interface with stakeholders to help ensure that issues are addressed and goals are met, help workers literally work themselves out of jobs--faster, and prepare the ''host'' communities to deal with the void left when the sites are closed and the government contractors are gone. The 12-months between January 04 and January 05 have seen dramatic transformations at both sites, as Fernald is now just about a year away from closure and FLuor's work at Hanford has made the transition from operations to deactivation and demolition. While Fernald continues to clean out silos of waste and ship it off site, Hanford is dealing with recent state legislation that has the potential to significantly impact the progress of cleanup. These changes have even further accentuated the differences in the content, distribution, and impact of communications.

  20. An Initial Evaluation Of Characterization And Closure Options For Underground Pipelines Within A Hanford Site Single-Shell Tank Farm

    SciTech Connect (OSTI)

    Badden, Janet W. [Washington River Protection Solutions, LLC, Richland, WA (United States); Connelly, Michael P. [Washington River Protection Solutions, LLC, Richland, WA (United States); Seeley, Paul N. [Cenibark International, Inc., Kennewick (United States); Hendrickson, Michelle L. [Washington State Univ., Richland (United States). Dept. of Ecology

    2013-01-10T23:59:59.000Z

    The Hanford Site includes 149 single-shell tanks, organized in 12 'tank farms,' with contents managed as high-level mixed waste. The Hanford Federal Facility Agreement and Consent Order requires that one tank farm, the Waste Management Area C, be closed by June 30, 2019. A challenge to this project is the disposition and closure of Waste Management Area C underground pipelines. Waste Management Area C contains nearly seven miles of pipelines and 200 separate pipe segments. The pipelines were taken out of service decades ago and contain unknown volumes and concentrations of tank waste residuals from past operations. To understand the scope of activities that may be required for these pipelines, an evaluation was performed. The purpose of the evaluation was to identify what, if any, characterization methods and/or closure actions may be implemented at Waste Management Area C for closure of Waste Management Area C by 2019. Physical and analytical data do not exist for Waste Management Area C pipeline waste residuals. To develop estimates of residual volumes and inventories of contamination, an extensive search of available information on pipelines was conducted. The search included evaluating historical operation and occurrence records, physical attributes, schematics and drawings, and contaminant inventories associated with the process history of plutonium separations facilities and waste separations and stabilization operations. Scoping analyses of impacts to human health and the environment using three separate methodologies were then developed based on the waste residual estimates. All analyses resulted in preliminary assessments, indicating that pipeline waste residuals presented a comparably low long-term impact to groundwater with respect to soil, tank and other ancillary equipment residuals, but exceeded Washington State cleanup requirement values. In addition to performing the impact analyses, the assessment evaluated available sampling technologies and pipeline removal or treatment technologies. The evaluation accounted for the potential high worker risk, high cost, and schedule impacts associated with characterization, removal, or treatment of pipelines within Waste Management Area C for closure. This assessment was compared to the unknown, but estimated low, long-term impacts to groundwater associated with remaining waste residuals should the pipelines be left "as is" and an engineered surface barrier or landfill cap be placed. This study also recommended that no characterization or closure actions be assumed or started for the pipelines within Waste Management Area C, likewise with the premise that a surface barrier or landfill cap be placed over the pipelines.

  1. 3013 DE INNER CONTAINER CLOSURE WELD CORROSION EVALUATION

    SciTech Connect (OSTI)

    Mickalonis, J.

    2013-09-30T23:59:59.000Z

    Destructive evaluation (DE) of 3013 containers is one part of the U. S. Department of Energy Integrated Surveillance Program. During standard DE of 3013 containers, visual examinations for pitting and stress corrosion cracking (SCC) are performed on the accessible surfaces of the outer, inner, and convenience containers, which make up the 3013 container. As a result of 3013 DE additional analysis, the area near the inner container closure weld has been identified as being a region of increased corrosion susceptibility, which may provide a pathway for corrosive gases to the outer container. This area has a higher residual stress, an altered microstructure, and less corrosion resistant weld oxides as a result of the welding process as well as a lower temperature than other areas of the container, which may increase the absorption of moisture on the surface. The deposition of moisture in this stressed region could lead to pitting and stress corrosion cracking. During FY2013, the inner container closure weld area was more closely evaluated on several archived samples from DE containers. These containers included FY09 DE2, FY12 DE4, FY12 DE6 and FY12 DE7 and the Hanford High Moisture Container. The additional examinations included visual observations with a stereomicroscope, scanning electron microscopy along with energy dispersive spectroscopy for chemical analysis, and serial metallography of the sidewall and lid that are part of the inner container closure weld region. Pitting was observed in all the samples taken from the closure weld regions of the examined inner containers. This pitting was generally less 20 μm with most less than 5m. These pits were similar in depth to those observed in the vapor exposed surfaces of teardrops in the shelf life corrosion testing. Cracking was not observed on either the vapor-exposed surfaces of the teardrop coupons or the inner container closure weld region. Further testing is necessary to determine if the conditions in the welded inner container could support SCC during the 50 year life time for the 3013 container.

  2. Self-testing security sensor for monitoring closure of vault doors and the like

    DOE Patents [OSTI]

    Cawthorne, D.C.

    1997-05-27T23:59:59.000Z

    A self-testing device is provided for a monitoring system for monitoring whether a closure member such as a door or window is closed. The monitoring system includes a switch unit mounted on the frame of the closure member being monitored and including magnetically biased switches connected in one or more electrical monitoring circuits, and a door magnet unit mounted on the closure member being monitored. The door magnet includes one or more permanent magnets that produce a magnetic field which, when the closure member is closed, cause said switches to assume a first state. When the closure member is opened, the switches switch to a second, alarm state. The self-testing device is electrically controllable from a remote location and produces a canceling or diverting magnetic field which simulates the effect of movement of the closure member from the closed position thereof without any actual movement of the member. 5 figs.

  3. Closure of hazardous and mixed radioactive waste management units at DOE facilities. [Contains glossary

    SciTech Connect (OSTI)

    Not Available

    1990-06-01T23:59:59.000Z

    This is document addresses the Federal regulations governing the closure of hazardous and mixed waste units subject to Resource Conservation and Recovery Act (RCRA) requirements. It provides a brief overview of the RCRA permitting program and the extensive RCRA facility design and operating standards. It provides detailed guidance on the procedural requirements for closure and post-closure care of hazardous and mixed waste management units, including guidance on the preparation of closure and post-closure plans that must be submitted with facility permit applications. This document also provides guidance on technical activities that must be conducted both during and after closure of each of the following hazardous waste management units regulated under RCRA.

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

    SciTech Connect (OSTI)

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

    2013-07-01T23:59:59.000Z

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

  5. River Corridor Cleanup Contract Fiscal Year 2006 Detailed Work Plan: D4 Project/Reactor ISS Closure Projects Field Remediation Project Waste Operations Project End State and Final Closure Project Mission/General Support, Volume 2

    SciTech Connect (OSTI)

    Project Integration

    2005-09-26T23:59:59.000Z

    The Hanford Site contains many surplus facilities and waste sites that remain from plutonium production activities. These contaminated facilities and sites must either be stabilized and maintained, or removed, to prevent the escape of potentially hazardous contaminants into the environment and exposure to workers and the public.

  6. The Office of Site Closure: Progress in the Face of Challenges

    SciTech Connect (OSTI)

    Fiore, J. J.; Murphie, W. E.; Meador, S. W.

    2002-02-26T23:59:59.000Z

    The Office of Site Closure (OSC) was formed in November 1999 when the Department of Energy's (DOE's) Office of Environmental Management (EM) reorganized to focus specifically on site cleanup and closure. OSC's objective is to achieve safe and cost-effective cleanups and closures that are protective of our workers, the public, and the environment, now and in the future. Since its inception, OSC has focused on implementing a culture of safe closure, with emphasis in three primary areas: complete our responsibility for the Closure Sites Rocky Flats, Mound, Fernald, Ashtabula, and Weldon Spring; complete our responsibility for cleanup at sites where the DOE mission has been completed (examples include Battelle King Avenue and Battelle West Jefferson in Columbus, and General Atomics) or where other Departmental organizations have an ongoing mission (examples include the Brookhaven, Livermore, or Los Alamos National Laboratories, and the Nevada Test Site); and create a framework a nd develop specific business closure tools that will help sites close, such as guidance for and decisions on post-contract benefit liabilities, records retention, and Federal employee incentives for site closure. This paper discusses OSC's 2001 progress in achieving site cleanups, moving towards site closure, and developing specific business closure tools to support site closure. It describes the tools used to achieve progress towards cleanup and closure, such as the application of new technologies, changes in contracting approaches, and the development of agreements between sites and with host states. The paper also identifies upcoming challenges and explores options for how Headquarters and the sites can work together to address these challenges. Finally, it articulates OSC's new focus on oversight of Field Offices to ensure they have the systems in place to oversee contractor activities resulting in site cleanups and closures.

  7. Closure report for CAU 93: Area 6 steam cleaning effluent ponds, Nevada Test Site. Volume 1

    SciTech Connect (OSTI)

    NONE

    1997-12-01T23:59:59.000Z

    The Steam Cleaning Effluent Ponds (SCEP) waste unit is located in Area 6 at the Nevada Test Site. The SCEPs are evaporation basins formerly used for the disposal of untreated liquid effluent discharged from steam cleaning activities associated with Buildings 6-623 and 6-800. This closure report documents the strategy and analytical results that support the clean closure or closure in place of each of the components within CAU 93. In addition, the report documents all deviations from the approved closure plan and provides rationale for all deviations.

  8. Post-Closure Inspection Letter Report for Corrective Action Units on the Nevada National Security Site

    SciTech Connect (OSTI)

    Boehlecke, Robert F.

    2013-05-28T23:59:59.000Z

    This letter serves as the post-closure inspection letter report for corrective action units on the Nevada Naational Security Site for calendar year 2012.

  9. Closure Plan for the Area 5 Radioactive Waste Management Site at the Nevada Test Site

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2008-09-01T23:59:59.000Z

    The Area 5 Radioactive Waste Management Site (RMWS) at the Nevada Test Site (NTS) is managed and operated by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This document is the first update of the preliminary closure plan for the Area 5 RWMS at the NTS that was presented in the Integrated Closure and Monitoring Plan (DOE, 2005a). The major updates to the plan include a new closure schedule, updated closure inventory, updated site and facility characterization data, the Title II engineering cover design, and the closure process for the 92-Acre Area of the RWMS. The format and content of this site-specific plan follows the Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans (DOE, 1999a). This interim closure plan meets closure and post-closure monitoring requirements of the order DOE O 435.1, manual DOE M 435.1-1, Title 40 Code of Federal Regulations (CFR) Part 191, 40 CFR 265, Nevada Administrative Code (NAC) 444.743, and Resource Conservation and Recovery Act (RCRA) requirements as incorporated into NAC 444.8632. The Area 5 RWMS accepts primarily packaged low-level waste (LLW), low-level mixed waste (LLMW), and asbestiform low-level waste (ALLW) for disposal in excavated disposal cells.

  10. Transitive closure and metric inequality of weighted graphs: detecting protein interaction modules using cliques

    E-Print Network [OSTI]

    Ding, Chris; He, Xiaofeng; Xiong, Hui; Peng, Hanchuan; Holbrook, Stephen R.

    2006-01-01T23:59:59.000Z

    Closure and Metric Inequality of Weighted Graphs – Detectingleads to a transitivity inequality which is equivalentto ultra-metric inequality. This can be used to de?ne

  11. A framework for the evaluation of turbulence closures used in mesoscale ocean large-eddy simulations

    E-Print Network [OSTI]

    Graham, Jonathan Pietarila

    2012-01-01T23:59:59.000Z

    We present a methodology to determine the best turbulence closure for an eddy-permitting ocean model: measurement of the error-landscape of the closure's subgrid spectral transfers and flux. Using a high-resolution benchmark, we compare each closure's model of energy and enstrophy transfer to the actual transfer observed in the benchmark run. The error-landscape norms enable us to both make objective comparisons between the closures and to optimize each closure's free parameter for a fair comparison. We apply this method to 6 different closures for forced-dissipative simulations of the barotropic vorticity equation on a f-plane (2D Navier-Stokes equation). The hyper-viscous closure most closely reproduces the enstrophy cascade especially at larger scales due to the concentration of its dissipative effects to the very smallest scales. The viscous and Leith closures perform nearly as well especially at smaller scales where all three models were dissipative. The Smagorinsky closure dissipates enstrophy at the wr...

  12. Maximum-Entropy Closures for Kinetic Theories of Neuronal Network Dynamics

    SciTech Connect (OSTI)

    Rangan, Aaditya V.; Cai, David [Courant Institute of Mathematical Sciences, New York University, New York, New York 10012 (United States)

    2006-05-05T23:59:59.000Z

    We analyze (1+1)D kinetic equations for neuronal network dynamics, which are derived via an intuitive closure from a Boltzmann-like equation governing the evolution of a one-particle (i.e., one-neuron) probability density function. We demonstrate that this intuitive closure is a generalization of moment closures based on the maximum-entropy principle. By invoking maximum-entropy closures, we show how to systematically extend this kinetic theory to obtain higher-order (1+1)D kinetic equations and to include coupled networks of both excitatory and inhibitory neurons.

  13. 2009 River Corridor Closure Contractor Revegetation and Mitigation Monitoring Report

    SciTech Connect (OSTI)

    C. T. Lindsey; K. A. Gano; R. D. Teel

    2009-09-30T23:59:59.000Z

    This document details the results of revegetation and mitigation monitoring conducted in 2009, including 25 revegetation/restoration projects, one revegetation/mitigation project, and three bat mitigation projects.

  14. M-Area basin closure, Savannah River Site

    SciTech Connect (OSTI)

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

    1991-12-31T23:59:59.000Z

    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.

  15. M-Area basin closure, Savannah River Site

    SciTech Connect (OSTI)

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

    1991-01-01T23:59:59.000Z

    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.

  16. West Coast Port Closure Enforcement Policy | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy China 2015ofDepartment of EnergyThe U.S. Department ofFebruary 27, 2015 Closures at 29

  17. RADIOACTIVE MATERIAL SHIPPING PACKAGINGS AND METAL TO METAL SEALS FOUND IN THE CLOSURES OF CONTAINMENT VESSELS INCORPORATING CONE SEAL CLOSURES

    SciTech Connect (OSTI)

    Loftin, B; Glenn Abramczyk, G; Allen Smith, A

    2007-06-06T23:59:59.000Z

    The containment vessels for the Model 9975 radioactive material shipping packaging employ a cone-seal closure. The possibility of a metal-to-metal seal forming between the mating conical surfaces, independent of the elastomer seals, has been raised. It was postulated that such an occurrence would compromise the containment vessel hydrostatic and leakage tests. The possibility of formation of such a seal has been investigated by testing and by structural and statistical analyses. The results of the testing and the statistical analysis demonstrate and procedural changes ensure that hydrostatic proof and annual leakage testing can be accomplished to the appropriate standards.

  18. Closure End States for Facilities, Waste Sites, and Subsurface Contamination - 12543

    SciTech Connect (OSTI)

    Gerdes, Kurt; Chamberlain, Grover; Whitehurst, Latrincy; Marble, Justin [Office of Groundwater and Soil Remediation, U.S. Department of Energy, Washington, DC 20585 (United States); Wellman, Dawn [Pacific Northwest National Laboratory, Richland, Washington 99352 (United States); Deeb, Rula; Hawley, Elisabeth [ARCADIS U.S., Inc., Emeryville, CA 94608 (United States)

    2012-07-01T23:59:59.000Z

    The United States (U.S.) Department of Energy (DOE) manages the largest groundwater and soil cleanup effort in the world. DOE's Office of Environmental Management (EM) has made significant progress in its restoration efforts at sites such as Fernald and Rocky Flats. However, remaining sites, such as Savannah River Site, Oak Ridge Site, Hanford Site, Los Alamos, Paducah Gaseous Diffusion Plant, Portsmouth Gaseous Diffusion Plant, and West Valley Demonstration Project possess the most complex challenges ever encountered by the technical community and represent a challenge that will face DOE for the next decade. Closure of the remaining 18 sites in the DOE EM Program requires remediation of 75 million cubic yards of contaminated soil and 1.7 trillion gallons of contaminated groundwater, deactivation and decommissioning (D and D) of over 3000 contaminated facilities and thousands of miles of contaminated piping, removal and disposition of millions of cubic yards of legacy materials, treatment of millions of gallons of high level tank waste and disposition of hundreds of contaminated tanks. The financial obligation required to remediate this volume of contaminated environment is estimated to cost more than 7% of the to-go life-cycle cost. Critical in meeting this goal within the current life-cycle cost projections is defining technically achievable end states that formally acknowledge that remedial goals will not be achieved for a long time and that residual contamination will be managed in the interim in ways that are protective of human health and environment. Formally acknowledging the long timeframe needed for remediation can be a basis for establishing common expectations for remedy performance, thereby minimizing the risk of re-evaluating the selected remedy at a later time. Once the expectations for long-term management are in place, remedial efforts can be directed towards near-term objectives (e.g., reducing the risk of exposure to residual contamination) instead of focusing on long-term cleanup requirements. An acknowledgement of the long timeframe for complete restoration and the need for long-term management can also help a site transition from the process of pilot testing different remedial strategies to selecting a final remedy and establishing a long-term management and monitoring approach. This approach has led to cost savings and the more efficient use of resources across the Department of Defense complex and at numerous industrial sites across the U.S. Defensible end states provide numerous benefits for the DOE environmental remediation programs including cost-effective, sustainable long-term monitoring strategies, remediation and site transition decision support, and long-term management of closure sites. (authors)

  19. Engineering study of tank fill options for landfill closure

    SciTech Connect (OSTI)

    Skelly, W.A.

    1996-09-27T23:59:59.000Z

    To prepare single-shell tanks for closure, it will be necessary to piece some type of load- bearing fill material inside the tanks to support the domes. Provision of internal support permits the simplifying assumption that the combined weight of the dome, the existing operational soil cover, and the surface barrier will eventually transfer to and be carried by the fill. This engineering study provides descriptions and evaluations of four alternative concepts for fitting and stabilizing nominally empty SSTs with fill materials. For this study it is assumed that 99 percent (or more) of tank wastes will be retrieved before closure is undertaken. The alternatives are: Gravel: tanks would be fitted with crushed aggregate using a rotating stinger apparatus installed in the central riser; Grout: tanks would be fitted with a pumpable, ex-situ mixed grout formulation; Hybrid: tanks would be fitted first with coarse aggregate, then with grout, producing a pre-placed aggregate concrete material; or Concrete: tank. would be filled with a highly-flowable, ex-situ mixed concrete formulation.

  20. Fiber optic interferometry: Statistics of visibility and closure phase

    E-Print Network [OSTI]

    E. Tatulli; A. Chelli

    2005-08-19T23:59:59.000Z

    Interferometric observations with three telescopes or more provide two observables: closure phase information together with visibilities measurements. When using single-mode interferometers, both observables have to be redefined in the light of the coupling phenomenon betwe en the incoming wavefront and the fiber. We introduce in this paper the estimator of both so-called modal visibility and modal closure phase. Then, we compute the statistics of the two observables in presence of partial correction by Adaptive Optics. From this theoretical analysis, data reduction process using classical least square minimization is investigated. In the framework of the AMBER instrument, the three beams recombiner of the VLTI, we simulate the observation of a single Gaussian source and we study the performances of the interferometer in terms of diameter measurements. We show that the observation is optimized, i.e. that the Signal to Noise Ratio (SNR) of the diameter is maximal, when the full width half maximum (FWHM) of the source is roughly 1/2 of the mean resolution of the interferometer. We finally point out that in the case of an observation with 3 telescopes, neglecting the correlation between the measurements leads to overestimate the SNR by a factor of $\\sqrt{2}$. We infer that in any cases, this value is an upper limit.

  1. Soil Vapor Extraction System Optimization, Transition, and Closure Guidance

    SciTech Connect (OSTI)

    Truex, Michael J.; Becker, Dave; Simon, Michelle A.; Oostrom, Martinus; Rice, Amy K.; Johnson, Christian D.

    2013-02-08T23:59:59.000Z

    Soil vapor extraction (SVE) is a prevalent remediation approach for volatile contaminants in the vadose zone. A diminishing rate of contaminant extraction over time is typically observed due to 1) diminishing contaminant mass, and/or 2) slow rates of removal for contamination in low-permeability zones. After a SVE system begins to show indications of diminishing contaminant removal rate, SVE performance needs to be evaluated to determine whether the system should be optimized, terminated, or transitioned to another technology to replace or augment SVE. This guidance specifically addresses the elements of this type of performance assessment. While not specifically presented, the approach and analyses in this guidance could also be applied at the onset of remediation selection for a site as a way to evaluate current or future impacts to groundwater from vadose zone contamination. The guidance presented here builds from existing guidance for SVE design, operation, optimization, and closure from the U.S. Environmental Protection Agency, U.S. Army Corps of Engineers, and the Air Force Center for Engineering and the Environment. The purpose of the material herein is to clarify and focus on the specific actions and decisions related to SVE optimization, transition, and/or closure.

  2. Closure of the Brewer Gold Mine by pit backfilling

    SciTech Connect (OSTI)

    Lewis-Russ, A.; Lupo, J.F. [Titan Environmental Corp., Englewood, CO (United States); Bronson, J.M. [Titan Environmental Corp., Tempe, AZ (United States)] [and others

    1996-12-31T23:59:59.000Z

    Brewer Gold Mine, located in north-central South Carolina, is implementing an innovative reclamation plan that includes backfilling the main Brewer open pit with mine waste. The primary goals of the closure are to reduce acid rock drainage and minimize or eliminate long-term operation and maintenance requirements by restoring the site property to approximate pre-mining topography. The plan calls for consolidation of approximately 200 acres of waste into approximately 20 hectares (50 acres). Much of the material to be backfilled into the pit, including spent heap leach material and waste rock, has acid-generating potential. Therefore, the backfill design integrated geochemical properties of the backfill materials with expected post-closure conditions. A prime consideration was the final position of the water table. Since mining at the site started in the early 1800`s, no records exist of the original groundwater levels. Therefore, the design incorporates a large anoxic limestone drain to control the final groundwater level. Additional amendments are to be placed in targeted areas of the backfill to maximize their utilization. A low-permeability cap system that includes a GEOSYNTHETIC clay liner has been designed to limit infiltration into the backfill.

  3. State property systems and closure spaces: a study of categorical equivalence

    E-Print Network [OSTI]

    Aerts, Diederik

    State property systems and closure spaces: a study of categorical equivalence Diederik Aerts, Eva system. We prove that the category of state property systems (and morphisms), SP, is equivalent to the category of closure spaces (and continuous maps), Cls. We show the equivalence of the `state determination

  4. 2727-S Nonradioactive Dangerous Waste Storage Facility clean closure evaluation report

    SciTech Connect (OSTI)

    Luke, S.N.

    1994-07-14T23:59:59.000Z

    This report presents the analytical results of 2727-S NRDWS facility closure verification soil sampling and compares these results to clean closure criteria. The results of this comparison will determine if clean closure of the unit is regulatorily achievable. This report also serves to notify regulators that concentrations of some analytes at the site exceed sitewide background threshold levels (DOE-RL 1993b) and/or the limits of quantitation (LOQ). This report also presents a Model Toxics Control Act Cleanup (MTCA) (WAC 173-340) regulation health-based closure standard under which the unit can clean close in lieu of closure to background levels or LOQ in accordance with WAC 173-303-610. The health-based clean closure standard will be closure to MTCA Method B residential cleanup levels. This report reconciles all analyte concentrations reported above background or LOQ to this health-based cleanup standard. Regulator acceptance of the findings presented in this report will qualify the TSD unit for clean closure in accordance with WAC 173-303-610 without further TSD unit soil sampling, or soil removal and/or decontamination. Nondetected analytes require no further evaluation.

  5. SpaceEfficient Closure Representations \\Lambda Zhong Shao and Andrew W. Appel

    E-Print Network [OSTI]

    .'' In a compiler based on Continuation­Passing Style (CPS), this ``frame'' is the closure of a continuation func­ tion [33]. In a CPS­based compiler, a closure environment is con­ structed at each function (or by a ``jump'' in­ struction. Function returns are implemented in the same way because they are essentially

  6. Preliminary Closure Plan for the Immobilized Low Activity Waste (ILAW) Disposal Facility

    SciTech Connect (OSTI)

    BURBANK, D.A.

    2000-08-31T23:59:59.000Z

    This document describes the preliminary plans for closure of the Immobilized Low-Activity Waste (ILAW) disposal facility to be built by the Office of River Protection at the Hanford site in southeastern Washington. The facility will provide near-surface disposal of up to 204,000 cubic meters of ILAW in engineered trenches with modified RCRA Subtitle C closure barriers.

  7. Detailed design report for an operational phase panel-closure system

    SciTech Connect (OSTI)

    NONE

    1996-01-11T23:59:59.000Z

    Under contract to Westinghouse Electric Corporation (Westinghouse), Waste Isolation Division (WID), IT Corporation has prepared a detailed design of a panel-closure system for the Waste Isolation Pilot Plant (WIPP). Preparation of this detailed design of an operational-phase closure system is required to support a Resource Conservation and Recovery Act (RCRA) Part B permit application and a non-migration variance petition. This report describes the detailed design for a panel-closure system specific to the WIPP site. The recommended panel-closure system will adequately isolate the waste-emplacement panels for at least 35 years. This report provides detailed design and material engineering specifications for the construction, emplacement, and interface-grouting associated with a panel-closure system at the WIPP repository, which would ensure that an effective panel-closure system is in place for at least 35 years. The panel-closure system provides assurance that the limit for the migration of volatile organic compounds (VOC) will be met at the point of compliance, the WIPP site boundary. This assurance is obtained through the inherent flexibility of the panel-closure system.

  8. Crude closure dynamics through large scale statistical theories Marcus J. Grote and Andrew J. Majda

    E-Print Network [OSTI]

    Majda, Andrew J.

    Crude closure dynamics through large scale statistical theories Marcus J. Grote and Andrew J. Majda 10012-1185 Received 22 January 1997; accepted 9 July 1997 Crude closure algorithms based on equilibrium on equilibrium energy-enstrophy statistical theory, or two parameters, the energy and circulation, for crude

  9. Closure report for housekeeping category, Corrective Action Unit 348, Nevada Test Site

    SciTech Connect (OSTI)

    NONE

    1998-01-01T23:59:59.000Z

    This Closure Report summarizes the corrective actions which were completed at twelve Corrective Action Sites within Corrective Action Unit 348 at the Nevada Test Site. Current site descriptions, observations and identification of wastes removed are included on FFACO Corrective Action Site housekeeping closure verification forms.

  10. Closure report for housekeeping category, Corrective Action Unit 347, Nevada Test Site

    SciTech Connect (OSTI)

    NONE

    1998-01-01T23:59:59.000Z

    This Closure Report summarizes the corrective actions which were completed at the Corrective Action Sites within Corrective Action Unit 347 at the Nevada Test Site. Current site descriptions, observations and identification of wastes removed are included on FFACO Corrective Action Site housekeeping closure verification forms.

  11. Closure Plan for the E-Area Low-Level Waste Facility

    SciTech Connect (OSTI)

    Cook, J.R.

    2000-10-30T23:59:59.000Z

    A closure plan has been developed to comply with the applicable requirements of the U.S. Department of Energy Order 435.2 Manual and Guidance. The plan is organized according to the specifications of the Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans.

  12. A study to examine community involvement in major U.S.military base closures and realignments from 1988 to 2001

    E-Print Network [OSTI]

    Yahn, Nancy Stiles

    2005-11-01T23:59:59.000Z

    This study examines community involvement in major U.S. military base closures and realignments from 1988 to 2001. There were four waves of base closures during this time. They were in 1988, 1991, 1993, and 1995. Community involvement became...

  13. TECHNOLOGY NEEDS AND STATUS ON CLOSURE OF DOE RADIOACTIVE WASTE TANK ANCILLARY SYSTEMS

    SciTech Connect (OSTI)

    Burns, H; Sharon Marra, S; Christine Langton, C

    2009-01-21T23:59:59.000Z

    This paper summarizes the current state of art of sampling, characterizing, retrieving, transferring and treating the incidental waste and stabilizing the void space in tank ancillary systems and the needs involved with closure of these systems. The overall effort for closing tank and ancillary systems is very large and is in the initial stages of being addressed in a systematic manner. It was recognized in doing this effort, that gaps in both technology and material application for characterization and removal of residual waste and closure of ancillary systems would be identified. Great efficiencies are to be gained by defining the technology need areas early in the closure process and providing recommendations for technical programs to improve the closure strategies. Therefore, this paper will not only summarize the state of closure of ancillary systems but also provide recommendations to address the technology gaps identified in this assessment.

  14. EVALUATION OF TROQUE VS CLOSURE BOLT PRELOAD FOR A TYPICAL CONTAINMENT VESSEL UNDER SERVICE CONDITIONS

    SciTech Connect (OSTI)

    Smith, A.

    2010-02-16T23:59:59.000Z

    Radioactive material package containment vessels typically employ bolted closures of various configurations. Closure bolts must retain the lid of a package and must maintain required seal loads, while subjected to internal pressure, impact loads and vibration. The need for insuring that the specified preload is achieved in closure bolts for radioactive materials packagings has been a continual subject of concern for both designers and regulatory reviewers. The extensive literature on threaded fasteners provides sound guidance on design and torque specification for closure bolts. The literature also shows the uncertainty associated with use of torque to establish preload is typically between 10 and 35%. These studies have been performed under controlled, laboratory conditions. The ability to insure required preload in normal service is, consequently, an important question. The study described here investigated the relationship between indicated torque and resulting bolt load for a typical radioactive materials package closure using methods available under normal service conditions.

  15. Interim Status Closure Plan Open Burning Treatment Unit Technical Area 16-399 Burn Tray

    SciTech Connect (OSTI)

    Vigil-Holterman, Luciana R. [Los Alamos National Laboratory

    2012-05-07T23:59:59.000Z

    This closure plan describes the activities necessary to close one of the interim status hazardous waste open burning treatment units at Technical Area (TA) 16 at the Los Alamos National Laboratory (LANL or the Facility), hereinafter referred to as the 'TA-16-399 Burn Tray' or 'the unit'. The information provided in this closure plan addresses the closure requirements specified in the Code of Federal Regulations (CFR), Title 40, Part 265, Subparts G and P for the thermal treatment units operated at the Facility under the Resource Conservation and Recovery Act (RCRA) and the New Mexico Hazardous Waste Act. Closure of the open burning treatment unit will be completed in accordance with Section 4.1 of this closure plan.

  16. Remediation of the Melton Valley Watershed at Oak Ridge National Lab: An Accelerated Closure Success Story

    SciTech Connect (OSTI)

    Johnson, Ch.; Cange, J. [Bechtel Jacobs Company, LLC, Oak Ridge, TN (United States); Skinner, R. [U.S. DOE, Oak Ridge Operations Office, Oak Ridge, TN (United States); Adams, V. [U.S. DOE, Office of Groundwater and Soil Remediation, Washington, DC (United States)

    2008-07-01T23:59:59.000Z

    The Melton Valley (MV) Watershed at the U. S. Department of Energy's (DOE's) Oak Ridge National Laboratory (ORNL) encompasses approximately 430 hectares (1062 acres). Historic operations at ORNL produced a diverse legacy of contaminated facilities and waste disposal areas in the valley. In addition, from 1955 to 1963, ORNL served as a major disposal site for wastes from over 50 off-site government-sponsored installations, research institutions, and other isotope users. Contaminated areas in the watershed included burial grounds, landfills, underground tanks, surface impoundments, liquid disposal pits/trenches, hydro-fracture wells, leak and spill sites, inactive surface structures, and contaminated soil and sediment. Remediation of the watershed in accordance with the requirements specified in the Melton Valley Record of Decision (ROD) for Interim Actions in Melton Valley, which estimated that remedial actions specified in the ROD would occur over a period of 14 years, with completion by FY 2014. Under the terms of the Accelerated Closure Contract between DOE and its contractor, Bechtel Jacobs Company, LLC, the work was subdivided into 14 separate sub-projects which were completed between August 2001 and September 2006, 8 years ahead of the original schedule. (authors)

  17. Homophily and Triadic Closure in Evolving Social Networks

    E-Print Network [OSTI]

    Crimaldi, Irene; Morrison, Greg; Quattrociocchi, Walter; Riccaboni, Massimo

    2015-01-01T23:59:59.000Z

    We present a new network model accounting for homophily and triadic closure in the evolution of social networks. In particular, in our model, each node is characterized by a number of features and the probability of a link between two nodes depends on common features. The bipartite network of the actors and features evolves according to a dynamics that depends on three parameters that respectively regulate the preferential attachment in the transmission of the features to the nodes, the number of new features per node, and the power-law behavior of the total number of observed features. We provide theoretical results and statistical estimators for the parameters of the model. We validate our approach by means of simulations and an empirical analysis of a network of scientific collaborations.

  18. Project Year Project Title

    E-Print Network [OSTI]

    Gray, Jeffrey J.

    Project Year 2011-2012 Project Title Using M-Health and GIS Technology in the Field to Improve-specialized, but practically useless skill. Solution One goal of this summer's Applied Geographic Information Systems in Public lessons about observational epidemiology. Technologies Used Geographic Info System (GIS), Blackboard

  19. 303-K Storage Facility closure plan. Revision 2

    SciTech Connect (OSTI)

    Not Available

    1993-12-15T23:59:59.000Z

    Recyclable scrap uranium with zircaloy-2 and copper silicon alloy, uranium-titanium alloy, beryllium/zircaloy-2 alloy, and zircaloy-2 chips and fines were secured in concrete billets (7.5-gallon containers) in the 303-K Storage Facility, located in the 300 Area. The beryllium/zircaloy-2 alloy and zircaloy-2 chips and fines are designated as mixed waste with the characteristic of ignitability. The concretion process reduced the ignitability of the fines and chips for safe storage and shipment. This process has been discontinued and the 303-K Storage Facility is now undergoing closure as defined in the Resource Conservation and Recovery Act (RCRA) of 1976 and the Washington Administrative Code (WAC) Dangerous Waste Regulations, WAC 173-303-040. This closure plan presents a description of the 303-K Storage Facility, the history of materials and waste managed, and the procedures that will be followed to close the 303-K Storage Facility. The 303-K Storage Facility is located within the 300-FF-3 (source) and 300-FF-5 (groundwater) operable units, as designated in the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1992). Contamination in the operable units 300-FF-3 and 300-FF-5 is scheduled to be addressed through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 remedial action process. Therefore, all soil remedial action at the 304 Facility will be conducted as part of the CERCLA remedial action of operable units 300-FF-3 and 300-FF-5.

  20. 105-DR Large Sodium Fire Facility closure plan. Revision 1

    SciTech Connect (OSTI)

    Not Available

    1993-05-01T23:59:59.000Z

    The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, and activities associated with nuclear energy development. The 105-DR Large Sodium Fire Facility (LSFF), which was in operation from about 1972 to 1986, was a research laboratory that occupied the former ventilation supply room on the southwest side of the 105-DR Reactor facility. The LSFF was established to provide a means of investigating fire and safety aspects associated with large sodium or other metal alkali fires in the liquid metal fast breeder reactor (LMFBR) facilities. The 105-DR Reactor facility was designed and built in the 1950`s and is located in the 100-D Area of the Hanford Site. The building housed the 105-DR defense reactor, which was shut down in 1964. The LSFF was initially used only for engineering-scale alkali metal reaction studies. In addition, the Fusion Safety Support Studies program sponsored intermediate-size safety reaction tests in the LSFF with lithium and lithium lead compounds. The facility has also been used to store and treat alkali metal waste, therefore the LSFF is subject to the regulatory requirements for the storage and treatment of dangerous waste. Closure will be conducted pursuant to the requirements of the Washington Administrative Code (WAC) 173-303-610. This closure plan presents a description of the facility, the history of waste managed, and the procedures that will be followed to close the LSFF as an Alkali Metal Treatment Facility. No future use of the LSFF is expected.

  1. 2007 River Corridor Closure Contractor Revegetation and Mitigation Monitoring Report

    SciTech Connect (OSTI)

    K. A. Gano; C. T. Lindsey

    2007-09-27T23:59:59.000Z

    The purpose of this report is to document the status of revegetation projects and natural resources mitigation efforts that have been conducted for remediated waste sites and other activities associated with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) cleanup of National Priorities List waste sites at Hanford. This report documents the results of revegetation and mitigation monitoring conducted in 2007 and includes 11 revegetation/restoration projects, one revegetation/mitigation project, and 3 bat habitat mitigation projects.

  2. 2008 River Corridor Closure Contractor Revegetation and Mitigation Monitoring Report

    SciTech Connect (OSTI)

    C. T. Lindsey; K. A. Gano

    2008-09-30T23:59:59.000Z

    The purpose of this report is to document the status of revegetation projects and natural resources mitigation efforts that have been conducted for remediated waste sites and other activities associated with the Comprehensive Environmental Response, Compensation, and Liability Act cleanup of National Priorities List waste sites at Hanford. This report documents the results of revegetation and mitigation monitoring conducted in 2008 and includes 22 revegetation/restoration projects, one revegetation/mitigation project, and two bat habitat mitigation projects.

  3. The surplus facility inventory and assessment project

    SciTech Connect (OSTI)

    Weiner, L.A.; Szilagyi, A.P. [DOE, Washington, DC (United States); Rae, L.J.

    1994-12-31T23:59:59.000Z

    As a result of the ending of the Cold War, the Department of Energy (DOE) is experiencing a downsizing of the DOE nuclear weapons complex similar to the downsizing and base closures being experienced by the armed forces. Declining budgets across all DOE programs have further contributed to the extent and rate at which DOE`s assets are being declared surplus. The Surplus Facility Inventory and Assessment (SFIA) Project will define the magnitude of risk associated with the DOE surplus, contaminated assets. The results of the SFIA Project will be fundamental to all planning, budgeting, and management associated with the surplus, contaminated inventory.

  4. THE INTEGRATION OF A PROPOSED ZONE CLOSURE APPROACH FOR THE PLUTONIUM FINISHING PLANT (PFP) DECOMMISSIONING & THE PFP ZONE HANFORD SITE WASHINGTON

    SciTech Connect (OSTI)

    HOPKINS, A.M.

    2005-02-23T23:59:59.000Z

    The Plutonium Finishing Plant (PFP) and associated processing facilities are located in the 200 area of the Hanford Site in Eastern Washington. This area is part of what is now called the Central Plateau. In order to achieve closure of the contaminated facilities and waste sites at Hanford on the Central Plateau (CP), a geographic re-districting of the area into zones has been proposed in the recently published Plan for Central Plateau Closure. One of the 22 zones proposed in the Central Plateau encompasses the PFP and ancillary facilities. Approximately eighty six buildings are included in the PFP Zone. This paper addresses the approach for the closure of the PFP Zone within the Central Plateau. The PFP complex of buildings forms the bulk of the structures in the PFP Zone. For closure of the above-grade portion of structures within the PFP complex, the approach is to remove them to a state called ''slab-on-grade'' per the criteria contained in PFP End Point Criteria document and as documented in action memoranda. For below-grade portions of the structures (such as below-grade rooms, pipe trenches and underground ducts), the approach is to remove as much residual contamination as practicable and to fill the void spaces with clean fill material such as sand, grout, or controlled density fill. This approach will be modified as planning for the waste sites progresses to ensure that the actions of the PFP decommissioning projects do not negatively impact future planned actions under the CERCLA. Cribs, settling tanks, septic tanks and other miscellaneous below-grade void spaces will either be cleaned to the extent practicable and filled or will be covered with an environmental barrier as determined by further studies and CERCLA decision documents. Currently, between two and five environmental barriers are proposed to be placed over waste sites and remaining building slabs in the PFP Zone.

  5. Chemical hazard evaluation of material disposal area (MDA) B closure project

    SciTech Connect (OSTI)

    Laul, Jagdish C [Los Alamos National Laboratory

    2010-04-19T23:59:59.000Z

    TA-21, MDA-B (NES) is the 'contaminated dump,' landfill with radionuclides and chemicals from process waste disposed in 1940s. This paper focuses on chemical hazard categorization and hazard evaluation of chemicals of concern (e.g., peroxide, beryllium). About 170 chemicals were disposed in the landfill. Chemicals included products, unused and residual chemicals, spent, waste chemicals, non-flammable oils, mineral oil, etc. MDA-B was considered a High hazard site. However, based on historical records and best engineering judgment, the chemical contents are probably at best 5% of the chemical inventory. Many chemicals probably have oxidized, degraded or evaporated for volatile elements due to some fire and limited shelf-life over 60 yrs, which made it possible to downgrade from High to Low chemical hazard site. Knowing the site history and physical and chemical properties are very important in characterizing a NES site. Public site boundary is only 20 m, which is a major concern. Chemicals of concern during remediation are peroxide that can cause potential explosion and beryllium exposure due to chronic beryllium disease (CBD). These can be prevented or mitigated using engineering control (EC) and safety management program (SMP) to protect the involved workers and public.

  6. Closure of Project Chariot Soil Disposal Mound and Cesium 137 Plot.

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA group currentBradleyTableSelling7111A Lithologic andRECORD OFChupadera Mesa,

  7. Project Fact Sheet Project Update

    E-Print Network [OSTI]

    & Figures: Budget: Ł51,074,000 Funding Source: Capital Plan Construction Project Programme: Start on SiteProject Fact Sheet Project Update: Project Brief: The concept of the new scheme is to redevelop Gardens project http://www.imperial.ac.uk/princesgardens/ Construction Project Team: Project Facts

  8. Saltstone Disposal Facility Mechanically Stabilized Earth Vault Closure Cap Degradation: Sensitivity Analysis

    SciTech Connect (OSTI)

    PHIFER, MARK

    2004-03-19T23:59:59.000Z

    As part of the current Saltstone Disposal Facility (SDF) Performance Assessment (PA) revision, Mechanically Stabilized Earth (MSE) vault closure cap degradation mechanisms and their impact upon filtration through the MSE vault closure cap were evaluated for the base case land use scenario (i.e. institutional control to pine forest). The degradation mechanisms evaluated included pine forest succession, erosion, and colloidal clay migration (Phifer 2003). Infiltration through the upper hydraulic barrier layer of the closure cap as determined by this evaluation will be utilized as the infiltration input to subsequent PORFLOW vadose zone contaminant transport modeling, which will also be performed as part of the PA revision.

  9. An Overview Comparison of Tank Closure Activities at Certain DOE Site

    SciTech Connect (OSTI)

    LUKE, J.J.

    2003-01-01T23:59:59.000Z

    This paper presents a summary-level comparison of the similarities and differences of tank closure programs at the four primary radioactive waste tank sites in the US Department of Energy (DOE) complex. The sites are Hanford, Idaho National Engineering and Environmental Laboratory (INEEL), Oak Ridge Reservation (ORR), and the Savannah River Site (SRS). The depth of our understanding of the closure programs varies with the amount of detailed information each of the four sites has provided to date. This paper was prepared using the best available information, including direct communications with key tank closure personnel at each of the sites. Many of the current schedules are under review for possible acceleration.

  10. Project Funding

    Broader source: Energy.gov [DOE]

    Federal energy projects require funding to generate results. Carefully matching available funding options with specific project needs can make the difference between a stalled, unfunded project and a successful project generating energy and cost savings.

  11. Final Report for the portion performed in the University of Illinois on the project entitled "Optimizing the Cloud-Aerosol-Radiation Ensemble Modeling System to Improve Future Climate Change Projections at Regional to Local Scales"

    SciTech Connect (OSTI)

    Liang, Xin-Zhong

    2011-01-31T23:59:59.000Z

    This is the final report for the closure of the research tasks on the project that have performed during the entire reporting period in the University of Illinois. It contains a summary of the achievements and details of key results as well as the future plan for this project to be continued in the University of Maryland.

  12. Tank Closure and Waste Management Environmental Impact Statement...

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

    the environmental impacts of construction and operation of a new facility at Hanford equivalent to the Remote Treatment Project (RTP) at INL. Response: This TC & WM EIS provides...

  13. 2006 River Corridor Closure Contractor Revegetation and Mitigation Monitoring Report

    SciTech Connect (OSTI)

    A. L. Johnson; K. A. Gano

    2006-10-03T23:59:59.000Z

    The purpose of this report is to document the status of revegetation projects and natural resources mitigation efforts that have been conducted for remediated waste sites and other activities associated with the Comprehensive Environmental Response, Compensation, and Liability Act cleanup of National Priorities List waste sites at Hanford. One of the objectives of restoration is the revegetation of remediated waste sites to stabilize the soil and restore the land to native vegetation. The report documents the results of revegetation and mitigation monitoring conducted in 2006 and includes 11 revegetation/restoration projects, one revegetation/mitigation project, and 2 bat habitat mitigation projects.

  14. On the Number of Connected Components of the Relative Closure ...

    E-Print Network [OSTI]

    1910-20-53T23:59:59.000Z

    usual definitions related to Pfaffian functions, then we cover the essential material .... Counting the number of critical points of a generic projection, we obtain the.

  15. Compilation of current literature on seals, closures, and leakage for radioactive material packagings

    SciTech Connect (OSTI)

    Warrant, M.M.; Ottinger, C.A.

    1989-01-01T23:59:59.000Z

    This report presents an overview of the features that affect the sealing capability of radioactive material packagings currently certified by the US Nuclear Regulatory Commission. The report is based on a review of current literature on seals, closures, and leakage for radioactive material packagings. Federal regulations that relate to the sealing capability of radioactive material packagings, as well as basic equations for leakage calculations and some of the available leakage test procedures are presented. The factors which affect the sealing capability of a closure, including the properties of the sealing surfaces, the gasket material, the closure method and the contents are discussed in qualitative terms. Information on the general properties of both elastomer and metal gasket materials and some specific designs are presented. A summary of the seal material, closure method, and leakage tests for currently certified packagings with large diameter seals is provided. 18 figs., 9 tabs.

  16. Complete hierarchies of SIR models on arbitrary networks with exact and approximate moment closure

    E-Print Network [OSTI]

    Sharkey, Kieran J

    2015-01-01T23:59:59.000Z

    We first generalise ideas discussed by Kiss et al. (2015) to prove a theorem for generating exact closures (here expressing joint probabilities in terms of their constituent marginal probabilities) for susceptible-infectious-removed (SIR) dynamics on arbitrary graphs (networks). For Poisson transmission and removal processes, this enables us to obtain a systematic reduction in the number of differential equations needed for an exact `moment closure' representation of the underlying stochastic model. We define `transmission blocks' as a possible extension of the block concept in graph theory and show that the order at which the exact moment closure representation is curtailed is the size of the largest transmission block. More generally, approximate closures of the hierarchy of moment equations for these dynamics are typically defined for the first and second order yielding mean-field and pairwise models respectively. It is frequently implied that, in principle, closed models can be written down at arbitrary o...

  17. The voice-bar after closure of coda consonants in the speech of young children

    E-Print Network [OSTI]

    Cho, Won Ron

    2008-01-01T23:59:59.000Z

    The purpose of this study is to gain some insight into the speech acquisition process and articulator development of young children whose mother-tongue is American English. The presence of voice-bars after the closure of ...

  18. TECHNIQUES FOR X-RAY EXAMINATIONS OF ENDWELD CLOSURES AND CAN...

    Office of Scientific and Technical Information (OSTI)

    end-weld closures and cap-to-can brazes for the detection of porosity, cracks, lack of fusion of the weld, non-bonding of the edge, voids, and inclusions. The radiographic method...

  19. Making lives under closure : birth and medicine in Palestine's waiting zones

    E-Print Network [OSTI]

    Wick, Livia

    2006-01-01T23:59:59.000Z

    Reproduction is a site for understanding the ways in which people reconceptualize and re-organize the world in which they live. This dissertation tries to understand the world of birth under the regime of closures and ...

  20. EA-1345: Cleanup and Closure of the Energy Technology Engineering Center

    Broader source: Energy.gov [DOE]

    DOE prepared an EA and finding of no significant impact (FONSI) for cleanup and closure of DOE’s Energy Technology Engineering Center at the Santa Susana Field Laboratory in 2003. However, DOE’s...

  1. Estimation of economic impact of freight distribution due to highway closure

    E-Print Network [OSTI]

    Hu, Shiyin

    2008-01-01T23:59:59.000Z

    The main aim of this study is to provide a theoretical framework and methodology to estimate and analyze the economic impact of freight disruption due to highway closure. The costs in this study will be classified into ...

  2. Actions to Support Employees of Accelerated Closure Sites, 5/19/2000

    Broader source: Energy.gov [DOE]

    At present, there are approximately 400 employees assigned to accelerated closure sites. These sites are among our former nuclear production sites that are now being managed for clean up and...

  3. Remote Handling Equipment for a High-Level Waste Waste Package Closure System

    SciTech Connect (OSTI)

    Kevin M. Croft; Scott M. Allen; Mark W. Borland

    2006-04-01T23:59:59.000Z

    High-level waste will be placed in sealed waste packages inside a shielded closure cell. The Idaho National Laboratory (INL) has designed a system for closing the waste packages including all cell interior equipment and support systems. This paper discusses the material handling aspects of the equipment used and operations that will take place as part of the waste package closure operations. Prior to construction, the cell and support system will be assembled in a full-scale mockup at INL.

  4. HWMA/RCRA Closure Plan for the CPP-602 Laboratory Lines

    SciTech Connect (OSTI)

    Idaho Cleanup Project

    2009-09-30T23:59:59.000Z

    This Hazardous Waste Management Act/Resource Conservation and Recovery Act Closure (HWMA/RCRA) Plan for the CPP-602 laboratory lines was developed to meet the tank system closure requirements of the Idaho Administrative Procedures Act 58.01.05.008 and 40 Code of Federal Regulations 264, Subpart G. CPP-602 is located at the Idaho Nuclear Technology and Engineering Center at the Idaho National Laboratory Site. The lines in CPP-602 were part of a liquid hazardous waste collection system included in the Idaho Nuclear Technology and Engineering Center Liquid Waste Management System Permit. The laboratory lines discharged to the Deep Tanks System in CPP-601 that is currently being closed under a separate closure plan. This closure plan presents the closure performance standards and the methods for achieving those standards. The closure approach for the CPP-602 laboratory lines is to remove the lines, components, and contaminants to the extent practicable. Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Site CPP-117 includes the CPP-602 waste trench and the area beneath the basement floor where waste lines are direct-buried. Upon completion of rinsing or mopping to remove contamination to the extent practicable from the waste trench and rinsing the intact buried lines (i.e., stainless steel sections), these areas will be managed as part of CERCLA Site CPP-117 and will not be subject to further HWMA/RCRA closure activities. The CPP-602 building is being decontaminated and decommissioned under CERCLA as a non-time critical removal action in accordance with the Federal Facility Agreement/Consent Order. As such, all waste generated by this CERCLA action, including closure-generated waste, will be managed in coordination with that CERCLA action in substantive compliance with HWMA/RCRA regulations. All waste will be subject to a hazardous waste determination for the purpose of supporting appropriate management and will be managed in accordance with this plan. ii

  5. Final closure cover for a Hanford radioactive mixed waste disposal facility

    SciTech Connect (OSTI)

    Johnson, K.D.

    1996-02-06T23:59:59.000Z

    This study provides a preliminary design for a RCRA mixed waste landfill final closure cover. The cover design was developed by a senior class design team from Seattle University. The design incorporates a layered design of indigenous soils and geosynthetics in a layered system to meet final closure cover requirements for a landfill as imposed by the Washington Administrative Code WAC-173-303 implementation of the Resource Conservation and Recovery Act.

  6. Low-level radioactive waste disposal facility closure

    SciTech Connect (OSTI)

    White, G.J.; Ferns, T.W.; Otis, M.D.; Marts, S.T.; DeHaan, M.S.; Schwaller, R.G.; White, G.J. (EG and G Idaho, Inc., Idaho Falls, ID (USA))

    1990-11-01T23:59:59.000Z

    Part I of this report describes and evaluates potential impacts associated with changes in environmental conditions on a low-level radioactive waste disposal site over a long period of time. Ecological processes are discussed and baselines are established consistent with their potential for causing a significant impact to low-level radioactive waste facility. A variety of factors that might disrupt or act on long-term predictions are evaluated including biological, chemical, and physical phenomena of both natural and anthropogenic origin. These factors are then applied to six existing, yet very different, low-level radioactive waste sites. A summary and recommendations for future site characterization and monitoring activities is given for application to potential and existing sites. Part II of this report contains guidance on the design and implementation of a performance monitoring program for low-level radioactive waste disposal facilities. A monitoring programs is described that will assess whether engineered barriers surrounding the waste are effectively isolating the waste and will continue to isolate the waste by remaining structurally stable. Monitoring techniques and instruments are discussed relative to their ability to measure (a) parameters directly related to water movement though engineered barriers, (b) parameters directly related to the structural stability of engineered barriers, and (c) parameters that characterize external or internal conditions that may cause physical changes leading to enhanced water movement or compromises in stability. Data interpretation leading to decisions concerning facility closure is discussed. 120 refs., 12 figs., 17 tabs.

  7. Closure measures for coarse-graining of the tent map

    SciTech Connect (OSTI)

    Pfante, Oliver, E-mail: pfante@mis.mpg.de; Olbrich, Eckehard; Bertschinger, Nils [Max Planck Institute for Mathematics in the Sciences, Inselstrasse 22, 04103 Leipzig (Germany)] [Max Planck Institute for Mathematics in the Sciences, Inselstrasse 22, 04103 Leipzig (Germany); Ay, Nihat; Jost, Jürgen [Max Planck Institute for Mathematics in the Sciences, Inselstrasse 22, 04103 Leipzig (Germany) [Max Planck Institute for Mathematics in the Sciences, Inselstrasse 22, 04103 Leipzig (Germany); Department of Mathematics and Computer Science, Leipzig University, PF 100920, 04009 Leipzig (Germany); Santa Fe Institute, 1399 Hyde Park Road, Santa Fe, New Mexico 87501 (United States)

    2014-03-15T23:59:59.000Z

    We quantify the relationship between the dynamics of a time-discrete dynamical system, the tent map T and its iterations T{sup m}, and the induced dynamics at a symbolical level in information theoretical terms. The symbol dynamics, given by a binary string s of length m, is obtained by choosing a partition point ??[0,1] and lumping together the points x?[0,1] s.t. T{sup i}(x) concurs with the i ? 1th digit of s—i.e., we apply a so called threshold crossing technique. Interpreting the original dynamics and the symbolic one as different levels, this allows us to quantitatively evaluate and compare various closure measures that have been proposed for identifying emergent macro-levels of a dynamical system. In particular, we can see how these measures depend on the choice of the partition point ?. As main benefit of this new information theoretical approach, we get all Markov partitions with full support of the time-discrete dynamical system induced by the tent map. Furthermore, we could derive an example of a Markovian symbol dynamics whose underlying partition is not Markovian at all, and even a whole hierarchy of Markovian symbol dynamics.

  8. Design, permitting, and construction issues associated with closure of the Panna Maria uranium tailings impoundment

    SciTech Connect (OSTI)

    Strachan, C.L. [Shepherd Miller, Inc., Fort Collins, CO (United States); Raabe, K.L. [Panna Maria Uranium Operations, Hobson, TX (United States)

    1997-12-31T23:59:59.000Z

    In 1992, Panna Maria Uranium Operations (PMUO) initiated licensing and engineering activities for closure of the Panna Maria mill and 150-acre tailings impoundment located in southeast Texas. Closure of the tailings impoundment is permitted by license amendment through the Texas Natural Resources Conservation Commission (TNRCC), and based on closure criteria outlined in Texas regulations. The closure plan for the Panna Maria tailings impoundment was submitted for Texas regulatory agency review in April 1993, with details of the closure plan modified in 1994, 1995, and 1996. The closure plan included a multi-layered cover over the regraded tailings surface which was designed for long-term isolation of tailings, reduction of radon emanation to regulated levels, and reduction of infiltration to TNRCC-accepted levels. The cover and embankment slope surfaces and surrounding areas were designed to provide acceptable erosional stability as compared to runoff velocities from the Probable Maximum Precipitation event. Cover materials were selected from on-site materials and evaluated for suitability based on permeability, radon attenuation, and soil dispersivity characteristics. Off-site materials were used when necessary. The cover over the tailings has a maximum slope of 0.5 percent, and the regraded embankment slopes outside the perimeter of the impoundment have a maximum slope of 20 percent. All reclaimed slopes are covered with topsoil and revegetated. A riprap-lined channel is to be used to convey runoff from within the perimeter of the reclaimed impoundment to the north of the impoundment.

  9. An Initial Evaluation of Characterization and Closure Options for Underground Pipelines within a Hanford Site Single-Shell Tank Farm - 13210

    SciTech Connect (OSTI)

    Badden, Janet W.; Connelly, Michael P. [Washington River Protection Services, P.O. Box 850, Richland, Washington, 99352 (United States)] [Washington River Protection Services, P.O. Box 850, Richland, Washington, 99352 (United States); Seeley, Paul N. [Cenibark International, Inc., 104318 Nicole Drive, Kennewick, Washington, 99338-7596 (United States)] [Cenibark International, Inc., 104318 Nicole Drive, Kennewick, Washington, 99338-7596 (United States); Hendrickson, Michelle L. [Washington State Department of Ecology, 3100 Port of Benton Blvd, Richland, Washington, 99354 (United States)] [Washington State Department of Ecology, 3100 Port of Benton Blvd, Richland, Washington, 99354 (United States)

    2013-07-01T23:59:59.000Z

    The Hanford Site includes 149 single-shell tanks, organized in 12 'tank farms,' with contents managed as high-level mixed waste. The Hanford Federal Facility Agreement and Consent Order requires that one tank farm, the Waste Management Area C, be closed by June 30, 2019. A challenge to this project is the disposition and closure of Waste Management Area C underground pipelines. Waste Management Area C contains nearly seven miles of pipelines and 200 separate pipe segments. The pipelines were taken out of service decades ago and contain unknown volumes and concentrations of tank waste residuals from past operations. To understand the scope of activities that may be required for these pipelines, an evaluation was performed. The purpose of the evaluation was to identify what, if any, characterization methods and/or closure actions may be implemented at Waste Management Area C for closure of Waste Management Area C by 2019. Physical and analytical data do not exist for Waste Management Area C pipeline waste residuals. To develop estimates of residual volumes and inventories of contamination, an extensive search of available information on pipelines was conducted. The search included evaluating historical operation and occurrence records, physical attributes, schematics and drawings, and contaminant inventories associated with the process history of plutonium separations facilities and waste separations and stabilization operations. Scoping analyses of impacts to human health and the environment using three separate methodologies were then developed based on the waste residual estimates. All analyses resulted in preliminary assessments, indicating that pipeline waste residuals presented a comparably low long-term impact to groundwater with respect to soil, tank and other ancillary equipment residuals, but exceeded Washington State cleanup requirement values. In addition to performing the impact analyses, the assessment evaluated available sampling technologies and pipeline removal or treatment technologies. The evaluation accounted for the potential high worker risk, high cost, and schedule impacts associated with characterization, removal, or treatment of pipelines within Waste Management Area C for closure. This assessment was compared to the unknown, but estimated low, long-term impacts to groundwater associated with remaining waste residuals should the pipelines be left 'as is' and an engineered surface barrier or landfill cap be placed. This study also recommended that no characterization or closure actions be assumed or started for the pipelines within Waste Management Area C, likewise with the premise that a surface barrier or landfill cap be placed over the pipelines. (authors)

  10. Closure Report for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2009-07-31T23:59:59.000Z

    Corrective Action Unit (CAU) 139 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Waste Disposal Sites' and consists of the following seven Corrective Action Sites (CASs), located in Areas 3, 4, 6, and 9 of the Nevada Test Site: CAS 03-35-01, Burn Pit; CAS 04-08-02, Waste Disposal Site; CAS 04-99-01, Contaminated Surface Debris; CAS 06-19-02, Waste Disposal Site/Burn Pit; CAS 06-19-03, Waste Disposal Trenches; CAS 09-23-01, Area 9 Gravel Gertie; and CAS 09-34-01, Underground Detection Station. Closure activities were conducted from December 2008 to April 2009 according to the FFACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 139 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. Closure activities are summarized. CAU 139, 'Waste Disposal Sites,' consists of seven CASs in Areas 3, 4, 6, and 9 of the NTS. The closure alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 139 as documented in this CR: (1) At CAS 03-35-01, Burn Pit, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (2) At CAS 04-08-02, Waste Disposal Site, an administrative UR was implemented. No postings or post-closure monitoring are required. (3) At CAS 04-99-01, Contaminated Surface Debris, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (4) At CAS 06-19-02, Waste Disposal Site/Burn Pit, no work was performed. (5) At CAS 06-19-03, Waste Disposal Trenches, a native soil cover was installed, and a UR was implemented. (6) At CAS 09-23-01, Area 9 Gravel Gertie, a UR was implemented. (7) At CAS 09-34-01, Underground Detection Station, no work was performed.

  11. Project Title:

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

    Repair flowline 61-66-SX-3 DOE Code: Project Lead: Wes Riesland NEPA COMPLIANCE SURVEY 291 Project Information Date: 31 12010 Contractor Code: Project Overview In order to...

  12. Saltstone Disposal Facility Mechanically Stabilized Earth Vault Closure Cap Degradation Base Case: Institutional Control To Pine Forest Scenario

    SciTech Connect (OSTI)

    Phifer, MA

    2004-03-19T23:59:59.000Z

    As part of the current Saltstone Disposal Facility (SDF) Performance Assessment (PA) revision, the closure cap configuration was reevaluated and closure cap degradation mechanisms and their impact upon infiltration through the closure cap was evaluated for the existing SDF concrete vaults (i.e. vaults 1 and 4) for the base case land use scenario (i.e. institutional control to pine forest scenario) and documented in Phifer and Nelson (2003). The closure cap configuration was modified from a compacted kaolin barrier layer concept to a geosynthetic clay layer (GCL) barrier layer concept. The degradation mechanisms developed included pine forest succession, erosion, and colloidal clay migration. These degradation mechanisms resulted in changes in the hydraulic properties of the closure cap layers and resulting increases in infiltration through the closure cap over time.

  13. Fall 2010 Semiannual (III.H. and I.U.) Report for the HWMA/RCRA Post Closure Permit for the INTEC Waste Calcining Facility and the CPP 601/627/640 Facility at the INL Site

    SciTech Connect (OSTI)

    Boehmer, Ann

    2010-11-01T23:59:59.000Z

    The Waste Calcining Facility is located at the Idaho Nuclear Technology and Engineering Center. In 1999, the Waste Calcining Facility was closed under an approved Hazardous Waste Management Act/Resource Conservation and Recovery Act (HWMA/RCRA) Closure Plan. Vessels and spaces were grouted and then covered with a concrete cap. The Idaho Department of Environmental Quality issued a final HWMA/RCRA post-closure permit on September 15, 2003, with an effective date of October 16, 2003. This permit sets forth procedural requirements for groundwater characterization and monitoring, maintenance, and inspections of the Waste Calcining Facility to ensure continued protection of human health and the environment. The post closure permit also includes semiannual reporting requirements under Permit Conditions III.H. and I.U. These reporting requirements have been combined into this single semiannual report, as agreed between the Idaho Cleanup Project and Idaho Department of Environmental Quality. The Permit Condition III.H. portion of this report includes a description and the results of field methods associated with groundwater monitoring of the Waste Calcining Facility. Analytical results from groundwater sampling, results of inspections and maintenance of monitoring wells in the Waste Calcining Facility groundwater monitoring network, and results of inspections of the concrete cap are summarized. The Permit Condition I.U. portion of this report includes noncompliances not otherwise required to be reported under Permit Condition I.R. (advance notice of planned changes to facility activity which may result in a noncompliance) or Permit Condition I.T. (reporting of noncompliances which may endanger human health or the environment). This report also provides groundwater sampling results for wells that were installed and monitored as part of the Phase 1 post-closure period of the landfill closure components in accordance with HWMA/RCRA Landfill Closure Plan for the CPP-601 Deep Tanks System Phase 1. These monitoring wells are intended to monitor for the occurrence of contaminants of concern in the perched water beneath and adjacent to the CPP-601/627/640 Landfill. The wells were constructed to satisfy requirements of the HWMA/RCRA Post-Closure Plan for the CPP 601/627/640 Landfill.

  14. Closure Report for Corrective Action Unit 516: Septic Systems and Discharge Points

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2007-02-01T23:59:59.000Z

    Corrective Action Unit (CAU) 516 is located in Areas 3, 6, and 22 of the Nevada Test Site. CAU 516 is listed in the Federal Facility Agreement and Consent Order of 1996 as Septic Systems and Discharge Points, and is comprised of six Corrective Action Sites (CASs): {sm_bullet} CAS 03-59-01, Bldg 3C-36 Septic System {sm_bullet} CAS 03-59-02, Bldg 3C-45 Septic System {sm_bullet} CAS 06-51-01, Sump and Piping {sm_bullet} CAS 06-51-02, Clay Pipe and Debris {sm_bullet} CAS 06-51-03, Clean Out Box and Piping {sm_bullet} CAS 22-19-04, Vehicle Decontamination Area The Nevada Division of Environmental Protection (NDEP)-approved corrective action alternative for CASs 06-51-02 and 22-19-04 is no further action. The NDEP-approved corrective action alternative for CASs 03-59-01, 03-59-02, 06-51-01, and 06-51-03 is clean closure. Closure activities included removing and disposing of total petroleum hydrocarbon (TPH)-impacted septic tank contents, septic tanks, distribution/clean out boxes, and piping. CAU 516 was closed in accordance with the NDEP-approved CAU 516 Corrective Action Plan (CAP). The closure activities specified in the CAP were based on the recommendations presented in the CAU 516 Corrective Action Decision Document (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2004). This Closure Report documents CAU 516 closure activities. During closure activities, approximately 186 tons of hydrocarbon waste in the form of TPH-impacted soil and debris, as well as 89 tons of construction debris, were generated and managed and disposed of appropriately. Waste minimization techniques, such as field screening of soil samples and the utilization of laboratory analysis to characterize and classify waste streams, were employed during the performance of closure work.

  15. Closure Report for Corrective Action Unit 177: Mud Pits and Cellars Nevada Test Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Alfred Wickline

    2007-02-01T23:59:59.000Z

    This Closure Report presents information supporting the closure of Corrective Action Unit (CAU) 177: Mud Pits and Cellars, Nevada Test Site, Nevada. This Closure Report complies with the requirements of the Federal Facility Agreement and Consent Order (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. The Corrective Action Sites (CASs) within CAU 177 are located within Areas 8, 9, 19, and 20 of the Nevada Test Site. The purpose of this Closure Report is to provide documentation supporting the completed corrective actions and data that confirm the corrective actions implemented for CAU 177 CASs.

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

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2012-07-17T23:59:59.000Z

    This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 547, Miscellaneous Contaminated Waste Sites, and provides documentation supporting the completed corrective actions and confirmation that closure objectives for CAU 547 were met. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; the U.S. Department of Energy (DOE), Environmental Management; the U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996 as amended). CAU 547 consists of the following three Corrective Action Sites (CASs), located in Areas 2, 3, and 9 of the Nevada National Security Site: (1) CAS 02-37-02, Gas Sampling Assembly; (2) CAS 03-99-19, Gas Sampling Assembly; AND (3) CAS 09-99-06, Gas Sampling Assembly Closure activities began in August 2011 and were completed in June 2012. Activities were conducted according to the Corrective Action Decision Document/Corrective Action Plan (CADD/CAP) for CAU 547 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2011). The recommended corrective action for the three CASs in CAU 547 was closure in place with administrative controls. The following closure activities were performed: (1) Open holes were filled with concrete; (2) Steel casings were placed over vertical expansion joints and filled with cement; (3) Engineered soil covers were constructed over piping and exposed sections of the gas sampling system components; (4) Fencing, monuments, Jersey barriers, radiological postings, and use restriction (UR) warning signs were installed around the perimeters of the sites; (5) Housekeeping debris was picked up from around the sites and disposed; and (6) Radiological surveys were performed to confirm final radiological postings. UR documentation is included in Appendix D. The post-closure plan was presented in detail in the CADD/CAP for CAU 547 and is included as Appendix F of this report. The requirements are summarized in Section 5.2 of this report. The proposed post-closure requirements consist of visual inspections to determine the condition of postings and radiological surveys to verify contamination has not migrated. NNSA/NSO requests the following: (1) A Notice of Completion from the Nevada Division of Environmental Protection to NNSA/NSO for closure of CAU 547; and (2) The transfer of CAU 547 from Appendix III to Appendix IV, Closed Corrective Action Units, of the FFACO.

  17. Project Controls

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

    1997-03-28T23:59:59.000Z

    Project controls are systems used to plan, schedule, budget, and measure the performance of a project/program. The cost estimation package is one of the documents that is used to establish the baseline for project controls. This chapter gives a brief description of project controls and the role the cost estimation package plays.

  18. Closure Report for Corrective Action Unit 543: Liquid Disposal Units, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2008-01-01T23:59:59.000Z

    This Closure Report (CR) documents closure activities for Corrective Action Unit (CAU) 543, Liquid Disposal Units, according to the Federal Facility Agreement and Consent Order (FFACO, 1996) and the Corrective Action Plan (CAP) for CAU 543 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2007). CAU 543 is located at the Nevada Test Site (NTS), Nevada (Figure 1), and consists of the following seven Corrective Action Sites (CASs): CAS 06-07-01, Decon Pad; CAS 15-01-03, Aboveground Storage Tank; CAS 15-04-01, Septic Tank; CAS 15-05-01, Leachfield; CAS 15-08-01, Liquid Manure Tank; CAS 15-23-01, Underground Radioactive Material Area; CAS 15-23-03, Contaminated Sump, Piping; and CAS 06-07-01 is located at the Decontamination Facility in Area 6, adjacent to Yucca Lake. The remaining CASs are located at the former U.S. Environmental Protection Agency (EPA) Farm in Area 15. The purpose of this CR is to provide a summary of the completed closure activities, to document waste disposal, and to present analytical data confirming that the remediation goals were met. The closure alternatives consisted of closure in place for two of the CASs, and no further action with implementation of best management practices (BMPs) for the remaining five CASs.

  19. Neutrinoless double beta decay of 48Ca in the shell model: Closure versus nonclosure approximation

    E-Print Network [OSTI]

    R. A. Sen'kov; M. Horoi

    2013-12-16T23:59:59.000Z

    Neutrinoless double-beta decay is a unique process that could reveal physics beyond the Standard Model. Essential ingredients in the analysis of neutrinoless double-beta rates are the associated nuclear matrix elements. Most of the approaches used to calculate these matrix elements rely on the closure approximation. Here we analyze the light neutrino-exchange matrix elements of 48Ca neutrinoless double-beta decay and test the closure approximation in a shell-model approach. We calculate the neutrinoless double-beta nuclear matrix elements for 48Ca using both the closure approximation and a nonclosure approach, and we estimate the uncertainties associated with the closure approximation. We demonstrate that the nonclosure approach has excellent convergence properties which allow us to avoid unmanageable computational cost. Combining the nonclosure and closure approaches we propose a new method of calculation for neutrinoless double-beta decay rates which can be applied to the neutrinoless double-beta decay rates of heavy nuclei, such as 76Ge or 82Se.

  20. Project Fact Sheet Project Update

    E-Print Network [OSTI]

    Project Fact Sheet Project Update: Project Brief: The works cover the refurbishment of floors 4, 5, with `wet' labs for molecular biology, materials characterisation, cell culture and flow studies, and `dry operating theatre. The Bionanotechnology Centre is one of the projects funded from the UK Government's ÂŁ20

  1. Project Fact Sheet Project Brief

    E-Print Network [OSTI]

    .union.ic.ac.uk/marketing/building Construction Project Team: Project Facts & Figures: Budget: Ł1,400,000 Funding Source: Capital PlanProject Fact Sheet Project Brief: In the first phase of the Union Building re that it adapts to meet the needs of a changing student body. The re-development plans are grounded in a full

  2. Project Fact Sheet Project Brief

    E-Print Network [OSTI]

    Facts & Figures: Budget: Ł3,500,000 Funding Source: SRIF III Construction Project Programme: StartProject Fact Sheet Project Brief: This project refurbished half of the 5th and 7th floors of work includes: · Building fabric replacement and revised space planning · New mechanical and electrical

  3. Saltstone Disposal Facility Closure Cap Configuration and Degradation Base Case: Institutional Control to Pine Forest Scenario

    SciTech Connect (OSTI)

    Phifer, M.A.

    2004-03-19T23:59:59.000Z

    The Performance Assessment (PA) for the Saltstone Disposal Facility (SDF) is currently under revision. As part of the PA revision and as documented herein, the closure cap configuration has been reevaluated and closure cap degradation mechanisms and their impact upon infiltration through the closure cap have been evaluated for the institutional control to pine forest, land use scenario. This land use scenario is considered the base case land use scenario. This scenario assumes a 100-year institutional control period following final SDF closure during which the closure cap is maintained. At the end of institutional control, it is assumed that a pine forest succeeds the cap's original bamboo cover. Infiltration through the upper hydraulic barrier layer of the closure cap as determined by this evaluation will be utilized as the infiltration input to subsequent PORFLOW vadose zone contaminant transport modeling, which will also be performed as part of the PA revision. The impacts of pine forest succession, erosion, and colloidal clay migration as degradation mechanisms on the hydraulic properties of the closure cap layers over time have been estimated and the resulting infiltration through the closure cap has been evaluated. The primary changes caused by the degradation mechanisms that result in increased infiltration are the formation of holes in the upper GCL by pine forest succession and the reduction in the saturated hydraulic conductivity of the drainage layers due to colloidal clay migration into the layers. Erosion can also result in significant increases in infiltration if it causes the removal of soil layers, which provide water storage for the promotion of evapotranspiration. For this scenario, infiltration through the upper GCL was estimated at approximately 0.29 inches/year under initial intact conditions, it increased to approximately 11.6 inches/year at year 1000 in nearly a linear fashion, and it approached an asymptote of around 14.1 inches/year at year 1800 and thereafter. At year 1800, it was estimated that holes covered approximately 0.3 percent of the GCL due to root penetration, and that this resulted in an infiltration near that of typical background infiltration (i.e. as though the GCL were not there at all). This demonstrated that a very small area of holes essentially controlled the hydraulic performance of the GCL.

  4. Entrapment of the StarClose Vascular Closure System After Attempted Common Femoral Artery Deployment

    SciTech Connect (OSTI)

    Durack, Jeremy C., E-mail: jeremy.durack@ucsf.edu; Thor Johnson, D.; Fidelman, Nicholas; Kerlan, Robert K.; LaBerge, Jeanne M. [University of California, Department of Radiology and Biomedical Imaging (United States)

    2012-08-15T23:59:59.000Z

    A complication of the StarClose Vascular Closure System (Abbott, Des Plaines, IL) after a transarterial hepatic chemoembolization is described. After attempted clip deployment, the entire device became lodged in the tissues overlying the common femoral artery and could not be removed percutaneously. Successful removal of the device required surgical cutdown for removal and arterial repair. Entrapment of the StarClose vascular closure deployment system is a potentially serious complication that has been reported in the Manufacturer and User Facility Device Experience database, but has not been recognized in the literature.

  5. Risk and Performance Analyses Supporting Closure of WMA C at the Hanford Site in Southeast Washington

    SciTech Connect (OSTI)

    Eberlein, Susan J. [Washington River Protection Systems, Richland, WA (United States); Bergeron, Marcel P. [Washington River Protection Systems, Richland, WA (United States); Kemp, Christopher J. [USDOE Office of River Protection, Richland, WA (United States); Hildebrand, R. Douglas [USDOE Office of River Protection, Richland, WA (United States); Aly, Alaa [INTERA, Inc., Richland, WA (United States); Kozak, Matthew [INTERA, Inc., Richland, WA (United States); Mehta, Sunil [INTERA, Inc., Richland, WA (United States); Connelly, Michael [Freestone Environmental Services, Richland, WA (United States)

    2013-11-11T23:59:59.000Z

    The Office of River Protection under the U.S. Department of Energy (DOE) is pursuing closure of the Single-Shell Tank (SST) Waste Management Area (WMA) C as stipulated by the Hanford Federal Facility Agreement and Consent Order (HFFACO) under federal requirements and work tasks will be done under the State-approved closure plans and permits. An initial step in meeting the regulatory requirements is to develop a baseline risk assessment representing current conditions based on available characterization data and information collected at the WMA C location. The baseline risk assessment will be supporting a Resource Conservation and Recovery Act of 1976 (RCRA) Field Investigation (RFI)/Corrective Measures Study (CMS) for WMA closure and RCRA corrective action. Complying with the HFFACO conditions also involves developing a long-term closure Performance Assessment (PA) that evaluates human health and environmental impacts resulting from radionuclide inventories in residual wastes remaining in WMA C tanks and ancillary equipment. This PA is being developed to meet the requirements necessary for closure authorization under DOE Order 435.1 and Washington State Hazardous Waste Management Act. To meet the HFFACO conditions, the long-term closure risk analysis will include an evaluation of human health and environmental impacts from hazardous chemical inventories along with other performance Comprehensive Environmental Response, Compensation, and Liability Act Appropriate and Applicable Requirements (CERCLA ARARs) in residual wastes left in WMA C facilities after retrieval and removal. This closure risk analysis is needed to needed to comply with the requirements for permitted closure. Progress to date in developing a baseline risk assessment of WMA C has involved aspects of an evaluation of soil characterization and groundwater monitoring data collected as a part of the RFI/CMS and RCRA monitoring. Developing the long-term performance assessment aspects has involved the construction of detailed numerical models of WMA C using the Subsurface Transport Over Multiple Phases (STOMP©) computer code, the development of a technical approach for abstraction of a range of representative STOMP© simulations into a system-level model based on the GoldSim© system-level model software.The STOMP©-based models will be used to evaluate local-scale impacts and closed facility performance over a sufficient range of simulations to allow for development of the system-level model of the WMA C. The GoldSim©-based system-level model will be used to evaluate overall sensitivity of modeled parameters and the estimate the uncertainty in potential future impacts from a closed WMA C facility.

  6. Economic evaluation of closure CAP barrier materials Volume I and Volume II

    SciTech Connect (OSTI)

    Serrato, M.G.; Bhutani, J.S.; Mead, S.M.

    1993-09-01T23:59:59.000Z

    This study prepared by the Site Geotechnical Services (SGS) and Environmental Restoration (ER) departments of the WSRC evaluates a generic closure cover system for a hazardous waste site, using 10 different surface areas, ranging from 0.1 acre to 80 acres, and 12 barrier materials. This study presents a revision to the previous study (Rev. 0) published in June 1993, under the same title. The objective of this study was to revise the previous study by incorporating four additional site sizes into the evaluation process and identifying the most cost-effective barrier material for a given closure cover system at the SRS.

  7. Crack closure effects on fatigue crack growth thresholds and remaining life in an HSLA steel

    SciTech Connect (OSTI)

    Todd, J.A.; Mostovoy, S. [Illinois Inst. of Tech., Chicago, IL (United States). Dept. of Mechanical, Materials and Aerospace Engineering; Chen, L. [Texas Instruments, Attleboro, MA (United States); Yankov, E.Y. [A. Finkl and Sons, Chicago, IL (United States)

    1997-02-01T23:59:59.000Z

    The effects of crack closure on the near-threshold corrosion fatigue crack growth behavior of Mil S-24645 HSLA steel and its weld metal have been investigated in air, ASTM seawater at the free corrosion potential, and ASTM seawater at {minus}0.8V and {minus}1.0V (SCE) using frequencies of 10, 2, and 0.2 Hz, and a stress ratio, R = 0.1. Remaining life, in the presence and absence of crack closure, has been estimated as a function of applied stress range for a structure containing a 3-mm-deep surface semi-elliptical flaw.

  8. EXPEDITING THE PATH TO CLOSURE THE CHEMICAL WASTE LANDFILL, SANDIA NATIONAL LABORATORIES, NEW MEXICO

    SciTech Connect (OSTI)

    Young, S.G.; Schofield, D.P.; Davis, M.J.; Methvin, R.; Mitchell, M.

    2003-02-27T23:59:59.000Z

    The Chemical Waste Landfill (CWL) at Sandia National Laboratories, New Mexico (SNL/NM) is undergoing closure subject to the requirements of Subtitle C of RCRA. This paper identifies regulatory mechanisms that have and continue to expedite and simplify the closure of the CWL. These include (1) the Environmental Restoration (ER) Programmatic effort to achieve progress quickly with respect to the standard regulatory processes, which resulted in the performance of voluntary corrective measures at the CWL years in advance of the standard process schedule, (2) the management and disposal of CWL remediation wastes and materials according to the risks posed, and (3) the combination of multiple regulatory requirements into a single submittal.

  9. Proceedings of the tenth annual DOE low-level waste management conference: Session 6: Closure and decommissioning

    SciTech Connect (OSTI)

    Not Available

    1988-12-01T23:59:59.000Z

    This document contains eight papers on various aspects of low-level radioactive waste management. Topics include: site closure; ground cover; alternate cap designs; performance monitoring of waste trenches; closure options for a mixed waste site; and guidance for environmental monitoring. Individual papers were processed separately for the data base. (TEM)

  10. Front-end planning and evaluation for West Valley Demonstration Project completion

    SciTech Connect (OSTI)

    Gramling, J.; Sharma, V. [West Valley Nuclear Services Company, West Valley, NY (United States); Marschke, S. [Raytheon Nuclear, Inc., New York, NY (United States)

    1995-12-31T23:59:59.000Z

    In December 1988, the U.S. Department of Energy and the New York State Energy Research and Development Authority announced their intent to prepare a joint environmental impact statement (EIS) to evaluate alternatives for West Valley Demonstration Project (WVDP) completion and closure and/or long-term maintenance of the Western New York Nuclear Service Center (WNYNSC) in West Valley, New York. Planning was initiated for the eventual closure of the site, even though vitrification of the high-level waste (HLW) stored at the site was, at that time, a number of years in the future. West Valley Nuclear Services Company (WVNSC), the WVDP management and operations contractor, and their architect/engineer, Raytheon Nuclear Incorporated, were authorized to develop characterization studies and engineering evaluations of closure alternatives for the various facilities of the WNYNSC. This paper presents a summary of the status of that effort, including the resolution of unique problems.

  11. Idaho HWMA/RCRA Closure Plan for Idaho Nuclear Technology and Engineering Center Tanks WM-182 and WM-183 - Rev. 2

    SciTech Connect (OSTI)

    Evans, Susan Kay; unknown

    2000-12-01T23:59:59.000Z

    This document presents the plan for the closure of the Idaho Nuclear Technology and Engineering Center Tank Farm Facility tanks WM-182 and WM-183 in accordance with Idaho Hazardous Waste Management Act/Resource Conservation and Recovery Act interim status closure requirements. Closure of these two tanks is the first in a series of closures leading to the final closure of the eleven 300,000-gal tanks in the Tank Farm Facility. As such, closure of tanks WM-182 and WM-183 will serve as a proof-of-process demonstration of the waste removal, decontamination, and sampling techniques for the closure of the remaining Tank Farm Facility tanks. Such an approach is required because of the complexity and uniqueness of the Tank Farm Facility closure. This plan describes the closure units, objectives, and compliance strategy as well as the operational history and current status of the tanks. Decontamination, closure activities, and sampling and analysis will be performed with the goal of achieving clean closure of the tanks. Coordination with other regulatory requirements, such as U.S. Department of Energy closure requirements, is also discussed.

  12. The power of multifolds: Folding the algebraic closure of the rational numbers

    E-Print Network [OSTI]

    Timothy Y. Chow; C. Kenneth Fan

    2008-08-11T23:59:59.000Z

    It is well known that the usual Huzita-Hatori axioms for origami enable angle trisection but not angle quintisection. Using the concept of a multifold, Lang has achieved quintisection but not arbitrary algebraic numbers. We define the n-parameter multifold and show how to use one-parameter multifolds to obtain the algebraic closure of the rational numbers.

  13. Friction factor for turbulent flow in rough pipes from Heisenberg's closure hypothesis

    E-Print Network [OSTI]

    Esteban Calzetta

    2009-04-17T23:59:59.000Z

    We show that the main results of the analysis of the friction factor for turbulent pipe flow reported in G. Gioia and P. Chakraborty (GC), Phys. Rev. Lett. 96, 044502 (1996) can be recovered by assuming the Heisenberg closure hypothesis for the turbulent spectrum. This highlights the structural features of the turbulent spectrum underlying GC's analysis.

  14. E#cient and SafeforSpace Closure Conversion Yale University

    E-Print Network [OSTI]

    in the same way because they are essentially calls to continuation functions if represented in CPS. A non­CPS­Passing Style (CPS), this frame is the closure of a continuation function [Steele 1978]. In a CPS­based compiler

  15. Optical closure in a complex coastal environment: particle Grace Chang,1,

    E-Print Network [OSTI]

    Chang, Grace C.

    Optical closure in a complex coastal environment: particle effects Grace Chang,1, * Andrew Barnard October 2007 An optical dataset was collected on a mooring in the Santa Barbara Channel. Radiative optical properties and the slope of the particle size distribution ( ) were strongly related

  16. Oakwood crown closure estimation by unmixing Landsat TM data R. PU*, B. XU and P. GONG

    E-Print Network [OSTI]

    Silver, Whendee

    classi- fication and tree crown closure estimation. However, photo interpretation is dependent on the experience of photo interpretators (Biging et al. 1991, Gong and Chen 1992, Davis et al. 1995) and needs.g. Landsat sensor imagery) classification as an information extraction tool has been used for more than three

  17. SIAM J. on Applied Mathematics, submitted 20 February 1996 The Gaussian Moment Closure for Gas Dynamics

    E-Print Network [OSTI]

    Soatto, Stefano

    of extremely low pressure rarefied gas flows is important in a wide range of applications, from the reentrySIAM J. on Applied Mathematics, submitted 20 February 1996 The Gaussian Moment Closure for Gas of Levermore applied to the Boltzmann equation for rarefied gas dynamics leads to a hierarchy of symmetric

  18. Summary of Group Development and Testing for Single Shell Tank Closure at Hanford

    SciTech Connect (OSTI)

    Harbour, John, R.

    2005-04-28T23:59:59.000Z

    This report is a summary of the bench-scale and large scale experimental studies performed by Savannah River National Laboratory for CH2M HILL to develop grout design mixes for possible use in producing fill materials as a part of Tank Closure of the Single-Shell Tanks at Hanford. The grout development data provided in this report demonstrates that these design mixes will produce fill materials that are ready for use in Hanford single shell tank closure. The purpose of this report is to assess the ability of the proposed grout specifications to meet the current requirements for successful single shell tank closure which will include the contracting of services for construction and operation of a grout batch plant. The research and field experience gained by SRNL in the closure of Tanks 17F and 20F at the Savannah River Site was leveraged into the grout development efforts for Hanford. It is concluded that the three Hanford grout design mixes provide fill materials that meet the current requirements for successful placement. This conclusion is based on the completion of recommended testing using Hanford area materials by the operators of the grout batch plant. This report summarizes the regulatory drivers and the requirements for grout mixes as tank fill material. It is these requirements for both fresh and cured grout properties that drove the development of the grout formulations for the stabilization, structural and capping layers.

  19. traveladvisory Terminal Roadway Closure 6-23 to 7-01-2010

    E-Print Network [OSTI]

    Paulsson, Johan

    traveladvisory Terminal Roadway Closure 6-23 to 7-01-2010 PASSENGER PICK UP/DROP OFF · Drivers meeting arriving passengers at Terminal B will enter the Terminal B garage where they will be directed passengers getting picked up by a private vehicle should exit the terminal at the lower level and use

  20. 3718-F Alkali Metal Treatment and Storage Facility Closure Plan. Revision 1

    SciTech Connect (OSTI)

    none,

    1992-11-01T23:59:59.000Z

    The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, as well as for activities associated with nuclear energy development. The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. The 3718-F Alkali Metal Treatment and Storage Facility (3718-F Facility), located in the 300 Area, was used to store and treat alkali metal wastes. Therefore, it is subject to the regulatory requirements for the storage and treatment of dangerous wastes. Closure will be conducted pursuant to the requirements of the Washington Administrative Code (WAC) 173-303-610 (Ecology 1989) and 40 CFR 270.1. Closure also will satisfy the thermal treatment facility closure requirements of 40 CFR 265.381. This closure plan presents a description of the 3718-F Facility, the history of wastes managed, and the approach that will be followed to close the facility. Only hazardous constituents derived from 3718-F Facility operations will be addressed.

  1. North Carolina State University Emergency Facilities Closure Checklist-Part I

    E-Print Network [OSTI]

    reactive, radioactive, and bio hazardous materials via break resistant plastic containers with screw type closures. These are secondary protective containers and must be large enough so breakable primary containers can be placed inside and secured. They are used to protect against the release of harmful

  2. Closure Plan for the Area 3 Radioactive Waste Management Site at the Nevada Test Site

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2007-09-01T23:59:59.000Z

    The Area 3 Radioactive Waste Management Site (RMWS) at the Nevada Test Site (NTS) is managed and operated by National Security Technologies, LLC (NSTec) for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This document is the first update of the interim closure plan for the Area 3 RWMS, which was presented in the Integrated Closure and Monitoring Plan (ICMP) (DOE, 2005). The format and content of this plan follows the Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans (DOE, 1999a). The major updates to the plan include a new closure date, updated closure inventory, the new institutional control policy, and the Title II engineering cover design. The plan identifies the assumptions and regulatory requirements, describes the disposal sites and the physical environment in which they are located, presents the design of the closure cover, and defines the approach and schedule for both closing and monitoring the site. The Area 3 RWMS accepts low-level waste (LLW) from across the DOE Complex in compliance with the NTS Waste Acceptance Criteria (NNSA/NSO, 2006). The Area 3 RWMS accepts both packaged and unpackaged unclassified bulk LLW for disposal in subsidence craters that resulted from deep underground tests of nuclear devices in the early 1960s. The Area 3 RWMS covers 48 hectares (119 acres) and comprises seven subsidence craters--U-3ax, U-3bl, U-3ah, U-3at, U-3bh, U-3az, and U-3bg. The area between craters U-3ax and U-3bl was excavated to form one large disposal unit (U-3ax/bl); the area between craters U-3ah and U-3at was also excavated to form another large disposal unit (U-3ah/at). Waste unit U-3ax/bl is closed; waste units U-3ah/at and U-3bh are active; and the remaining craters, although currently undeveloped, are available for disposal of waste if required. This plan specifically addresses the closure of the U-3ah/at and the U-3bh LLW units. A final closure cover has been placed on unit U-3ax/bl (Corrective Action Unit 110) at the Area 3 RWMS. Monolayer-evapotranspirative closure cover designs for the U-3ah/at and U-3bh units are provided in this plan. The current-design closure cover thickness is 3 meters (10 feet). The final design cover will have an optimized cover thickness, which is expected to be less than 3 m (10 ft). Although waste operations at the Area 3 RWMS have ceased at the end of June 2006, disposal capacity is available for future disposals at the U-3ah/at and U-3bh units. The Area 3 RWMS is expected to start closure activities in fiscal year 2025, which include the development of final performance assessment and composite analysis documents, closure plan, closure cover design for construction, cover construction, and initiation of the post-closure care and monitoring activities. Current monitoring at the Area 3 RWMS includes monitoring the cover of the closed mixed waste unit U-3ax/bl as required by the Nevada Department of Environmental Protection, and others required under federal regulations and DOE orders. Monitoring data, collected via sensors and analysis of samples, are needed to evaluate radiation doses to the general public, for performance assessment maintenance, to demonstrate regulatory compliance, and to evaluate the actual performance of the RWMSs. Monitoring provides data to ensure the integrity and performance of waste disposal units. The monitoring program is designed to forewarn management and regulators of any failure and need for mitigating actions. The plan describes the program for monitoring direct radiation, air, vadose zone, biota, groundwater, meteorology, and subsidence. The requirements of post-closure cover maintenance and monitoring will be determined in the final closure plan.

  3. Fluid transport in branched structures with temporary closures: A model for quasistatic lung inflation

    E-Print Network [OSTI]

    Alencar, Adriano Mesquita

    Fluid transport in branched structures with temporary closures: A model for quasistatic lung a model system relevant to the inflation of a mammalian lung, an asymmetric bifurcating structure description of the underlying branching structure of the lung, by analyzing experimental pressure-volume data

  4. Analysis of the pressure-wall interaction at the release of a stop closure

    E-Print Network [OSTI]

    Chen, Lan, S.M. Massachusetts Institute of Technology

    2011-01-01T23:59:59.000Z

    In producing a stop consonant, a soft tissue articulator, such as the lower lip, the tongue tip, or the tongue body, is raised to make an airtight closure. Stevens [I] pp 32 9-3 30 hypothesized that the interaction of the ...

  5. CLOSURE WELDING RADIOACTIVE MATERIALS CONTAINERS AT THE DEPARTMENT OF ENERGY (DOE) HANFORD SITE

    SciTech Connect (OSTI)

    CANNELL, G.R.

    2006-09-01T23:59:59.000Z

    The Department of Energy's (DOE) responsibility for the disposition of radioactive materials has given rise to several unique welding applications. Many of these materials require packaging into containers for either Interim or long-term storage. It is not uncommon that final container fabrication, i.e., closure welding, is performed with these materials already placed into the container. Closure welding is typically performed remote to the container, and routine post-weld testing and nondestructive examination (NDE) are often times not feasible. Fluor Hanford has packaged many such materials in recent years as park of the Site's cleanup mission. In lieu of post-weld testing and NDE, the Fluor-Hanford approach has been to establish weld quality through ''upfront'' development and qualification of welding parameters, and then ensure parameter compliance during welding. This approach requires a rigor not usually afforded to typical welding development activities, and may involve statistical analysis and extensive testing, including burst, drop, sensitive leak testing, etc. This paper provides an instructive review of the development and qualification activities associated with the closure of radioactive materials containers, including a brief report on activities for closure welding research reactor, spent nuclear fuel (SNF) overpacks at the Hanford Site.

  6. Aerosol--cloud drop concentration closure in warm cumulus W. C. Conant,1

    E-Print Network [OSTI]

    Jimenez, Jose-Luis

    layer aerosol's effect on cloud microphysics throughout the lowest 1 km of cloud depth. Onboard the radiation balance and hydrological cycle, they are called indirect effects of aerosol on climate, or 4Aerosol--cloud drop concentration closure in warm cumulus W. C. Conant,1 T. M. VanReken,2 T. A

  7. Evaluating Radiative Closure in the Middle-to-Upper Troposhere

    SciTech Connect (OSTI)

    Tobin, David C; Turner, David D; Knuteson, Robert O

    2013-01-02T23:59:59.000Z

    This project had two general objectives. The first is the characterization and improvement of the radiative transfer parameterization in strongly absorbing water vapor bands, as these strongly absorbing bands dictate the clear sky radiative heating rate. The second is the characterization and improvement of the radiative transfer in cirrus clouds, with emphasis on ensuring that the parameterization of the radiative transfer is consistent and accurate across the spectrum. Both of these objectives are important for understanding the radiative processes in the mid-to-upper troposphere. The research on this project primarily involved analysis of data from the First and Second Radiative Heating in Underexplored Bands Campaigns, RHUBC-I and II. This included a climate model sensitivity study using results from RHUBC-I. The RHUBC experiments are ARM-funded activities that directly address the objectives of this research project. A secondary effort was also conducted that investigated the trends in the long-term (~14 year) dataset collected by the Atmospheric Emitted Radiance Interferometer (AERI) at the ARM Southern Great Plains site. This work, which was primarily done by a post-doc at the University of Wisconsin �������¢���������������� Madison under Dr. Turner�������¢����������������s direction, uses the only NIST-traceable instrument at the ARM site that has a well-documented calibration and uncertainty performance to investigate long-term trends in the downwelling longwave radiance above this site.

  8. Closure Report for Corrective Action Unit 130: Storage Tanks Nevada Test Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Alfred Wickline

    2009-03-01T23:59:59.000Z

    This Closure Report (CR) presents information supporting the closure of Corrective Action Unit (CAU) 130: Storage Tanks, Nevada Test Site, Nevada. This CR complies with the requirements of the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management. The corrective action sites (CASs) within CAU 130 are located within Areas 1, 7, 10, 20, 22, and 23 of the Nevada Test Site. Corrective Action Unit 130 is comprised of the following CASs: • 01-02-01, Underground Storage Tank • 07-02-01, Underground Storage Tanks • 10-02-01, Underground Storage Tank • 20-02-03, Underground Storage Tank • 20-99-05, Tar Residue • 22-02-02, Buried UST Piping • 23-02-07, Underground Storage Tank This CR provides documentation supporting the completed corrective action investigations and provides data confirming that the closure objectives for CASs within CAU 130 were met. To achieve this, the following actions were performed: • Reviewed the current site conditions, including the concentration and extent of contamination. • Implemented any corrective actions necessary to protect human health and the environment. • Properly disposed of corrective action and investigation-derived wastes. From August 4 through September 30, 2008, closure activities were performed as set forth in the Streamlined Approach for Environmental Restoration Plan for CAU 130, Storage Tanks, Nevada Test Site, Nevada. The purposes of the activities as defined during the data quality objectives process were: • Determine whether contaminants of concern (COCs) are present. • If COCs are present, determine their nature and extent, implement appropriate corrective actions, confirm that no residual contamination is present, and properly dispose of wastes. Constituents detected during the closure activities were evaluated against final action levels to identify COCs for CAU 130. Assessment of the data generated from closure activities indicates that no further action is necessary because no COCs were identified at any CAU 130 CAS. Debris removal from these CASs was considered a best management practice because no contamination was detected. The DOE, National Nuclear Security Administration Nevada Site Office provides the following recommendations: • No further corrective action is required at all CAU 130 CASs. • A Notice of Completion to DOE, National Nuclear Security Administration Nevada Site Office, is requested from the Nevada Division of Environmental Protection for closure of CAU 130. • Corrective Action Unit 130 should be moved from Appendix III to Appendix IV of the Federal Facility Agreement and Consent Order.

  9. Closure Report for Corrective Action Unit 562: Waste Systems, Nevada National Security Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2012-08-15T23:59:59.000Z

    This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 562, Waste Systems, and provides documentation supporting the completed corrective actions and confirmation that closure objectives for CAU 562 were met. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; the U.S. Department of Energy (DOE), Environmental Management; the U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996 as amended). CAU 562 consists of the following 13 Corrective Action Sites (CASs), located in Areas 2, 23, and 25 of the Nevada National Security Site: · CAS 02-26-11, Lead Shot · CAS 02-44-02, Paint Spills and French Drain · CAS 02-59-01, Septic System · CAS 02-60-01, Concrete Drain · CAS 02-60-02, French Drain · CAS 02-60-03, Steam Cleaning Drain · CAS 02-60-04, French Drain · CAS 02-60-05, French Drain · CAS 02-60-06, French Drain · CAS 02-60-07, French Drain · CAS 23-60-01, Mud Trap Drain and Outfall · CAS 23-99-06, Grease Trap · CAS 25-60-04, Building 3123 Outfalls Closure activities began in October 2011 and were completed in April 2012. Activities were conducted according to the Corrective Action Plan for CAU 562 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2011). The corrective actions included No Further Action and Clean Closure. Closure activities generated sanitary waste and hazardous waste. Some wastes exceeded land disposal limits and required offsite treatment prior to disposal. Other wastes met land disposal restrictions and were disposed in appropriate onsite or offsite landfills. NNSA/NSO requests the following: · A Notice of Completion from the Nevada Division of Environmental Protection to NNSA/NSO for closure of CAU 562 · The transfer of CAU 562 from Appendix III to Appendix IV, Closed Corrective Action Units, of the FFACO

  10. Closure Report for Corrective Action Unit 224: Decon Pad and Septic Systems, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2007-10-01T23:59:59.000Z

    Corrective Action Unit (CAU) 224 is located in Areas 02, 03, 05, 06, 11, and 23 of the Nevada Test Site, which is situated approximately 65 miles northwest of Las Vegas, Nevada. CAU 224 is listed in the Federal Facility Agreement and Consent Order (FFACO) of 1996 as Decon Pad and Septic Systems and is comprised of the following nine Corrective Action Sites (CASs): CAS 02-04-01, Septic Tank (Buried); CAS 03-05-01, Leachfield; CAS 05-04-01, Septic Tanks (4)/Discharge Area; CAS 06-03-01, Sewage Lagoons (3); CAS 06-05-01, Leachfield; CAS 06-17-04, Decon Pad and Wastewater Catch; CAS 06-23-01, Decon Pad Discharge Piping; CAS 11-04-01, Sewage Lagoon; and CAS 23-05-02, Leachfield. The Nevada Division of Environmental Protection (NDEP)-approved corrective action alternative for CASs 02-04-01, 03-05-01, 06-03-01, 11-04-01, and 23-05-02 is no further action. As a best management practice, the septic tanks and distribution box were removed from CASs 02-04-01 and 11-04-01 and disposed of as hydrocarbon waste. The NDEP-approved correction action alternative for CASs 05-04-01, 06-05-01, 06-17-04, and 06-23-01 is clean closure. Closure activities for these CASs included removing and disposing of radiologically and pesticide-impacted soil and debris. CAU 224 was closed in accordance with the NDEP-approved CAU 224 Corrective Action Plan (CAP). The closure activities specified in the CAP were based on the recommendations presented in the CAU 224 Corrective Action Decision Document (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2005). This Closure Report documents CAU 224 closure activities. During closure activities, approximately 60 cubic yards (yd3) of mixed waste in the form of soil and debris; approximately 70 yd{sup 3} of sanitary waste in the form of soil, liquid from septic tanks, and concrete debris; approximately 10 yd{sup 3} of hazardous waste in the form of pesticide-impacted soil; approximately 0.5 yd{sup 3} of universal waste in the form of fluorescent light bulbs; and approximately 0.5 yd{sup 3} of low-level waste in the form of a radiologically impacted fire hose rack were generated, managed, and disposed of appropriately. Waste minimization techniques, such as the utilization of laboratory analysis and field screening to guide the extent of excavations, were employed during the performance of closure work.

  11. Microsoft Word - CPMI Closure_Report 4-17

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy China 2015of 2005 atthe DistrictIndependent Research Assessment of Project CONTRACT AND

  12. Post-Closure Inspection Report for the Tonopah Test Range, Nevada, For Calendar Year 2011

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2012-02-21T23:59:59.000Z

    This report provides the results of the annual post-closure inspections conducted at the closed Corrective Action Units (CAUs) located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2011 and includes inspection and repair activities completed at the following CAUs: (1) CAU 400: Bomblet Pit and Five Points Landfill (TTR); (2) CAU 407: Roller Coaster RadSafe Area (TTR); (3) CAU 424: Area 3 Landfill Complexes (TTR); (4) CAU 453: Area 9 UXO Landfill (TTR); and (5) CAU 487: Thunderwell Site (TTR) Inspections were conducted according to the post-closure plans in the approved Closure Reports. The post-closure inspection plan for each CAU is included in Appendix B. The inspection checklists are included in Appendix C, field notes are included in Appendix D, and photographs taken during inspections are included in Appendix E. The annual post-closure inspections were conducted May 3 and 4, 2011. Maintenance was performed at CAU 424, CAU 453, and CAU 487. At CAU 424, two surface grade monuments at Landfill Cell A3-3 could not be located during the inspection. The two monuments were located and marked with lava rock on July 13, 2011. At CAU 453, there was evidence of animal burrowing. Animal burrows were backfilled on July 13, 2011. At CAU 487, one use restriction warning sign was missing, and wording was faded on the remaining signs. A large animal burrow was also present. The signs were replaced, and the animal burrow was backfilled on July 12, 2011. As a best management practice, the use restriction warning signs at CAU 407 were replaced with standard Federal Facility Agreement and Consent Order signs on July 13, 2011. Vegetation monitoring was performed at the CAU 400 Five Points Landfill and CAU 407 in June 2011, and the vegetation monitoring report is included in Appendix F.

  13. Closure Report for Corrective Action Unit 151: Septic Systems and Discharge Area, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2008-04-01T23:59:59.000Z

    Corrective Action Unit (CAU) 151 is identified in the Federal Facility Agreement and Consent Order (FFACO) as Septic Systems and Discharge Area. CAU 151 consists of the following eight Corrective Action Sites (CASs), located in Areas 2, 12, and 18 of the Nevada Test Site, approximately 65 miles northwest of Las Vegas, Nevada: (1) CAS 02-05-01, UE-2ce Pond; (2) CAS 12-03-01, Sewage Lagoons (6); (3) CAS 12-04-01, Septic Tanks; (4) CAS 12-04-02, Septic Tanks; (5) CAS 12-04-03, Septic Tank; (6) CAS 12-47-01, Wastewater Pond; (7) CAS 18-03-01, Sewage Lagoon; and (8) CAS 18-99-09, Sewer Line (Exposed). CAU 151 closure activities were conducted according to the FFACO (FFACO, 1996; as amended February 2008) and the Corrective Action Plan for CAU 151 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007) from October 2007 to January 2008. The corrective action alternatives included no further action, clean closure, and closure in place with administrative controls. CAU 151 closure activities are summarized in Table 1. Closure activities generated liquid remediation waste, sanitary waste, hydrocarbon waste, and mixed waste. Waste generated was appropriately managed and disposed. Waste that is currently staged onsite is being appropriately managed and will be disposed under approved waste profiles in permitted landfills. Waste minimization activities included waste characterization sampling and segregation of waste streams. Some waste exceeded land disposal restriction limits and required offsite treatment prior to disposal. Other waste meeting land disposal restrictions was disposed of in appropriate onsite or offsite landfills. Waste disposition documentation is included as Appendix C.

  14. Post-Closure Inspection Report for the Tonopah Test Range, Nevada, for Calendar Year 2013

    SciTech Connect (OSTI)

    Silvas, A. J.

    2014-03-03T23:59:59.000Z

    This report provides the results of the annual post-closure inspections conducted at the closed Corrective Action Units (CAUs) located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2013 and includes inspection and repair activities completed at the following CAUs: • CAU 400: Bomblet Pit and Five Points Landfill (TTR) • CAU 407: Roller Coaster RadSafe Area (TTR) • CAU 424: Area 3 Landfill Complexes (TTR) • CAU 453: Area 9 UXO Landfill (TTR) • CAU 487: Thunderwell Site (TTR) Inspections were conducted according to the post-closure plans in the approved Closure Reports and subsequent correspondence with the Nevada Division of Environmental Protection. The post-closure inspection plans and subsequent correspondence modifying the requirements for each CAU are included in Appendix B. The inspection checklists are included in Appendix C. Field notes are included in Appendix D. Photographs taken during inspections are included in Appendix E. The annual post-closure inspections were conducted on May 14, 2013. Maintenance was performed at CAU 400, CAU 424, and CAU 453. At CAU 400, animal burrows were backfilled. At CAU 424, erosion repairs were completed at Landfill Cell A3-3, subsidence was repaired at Landfill Cell A3-4, and additional lava rock was placed in high-traffic areas to mark the locations of the surface grade monuments at Landfill Cell A3-3 and Landfill Cell A3-8. At CAU 453, two areas of subsidence were repaired and animal burrows were backfilled. Vegetation monitoring was performed at the CAU 400 Five Points Landfill and CAU 407 in June 2013. The vegetation monitoring report is included in Appendix F.

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

    SciTech Connect (OSTI)

    NA

    2006-03-01T23:59:59.000Z

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

  16. Determination of H{sub 2} Diffusion Rates through Various Closures on TRU Waste Bag-Out Bags

    SciTech Connect (OSTI)

    Phillip D. Noll, Jr.; E. Larry Callis; Kirsten M. Norman

    1999-06-01T23:59:59.000Z

    The amount of H{sub 2} diffusion through twist and tape (horse-tail), wire tie, plastic tie, and heat sealed closures on transuranic (TRU) waste bag-out bags has been determined. H{sub 2} diffusion through wire and plastic tie closures on TRU waste bag-out bags has not been previously characterized and, as such, TRU waste drums containing bags with these closures cannot be certified and/or shipped to the Waste Isolation Pilot Plant (WIPP). Since wire ties have been used at Los Alamos National Laboratory (LANL) from 1980 to 1991 and the plastic ties from 1991 to the present, there are currently thousands of waste drums that cannot be shipped to the WIPP site. Repackaging the waste would be prohibitively expensive. Diffusion experiments performed on the above mentioned closures show that the diffusion rates of plastic tie and horse-tail closures are greater than the accepted value presented in the TRU-PACT 11 Safety Analysis Report (SAR). Diffusion rates for wire tie closures are not statistically different from the SAR value. Thus, drums containing bags with these closures can now potentially be certified which would allow for their consequent shipment to WIPP.

  17. Emergency evacuation/transportation plan update: Traffic model development and evaluation of early closure procedures. Final report

    SciTech Connect (OSTI)

    NONE

    1993-10-28T23:59:59.000Z

    Prolonged delays in traffic experienced by Laboratory personnel during a recent early dismissal in inclement weather, coupled with reconstruction efforts along NM 502 east of the White Rock Wye for the next 1 to 2 years, has prompted Los Alamos National Laboratory (LANL) to re-evaluate and improve the present transportation plan and its integration with contingency plans maintained in other organizations. Facilities planners and emergency operations staff need to evaluate the transportation system`s capability to inefficiently and safely evacuate LANL under different low-level emergency conditions. A variety of potential procedures governing the release of employees from the different technical areas (TAs) requires evaluation, perhaps with regard to multiple emergency-condition scenarios, with one or more optimal procedures ultimately presented for adoption by Lab Management. The work undertaken in this project will hopefully lay a foundation for an on-going, progressive transportation system analysis capability. It utilizes microscale simulation techniques to affirm, reassess and validate the Laboratory`s Early Dismissal/Closure/Delayed Opening Plan. The Laboratory is required by Federal guidelines, and compelled by prudent practice and conscientious regard for the welfare of employees and nearby residents, to maintain plans and operating procedures for evacuation if the need arises. The tools developed during this process can be used outside of contingency planning. It is anticipated that the traffic models developed will allow site planners to evaluate changes to the traffic network which could better serve the normal traffic levels. Changes in roadway configuration, control strategies (signalization and signing), response strategies to traffic accidents, and patterns of demand can be modelled using the analysis tools developed during this project. Such scenarios typically are important considerations in master planning and facilities programming.

  18. Magnesium Projects

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

    cyberinfrastructure projects and will be augmented by original research in Computer Science and Software Engineering towards the creation of large, distributed, autonomic and...

  19. Project Construction

    Broader source: Energy.gov [DOE]

    Integrating renewable energy into Federal new construction or major renovations requires effective structuring of the construction team and project schedule. This overview discusses key construction team considerations for renewable energy as well as timing and expectations for the construction phase. The project construction phase begins after a project is completely designed and the construction documents (100%) have been issued. Construction team skills and experience with renewable energy technologies are crucial during construction, as is how the integration of renewable energy affects the project construction schedule.

  20. HWMA/RCRA Closure Plan for the TRA Fluorinel Dissolution Process Mockup and Gamma Facilities Waste System

    SciTech Connect (OSTI)

    K. Winterholler

    2007-01-31T23:59:59.000Z

    This Hazardous Waste Management Act/Resource Conservation and Recovery Act closure plan was developed for the Test Reactor Area Fluorinel Dissolution Process Mockup and Gamma Facilities Waste System, located in Building TRA-641 at the Reactor Technology Complex (RTC), Idaho National Laboratory Site, to meet a further milestone established under the Voluntary Consent Order SITE-TANK-005 Action Plan for Tank System TRA-009. The tank system to be closed is identified as VCO-SITE-TANK-005 Tank System TRA-009. This closure plan presents the closure performance standards and methods for achieving those standards.

  1. Closure Report for Corrective Action Unit 366: Area 11 Plutonium Valley Dispersion Sites, Nevada National Security Site, Nevada

    SciTech Connect (OSTI)

    none,

    2013-12-31T23:59:59.000Z

    This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 366, Area 11 Plutonium Valley Dispersion Sites, and provides documentation supporting the completed corrective actions and confirmation that closure objectives for CAU 366 were met. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; the U.S. Department of Energy (DOE), Environmental Management; the U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996 as amended).

  2. Legacy sample disposition project. Volume 2: Final report

    SciTech Connect (OSTI)

    Gurley, R.N.; Shifty, K.L.

    1998-02-01T23:59:59.000Z

    This report describes the legacy sample disposition project at the Idaho Engineering and Environmental Laboratory (INEEL), which assessed Site-wide facilities/areas to locate legacy samples and owner organizations and then characterized and dispositioned these samples. This project resulted from an Idaho Department of Environmental Quality inspection of selected areas of the INEEL in January 1996, which identified some samples at the Test Reactor Area and Idaho Chemical Processing Plant that had not been characterized and dispositioned according to Resource Conservation and Recovery Act (RCRA) requirements. The objective of the project was to manage legacy samples in accordance with all applicable environmental and safety requirements. A systems engineering approach was used throughout the project, which included collecting the legacy sample information and developing a system for amending and retrieving the information. All legacy samples were dispositioned by the end of 1997. Closure of the legacy sample issue was achieved through these actions.

  3. Transseptal Guidewire Stabilization for Device Closure of a Large Pulmonary Arteriovenous Malformation

    SciTech Connect (OSTI)

    Joseph, George, E-mail: joseph59@gmail.com; Kunwar, Brajesh Kumar, E-mail: kunwar_brajesh@yahoo.com [Christian Medical College, Department of Cardiology (India)

    2013-06-15T23:59:59.000Z

    A 46-year-old man presenting with massive hemoptysis was found to have a large pulmonary arteriovenous malformation (PAVM) in the right lung. Closure of the PAVM with an Amplatzer-type duct occluder was hampered by inability to advance the device delivery sheath into the PAVM due to vessel tortuosity and inadequate guidewire support. Atrial septal puncture was performed and a femorofemoral arteriovenous guidewire loop through the right pulmonary artery, PAVM, and left atrium was created. Traction on both ends of the guidewire loop allowed advancement of the device delivery sheath into the PAVM and successful completion of the procedure. Transseptal guidewire stabilization can be a valuable option during device closure of large PAVMs when advancement, stability, or kinking of the device delivery sheath is an issue.

  4. Drop Simulation of 6M Drum with Locking-Ring Closure and Liquid Contents

    SciTech Connect (OSTI)

    Wu, T

    2006-04-17T23:59:59.000Z

    This paper presents the dynamic simulation of the 6M drum with a locking-ring type closure subjected to a 4.9-foot drop. The drum is filled with water to 98 percent of overflow capacity. A three dimensional finite-element model consisting of metallic, liquid and rubber gasket components is used in the simulation. The water is represented by a hydrodynamic material model in which the material's volume strength is determined by an equation of state. The explicit numerical method based on the theory of wave propagation is used to determine the combined structural response to the torque load for tightening the locking-ring closure and to the impact load due to the drop.

  5. DESIGN OF THE HANFORD MULTI CANISTER OVERPACK (MCO) & DEVELOPMENT & QUALIFICATION OF THE CLOSURE WELDING PROCESS

    SciTech Connect (OSTI)

    CANNELL, G. R.

    2004-04-30T23:59:59.000Z

    Processing more than 2,100 metric tons of metallic uranium spent nuclear fuel (SNF) into large stainless steel containers called Multi-Canister Overpacks (MCOs) is one of the top priorities for the Department of Energy (DOE) at the Hanford Site, located in southeastern Washington state. The MCOs will be temporarily stored on site and eventually shipped to the federal geologic repository for long-term storage. MCOs are constructed and ''N''stamped in accordance with the requirements of the American Society of Mechanical Engineers (ASME) Section III, Division 1, Class 1 Components. Final closure welding poses a challenge after the fuel is loaded. Performing required examination and testing activities (volumetric examination and hydrostatic leak testing) can be difficult, if not impractical. An ASME Code Case N-595-3, was written specifically to allow code stamping by addressing such closures and providing alternative rules. MCOs are the first SNF canisters within the DOE complex to successfully use this code case for receiving ASME stamps. This paper discusses the design of the MCO, application of the N-595-3 code case, and development and qualification of the final welded closure. The MCO design considers internal pressure and handling loads, as well as processing and interim storage activities. The MCO functions as the primary or innermost containment as part of an overall transportation package so the design also considered interface features with secondary and transport containers. The MCO, approximately 2 feet in diameter and nearly 14 feet tall, is constructed primarily of Type 304/304L stainless steel and the final pressure boundary is of all-welded construction. The closure-weld is made with the Gas Tungsten Arc Welding (GTAW) process, using an automatic, machine-welding mode. Examination and testing of the closure includes the N-595-3 specified requirements-progressive Liquid Penetrant testing (PT) and final helium leak testing. At completion of the closure, the MCO is ''N'' stamped as a 450 pounds per square inch (design pressure) vessel. To ensure the process consistently achieves the required weld penetration, a series of developmental tests was performed to identify an optimum and robust set of welding parameters. Testing included test welds made on plate mockups and then actual MCO mockups. With the primary welding parameters (welding current and travel speed) established, a simple two-factor, two-level, factorial experiment with replication at high and low heat input conditions was conducted. Evaluation of the results included weld photomicrographs, which helped establish process range limits for these parameters broad enough to cover typical equipment and measurement variations and provide additional operating margin. To date, over 316 MCOs have been loaded, dried, and transported to the Canister Storage Building (CSB), where the welding is done. Of those, 161 MCOs have received final welded closure and ''N'' stamps. All cover cap final closure welds have met specified requirements without incident.

  6. 324 Building radiochemical engineering cells, high-level vault, low-level vault, and associated areas closure plan

    SciTech Connect (OSTI)

    Barnett, J.M.

    1998-03-25T23:59:59.000Z

    The Hanford Site, located adjacent to and north of Richland, Washington, is operated by the US Department of Energy, Richland Operations Office (RL). The 324 Building is located in the 300 Area of the Hanford Site. The 324 Building was constructed in the 1960s to support materials and chemical process research and development activities ranging from laboratory/bench-scale studies to full engineering-scale pilot plant demonstrations. In the mid-1990s, it was determined that dangerous waste and waste residues were being stored for greater than 90 days in the 324 Building Radiochemical Engineering Cells (REC) and in the High-Level Vault/Low-Level Vault (HLV/LLV) tanks. [These areas are not Resource Conservation and Recovery Act of 1976 (RCRA) permitted portions of the 324 Building.] Through the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-89, agreement was reached to close the nonpermitted RCRA unit in the 324 Building. This closure plan, managed under TPA Milestone M-20-55, addresses the identified building areas targeted by the Tri-Party Agreement and provides commitments to achieve the highest degree of compliance practicable, given the special technical difficulties of managing mixed waste that contains high-activity radioactive materials, and the physical limitations of working remotely in the areas within the subject closure unit. This closure plan is divided into nine chapters. Chapter 1.0 provides the introduction, historical perspective, 324 Building history and current mission, and the regulatory basis and strategy for managing the closure unit. Chapters 2.0, 3.0, 4.0, and 5.0 discuss the detailed facility description, process information, waste characteristics, and groundwater monitoring respectively. Chapter 6.0 deals with the closure strategy and performance standard, including the closure activities for the B-Cell, D-Cell, HLV, LLV; piping and miscellaneous associated building areas. Chapter 7.0 addresses the closure activities identified in Chapter 6.0, and also adds information on closure activities for the soil directly beneath the unit, regulated material removed during closure, and the schedule for closure. Chapter 8.0 provides Surveillance, monitoring and post-closure information and Chapter 9.0 provides a list of references used throughout the document.

  7. Post-Closure Inspection Report for Corrective Action Unit 92: Area 6 Decon Pond Facility

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2008-03-01T23:59:59.000Z

    This Post-Closure Inspection Report provides an analysis and summary of inspections for Corrective Action Unit (CAU) 92, Area 6 Decon Pond Facility. CAU 92 was closed according to the Resource Conservation and Recovery Act (RCRA) Part B Operational Permit (Nevada Division of Environmental Protection [NDEP], 1995) and the Federal Facility Agreement and Consent Order (FFACO) of 1996 (FFACO, 1996; as amended January 2007). Closure activities were completed on February 16, 1999, and the Closure Report (U.S. Department of Energy, Nevada Operations Office, 1999) was approved and a Notice of Completion issued by NDEP on May 11, 1999. CAU 92 consists of two Corrective Action Sites (CASs): CAS 06-04-01, Decon Pad Oil/Water Separator, and CAS 06-05-02, Decontamination Pond (RCRA). Both CASs have use restrictions; however, only CAS 06-05-02 requires post-closure inspections. Visual inspections of the cover and fencing at CAS 06-05-02 are performed quarterly. Additional inspections are conducted if precipitation occurs in excess of 1.28 centimeters (cm) (0.50 inches [in.]) in a 24-hour period. This report covers calendar year 2007. Quarterly site inspections were performed in March, June, September, and December of 2007. All observations indicated the continued integrity of the unit. No issues or concerns were noted, and no corrective actions were necessary. Copies of the inspection checklists and field notes completed during each inspection are included in Appendix A of this report, and photographs taken during the site inspections are included in Appendix B of this report. Two additional inspections were performed after precipitation events that exceeded 1.28 cm (0.50 in.) within a 24-hour period during 2007. No significant changes in site conditions were noted during these inspections, and no corrective actions were necessary. A copy of the inspection checklists and field notes completed during these additional inspections are included in Appendix A. Precipitation records for 2007 are included in Appendix C.

  8. PROTOCOL FOR EXAMINATION OF THE INNER CAN CLOSURE WELD REGION FOR 3013 DE CONTAINERS

    SciTech Connect (OSTI)

    Mickalonis, J.

    2014-09-16T23:59:59.000Z

    The protocol for the examination of the inner can closure weld region (ICCWR) for 3013 DE containers is presented within this report. The protocol includes sectioning of the inner can lid section, documenting the surface condition, measuring corrosion parameters, and storing of samples. This protocol may change as the investigation develops since findings may necessitate additional steps be taken. Details of the previous analyses, which formed the basis for this protocol, are also presented.

  9. Regulatory Closure Options for the Residue in the Hanford Site Single-Shell Tanks

    SciTech Connect (OSTI)

    Cochran, J.R. Shyr, L.J.

    1998-10-05T23:59:59.000Z

    Liquid, mixed, high-level radioactive waste (HLW) has been stored in 149 single-shell tanks (SSTS) located in tank farms on the U.S. Department of Energy's (DOE's) Hanford Site. The DOE is developing technologies to retrieve as much remaining HLW as technically possible prior to physically closing the tank farms. In support of the Hanford Tanks Initiative, Sandia National Laboratories has addressed the requirements for the regulatory closure of the radioactive component of any SST residue that may remain after physical closure. There is significant uncertainty about the end state of each of the 149 SSTS; that is, the nature and amount of wastes remaining in the SSTS after retrieval is uncertain. As a means of proceeding in the face of these uncertainties, this report links possible end-states with associated closure options. Requirements for disposal of HLW and low-level radioactive waste (LLW) are reviewed in detail. Incidental waste, which is radioactive waste produced incidental to the further processing of HLW, is then discussed. If the low activity waste (LAW) fraction from the further processing of HLW is determined to be incidental waste, then DOE can dispose of that incidental waste onsite without a license from the U.S. Nuclear Regulatory Commissions (NRC). The NRC has proposed three Incidental Waste Criteria for determining if a LAW fraction is incidental waste. One of the three Criteria is that the LAW fraction should not exceed the NRC's Class C limits.

  10. Closure Report for Corrective Action Unit 107: Low Impact Soil Sites, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2009-06-01T23:59:59.000Z

    Corrective Action Unit (CAU) 107 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Low Impact Soil Sites' and consists of the following 15 Corrective Action Sites (CASs), located in Areas 1, 2, 3, 4, 5, 9, 10, and 18 of the Nevada Test Site: CAS 01-23-02, Atmospheric Test Site - High Alt; CAS 02-23-02, Contaminated Areas (2); CAS 02-23-03, Contaminated Berm; CAS 02-23-10, Gourd-Amber Contamination Area; CAS 02-23-11, Sappho Contamination Area; CAS 02-23-12, Scuttle Contamination Area; CAS 03-23-24, Seaweed B Contamination Area; CAS 03-23-27, Adze Contamination Area; CAS 03-23-28, Manzanas Contamination Area; CAS 03-23-29, Truchas-Chamisal Contamination Area; CAS 04-23-02, Atmospheric Test Site T4-a; CAS 05-23-06, Atmospheric Test Site; CAS 09-23-06, Mound of Contaminated Soil; CAS 10-23-04, Atmospheric Test Site M-10; and CAS 18-23-02, U-18d Crater (Sulky). Closure activities were conducted from February through April 2009 according to the FFACO (1996; as amended February 2008) and Revision 1 of the Streamlined Approach for Environmental Restoration Plan for CAU 107 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2009). The corrective action alternatives included No Further Action and Closure in Place with Administrative Controls. Closure activities are summarized.

  11. Recommended management practices for operation and closure of shallow injection wells at DOE facilities

    SciTech Connect (OSTI)

    Not Available

    1993-07-01T23:59:59.000Z

    The Safe Drinking Water Act established the Underground Injection Control (UIC) program to ensure that underground injection of wastes does not endanger an underground source of drinking water. Under UIC regulations, an injection well is a hole in the ground, deeper than it is wide, that receives wastes or other fluid substances. Types of injection wells range from deep cased wells to shallow sumps, drywells, and drainfields. The report describes the five classes of UIC wells and summarizes relevant regulations for each class of wells and for the UIC program. The main focus of the report is Class IV and V shallow injection wells. Class IV wells are prohibited and should be closed when they are identified. Class V wells are generally authorized by rule, but EPA or a delegated state may require a permit for a Class V well. This report provides recommendations on sound operating and closure practices for shallow injection wells. In addition the report contains copies of several relevant EPA documents that provide additional information on well operation and closure. Another appendix contains information on the UIC programs in 21 states in which there are DOE facilities discharging to injection wells. The appendix includes the name of the responsible regulatory agency and contact person, a summary of differences between the state`s regulations and Federal regulations, and any closure guidelines for Class IV and V wells.

  12. Site-Wide Integrated Water Monitoring - Defining and Implementing Sampling Objectives to Support Site Closure - 13060

    SciTech Connect (OSTI)

    Wilborn, Bill; Knapp, Kathryn [U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (United States)] [U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (United States); Farnham, Irene; Marutzky, Sam [Navarro-Intera (United States)] [Navarro-Intera (United States)

    2013-07-01T23:59:59.000Z

    The Underground Test Area (UGTA) activity is responsible for assessing and evaluating the effects of the underground nuclear weapons tests on groundwater at the Nevada National Security Site (NNSS), formerly the Nevada Test Site (NTS), and implementing a corrective action closure strategy. The UGTA strategy is based on a combination of characterization, modeling studies, monitoring, and institutional controls (i.e., monitored natural attenuation). The closure strategy verifies through appropriate monitoring activities that contaminants of concern do not exceed the SDWA at the regulatory boundary and that adequate institutional controls are established and administered to ensure protection of the public. Other programs conducted at the NNSS supporting the environmental mission include the Routine Radiological Environmental Monitoring Program (RREMP), Waste Management, and the Infrastructure Program. Given the current programmatic and operational demands for various water-monitoring activities at the same locations, and the ever-increasing resource challenges, cooperative and collaborative approaches to conducting the work are necessary. For this reason, an integrated sampling plan is being developed by the UGTA activity to define sampling and analysis objectives, reduce duplication, eliminate unnecessary activities, and minimize costs. The sampling plan will ensure the right data sets are developed to support closure and efficient transition to long-term monitoring. The plan will include an integrated reporting mechanism for communicating results and integrating process improvements within the UGTA activity as well as between other U.S. Department of Energy (DOE) Programs. (authors)

  13. Site-Wide Integrated Water Monitoring -- Defining and Implementing Sampling Objectives to Support Site Closure

    SciTech Connect (OSTI)

    Wilborn, Bill [NNSA/NFO, Nevada Site Office (United States); Farnham, Irene [Navarro-Interra LLC, Las Vegas (United States); Marutzky, Sam [Navarro-Interra LLC, Las Vegas (United States); Knapp, Kathryn [NNSA/NFO, Nevada Site Office (United States)

    2013-02-24T23:59:59.000Z

    The Underground Test Area (UGTA) activity is responsible for assessing and evaluating the effects of the underground nuclear weapons tests on groundwater at the Nevada National Security Site (NNSS), formerly the Nevada Test Site (NTS), and implementing a corrective action closure strategy. The UGTA strategy is based on a combination of characterization, modeling studies, monitoring, and institutional controls (i.e., monitored natural attenuation). The closure strategy verifies through appropriate monitoring activities that contaminants of concern do not exceed the SDWA at the regulatory boundary and that adequate institutional controls are established and administered to ensure protection of the public. Other programs conducted at the NNSS supporting the environmental mission include the Routine Radiological Environmental Monitoring Program (RREMP), Waste Management, and the Infrastructure Program. Given the current programmatic and operational demands for various water-monitoring activities at the same locations, and the ever-increasing resource challenges, cooperative and collaborative approaches to conducting the work are necessary. For this reason, an integrated sampling plan is being developed by the UGTA activity to define sampling and analysis objectives, reduce duplication, eliminate unnecessary activities, and minimize costs. The sampling plan will ensure the right data sets are developed to support closure and efficient transition to long-term monitoring. The plan will include an integrated reporting mechanism for communicating results and integrating process improvements within the UGTA activity as well as between other U.S. Department of Energy (DOE) Programs.

  14. DYNAMIC ANALYSIS OF THE BULK TRITIUM SHIPPING PACKAGE SUBJECTED TO CLOSURE TORQUES AND SEQUENTIAL IMPACTS

    SciTech Connect (OSTI)

    Wu, T; Paul Blanton, P; Kurt Eberl, K

    2007-07-09T23:59:59.000Z

    This paper presents a finite-element technique to simulate the structural responses and to evaluate the cumulative damage of a radioactive material packaging requiring bolt closure-tightening torque and subjected to the scenarios of the Hypothetical Accident Conditions (HAC) defined in the Code of Federal Regulations Title 10 part 71 (10CFR71). Existing finite-element methods for modeling closure stresses from bolt pre-load are not readily adaptable to dynamic analyses. The HAC events are required to occur sequentially per 10CFR71 and thus the evaluation of the cumulative damage is desirable. Generally, each HAC event is analyzed separately and the cumulative damage is partially addressed by superposition. This results in relying on additional physical testing to comply with 10CFR71 requirements for assessment of cumulative damage. The proposed technique utilizes the combination of kinematic constraints, rigid-body motions and structural deformations to overcome some of the difficulties encountered in modeling the effect of cumulative damage. This methodology provides improved numerical solutions in compliance with the 10CFR71 requirements for sequential HAC tests. Analyses were performed for the Bulk Tritium Shipping Package (BTSP) designed by Savannah River National Laboratory to demonstrate the applications of the technique. The methodology proposed simulates the closure bolt torque preload followed by the sequential HAC events, the 30-foot drop and the 30-foot dynamic crush. The analytical results will be compared to the package test data.

  15. Technical Review of Retrieval and Closure Plans for the INEEL INTEC Tank Farm Facility

    SciTech Connect (OSTI)

    Bamberger, Judith A.; Burks, Barry L.; Quigley, Keith D.; Butterworth, S. W.; Falter, Diedre D.

    2001-09-28T23:59:59.000Z

    The purpose of this report is to document the conclusions of a technical review of retrieval and closure plans for the Idaho National Energy and Environmental Laboratory (INEEL) Idaho Nuclear Technology and Engineering Center (INTEC) Tank Farm Facility. In addition to reviewing retrieval and closure plans for these tanks, the review process served as an information exchange mechanism so that staff in the INEEL High Level Waste (HLW) Program could become more familiar with retrieval and closure approaches that have been completed or are planned for underground storage tanks at the Oak Ridge National Laboratory (ORNL) and Hanford sites. This review focused not only on evaluation of the technical feasibility and appropriateness of the approach selected by INEEL but also on technology gaps that could be addressed through utilization of technologies or performance data available at other DOE sites and in the private sector. The reviewers, Judith Bamberger of Pacific Northwest National Laboratory (PNNL) and Dr. Barry Burks of The Providence Group Applied Technology, have extensive experience in the development and application of tank waste retrieval technologies for nuclear waste remediation.

  16. Hydrogen-bond driven loop-closure kinetics in unfolded polypeptide chains

    SciTech Connect (OSTI)

    Daidone, Isabella [University of Heidelberg; Neuweiler, H [University of Heidelberg; Doose, S [University of Heidelberg; Sauer, M [University of Heidelberg; Smith, Jeremy C [ORNL

    2010-12-01T23:59:59.000Z

    Characterization of the length dependence of end-to-end loop-closure kinetics in unfolded polypeptide chains provides an understanding of early steps in protein folding. Here, loop-closure in poly-glycine-serine peptides is investigated by combining single-molecule fluorescence spectroscopy with molecular dynamics simulation. For chains containing more than 10 peptide bonds loop-closing rate constants on the 20-100 nanosecond time range exhibit a power-law length dependence. However, this scaling breaks down for shorter peptides, which exhibit slower kinetics arising from a perturbation induced by the dye reporter system used in the experimental setup. The loop-closure kinetics in the longer peptides is found to be determined by the formation of intra-peptide hydrogen bonds and transient beta-sheet structure, that accelerate the search for contacts among residues distant in sequence relative to the case of a polypeptide chain in which hydrogen bonds cannot form. Hydrogen-bond-driven polypeptide-chain collapse in unfolded peptides under physiological conditions found here is not only consistent with hierarchical models of protein folding, that highlights the importance of secondary structure formation early in the folding process, but is also shown to speed up the search for productive folding events.

  17. Changes in rainwater acidity associated with closure of a copper smelter

    SciTech Connect (OSTI)

    Vong, R.J.; Moseholm, L.; Convert, D.S.; Sampson, P.D.; O'Loughlin, J.F.; Stevenson, M.N.; Larson, T.V.

    1988-06-20T23:59:59.000Z

    The influence of the sulfur dioxide emissions from a large copper smelter in Tacoma, Washington was studied by measuring the chemical composition of rainwater collected upwind and downwind of the source, before and after permanent closure of the smelter in 1985. Data analysis was based on a statistical model that accounted for variability associated with location of 25 sampling sites within three geographic regions, smelter operation, 10 individual rain events observed over 2 years, and measurement uncertanity. After smelter closure the unwind-downwind differences in mean hydrogen ion and excess sulfate ion concentrations within a 600 km/sup 2/ region, extending to 25 km downwind of the source, had decreased significantly compared to the preclosure value. No significant decreases in mean ion concentrations were observed farther downwind in the Seattle urban area. During five events sampled prior to smelter closure, we estimate that an average of 4.4% (range 0.7--8.6%) of the sulfur dioxide emitted by the smelter was wet deposited as sulfate ion within a 3600 km/sup 2/ area extending 60 km downwind of the source. copyright American Geophysical Union 1988

  18. Development of weld closure stations for plutonium long-term storage containers

    SciTech Connect (OSTI)

    Fernandez, R.; Martinez, D.A.; Martinez, H.E.; Nelson, T.O.; Ortega, R.E.; Rofer, C.K.; Romero, W.; Stewart, J.; Trujillo, V.L.

    1998-12-31T23:59:59.000Z

    Weld closure stations for plutonium long-term storage containers have been designed, fabricated, and tested for the Advanced Recovery and Integrated Extraction System (ARIES) at the TA-55 Plutonium Facility of the Los Alamos National Laboratory. ARIES is a processing system used for the dismantlement of the plutonium pits from nuclear weapons. ARIES prepares the extracted-plutonium in a form which is compatible with long-term storage and disposition options and meets international inspection requirements. The processed plutonium is delivered to the canning module of the ARIES line, where it is packaged in a stainless steel container. This container is then packaged in a secondary container for long-term storage. Each of the containers is hermetically sealed with a full penetration weld closure that meets the requirements of the ASME Section IX Boiler and Pressure Vessel Code. Welding is performed with a gas tungsten arc process in an inert atmosphere of helium. The encapsulated helium in the nested containers allows for leak testing the weld closure and container. The storage package was designed to meet packaging requirements of DOE Standard 3013-96 for long-term storage of plutonium metal and oxides. Development of the process parameters, weld fixture, weld qualification, and the welding chambers is discussed in this paper.

  19. Chestnut Ridge Sediment Disposal Basin (D-025): Summary of closure under Rules Governing Hazardous Waste Management in Tennessee

    SciTech Connect (OSTI)

    Stone, J.E.

    1989-07-01T23:59:59.000Z

    On February 29, 1988, the Revised Closure Plan for Chestnut Ridge Sediment Disposal Basin,'' Y/TS-390 (Reference 1) was submitted to the United States Department of Energy (DOE) for review and transmittal to the Tennessee Department of Health and Environment (TDHE). The closure activities described in the closure plan have been performed. The purpose of this document is to summarize the closure activities for the Chestnut Ridge Sediment Disposal (CRSDB). The closure of CRSDB is a final closure. The Chestnut Ridge Sediment Disposal Basin (CRSDB), Unit D-025, was an unlined, man-made sediment disposal facility on Chestnut Ridge, south of New Hope Pond (NHP). The CRSDB was constructed during 1972--73 for the disposal of sediments hydraulically dredged from NHP. It was designed to hold approximately 30,000 cubic yards of sediments. Since 1973, the basin had been used for the periodic disposal of sediments excavated from NHP and its appurtenant structures. NHP has previously received discharges form RCRA-related waste streams. 19 refs., 3 figs., 1 tab.

  20. Project Manager

    Broader source: Energy.gov [DOE]

    A successful candidate in this position will serve as a project manager in the Fuel Cell Technologies Office in the DOE-EERE Office of Transportation responsible for a wide variety of highly...

  1. RENOTER Project

    Broader source: Energy.gov [DOE]

    Overview of French project on thermoelectric waste heat recovery for cars and trucks with focus on cheap, available, efficient, and sustainable TE materials, as well as efficient material integration and production process.

  2. Radionuclide Inventory Distribution Project Data Evaluation and Verification White Paper

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2010-05-17T23:59:59.000Z

    Testing of nuclear explosives caused widespread contamination of surface soils on the Nevada Test Site (NTS). Atmospheric tests produced the majority of this contamination. The Radionuclide Inventory and Distribution Program (RIDP) was developed to determine distribution and total inventory of radionuclides in surface soils at the NTS to evaluate areas that may present long-term health hazards. The RIDP achieved this objective with aerial radiological surveys, soil sample results, and in situ gamma spectroscopy. This white paper presents the justification to support the use of RIDP data as a guide for future evaluation and to support closure of Soils Sub-Project sites under the purview of the Federal Facility Agreement and Consent Order. Use of the RIDP data as part of the Data Quality Objective process is expected to provide considerable cost savings and accelerate site closures. The following steps were completed: - Summarize the RIDP data set and evaluate the quality of the data. - Determine the current uses of the RIDP data and cautions associated with its use. - Provide recommendations for enhancing data use through field verification or other methods. The data quality is sufficient to utilize RIDP data during the planning process for site investigation and closure. Project planning activities may include estimating 25-millirem per industrial access year dose rate boundaries, optimizing characterization efforts, projecting final end states, and planning remedial actions. In addition, RIDP data may be used to identify specific radionuclide distributions, and augment other non-radionuclide dose rate data. Finally, the RIDP data can be used to estimate internal and external dose rates. The data quality is sufficient to utilize RIDP data during the planning process for site investigation and closure. Project planning activities may include estimating 25-millirem per industrial access year dose rate boundaries, optimizing characterization efforts, projecting final end states, and planning remedial actions. In addition, RIDP data may be used to identify specific radionuclide distributions, and augment other non-radionuclide dose rate data. Finally, the RIDP data can be used to estimate internal and external dose rates.

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

    SciTech Connect (OSTI)

    PRIGNANO, A.L.

    2000-07-01T23:59:59.000Z

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

  4. Closure Plan for Corrective Action Unit 110: Area 3 RWMS U-3ax/bl Disposal Unit, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    T. M. Fitzmaurice

    2000-08-01T23:59:59.000Z

    This Closure Plan has been prepared for the Area 3 RWMS U-3ax/bl Disposal Unit Corrective Action Unit 110 in accordance with the Federal Facility and Consent Order (Nevada Division of Environmental Protection [NDEP] et al., 1996). The U-3ax/bl is a historic disposal unit within the Area 3 Radioactive Waste Management Site located on the Nevada Test Site (NTS). The unit, which was formed by excavating the area between two subsidence craters (U-3ax and U-3bl), was operationally closed in 1987. The U-3ax/bl disposal unit is scheduled for permanent closure under the Resource Conservation and Recovery Act as a hazardous waste landfill. Existing records indicate that, from July 1968 to December 1987, U-3ax/bl received 2.3 x 10{sup 5} cubic meters (8.12 x 10{sup 6} cubic feet) of waste. NTS nuclear device testing generated approximately 95 percent of the total volume disposed of in U-3ax/bl, the majority of which came from the Waste Consolidation Project (80 percent of the total volume) (Elletson and Johnejack, 1995). Area 3 is located in Yucca Flat, within the northeast quadrant of the NTS. The Yucca Flat watershed is a structurally closed basin encompassing an area of approximately 780 square kilometers (300 square miles). The structural geomorphology of Yucca Flat is typical of the Basin and Range Physiographic Province. Yucca Flat lies in one of the most arid regions of the country. Water balance calculations for Area 3 indicate that it is continuously in a state of moisture deficit. The U-3ax/bl Disposal Unit will be closed in place by installing a Resource Conservation and Recovery Act equivalent cover. Following cover construction a fence will be installed around the cover to prevent accidental damage to the cover. Post-closure monitoring will consist of site inspections to determine the condition of the engineered cover and cover performance monitoring using Time-Domain Reflectometry arrays to monitor moisture migration in the cover. Any identified maintenance and repair requirements will be remedied within 60 working days of discovery and documented in writing at the time of repair. Results of all inspections/repairs for a given year will be addressed in a single report submitted annually to the NDEP. Soil moisture will be monitored within the cover for a period of at least two years prior to establishing performance criteria for NDEP regulatory purposes.

  5. Closure Report for Corrective Action Unit 166: Storage Yards and Contaminated Materials, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2009-08-01T23:59:59.000Z

    Corrective Action Unit (CAU) 166 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Storage Yards and Contaminated Materials' and consists of the following seven Corrective Action Sites (CASs), located in Areas 2, 3, 5, and 18 of the Nevada Test Site: CAS 02-42-01, Condo Release Storage Yd - North; CAS 02-42-02, Condo Release Storage Yd - South; CAS 02-99-10, D-38 Storage Area; CAS 03-42-01, Conditional Release Storage Yard; CAS 05-19-02, Contaminated Soil and Drum; CAS 18-01-01, Aboveground Storage Tank; and CAS 18-99-03, Wax Piles/Oil Stain. Closure activities were conducted from March to July 2009 according to the FF ACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 166 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action and Clean Closure. Closure activities are summarized. CAU 166, Storage Yards and Contaminated Materials, consists of seven CASs in Areas 2, 3, 5, and 18 of the NTS. The closure alternatives included No Further Action and Clean Closure. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 166 as documented in this CR: (1) At CAS 02-99-10, D-38 Storage Area, approximately 40 gal of lead shot were removed and are currently pending treatment and disposal as MW, and approximately 50 small pieces of DU were removed and disposed as LLW. (2) At CAS 03-42-01, Conditional Release Storage Yard, approximately 7.5 yd{sup 3} of soil impacted with lead and Am-241 were removed and disposed as LLW. As a BMP, approximately 22 ft{sup 3} of asbestos tile were removed from a portable building and disposed as ALLW, approximately 55 gal of oil were drained from accumulators and are currently pending disposal as HW, the portable building was removed and disposed as LLW, and accumulators, gas cylinders, and associated debris were removed and are currently pending treatment and disposal as MW. (3) At CAS 05-19-02, Contaminated Soil and Drum, as a BMP, an empty drum was removed and disposed as sanitary waste. (4) At CAS 18-01-01, Aboveground Storage Tank, approximately 165 gal of lead-impacted liquid were removed and are currently pending disposal as HW, and approximately 10 gal of lead shot and 6 yd{sup 3} of wax embedded with lead shot were removed and are currently pending treatment and disposal as MW. As a BMP, approximately 0.5 yd{sup 3} of wax were removed and disposed as hydrocarbon waste, approximately 55 gal of liquid were removed and disposed as sanitary waste, and two metal containers were grouted in place. (5) At CAS 18-99-03, Wax Piles/Oil Stain, no further action was required; however, as a BMP, approximately l.5 yd{sup 3} of wax were removed and disposed as hydrocarbon waste, and one metal container was grouted in place.

  6. Driving toward excellence in transportation and logistics operations and safety

    SciTech Connect (OSTI)

    Ashworth, D. [Office of Transportation, U.S. Dept. of Energy, Washington, DC (United States)

    2007-07-01T23:59:59.000Z

    DoE's EM is the largest cleanup project in the world: 114 sites, 31 states, 2,000,000 acres. EM scope includes remediation, processing and transportation of approximately: 25 tons of plutonium, 108 tons of plutonium residues, 88 million gallons of radioactive liquid waste, 2,500 tons of spent nuclear fuel, 137,000 cubic meters of transuranic waste, 1.3 million cubic meters of low-level waste. This series of slides presents: the Rocky Flats Status, the Fernald Closure Project, the Mound/Miamisburg and Battelle Columbus statuses, the DUF{sub 6} (Depleted Uranium Hexafluoride) Conversion Project Overview, Conversion and Transport Logistics; DoE's EM Measures of Success and performance (transportation incident criteria); the application of technology to Enhance Motor Carrier Performance, Safety, and Emergency Preparedness (technological capabilities for DOE to improve driver performance, shipment safety, and emergency response); the Motor Carrier Tracking and Alert system; DOE Load Securement Field Guide and Checklist developed to ensure all shipments are secured prior to shipment; The transportation Emergency Preparedness Program (TEPP) and outreach support; the EM Transportation Community Awareness and Emergency Response (TransCAER); and the Commodity Flow Survey data of Tennessee, Flagstaff, and Texas/Louisiana.

  7. Characterization ReportOperational Closure Covers for the Area 5 Radioactive Waste Management Site at the Nevada Test Site

    SciTech Connect (OSTI)

    Bechtel Nevada Geotechnical Sciences

    2005-06-01T23:59:59.000Z

    Bechtel Nevada (BN) manages two low-level Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site (NTS) for the U.S. Department of Energy (DOE) National Nuclear Security Administration Nevada Site Office (NNSA/NSO). The Area 3 RWMS is located in south-central Yucca Flat and the Area 5 RWMS is located about 15 miles south, in north-central Frenchman Flat. Though located in two separate topographically closed basins, they are similar in climate and hydrogeologic setting. The Area 5 RWMS uses engineered shallow-land burial cells to dispose of packaged waste, while the Area 3 RWMS uses subsidence craters formed from underground testing of nuclear weapons for the disposal of packaged and unpackaged bulk waste. Over the next several decades, most waste disposal units at both the Area 3 and Area 5 RWMSs are anticipated to be closed. Closure of the Area 3 and Area 5 RWMSs will proceed through three phases: operational closure, final closure, and institutional control. Many waste disposal units at the Area 5RWMS are operationally closed and final closure has been placed on one unit at the Area 3 RWMS (U-3ax/bl). Because of the similarities between the two sites (e.g., type of wastes, environmental factors, operational closure cover designs, etc.), many characterization studies and data collected at the Area 3 RWMS are relevant and applicable to the Area 5 RWMS. For this reason, data and closure strategies from the Area 3 RWMS are referred to as applicable. This document is an interim Characterization Report – Operational Closure Covers, for the Area 5 RWMS. The report briefly describes the Area 5 RWMS and the physical environment where it is located, identifies the regulatory requirements, reviews the approach and schedule for closing, summarizes the monitoring programs, summarizes characterization studies and results, and then presents conclusions and recommendations.

  8. Cloudnet Project

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

    Hogan, Robin

    Cloudnet is a research project supported by the European Commission. This project aims to use data obtained quasi-continuously for the development and implementation of cloud remote sensing synergy algorithms. The use of active instruments (lidar and radar) results in detailed vertical profiles of important cloud parameters which cannot be derived from current satellite sensing techniques. A network of three already existing cloud remote sensing stations (CRS-stations) will be operated for a two year period, activities will be co-ordinated, data formats harmonised and analysis of the data performed to evaluate the representation of clouds in four major european weather forecast models.

  9. Spent Nuclear Fuel project, project management plan

    SciTech Connect (OSTI)

    Fuquay, B.J.

    1995-10-25T23:59:59.000Z

    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. Closure certification report for the Bear Creek burial grounds B area and walk-in pits at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    Not Available

    1994-06-01T23:59:59.000Z

    On July 5, 1993, the revised RCRA Closure Plan for the Bear Creek Burial Grounds B Area and Walk-In Pits at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee, DOE/OR/01-1100&D3 and Y/ER-53&D3, was approved by the Tennessee Department of Environment and Conservation (TDEC). The closure activities described in that closure plan have been performed. The purpose of this document is to summarize the closure activities for B Area and Walk-In Pits (WIPs), including placement of the Kerr Hollow Quarry debris at the WIPs.

  11. ERIS Project 

    E-Print Network [OSTI]

    Hunter, Philip

    repositories. If these (generally) smaller institutions wished to continue to have access to these hosted repository spaces after the end of the project, it was proposed that these repository-lite services would be administered by the SDLC (the Scottish Digital...

  12. Safety Oversight of Decommissioning Activities at DOE Nuclear Sites

    SciTech Connect (OSTI)

    Zull, Lawrence M.; Yeniscavich, William [Defense Nuclear Facilities Safety Board, 625 Indiana Ave., NW, Suite 700, Washington, DC 20004-2901 (United States)

    2008-01-15T23:59:59.000Z

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

  13. Closure Strategy for a Waste Disposal Facility with Multiple Waste Types and Regulatory Drivers at the Nevada Test Site

    SciTech Connect (OSTI)

    L. Desotell; D. Wieland; V. Yucel; G. Shott; J. Wrapp

    2008-03-01T23:59:59.000Z

    The U.S. Department of Energy, National Security Administration Nevada Site Office (NNSA/NSO) is planning to close the 92-Acre Area of the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS), which is about 65 miles northwest of Las Vegas, Nevada. Closure planning for this facility must take into account the regulatory requirements for a diversity of waste streams, disposal and storage configurations, disposal history, and site conditions. This paper provides a brief background of the Area 5 RWMS, identifies key closure issues, and presents the closure strategy. Disposals have been made in 25 shallow excavated pits and trenches and 13 Greater Confinement Disposal (GCD) boreholes at the 92-Acre Area since 1961. The pits and trenches have been used to dispose unclassified low-level waste (LLW), low-level mixed waste (LLMW), and asbestiform waste, and to store classified low-level and low-level mixed materials. The GCD boreholes are intermediate-depth disposal units about 10 feet (ft) in diameter and 120 ft deep. Classified and unclassified high-specific activity LLW, transuranic (TRU), and mixed TRU are disposed in the GCD boreholes. TRU waste was also disposed inadvertently in trench T-04C. Except for three disposal units that are active, all pits and trenches are operationally covered with 8-ft thick alluvium. The 92-Acre Area also includes a Mixed Waste Disposal Unit (MWDU) operating under Resource Conservation and Recovery Act (RCRA) Interim Status, and an asbestiform waste unit operating under a state of Nevada Solid Waste Disposal Site Permit. A single final closure cover is envisioned over the 92-Acre Area. The cover is the evapotranspirative-type cover that has been successfully employed at the NTS. Closure, post-closure care, and monitoring must meet the requirements of the following regulations: U.S. Department of Energy Order 435.1, Title 40 Code of Federal Regulations (CFR) Part 191, Title 40 CFR Part 265, Nevada Administrative Code (NAC) 444.743, RCRA requirements as incorporated into NAC 444.8632, and the Federal Facility Agreement and Consent Order (FFACO). A grouping of waste disposal units according to waste type, location, and similarity in regulatory requirements identified six closure units: LLW Unit, Corrective Action Unit (CAU) 111 under FFACO, Asbestiform LLW Unit, Pit 3 MWDU, TRU GCD Borehole Unit, and TRU Trench Unit. The closure schedule of all units is tied to the closure schedule of the Pit 3 MWDU under RCRA.

  14. CONSIDERATIONS FOR GROUT FORMULATIONS FOR FACILITY CLOSURES USING IN SITU STRATEGIES

    SciTech Connect (OSTI)

    Gladden, J.; Serrato, M.; Langton, C.; Long, T.; Blankenship, J.; Hannah, G.; Stubblefield, R.; Szilagyi, A.

    2010-08-25T23:59:59.000Z

    The U.S. Department of Energy (DOE) is conducting in situ closures (entombment) at a large number of facilities throughout the complex. Among the largest closure actions currently underway are the closures of the P and R Reactors at the Savannah River Site (SRS), near Aiken, South Carolina. In these facilities, subgrade open spaces are being stabilized with grout; this ensures the long term structural integrity of the facilities and permanently immobilizes and isolates residual contamination. The large size and structural complexity of these facilities present a wide variety of challenges for the identification and selection of appropriate fill materials. Considerations for grout formulations must account for flowability, long term stability, set times, heat generation and interactions with materials within the structure. The large size and configuration of the facility necessitates that grout must be pumped from the exterior to the spaces to be filled, which requires that the material must retain a high degree of flowability to move through piping without clogging while achieving the required leveling properties at the pour site. Set times and curing properties must be controlled to meet operations schedules, while not generating sufficient heat to compromise the properties of the fill material. The properties of residual materials can result in additional requirements for grout formulations. If significant quantities of aluminum are present in the facility, common formulations of highly alkaline grouts may not be appropriate because of the potential for hydrogen generation with the resultant risks. SRS is developing specialized inorganic grout formulations that are designed to address this issue. One circum-neutral chemical grout formulation identified for initial consideration did not possess the proper chemical characteristics, having exceptionally short set times and high heat of hydration. Research efforts are directed toward developing grout formulations that can meet operational requirements for chemical compatibility, extended set times and reduced heat generation.

  15. Post-Closure Inspection Letter Report for Corrective Action Units on the Nevada National Security Site

    SciTech Connect (OSTI)

    Boehleke, R. F.

    2014-05-06T23:59:59.000Z

    This letter serves as the post-closure inspection letter report for Corrective Action Units (CAUs) on the Nevada National Security Site for calendar year 2013. The inspections identified maintenance and repair is required at the following sites: sign and/or fence repair is necessary at CAUs 113, 137, 139, 140, 143, 262, 370, 371, 372, 374, 476, 478, 529, 542, and 560; animal burrows were identified at CAU 547; and erosion was identified at CAUs 366, 367, 383, 551, and 574. In addition, the following use restrictions were removed during 2013 and will no longer be inspected in 2014: 165, 357, and 528.

  16. Closure of logging wounds after 10 years. Forest Service research paper (Final)

    SciTech Connect (OSTI)

    Smith, H.C.; Miller, G.W.; Schuler, T.M.

    1994-09-01T23:59:59.000Z

    Closure of logging wounds on 96 sample trees was evaluated after 2, 5, and 10 years for Appalachian hardwood trees in north-central West Virginia. For yellow-poplar, northern red oak, black cherry, and white oak, many small wounds, 1 to 50 square inches in size, closed between 5 and 10 years after logging. For larger wounds, 50 to 200 square inches, it appears that many of these wounds may not close for at least 15 or perhaps 20 years after logging. Recommendations are provided to minimize logging wounds on residual trees in partially cut stands.

  17. Microsoft Word - N01401_NE and 4-5 Closure Mon Plan.doc

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA group currentBradleyTableSelling CorpNewCFRemediation Agreement for8Closure

  18. D and D (System Closure) Mockup Testing Demonstration. Remediation of Legacy Radioactive Piping and Tank Systems at the Reactor Technology Complex (RTC) (2007)

    SciTech Connect (OSTI)

    Byrne-Kelly, D.; Brown, Ch.; Hart, A. [MSE Technology Applications, Inc., Butte, Montana (United States); Welty, B. [Portage, Inc., Idaho Falls, ID (United States); Winterholler, K. [CWI, Idaho Falls, ID (United States)

    2008-07-01T23:59:59.000Z

    This paper presents the results of an integrated mockup demonstration of technologies and equipment designed to remove radioactively contaminated piping systems from underground vaults and pipe trenches at the Idaho National Laboratory. The integrated mockup demonstration included performing a bench scale wax fixative study and field demonstrations of the remotely operated equipment that will be used to remove radioactively contaminated pipe systems. The bench-scale wax fixative study involved defining optimum temperature and moisture conditions for effectively filling pipe sections containing residual wastes with a wax based fixative. The field demonstrations involved dismantling underground vault and trench piping systems, including pipe sections filled with the wax fixative. The purpose of the demonstration was to ensure the selected technologies and equipment would be effective prior to field deployment. The demonstration was conducted as a joint effort by MSE Technology Applications, Inc., and CWI on behalf of the U.S. Department of Energy at the Mike Mansfield Advanced Technology Center in Butte Montana. In summary: The mockup included two main tests at the MSE facility: 1) a vault mockup that included stainless and carbon steel pipe cutting and removal; and 2) a trench mockup that included cutting and removing buried Duriron and ductile iron piping. Both mockups included cutting and removing a pipe filled with the WAXFIX stabilizing material. Based on the MSE moisture tests, project personnel concluded that the WAXFIX product would be effective when used on wastes with different moisture contents that may be encountered in piping systems during the closure of the TRA-630 Catch Tank System at INL. A section of stainless steel pipe was also used to test a number of leak stop alternatives for wax leaks that may be encountered in a degraded piping system. Both the vault and the trench mockup demonstration proved successful for ICP, DOE, and MSE. The ICP operators received valuable hands-on training using the selected equipment and tooling in situations very similar to what they will encounter at INL. Proper tool selection and tool change procedures were defined as situations requiring these operations were encountered. Methodologies for approaching similar trench and vault situations (including safety concerns) were identified and experienced, and wax filled pipes were successfully cut and removed without spilling the surrogate materials within the pipes. All of the tools performed well except the band saw tool. The band saw was specifically designed to cut pipe; however, it was not robust enough and generally the shear was used in its place. Mockups are essential in gaining actual hands on training before going to the field. Mockups improve efficiency and safety that results in cost effective remediation. The MSE facility provides a valuable resource for demonstration of mockups. The facility has several acres of available space and a highly qualified support staff. The integrated mockup demonstration was considered a great success by all involved parties. ICP operators received valuable experience using the equipment selected for catch tank system closure before field deployment in a radiological contaminated environment. The selected equipment proved to be applicable to the safe and effective closure of the catch tank systems, and MSE demonstrated the ability to provide facility and services necessary to support closure mockup demonstrations. (authors)

  19. Management and integration of engineering and construction activities: Lessons learned from the AP1000{sup R} nuclear power plant China project

    SciTech Connect (OSTI)

    McCullough, M. C.; Ebeling-Koning, D.; Evans, M. C. [Westinghouse Electric Company LLC, 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

    2012-07-01T23:59:59.000Z

    The lessons learned during the early phase of design engineering and construction activities for the AP1000 China Project can be applied to any project involving multiple disciplines and multiple organizations. Implementation of a first-of-a-kind design to directly support construction activities utilizing resources assigned to design development and design delivery creates challenges with prioritization of activities, successful closure of issues, and communication between site organizations and the home office. To ensure successful implementation, teams were assigned and developed to directly support construction activities including prioritization of activities, site communication and ensuring closure of site emergent issues. By developing these teams, the organization is better suited to meet the demands of the construction schedule while continuing with design evolution of a standard plant and engineering delivery for multiple projects. For a successful project, proper resource utilization and prioritization are key for overcoming obstacles and ensuring success of the engineering organization. (authors)

  20. Project Fact Sheet Project Brief

    E-Print Network [OSTI]

    Name: Centre for Assisted Robotic Surgery Number: BESS1002b Project Champion: Professor Guang-Zong Yang of the refurbishment is to renew and expand the laboratory space for Robotic Assisted Surgery at the South Kensington Campus as par to the Hamlyn Centre for Robotic Surgery. The overall programme incorpo- rates both core

  1. Tank Closure

    Office of Environmental Management (EM)

    Program Two Tank Farms - F Area and H Area Permitted by SC as Industrial Wastewater Facilities under the Pollution Control Act Three agency Federal Facility...

  2. CLOSURE REPORT

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA group currentBradleyTableSelling7111A Lithologic andRECORD OF DECISION:L ,_ -*

  3. Tank Closure

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2Uranium Transferon the PassingRouting TECFinish Line |PaulTable

  4. Report for the HWMA/RCRA Post Closure Permit for the INTEC Waste Calcining Facility at the INL Site

    SciTech Connect (OSTI)

    Idaho Cleanup Project

    2006-06-01T23:59:59.000Z

    The Waste Calcining Facility (WCF) is located at the Idaho Nuclear Technology and Engineering Center. In 1998, the WCF was closed under an approved Hazardous Waste Management Act/Resource Conservation and Recovery Act (HWMA/RCRA) Closure Plan. Vessels and spaces were grouted and then covered with a concrete cap. The Idaho Department of Environmental Quality issued a final HWMA/RCRA post-closure permit on September 15, 2003, with an effective date of October 16, 2003. This permit sets forth procedural requirements for groundwater characterization and monitoring, maintenance, and inspections of the WCF to ensure continued protection of human health and the environment. The post-closure permit also includes semiannual reporting requirements under Permit Conditions III.H. and I.U. These reporting requirements have been combined into this single semiannual report.

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

    SciTech Connect (OSTI)

    Alfred Wickline

    2008-01-01T23:59:59.000Z

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

  6. ICPP tank farm closure study. Volume 3: Cost estimates, planning schedules, yearly cost flowcharts, and life-cycle cost estimates

    SciTech Connect (OSTI)

    NONE

    1998-02-01T23:59:59.000Z

    This volume contains information on cost estimates, planning schedules, yearly cost flowcharts, and life-cycle costs for the six options described in Volume 1, Section 2: Option 1 -- Total removal clean closure; No subsequent use; Option 2 -- Risk-based clean closure; LLW fill; Option 3 -- Risk-based clean closure; CERCLA fill; Option 4 -- Close to RCRA landfill standards; LLW fill; Option 5 -- Close to RCRA landfill standards; CERCLA fill; and Option 6 -- Close to RCRA landfill standards; Clean fill. This volume is divided into two portions. The first portion contains the cost and planning schedule estimates while the second portion contains life-cycle costs and yearly cash flow information for each option.

  7. Advanced Ultrasonic Inspection Techniques for General Purpose Heat Source Fueled Clad Closure Welds

    SciTech Connect (OSTI)

    Moyer, M.W.

    2001-01-11T23:59:59.000Z

    A radioisotope thermoelectric generator is used to provide a power source for long-term deep space missions. This General Purpose Heat Source (GPHS) is fabricated using iridium clad vent sets to contain the plutonium oxide fuel pellets. Integrity of the closure weld is essential to ensure containment of the plutonium. The Oak Ridge Y-12 Plant took the lead role in developing the ultrasonic inspection for the closure weld and transferring the inspection to Los Alamos National Laboratory for use in fueled clad inspection for the Cassini mission. Initially only amplitude and time-of-flight data were recorded. However, a number of benign geometric conditions produced signals that were larger than the acceptance threshold. To identify these conditions, a B-scan inspection was developed that acquired full ultrasonic waveforms. Using a test protocol the B-scan inspection was able to identify benign conditions such as weld shield fusion and internal mismatch. Tangential radiography was used to confirm the ultrasonic results. All but two of 29 fueled clads for which ultrasonic B-scan data was evaluated appeared to have signals that could be attributed to benign geometric conditions. This report describes the ultrasonic inspection developed at Y-12 for the Cassini mission.

  8. Loop-closure events during protein folding: Rationalizing the shape of Phi-value distributions

    E-Print Network [OSTI]

    Thomas R. Weikl

    2005-02-15T23:59:59.000Z

    In the past years, the folding kinetics of many small single-domain proteins has been characterized by mutational Phi-value analysis. In this article, a simple, essentially parameter-free model is introduced which derives folding routes from native structures by minimizing the entropic loop-closure cost during folding. The model predicts characteristic folding sequences of structural elements such as helices and beta-strand pairings. Based on few simple rules, the kinetic impact of these structural elements is estimated from the routes and compared to average experimental Phi-values for the helices and strands of 15 small, well-characterized proteins. The comparison leads on average to a correlation coefficient of 0.62 for all proteins with polarized Phi-value distributions, and 0.74 if distributions with negative average Phi-values are excluded. The diffuse Phi-value distributions of the remaining proteins are reproduced correctly. The model shows that Phi-value distributions, averaged over secondary structural elements, can often be traced back to entropic loop-closure events, but also indicates energetic preferences in the case of a few proteins governed by parallel folding processes.

  9. AREA COMPLETION STRATEGIES AT SAVANNAH RIVER SITE: CHARACTERIZATION FOR CLOSURE AND BEYOND

    SciTech Connect (OSTI)

    Bagwell, L; Mark Amidon, M; Sadika Baladi, S

    2007-06-11T23:59:59.000Z

    During the first four decades of its 56 year existence, the Savannah River Site (SRS) was a key supplier of nuclear material for national defense. During the 1990s, the site's primary missions became waste site closure, environmental restoration, and deactivation and decommissioning (D&D) of remnant cold war apparatus. Since 1989, with the approval of State and Federal regulatory agencies and with the participation of interested stakeholders, SRS has implemented a final remedy for a majority of the more than 500 individual waste sites at the former nuclear materials complex. These waste sites range from small, inert rubble pits to large, heavy industrial areas and radioactive waste disposal grounds. The closure and final remediation of these waste sites mark significant progress toward achieving SRS's overarching goal of reducing or eliminating future environmental damage and human health threats. However, larger challenges remain. For example, what are appropriate and achievable end-states for decommissioned nuclear facilities? What environmental and human health risks are associated with these end-states? To answer these questions within the strictures of smaller budgets and accelerated schedules, SRS is implementing an ''area completion'' strategy that: (1) unites several discrete waste units into one conceptual model, (2) integrates historically disparate environmental characterization and D&D activities, (3) reduces the number of required regulatory documents, and (4) in some cases, compresses schedules for achieving a stakeholder-approved end-state.

  10. Decommissioning and Closure of the Morsleben Deep Geological Repository - The Final Step

    SciTech Connect (OSTI)

    Ripkens, M.; Biurrun, E.

    2002-02-26T23:59:59.000Z

    In Germany, a deep geologic repository for low and intermediate-level waste has been in operation since 1971. This repository, which is located in the territory of former Eastern Germany, became a Federal Facility in the wake of German reunification in 1990. Since then, waste from all of Germany was disposed of until a stop ordered by BfS in 1998. The site is now in the process of being decommissioned and later closed down. This process includes updating the concept for guaranteeing appropriate waste isolation for as long as the waste remains a hazard. During the licensing procedure being currently conducted, in line with German requirements for repository sites, the site operator must provide convincing proof of the facility's long-term safety. Thereafter, implementation of the decommissioning and closure concept will follow. It is estimated that the licensing procedure will take until the year 2006. The decommissioning and closure process itself will require about 10 years. Reliable costs estimates are not yet available. This paper briefly covers the history of the Morsleben radioactive waste repository and provides a draft update on the status of the licensing procedure.

  11. Resource Conservation and Recovery Act (RCRA) Closure Plan Summary for Interim reasctive Waste Treatment Area (IRWTA)

    SciTech Connect (OSTI)

    Collins, E.T.

    1997-07-01T23:59:59.000Z

    This closure plan has been prepared for the interim Reactive Waste Treatment Area (IRWT'A) located at the Y-12 Pkmt in oak Ridge, Tennessee (Environmental Protection Agency [EPA] Identification TN 389-009-0001). The actions required to achieve closure of the IRWTA are outlined in this plan, which is being submitted in accordance with Tennessee Ruie 1200- 1-1 1-.0S(7) and Title 40, Code of Federal Regulations (CFR), Part 265, Subpart G. The IRWTA was used to treat waste sodium and potassium (NaK) that are regulated by the Resource Conservation and Recovery Act (RCRA). The location of the IRWT'A is shown in Figures 1 and 2, and a diagram is shown in Figure 3. This pkm details all steps that wdi be petiormed to close the IRWTA. Note that this is a fmai ciosure.and a diagram is shown in Figure 3. This pkm details all steps that wdi be petiormed to close the IRWTA. Note that this is a fmai ciosure.

  12. Closure Report for Corrective Action Unit 574: Neptune, Nevada National Security Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2012-04-30T23:59:59.000Z

    Corrective Action Unit (CAU) 574 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Neptune' and consists of the following two Corrective Action Sites (CASs), located in Area 12 of the Nevada National Security Site: (1) CAS 12-23-10, U12c.03 Crater (Neptune); and (2) CAS 12-45-01, U12e.05 Crater (Blanca). This Closure Report presents information supporting closure of CAU 574 according to the FFACO (FFACO, 1996 [as amended March 2010]) and the Streamlined Approach for Environmental Restoration Plan for CAU 574 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2011). The following activities were performed to support closure of CAU 574: (1) In situ external dose rate measurements were collected using thermoluminescent dosimeters at CAS 12-45-01, U12e.05 Crater (Blanca). (2) Total effective dose rates were determined at both sites by summing the internal and external dose rate components. (3) A use restriction (UR) was implemented at CAS 12-23-10, U12c.03 Crater (Neptune). Areas that exceed the final action level (FAL) of 25 millirems per year (mrem/yr) based on the Occasional Use Area exposure scenario are within the existing use restricted area for CAU 551. The 25-mrem/yr FAL is not exceeded outside the existing CAU 551 UR for any of the exposure scenarios (Industrial Area, Remote Work Area, and Occasional Use Area). Therefore, the existing UR for CAU 551 is sufficient to bound contamination that exceeds the FAL. (4) An administrative UR was implemented at CAS 12-45-01, U12e.05 Crater (Blanca) as a best management practice (BMP). The 25-mrem/yr FAL was not exceeded for the Remote Work Area or Occasional Use Area exposure scenarios; therefore, a UR is not required. However, because the 25-mrem/yr FAL was exceeded for the Industrial Area exposure scenario, an administrative UR was established as a BMP. UR documentation is included as Appendix B. The UR at CAS 12-23-10, U12c.03 Crater (Neptune), is within the existing UR for CAU 551. Additional postings were not installed, and annual post-closure inspections will be performed in conjunction with the inspections performed for CAU 551. At CAS 12-45-01, U12e.05 Crater (Blanca), the administrative UR does not require postings or inspections. NNSA/NSO requests the following: (1) A Notice of Completion from the Nevada Division of Environmental Protection to NNSA/NSO for closure of CAU 574; and (2) The transfer of CAU 574 from Appendix III to Appendix IV, Closed Corrective Action Units, of the FFACO

  13. Final closure plan for the high-explosives open burn treatment facility at Lawrence Livermore National Laboratory Experimental Test Site 300

    SciTech Connect (OSTI)

    Mathews, S.

    1997-04-01T23:59:59.000Z

    This document addresses the interim status closure of the HE Open Bum Treatment Facility, as detailed by Title 22, Division 4.5, Chapter 15, Article 7 of the Califonia Code of Regulations (CCR) and by Title 40, Code of Federal Regulations (CFR) Part 265, Subpart G, ``Closure and Post Closure.`` The Closure Plan (Chapter 1) and the Post- Closure Plan (Chapter 2) address the concept of long-term hazard elimination. The Closure Plan provides for capping and grading the HE Open Bum Treatment Facility and revegetating the immediate area in accordance with applicable requirements. The Closure Plan also reflects careful consideration of site location and topography, geologic and hydrologic factors, climate, cover characteristics, type and amount of wastes, and the potential for contaminant migration. The Post-Closure Plan is designed to allow LLNL to monitor the movement, if any, of pollutants from the treatment area. In addition, quarterly inspections will ensure that all surfaces of the closed facility, including the cover and diversion ditches, remain in good repair, thus precluding the potential for contaminant migration.

  14. Corrective Action Decision Document/Closure Report for Corrective Action Unit 105: Area 2 Yucca Flat Atmospheric Test Sites, Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Matthews, Patrick

    2013-09-01T23:59:59.000Z

    This Corrective Action Decision Document/Closure Report presents information supporting the closure of Corrective Action Unit (CAU) 105: Area 2 Yucca Flat Atmospheric Test Sites, Nevada National Security Site, Nevada. CAU 105 comprises the following five corrective action sites (CASs): -02-23-04 Atmospheric Test Site - Whitney Closure In Place -02-23-05 Atmospheric Test Site T-2A Closure In Place -02-23-06 Atmospheric Test Site T-2B Clean Closure -02-23-08 Atmospheric Test Site T-2 Closure In Place -02-23-09 Atmospheric Test Site - Turk Closure In Place The purpose of this Corrective Action Decision Document/Closure Report is to provide justification and documentation supporting the recommendation that no further corrective action is needed for CAU 105 based on the implementation of the corrective actions. Corrective action investigation (CAI) activities were performed from October 22, 2012, through May 23, 2013, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 105: Area 2 Yucca Flat Atmospheric Test Sites; and in accordance with the Soils Activity Quality Assurance Plan, which establishes requirements, technical planning, and general quality practices.

  15. Addendum to the post-closure permit application for the Bear Creek Hydrogeologic Regime at the Y-12 Plant: Walk-in pits. Revision 2

    SciTech Connect (OSTI)

    NONE

    1995-04-01T23:59:59.000Z

    The revised Closure Plan was initially intended to apply to A Area, C-West, B Area, and the Walk-In Pits (WIPs) of the Bear Creek Burial Grounds (BCBG). However, a strategy was developed to include the B Area [a solid waste management unit (SWMU)] with the WIPs so that both areas would be closed under one cap. The plan was presented to the State of Tennessee on March 8, 1990, and the Department of Energy was requested to review other unique alternatives to close the site. Therefore, in November 1992, the Closure Plan for B Area and the WIPs was prepared separately from that of the other sites associated with the BCBG and was presented in a RCRA Closure Plan. The Closure Plan revision issued April 1993 was intended to reflect the placement of the Kerr Hollow Quarry debris at the WIPs, revise the closure data, and acknowledge that the disposition of a monitoring well within the closure site could not be verified. A Post-Closure Permit Application (PCPA) was to include the WIPs; however, at the time of submittal, closure of the WIPs had not been certified. This addendum contains information on the WIPs to accompany the BCBG PCPA. The purpose of this document is to supplement the information provided in the BCBG PCPA. This document is not intended to be a stand-alone document. Only additional information regarding the WIPs is included in the sections of this document, which correspond to sections of the PCPA submitted in June 1994.

  16. PROJECT SUMMARY

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy ChinaofSchaeferAprilOverviewEfficiencyofHSSPIAProperty Management PlanPROJECT SUMMARY 1

  17. Hallmark Project

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy ChinaofSchaefer To: CongestionDevelopmentHEADQUARTERSOutreachApril 23, 2013Project

  18. Project Management

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)IntegratedSpeedingTechnical News,Program DirectionProject ATHENA creates

  19. Project Overview

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)IntegratedSpeedingTechnical News,Program DirectionProject ATHENAManagement

  20. Projects | ORNL

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)IntegratedSpeedingTechnical News,Program DirectionProject ATHENAManagementIn ThisPages

  1. Project Gnome

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's Possible forPortsmouth/Paducah47,193.70 Hg MercuryProject Final Report: HPC-Colony IIProject Gnome

  2. Project Title

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's Possible forPortsmouth/Paducah47,193.70 Hg MercuryProject FinalFluids |Storage Research and

  3. NEPA COMPLIANCE SURVEY Project Information Project Title:

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

    Boxes Date: Nov. 11 , 2010 DOE Code: 6740.010.00000 Contractor Code: 8067-451 Project Lead: Anthony Bowler Project Overview 1. Brief project description include anything that...

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

    SciTech Connect (OSTI)

    Mark Krauss

    2011-06-01T23:59:59.000Z

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

  5. Comparison Of Intake Gate Closure Methods At Lower Granite, Little Goose, Lower Monumental, And Mcnary Dams Using Risk-Based Analysis

    SciTech Connect (OSTI)

    Gore, Bryan F.; Blackburn, Tyrone R.; Heasler, Patrick G.; Mara, Neil L.; Phan, Hahn K.; Bardy, David M.; Hollenbeck, Robert E.

    2001-01-19T23:59:59.000Z

    The objective of this report is to compare the benefits and costs of modifications proposed for intake gate closure systems at four hydroelectric stations on the Lower Snake and Upper Columbia Rivers in the Walla Walla District that are unable to meet the COE 10-minute closure rule due to the installation of fish screens. The primary benefit of the proposed modifications is to reduce the risk of damage to the station and environs when emergency intake gate closure is required. Consequently, this report presents the results and methodology of an extensive risk analysis performed to assess the reliability of powerhouse systems and the costs and timing of potential damages resulting from events requiring emergency intake gate closure. As part of this analysis, the level of protection provided by the nitrogen emergency closure system was also evaluated. The nitrogen system was the basis for the original recommendation to partially disable the intake gate systems. The risk analysis quantifies this protection level.

  6. Addendum to the post-closure permit application for the Bear Creek hydrogeologic regime at the Y-12 plant: Walk-in pits

    SciTech Connect (OSTI)

    NONE

    1995-04-01T23:59:59.000Z

    In June 1987, the Resource Conservation and Recovery Act (RCRA) Closure/Post-Closure Plan for the Bear Creek Burial Grounds (BCBG) located at the Y-12 Plant on the Oak Ridge Reservation in Oak Ridge, Tennessee was submitted to the Tennessee Department of Environment and Conservation (TDEC) for review and approval.The Closure Plan has been modified and revised several times. This document is an addendum to the Post-Closure Permit Application submitted to TDEC in June, 1994. This addendum contains information on the Walk-In Pits of the BCBG which is meant to supplement the information provided in the Post-Closure Permit Application submitted for the BCBG. This document is not intended to be a stand-alone document.

  7. Project 57 Air Monitoring Annual Report - Fiscal Year 2013 (October 1, 2012 to September 30, 2013)

    SciTech Connect (OSTI)

    Miller, Julianne J. [DRI; McCurdy, Greg [DRI; Mizell, Steve A [DRI

    2014-07-01T23:59:59.000Z

    The U.S. Department of Energy (DOE), National Nuclear Security Administration, Nevada Field Office (NNSA/NFO) is currently working to achieve regulatory closure of radionuclide-contaminated Soils sites under its auspices. Corrective Action Unit (CAU) 415, Project 57 No. 1 Plutonium Dispersion Site is located in Emigrant Valley, Nevada, on Range 4808A of the Nevada Test and Training Range (NTTR), and consists of one Corrective Action Site (CAS): NAFR-23-02, Pu Contaminated Soil. Closure plans being developed for the CAUs both on and off of the Nevada National Security Site (NNSS) may include postclosure monitoring for the possible release of radioactive contaminants. Determining the potential for transport of radionuclide-contaminated soils under ambient climatic conditions will facilitate an appropriate closure design and postclosure monitoring program. The DOE has authorized the Desert Research Institute (DRI) to conduct field assessments of potential transport of radionuclide-contaminated soil from the Project 57 site during ambient wind events. The assessment is intended to provide site-specific information on meteorological conditions that result in airborne soil particle redistribution, as well as determine which, if any, radiological contaminants may be entrained with the soil particles and estimate their concentrations.

  8. Addendum to the Closure Report for Corrective Action Unit 403: Second Gas Station, Tonopah Test Range, Nevada, Revision 0

    SciTech Connect (OSTI)

    Grant Evenson

    2009-05-01T23:59:59.000Z

    This document constitutes an addendum to the Closure Report for Corrective Action Unit 403: Second Gas Station, Tonopah Test Range, Nevada, September 1998 as described in the document Supplemental Investigation Report for FFACO Use Restrictions, Nevada Test Site, Nevada (SIR) dated November 2008. The SIR document was approved by NDEP on December 5, 2008. The approval of the SIR document constituted approval of each of the recommended UR removals. In conformance with the SIR document, this addendum consists of: • This page that refers the reader to the SIR document for additional information • The cover, title, and signature pages of the SIR document • The NDEP approval letter • The corresponding section of the SIR document This addendum provides the documentation justifying the cancellation of the UR for CAS 03-02-004-0360, Underground Storage Tanks. This UR was established as part of a Federal Facility Agreement and Consent Order (FFACO) corrective action and is based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996). Since this UR was established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, this UR was reevaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006). This re-evaluation consisted of comparing the original data (used to define the need for the UR) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove the UR because contamination is not present at the site above the risk-based FALs. Requirements for inspecting and maintaining this UR will be canceled, and the postings and signage at this site will be removed. Fencing and posting may be present at this site that are unrelated to the FFACO UR such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at this site.

  9. Closure Report for Corrective Action Unit 417: Central Nevada Test Area Surface, Nevada

    SciTech Connect (OSTI)

    K. B. Campbell

    2001-11-01T23:59:59.000Z

    The following site closure activities were performed at the 34 Corrective Action Sites (CASs) comprising Corrective Action Unit (CAU) 417 and are documented in this report: (1) No closure action was taken at 13 CASs (17 sites): 58-05-01,58-07-01,58-05-04, 58-09-05 (Mud Pits C and D only), 58-35-01,58-05-02,58-09-06 (Mud Pits A, B, C, and D), 58-10-06,58-19-01,58-35-02,58-44-04,58-05-04, and 58-09-03 (Mud Pit E only). (2) Housekeeping activities, collecting scrap materials, and transporting to approved landfill sites at the NTS were used to close seven CASs: 58-44-01,58-44-02,58-44-05, 58-98-03,58-98-01,58-98-02, and 58-98-04. (3) Two CASs (58-05-03 and 58-99-01) were closed by excavation and removal of USTs. (4) Two septic tanks (CASs 58-05-05 and 58-05-06) were closed by backfilling with clean fill. (5) Site posting with above-grade monuments and attached warning signs and land-use restrictions were used to close seven CASs (nine sites): 58-09-02,58-09-05 (Mud Pit E only), 58-09-06 (Mud Pit E only), 58-10-01,58-25-01,58-09-03 (Mud Pits A, B, and D), and 58-10-05. (6) Clean closure by excavation soil with TPH levels greater than the NDEP action level of 100 mg/kg and limited regrading was used to close five CASs: 58-10-03,58-44-06, 58-44-03,58-10-02, and 58-10-04. (7) Construction of engineered covers was used to close in place two CASs: 58-09-01 and 58-09-03 (Mud Pit C only). Following construction, a fence was constructed around each cover to prevent damage to the cover or intrusion by wildlife.

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

    SciTech Connect (OSTI)

    D. H. Cox

    2001-06-01T23:59:59.000Z

    Corrective Action Unit (CAU) 135, Area 25 Underground Storage Tanks, was closed in accordance with the approved Corrective Action Plan (DOE/NV, 2000). CAU 135 consists of three Corrective Action Sites (CAS). Two of these CAS's were identified in the Corrective Action Investigation Data Quality Objective meeting as being improperly identified as underground storage tanks. CAS 25-02-03 identified as the Deluge Valve Pit was actually an underground electrical vault and CAS 25-02-10 identified as an Underground Storage Tank was actually a former above ground storage tank filled with demineralized water. Both of these CAS's are recommended for a no further action closure. CAS 25-02-01 the Underground Storage Tanks commonly referred to as the Engine Maintenance Assembly and Disassembly Waste Holdup Tanks and Vault was closed by decontaminating the vault structure and conducting a radiological verification survey to document compliance with the Nevada Test Site unrestricted use release criteria. The Area 25 Underground Storage Tanks, (CAS 25-02-01), referred to as the Engine Maintenance, Assembly, and Disassembly (E-MAD) Waste Holdup Tanks and Vault, were used to receive liquid waste from all of the radioactive and cell service area drains at the E-MAD Facility. Based on the results of the Corrective Action Investigation conducted in June 1999, discussed in ''The Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada'' (DOE/NV, 199a), one sample from the radiological survey of the concrete vault interior exceeded radionuclide preliminary action levels. The analytes from the sediment samples exceeded the preliminary action levels for polychlorinated biphenyls, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons as diesel-range organics, and radionuclides. The CAU 135 closure activities consisted of scabbling radiological ''hot spots'' from the concrete vault, and the drilling removal of the cement-lined vault sump. Field activities began on November 28, 2000, and ended on December 4, 2000. After verification samples were collected, the vault was repaired with cement. The concrete vault sump, soil excavated beneath the sump, and compactable hot line trash were disposed at the Area 23 Sanitary Landfill. The vault interior was field surveyed following the removal of waste to verify that unrestricted release criteria had been achieved. Since the site is closed by unrestricted release decontamination and verification, post-closure care is not required.

  11. THE NEED FOR A NEW JOINING TECHNOLOGY FOR THE CLOSURE WELDING OF RADIOACTIVE MATERIALS CONTAINERS

    SciTech Connect (OSTI)

    CANNELL GR; HILL BE; GRANT GJ

    2008-10-29T23:59:59.000Z

    One of the activities associated with cleanup throughout the Department of Energy (DOE) complex is packaging radioactive materials into storage containers. Much of this work will be performed in high-radiation environments requiring fully remote operations, for which existing, proven systems do not currently exist. These conditions demand a process that is capable of producing acceptable (defect-free) welds on a consistent basis; the need to perform weld repair, under fully-remote operations, can be extremely costly and time consuming. Current closure welding technology (fusion welding) is not well suited for this application and will present risk to cleanup cost and schedule. To address this risk, Fluor and the Pacific Northwest National Laboratory (PNNL), are proposing that a new and emerging joining technology, Friction Stir Welding (FSW), be considered for this work. FSW technology has been demonstrated in other industries (aerospace and marine) to produce near flaw-free welds on a consistent basis. FSW is judged capable of providing the needed performance for fully-remote closure welding of containers for radioactive materials for the following reasons: FSW is a solid-state process; material is not melted. As such, FSW does not produce the type of defects associated with fusion welding, e.g., solidification-induced porosity, cracking, distortion due to weld shrinkage, and residual stress. In addition, because FSW is a low-heat input process, material properties (mechanical, corrosion and environmental) are preserved and not degraded as can occur with 'high-heat' fusion welding processes. When compared to fusion processes, FSW produces extremely high weld quality. FSW is performed using machine-tool technology. The equipment is simple and robust and well-suited for high radiation, fully-remote operations compared to the relatively complex equipment associated with the fusion-welding processes. Additionally, for standard wall thicknesses of radioactive materials containers, the FSW process can perform final closure welding in a single pass (GTAW requires multiple passes) resulting in increased productivity. Together, the performance characteristics associated with FSW, i.e., high weld quality, simple machine-tool equipment and increased welding efficiency, are expected to reduce risk to upcoming DOE radioactive materials packaging campaigns. FSW technology requires some development/adaptation for this application, along with approval from the governing code of construction prior to production operations. This paper addresses the need for a new joining technology, a description of the FSW process and why it is well-suited for this application, and several activities required for commercialization.

  12. Soot formation modelling of n-heptane sprays under diesel engine conditions using the Conditional Moment Closure

    E-Print Network [OSTI]

    Daraio, Chiara

    1 Soot formation modelling of n-heptane sprays under diesel engine conditions using the Conditional-volume vessel under diesel engine conditions under different ambient densities (14.8 and 30 kg/m3 ) and ambient that the conditional moment closure approach is a promising framework for soot modelling under Diesel engine conditions

  13. Closure Report for Corrective Action Unit 116: Area 25 Test Cell C Facility, Nevada National Security Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2011-09-29T23:59:59.000Z

    This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 116, Area 25 Test Cell C Facility. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; the U.S. Department of Energy (DOE), Environmental Management; the U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996 [as amended March 2010]). CAU 116 consists of the following two Corrective Action Sites (CASs), located in Area 25 of the Nevada National Security Site: (1) CAS 25-23-20, Nuclear Furnace Piping and (2) CAS 25-41-05, Test Cell C Facility. CAS 25-41-05 consisted of Building 3210 and the attached concrete shield wall. CAS 25-23-20 consisted of the nuclear furnace piping and tanks. Closure activities began in January 2007 and were completed in August 2011. Activities were conducted according to Revision 1 of the Streamlined Approach for Environmental Restoration Plan for CAU 116 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2008). This CR provides documentation supporting the completed corrective actions and provides data confirming that closure objectives for CAU 116 were met. Site characterization data and process knowledge indicated that surface areas were radiologically contaminated above release limits and that regulated and/or hazardous wastes were present in the facility.

  14. BETA-DECAY STUDIES OF NEUTRON-RICH NUCLIDES AND THE POSSIBILITY OF AN N = 34 SUBSHELL CLOSURE

    E-Print Network [OSTI]

    Mantica, Paul F.

    BETA-DECAY STUDIES OF NEUTRON-RICH NUCLIDES AND THE POSSIBILITY OF AN N = 34 SUBSHELL CLOSURE of the requirements for the degree of DOCTOR OF PHILOSOPHY Department of Chemistry 2004 #12;ABSTRACT BETA this disser- tation would not have been possible. I would also like to thank all the members of the beta group

  15. Self-Assembly of Flux-Closure Polygons from Magnetite Nanocubes Megan W. Szyndler and Robert M. Corn*

    E-Print Network [OSTI]

    , shape, and arrangement are essential steps in the fabrication of novel nanostructured devices that has been suggested for high- density magnetic energy storage devices is a flux-closure ring memory storage and high-frequency magnetics. SECTION: Physical Processes in Nanomaterials

  16. Introduction Nonlinear Fourier Analysis Ocean Internal Waves KdV Hidden Solitons Closure Two case studies in nonlinear Fourier analysis

    E-Print Network [OSTI]

    Christov, Ivan C.

    Introduction Nonlinear Fourier Analysis Ocean Internal Waves KdV Hidden Solitons Closure Two case studies in nonlinear Fourier analysis: Ocean internal solitary waves and the Zabusky­Kruskal solitons Ivan Engineering, The University of Sheffield September 10, 2010 Ivan C. Christov (NU) Nonlinear Fourier Analysis

  17. Introduction Nonlinear Fourier Analysis Ocean Internal Waves KdV Hidden Solitons Closure Two case studies in nonlinear Fourier analysis

    E-Print Network [OSTI]

    Christov, Ivan C.

    Introduction Nonlinear Fourier Analysis Ocean Internal Waves KdV Hidden Solitons Closure Two case studies in nonlinear Fourier analysis: Ocean internal solitary waves and the Zabusky­Kruskal solitons Ivan Ivan C. Christov (PU) Nonlinear Fourier Analysis INRNE Seminar 1 / 26 #12;Introduction Nonlinear

  18. Project Management Lessons Learned

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

    2008-08-05T23:59:59.000Z

    The guide supports DOE O 413.3A, Program and Project Management for the Acquisition of Capital Assets, and aids the federal project directors and integrated project teams in the execution of projects.

  19. Closure Report for Corrective Action Unit 104: Area 7 Yucca Flat Atmospheric Test Sites, Nevada National Security Site, Nevada

    SciTech Connect (OSTI)

    none,

    2013-06-27T23:59:59.000Z

    This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 104, Area 7 Yucca Flat Atmospheric Test Sites, and provides documentation supporting the completed corrective actions and confirmation that closure objectives for CAU 104 were met. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; the U.S. Department of Energy (DOE), Environmental Management; the U.S. Department of Defense; and DOE, Legacy Management. CAU 104 consists of the following 15 Corrective Action Sites (CASs), located in Area 7 of the Nevada National Security Site: · CAS 07-23-03, Atmospheric Test Site T-7C · CAS 07-23-04, Atmospheric Test Site T7-1 · CAS 07-23-05, Atmospheric Test Site · CAS 07-23-06, Atmospheric Test Site T7-5a · CAS 07-23-07, Atmospheric Test Site - Dog (T-S) · CAS 07-23-08, Atmospheric Test Site - Baker (T-S) · CAS 07-23-09, Atmospheric Test Site - Charlie (T-S) · CAS 07-23-10, Atmospheric Test Site - Dixie · CAS 07-23-11, Atmospheric Test Site - Dixie · CAS 07-23-12, Atmospheric Test Site - Charlie (Bus) · CAS 07-23-13, Atmospheric Test Site - Baker (Buster) · CAS 07-23-14, Atmospheric Test Site - Ruth · CAS 07-23-15, Atmospheric Test Site T7-4 · CAS 07-23-16, Atmospheric Test Site B7-b · CAS 07-23-17, Atmospheric Test Site - Climax Closure activities began in October 2012 and were completed in April 2013. Activities were conducted according to the Corrective Action Decision Document/Corrective Action Plan for CAU 104. The corrective actions included No Further Action and Clean Closure. Closure activities generated sanitary waste, mixed waste, and recyclable material. Some wastes exceeded land disposal limits and required treatment prior to disposal. Other wastes met land disposal restrictions and were disposed in appropriate onsite landfills. The U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) requests the following: · A Notice of Completion from the Nevada Division of Environmental Protection to NNSA/NFO for closure of CAU 104 · The transfer of CAU 104 from Appendix III to Appendix IV, Closed Corrective Action Units, of the FFACO

  20. DROP TESTS RESULTS OF REVISED CLOSURE BOLT CONFIGURATION OF THE STANDARD WASTE BOX, STANDARD LARGE BOX 2, AND TEN DRUM OVERPACK PACKAGINGS

    SciTech Connect (OSTI)

    May, C.; Opperman, E.; Mckeel, C.

    2010-04-15T23:59:59.000Z

    The Transuranic (TRU) Disposition Project at Savannah River Site will require numerous transfers of radioactive materials within the site boundaries for sorting and repackaging. The three DOT Type A shipping packagings planned for this work have numerous bolts for securing the lids to the body of the packagings. In an effort to reduce operator time to open and close the packages during onsite transfers, thus reducing personnel exposure and costs, an evaluation was performed to analyze the effects of reducing the number of bolts required to secure the lid to the packaging body. The evaluation showed the reduction to one-third of the original number of bolts had no effect on the packagings capability to sustain vibratory loads, shipping loads, internal pressure loads, and the loads resulting from a 4-ft drop. However, the loads caused by the 4-ft drop are difficult to estimate and the study recommended each of the packages be dropped to show the actual effects on the package closure. Even with reduced bolting, the packagings were still required to meet the 49 CFR 178.350 performance criteria for Type A packaging. This paper discusses the effects and results of the drop testing of the three packagings.

  1. Exact PDF equations and closure approximations for advective-reactive transport

    SciTech Connect (OSTI)

    Venturi, D.; Tartakovsky, Daniel M.; Tartakovsky, Alexandre M.; Karniadakis, George E.

    2013-06-01T23:59:59.000Z

    Mathematical models of advection–reaction phenomena rely on advective flow velocity and (bio) chemical reaction rates that are notoriously random. By using functional integral methods, we derive exact evolution equations for the probability density function (PDF) of the state variables of the advection–reaction system in the presence of random transport velocity and random reaction rates with rather arbitrary distributions. These PDF equations are solved analytically for transport with deterministic flow velocity and a linear reaction rate represented mathematically by a heterog eneous and strongly-correlated random field. Our analytical solution is then used to investigate the accuracy and robustness of the recently proposed large-eddy diffusivity (LED) closure approximation [1]. We find that the solution to the LED-based PDF equation, which is exact for uncorrelated reaction rates, is accurate even in the presence of strong correlations and it provides an upper bound of predictive uncertainty.

  2. Erratum: A Comparison of Closures for Stochastic Advection-Diffusion Equations

    SciTech Connect (OSTI)

    Jarman, Kenneth D.; Tartakovsky, Alexandre M.

    2015-01-01T23:59:59.000Z

    This note corrects an error in the authors' article [SIAM/ASA J. Uncertain. Quantif., 1 (2013), pp. 319 347] in which the cited work [Neuman, Water Resour. Res., 29(3) (1993), pp. 633 645] was incorrectly represented and attributed. Concentration covariance equations presented in our article as new were in fact previously derived in the latter work. In the original abstract, the phrase " . . .we propose a closed-form approximation to two-point covariance as a measure of uncertainty. . ." should be replaced by the phrase " . . .we study a closed-form approximation to two-point covariance, previously derived in [Neuman 1993], as a measure of uncertainty." The primary results in our article--the analytical and numerical comparison of existing closure methods for specific example problems are not changed by this correction.

  3. Savannah River Site High-Level Waste Tank Closure Final Environmental Impact Statement

    SciTech Connect (OSTI)

    N /A

    2002-05-31T23:59:59.000Z

    The U.S. Atomic Energy Commission, a U.S. Department of Energy (DOE) predecessor agency, established the Savannah River Site (SRS) near Aiken, South Carolina, in the early 1950s. The primary mission of SRS was to produce nuclear materials for national defense. With the end of the Cold War and the reduction in the size of the United States stockpile of nuclear weapons, the SRS mission has changed. While national defense is still an important facet of the mission, SRS no longer produces nuclear materials and the mission is focused on material stabilization, environmental restoration, waste management, and decontamination and decommissioning of facilities that are no longer needed. As a result of its nuclear materials production mission, SRS generated large quantities of high-level radioactive waste (HLW). The HLW resulted from dissolving spent reactor fuel and nuclear targets to recover the valuable radioactive isotopes. DOE had stored the HLW in 51 large underground storage tanks located in the F- and H-Area Tank Farms at SRS. DOE has emptied and closed two of those tanks. DOE is treating the HLW, using a process called vitrification. The highly radioactive portion of the waste is mixed with a glass like material and stored in stainless steel canisters at SRS, pending shipment to a geologic repository for disposal. This process is currently underway at SRS in the Defense Waste Processing Facility (DWPF). The HLW tanks at SRS are of four different types, which provide varying degrees of protection to the environment due to different degrees of containment. The tanks are operated under the authority of the Atomic Energy Act of 1954 (AEA) and DOE Orders issued under the AEA. The tanks are permitted by the South Carolina Department of Health and Environmental Control (SCDHEC) under South Carolina wastewater regulations, which require permitted facilities to be closed after they are removed from service. DOE has entered into an agreement with the U.S. Environmental Protection Agency (EPA) and SCDHEC to close the HLW tanks after they have been removed from service. Closure of the HLW tanks would comply with DOE's responsibilities under the AEA and the South Carolina closure requirements and be carried out under a schedule agreed to by DOE, EPA, and SCDHEC. There are several ways to close the HLW tanks. DOE has prepared this Environmental Impact Statement (EIS) to ensure that the public and DOE's decision makers have a thorough understanding of the potential environmental impacts of alternative means of closing the tanks. This Summary: (1) describes the HLW tanks and the closure process, (2) describes the National Environmental Policy Act (NEPA) process that DOE is using to aid in decision making, (3) summarizes the alternatives for closing the HLW tanks and identifies DOE.s preferred alternative, and (4) identifies the major conclusions regarding environmental impacts, areas of controversy, and issues that remain to be resolved as DOE proceeds with the HLW tank closure process.

  4. Closure Report for Corrective Action Unit 396: Area 20 Spill Sites, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

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

    2004-06-01T23:59:59.000Z

    Corrective Action Unit (CAU) 396, Area 20 Spill Sites, is located on the Nevada Test Site approximately 105 kilometers (65 miles) northwest of Las Vegas, Nevada. CAU 396 is listed in Appendix II of the Federal Facility Agreement and Consent Order of 1996 and consists of the following four Corrective Action Sites (CASs) located in Area 20 of the Nevada Test Site: CAS 20-25-01, Oil Spills (2); CAS 20-25-02, Oil Spills; CAS 20-25-03, Oil Spill; CAS 20-99-08, Spill. Closure activities for CAU 396 were conducted in accordance with the Federal Facility Agreement and Consent Order and the Nevada Division of Environmental Protection-approved Streamlined Approach for Environmental Restoration Plan for CAU 396.

  5. Enabling completion of the material disposition area G closure at the Los Alamos National Laboratory

    SciTech Connect (OSTI)

    Blankenhorn, James Allen [Los Alamos National Laboratory; Bishop, Milton L [Los Alamos National Laboratory

    2010-01-01T23:59:59.000Z

    Los Alamos National Security, LLC (LANS) and the Los Alamos Site Office (LASO) have developed and are implementing an integrated strategy to accelerate the disposition of Los Alamos National Laboratory (LANL) legacy transuranic waste inventory currently stored in Technical Area 54, Material Disposition Area (MDA) G. As that strategy has been implemented the easier waste streams have been certified and shipped leaving the harder more challenging wastes to be dispositioned. Lessons learned from around the complex and a partnership with the National Transuranic Program located in Carlsbad, New Mexico, are enabling this acceleration. The Waste Disposition Program is responsible for the removal of both the above ground and below grade, retrievably stored transuranic waste in time to support the negotiated consent order with the State of New Mexico which requires closure of MDA G by the year 2015. The solutions and strategy employed at LANL are applicable to any organization that is currently managing legacy transuranic waste.

  6. Closure Report for Corrective Action Unit 117: Area 26 Pluto Disassembly Facility, Nevada Test Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Mark Burmeister

    2009-06-01T23:59:59.000Z

    This Closure Report (CR) presents information supporting the closure of Corrective Action Unit (CAU) 117: Area 26 Pluto Disassembly Facility, Nevada Test Site, Nevada. This CR complies with the requirements of the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management. Corrective Action Unit 117 comprises Corrective Action Site (CAS) 26-41-01, Pluto Disassembly Facility, located in Area 26 of the Nevada Test Site. The purpose of this CR is to provide documentation supporting the completed corrective actions and provide data confirming that the closure objectives for CAU 117 were met. To achieve this, the following actions were performed: • Review the current site conditions, including the concentration and extent of contamination. • Implement any corrective actions necessary to protect human health and the environment. • Properly dispose of corrective action and investigation wastes. • Document Notice of Completion and closure of CAU 117 issued by the Nevada Division of Environmental Protection. From May 2008 through February 2009, closure activities were performed as set forth in the Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 117, Area 26 Pluto Disassembly Facility, Nevada Test Site, Nevada. The purpose of the activities as defined during the data quality objectives process were: • Determine whether contaminants of concern (COCs) are present. • If COCs are present, determine their nature and extent, implement appropriate corrective actions, and properly dispose of wastes. Analytes detected during the closure activities were evaluated against final action levels to determine COCs for CAU 117. Assessment of the data generated from closure activities indicated that the final action levels were exceeded for polychlorinated biphenyls (PCBs) reported as total Aroclor and radium-226. A corrective action was implemented to remove approximately 50 cubic yards of PCB-contaminated soil, approximately 1 cubic foot of radium-226 contaminated soil (and scabbled asphalt), and a high-efficiency particulate air filter that was determined to meet the criteria of a potential source material (PSM). Electrical and lighting components (i.e., PCB-containing ballasts and capacitors) and other materials (e.g., mercury-containing thermostats and switches, lead plugs and bricks) assumed to be PSM were also removed from Building 2201, as practical, without the need for sampling. Because the COC contamination and PSMs have been removed, clean closure of CAS 26-41-01 is recommended, and no use restrictions are required to be placed on this CAU. No further action is necessary because no other contaminants of potential concern were found above preliminary action levels. The physical end state for Building 2201 is expected to be eventual demolition to slab. The DOE, National Nuclear Security Administration Nevada Site Office provides the following recommendations: • Clean closure is the recommended corrective action for CAS 26-41-01 in CAU 117. • A Notice of Completion to the DOE, National Nuclear Security Administration Nevada Site Office is requested from the Nevada Division of Environmental Protection for closure of CAU 117. • Corrective Action Unit 117 should be moved from Appendix III to Appendix IV of the Federal Facility Agreement and Consent Order.

  7. Corrosion Control during Closure Activities at the Savannah River Site - 13514

    SciTech Connect (OSTI)

    Wiersma, Bruce J. [Savannah River National Laboratory, Aiken, SC (United States)] [Savannah River National Laboratory, Aiken, SC (United States); Subramanian, Karthik H.; Martin, Keisha B. [Savannah River Remediation, Aiken, SC (United States)] [Savannah River Remediation, Aiken, SC (United States)

    2013-07-01T23:59:59.000Z

    Liquid radioactive wastes from the Savannah River Site (SRS) separation process are stored in large underground carbon steel tanks. Until the waste is removed from storage, transferred, and processed, the materials and structures of the tanks must maintain a confinement function by providing a barrier to the environment and by maintaining acceptable structural stability during normal service and design basis events (e.g., earthquake conditions). A corrosion control program is in place to ensure that degradation of the steel does not impact the structural and leak integrity functions of these waste tanks. The SRS is currently retrieving waste from older waste tanks and processing the waste through the vitrification for long term stabilization. The retrieval processes prepare the tanks for ultimate closure (i.e., grouting) by removing sludge by mechanical and/or sluicing methods, dissolving salt cake by adding water, and chemical cleaning of the residual sludge with oxalic acid. Each of these retrieval methods will result in waste chemistry that does not meet the requirements of the current corrosion control program. Given the short-term exposure and limited remaining service life for the tanks in which retrievals are being performed, an assessment of the need for corrosion controls in these tanks was performed. The assessment reviewed the corrosion rates in the more aggressive environments and the postulated loads on the structure during the closure activities. The assessment concluded that the current corrosion control program may be suspended for a short period of time while final retrieval of the waste is performed. (authors)

  8. State Environmental Policy Act (SEPA) environmental checklist forms for 304 Concretion Facility Closure Plan. Revision 2

    SciTech Connect (OSTI)

    Not Available

    1993-11-01T23:59:59.000Z

    The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. Recyclable scrap uranium with zircaloy-2 and copper silicon alloy, uranium-titanium alloy, beryllium/zircaloy-2 alloy, and zircaloy-2 chips and fines were secured in concrete billets (7.5-gallon containers) in the 304 Facility, located in the 300 Area. The beryllium/zircaloy-2 alloy and zircaloy-2 chips and fines are designated as mixed waste with the characteristic of ignitability. The concretion process reduced the ignitability of the fines and chips for safe storage and shipment. This process has been discontinued and the 304 Facility is now undergoing closure as defined in the Resource Conservation and Recovery Act (RCRA) of 1976 and the Washington Administrative Code (WAC) Dangerous Waste Regulations, WAC 173-303-040. This closure plan presents a description of the 304 Facility, the history of materials and waste managed, and the procedures that will be followed to close the 304 Facility. The 304 Facility is located within the 300-FF-3 (source) and 300-FF-5 (groundwater) operable units, as designated in the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1992). Contamination in the operable units 300-FF-3 and 300-FF-5 is scheduled to be addressed through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 remedial action process. Therefore, all soil remedial action at the 304 Facility will be conducted as part of the CERCLA remedial action of operable units 300-FF-3 and 300-FF-5.

  9. Livingston Solar Canopy Project The Project

    E-Print Network [OSTI]

    Delgado, Mauricio

    ,000 high efficiency solar panels on canopy structures over two major surface parking areasLivingston Solar Canopy Project The Project: This project entails the installation of more than 40. In conjunction with the existing 1.4 megawatt solar energy facility on this campus, this project will generate

  10. Information Visualization Graduate Project (Group Project)

    E-Print Network [OSTI]

    Rusu, Adrian

    Information Visualization Fall 2011 Graduate Project (Group Project) (100 points total) Handed out:59PM Research Article due by online submission on Sunday, December 11, 2011, 11:59PM Project Demo due last week of classes The idea of the project is to take the knowledge and background that you

  11. CONSTRAINING THE STRUCTURE OF SAGITTARIUS A*'s ACCRETION FLOW WITH MILLIMETER VERY LONG BASELINE INTERFEROMETRY CLOSURE PHASES

    SciTech Connect (OSTI)

    Broderick, Avery E. [Canadian Institute for Theoretical Astrophysics, 60 St. George Street, Toronto, ON M5S 3H8 (Canada); Fish, Vincent L.; Doeleman, Sheperd S. [Massachusetts Institute of Technology, Haystack Observatory, Route 40, Westford, MA 01886 (United States); Loeb, Abraham, E-mail: aeb@cita.utoronto.ca [Institute for Theory and Computation, Harvard University, Center for Astrophysics, 60 Garden Street, Cambridge, MA 02138 (United States)

    2011-09-01T23:59:59.000Z

    Millimeter wave very long baseline interferometry (mm-VLBI) provides access to the emission region surrounding Sagittarius A* (Sgr A*), the supermassive black hole at the center of the Milky Way, on sub-horizon scales. Recently, a closure phase of 0{sup 0} {+-} 40{sup 0} was reported on a triangle of Earth-sized baselines (SMT-CARMA-JCMT) representing a new constraint upon the structure and orientation of the emission region, independent from those provided by the previously measured 1.3 mm-VLBI visibility amplitudes alone. Here, we compare this to the closure phases associated with a class of physically motivated, radiatively inefficient accretion flow models and present predictions for future mm-VLBI experiments with the developing Event Horizon Telescope (EHT). We find that the accretion flow models are capable of producing a wide variety of closure phases on the SMT-CARMA-JCMT triangle and thus not all models are consistent with the recent observations. However, those models that reproduce the 1.3 mm-VLBI visibility amplitudes overwhelmingly have SMT-CARMA-JCMT closure phases between {+-}30{sup 0}, and are therefore broadly consistent with all current mm-VLBI observations. Improving station sensitivity by factors of a few, achievable by increases in bandwidth and phasing together multiple antennas at individual sites, should result in physically relevant additional constraints upon the model parameters and eliminate the current 180{sup 0} ambiguity on the source orientation. When additional stations are included, closure phases of order 45{sup 0}-90{sup 0} are typical. In all cases, the EHT will be able to measure these with sufficient precision to produce dramatic improvements in the constraints upon the spin of Sgr A*.

  12. RIVER PROTECTION PROJECT SYSTEM PLAN

    SciTech Connect (OSTI)

    CERTA PJ; KIRKBRIDE RA; HOHL TM; EMPEY PA; WELLS MN

    2009-09-15T23:59:59.000Z

    The U.S. Department of Energy (DOE), Office of River Protection (ORP) manages the River Protection Project (RPP). The RPP mission is to retrieve and treat Hanford's tank waste and close the tank farms to protect the Columbia River. As a result, ORP is responsible for the retrieval, treatment, and disposal of approximately 57 million gallons 1 of radioactive waste contained in the Hanford Site waste tanks and closure2 of all the tanks and associated facilities. The previous revision of the System Plan was issued in May 2008. ORP has made a number of changes to the tank waste treatment strategy and plans since the last revision of this document, and additional changes are under consideration. ORP has contracts in place to implement the strategy for completion of the mission and establish the capability to complete the overall mission. The current strategl involves a number of interrelated activities. ORP will reduce risk to the environment posed by tank wastes by the following: (1) Retrieving the waste from the single-shell tanks (SST) to double-shell tanks (DST) and delivering the waste to the Waste Treatment and Immobilization Plant (WTP). (2) Constructing and operating the WTP, which will safely treat all of the high-level waste (HLW) fraction contained in the tank farms. About one-third of the low-activity waste (LAW) fraction separated from the HLW fraction in the WTP will be immobilized in the WTP LAW Vitrification Facility. (3) Developing and deploying supplemental treatment capability assumed to be a second LAW vitrification facility that can safely treat about two-thirds of the LAW contained in the tank farms. (4) Developing and deploying supplemental pretreatment capability currently assumed to be an Aluminum Removal Facility (ARF) using a lithium hydrotalcite process to mitigate sodium management issues. (5) Developing and deploying treatment and packaging capability for contact-handled transuranic (CH-TRU) tank waste for possible shipment to and disposal at the Waste Isolation Pilot Plant (WIPP) in New Mexico. (6) Deploying interim storage capacity for the immobilized high-level waste (IHLW) pending determination of the final disposal pathway. (7) Closing the SST and DST tank farms, ancillary facilities, and all associated waste management and treatment facilities. (8) Optimizing the overall mission by resolution of technical and programmatic uncertainties, configuring the tank farms to provide a steady, well-balanced feed to the WTP, and performing trade-offs of the required amount and type of supplemental treatment and of the amount of HLW glass versus LAW glass. ORP has made and continues to make modifications to the WTP contract as needed to improve projected plant performance and address known or emerging risks. Key elements needed to implement the strategy described above are included within the scope of the Tank Operations Contract (TOC). Interim stabilization of the SSTs was completed in March 2004. As of April 2009, retrieval of seven SSTs has been completed and retrieval of four additional SSTs has been completed to the limits of technology. Demonstration of supplemental LAW treatment technologies has stopped temporarily pending revision of mission need requirements. Award of a new contract for tank operations (TOC), the ongoing tank waste retrieval experience, HLW disposal issues, and uncertainties in waste feed delivery and waste treatment led to the revision of the Performance Measurement Baseline (PM B), which is currently under review prior to approval. 6 This System Plan is aligned with the current WTP schedule, with hot commissioning beginning in 2018, and full operations beginning in late 2019. Major decisions regarding the use of supplemental treatment and the associated technology, the ultimate needed capacity, and its relationship to the WTP have not yet been finalized. This System Plan assumes that the outcome of these decisions will be to provide a second LAW vitrification facility. No final implementation decisions regarding supplemental technology can be made until the Tank Closure and

  13. Ashtabula Environmental Management Project Main Extrusion Plant Demolition Project. Demolition of the Ashtabula Environmental Management Project's Main Extrusion Plant

    SciTech Connect (OSTI)

    Colborn, Kurt; Johnson, Kathryn K.

    2003-02-27T23:59:59.000Z

    Significant progress was made this year toward closure of the Department of Energy's Ashtabula Environmental Management Project (AEMP) with the demolition of the 9-building Main Extrusion Plant Complex. The 44,000 square foot building complex formerly housed uranium extrusion facilities and equipment. At the start of the project in October of 2001, the buildings still contained a RCRA Part B storage area, operating mixed waste treatment facilities, active waste shredding and compacting process areas, and a state EPA permitted HEPA ventilation system. This paper presents a discussion of the multidisciplinary effort to bring the building to a safe shutdown condition in just six months, including relocation of existing process areas, utility isolation, and preliminary decontamination. Also discussed is the demolition strategy in which portions of the facility remained active while demolition was proceeding in other areas. Other details of the technical approach to the demolition are also discussed, including innovative techniques for demolition, galbestos removal, contamination control, and waste minimization. These techniques contributed to the early completion of demolition in July of 2002, fully two months ahead of schedule and $1.5 million under budget.

  14. The 100-C-7 Remediation Project. An Overview of One of DOE's Largest Remediation Projects - 13260

    SciTech Connect (OSTI)

    Post, Thomas C. [U.S. Department of Energy Richland Operations Office, Richland, WA 99352 (United States)] [U.S. Department of Energy Richland Operations Office, Richland, WA 99352 (United States); Strom, Dean [Washington Closure Hanford LLC, 2620 Fermi Avenue, Richland, WA 99354 (United States)] [Washington Closure Hanford LLC, 2620 Fermi Avenue, Richland, WA 99354 (United States); Beulow, Laura [U.S. Environmental Protection Agency, 309 Bradley Boulevard, Suite 115, Richland, WA 99352 (United States)] [U.S. Environmental Protection Agency, 309 Bradley Boulevard, Suite 115, Richland, WA 99352 (United States)

    2013-07-01T23:59:59.000Z

    The U.S. Department of Energy Richland Operations Office (RL), U.S. Environmental Protection Agency (EPA) and Washington Closure Hanford LLC (WCH) completed remediation of one of the largest waste sites in the U.S. Department of Energy complex. The waste site, 100-C-7, covers approximately 15 football fields and was excavated to a depth of 85 feet (groundwater). The project team removed a total of 2.3 million tons of clean and contaminated soil, concrete debris, and scrap metal. 100-C-7 lies in Hanford's 100 B/C Area, home to historic B and C Reactors. The waste site was excavated in two parts as 100-C-7 and 100-C-7:1. The pair of excavations appear like pit mines. Mining engineers were hired to design their tiered sides, with safety benches every 17 feet and service ramps which allowed equipment access to the bottom of the excavations. The overall cleanup project was conducted over a span of almost 10 years. A variety of site characterization, excavation, load-out and sampling methodologies were employed at various stages of remediation. Alternative technologies were screened and evaluated during the project. A new method for cost effectively treating soils was implemented - resulting in significant cost savings. Additional opportunities for minimizing waste streams and recycling were identified and effectively implemented by the project team. During the final phase of cleanup the project team applied lessons learned throughout the entire project to address the final, remaining source of chromium contamination. The C-7 cleanup now serves as a model for remediating extensive deep zone contamination sites at Hanford. (authors)

  15. HWMA/RCRA CLOSURE PLAN FOR THE MATERIALS TEST REACTOR WING (TRA-604) LABORATORY COMPONENTS VOLUNTARY CONSENT ORDER ACTION PLAN VCO-5.8 D REVISION2

    SciTech Connect (OSTI)

    KIRK WINTERHOLLER

    2008-02-25T23:59:59.000Z

    This Hazardous Waste Management Act/Resource Conservation and Recovery Act closure plan was developed for the laboratory components of the Test Reactor Area Catch Tank System (TRA-630) that are located in the Materials Test Reactor Wing (TRA-604) at the Reactor Technology Complex, Idaho National Laboratory Site, to meet a further milestone established under Voluntary Consent Order Action Plan VCO-5.8.d. The TRA-604 laboratory components addressed in this closure plan were deferred from the TRA-630 Catch Tank System closure plan due to ongoing laboratory operations in the areas requiring closure actions. The TRA-604 laboratory components include the TRA-604 laboratory warm wastewater drain piping, undersink drains, subheaders, and the east TRA-604 laboratory drain header. Potentially contaminated surfaces located beneath the TRA-604 laboratory warm wastewater drain piping and beneath the island sinks located in Laboratories 126 and 128 (located in TRA-661) are also addressed in this closure plan. The TRA-604 laboratory components will be closed in accordance with the interim status requirements of the Hazardous Waste Management Act/Resource Conservation and Recovery Act as implemented by the Idaho Administrative Procedures Act 58.01.05.009 and 40 Code of Federal Regulations 265, Subparts G and J. This closure plan presents the closure performance standards and the methods for achieving those standards.

  16. Citizen Contributions to the Closure of High-Level Waste (HLW) Tanks 18 and 19 at the Department of Energy's (DOE) Savannah River Site (SRS) - 13448

    SciTech Connect (OSTI)

    Lawless, W.F. [Paine College, Departments of Math and Psychology, 1235 15th Street, Augusta, GA 30901 (United States)] [Paine College, Departments of Math and Psychology, 1235 15th Street, Augusta, GA 30901 (United States)

    2013-07-01T23:59:59.000Z

    Citizen involvement in DOE's decision-making for the environmental cleanup from DOE's management of its nuclear wastes across the DOE complex has had a positive effect on the cleanup of its SRS site, characterized by an acceleration of cleanup not only for the Transuranic wastes at SRS, but also for DOE's first two closures of HLW tanks, both of which occurred at SRS. The Citizens around SRS had pushed successfully for the closures of Tanks 17 and 20 in 1997, becoming the first closures of HLW tanks under regulatory guidance in the USA. However, since then, HLW tank closures ceased due to a lawsuit, the application of new tank clean-up technology, interagency squabbling between DOE and NRC over tank closure criteria, and finally and almost fatally, from budget pressures. Despite an agreement with its regulators for the closure of Tanks 18 and 19 by the end of calendar year 2012, the outlook in Fall 2011 to close these two tanks had dimmed. It was at this point that the citizens around SRS became reengaged with tank closures, helping DOE to reach its agreed upon milestone. (authors)

  17. Closure Report for the 92-Acre Area and Corrective Action Unit 111: Area 5 WMD Retired Mixed Waste Pits, Nevada National Security Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2012-02-21T23:59:59.000Z

    This Closure Report (CR) presents information supporting closure of the 92-Acre Area, which includes Corrective Action Unit (CAU) 111, 'Area 5 WMD Retired Mixed Waste Pits.' This CR provides documentation supporting the completed corrective actions and confirmation that the closure objectives were met. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) (FFACO, 1996 [as amended March 2010]). Closure activities began in January 2011 and were completed in January 2012. Closure activities were conducted according to Revision 1 of the Corrective Action Decision Document/Corrective Action Plan (CADD/CAP) for the 92-Acre Area and CAU 111 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2010). The following closure activities were performed: (1) Construct an engineered evapotranspiration cover over the boreholes, trenches, and pits in the 92-Acre Area; (2) Install use restriction (UR) warning signs, concrete monuments, and subsidence survey monuments; and (3) Establish vegetation on the covers. UR documentation is included as Appendix C of this report. The post-closure plan is presented in detail in Revision 1 of the CADD/CAP for the 92-Acre Area and CAU 111, and the requirements are summarized in Section 5.2 of this document. When the next request for modification of Resource Conservation and Recovery Act Permit NEV HW0101 is submitted to the Nevada Division of Environmental Protection (NDEP), the requirements for post-closure monitoring of the 92-Acre Area will be included. NNSA/NSO requests the following: (1) A Notice of Completion from NDEP to NNSA/NSO for closure of CAU 111; and (2) The transfer of CAU 111 from Appendix III to Appendix IV, Closed Corrective Action Units, of the FFACO.

  18. Post-Closure RCRA Groundwater Monitoring Plan for the 216-S-10 Pond and Ditch

    SciTech Connect (OSTI)

    Barnett, D BRENT.; Williams, Bruce A.; Chou, Charissa J.; Hartman, Mary J.

    2006-03-17T23:59:59.000Z

    The purpose of this plan is to provide a post-closure groundwater monitoring program for the 216-S-10 Pond and Ditch (S-10) treatment, storage, and/or disposal (TSD) unit. The plan incorporates the sum of knowledge about the potential for groundwater contamination to originate from the S-10, including groundwater monitoring results, hydrogeology, and operational history. The S-10 has not received liquid waste since October 1991. The closure of S-10 has been coordinated with the 200-CS-1 source operable unit in accordance with the Tri-Party Agreement interim milestones M-20-39 and M-15-39C. The S-10 is closely situated among other waste sites of very similar operational histories. The proximity of the S-10 to the other facilities (216-S-17 pond, 216-S-11 Pond, 216-S-5,6 cribs, 216-S-16 ditch and pond, and 216-U-9 ditch) indicate that at least some observed groundwater contamination beneath and downgradient of S-10 could have originated from waste sites other than S-10. Hence, it may not be feasible to strictly discriminate between the contributions of each waste site to groundwater contamination beneath the S-10. A post-closure groundwater monitoring network is proposed that will include the drilling of three new wells to replace wells that have gone dry. When completed, the revised network will meet the intent for groundwater monitoring network under WAC 173-303-645, and enable an improved understanding of groundwater contamination at the S-10. Site-specific sampling constituents are based on the dangerous waste constituents of concern relating to RCRA TSD unit operations (TSD unit constituents) identified in the Part A Permit Application. Thus, a constituent is selected for monitoring if it is: A dangerous waste constituent identified in the Part A Permit Application, or A mobile decomposition product (i.e., nitrate from nitrite) of a Part A constituent, or A reliable indicator of the site-specific contaminants (i.e., specific conductance). Using these criteria, the following constituent list and sampling schedule is proposed: Constituent; Sampling Frequency Site-Specific Parameters; Hexavalent chromium (a); Semiannual Chloride; Semiannual Fluoride; Semiannual Nitrate; Semiannual Nitrite; Semiannual Specific conductance (field)(a); Semiannual Ancillary Parameters; Anions; Annual Alkalinity Annual Metals, (in addition to chromium); Annual pH (field) Semiannual Temperature (field); Semiannual Turbidity (field) Semiannual (a). These constituents will be subject to statistical tests after background is established. It will be necessary to install new monitoring wells and accumulate background data on the groundwater from those wells before statistical comparisons can be made. Until then, the constituents listed above will be evaluated by tracking and trending concentrations in all wells and comparing these results with the corresponding DWS or Hanford Site background concentration for each constituent. If a comparison value (background or DWS) for a constituent is exceeded, DOE will notify Ecology per WAC 173-303-645 (9) (g) requirements (within seven days or a time agreed to between DOE and Ecology).

  19. Closure Report for Corrective Action Unit 121: Storage Tanks and Miscellaneous Sites, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2008-09-01T23:59:59.000Z

    Corrective Action Unit (CAU) 121 is identified in the Federal Facility Agreement and Consent Order (FFACO) (1996, as amended February 2008) as Storage Tanks and Miscellaneous Sites. CAU 121 consists of the following three Corrective Action Sites (CASs) located in Area 12 of the Nevada Test Site, which is approximately 65 miles northwest of Las Vegas, Nevada: (1) CAS 12-01-01, Aboveground Storage Tank; (2) CAS 12-01-02, Aboveground Storage Tank; and (3) CAS 12-22-26, Drums; 2 AST's. CAU 121 closure activities were conducted according to the FFACO and the Streamlined Approach for Environmental Restoration Plan for CAU 121 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007). Field work took place from February through September 2008. Samples were collected to determine the path forward to close each site. Closure activities were completed as defined in the plan based on sample analytical results and site conditions. No contaminants of concern (COCs) were present at CAS 12-01-01; therefore, no further action was chosen as the corrective action alternative. As a best management practice (BMP), the empty aboveground storage tank (AST) was removed and disposed as sanitary waste. At CAS 12-01-02, polychlorinated biphenyls (PCBs) were present above the preliminary action level (PAL) in the soil beneath the AST that could possibly have originated from the AST contents. Therefore, PCBs were considered COCs, and the site was clean closed by excavating and disposing of soil containing PCBs. Approximately 5 cubic yards (yd{sup 3}) of soil were excavated and disposed as petroleum hydrocarbon PCB remediation waste, and approximately 13 yd3 of soil were excavated and disposed as PCB remediation waste. Cleanup samples were collected to confirm that the remaining soil did not contain PCBs above the PAL. Other compounds detected in the soil above PALs (i.e., total petroleum hydrocarbons [TPH] and semi-volatile organic compounds [SVOCs]) were determined to not likely have originated from the tank. Additional sample results showed that the compounds were likely present as a result of degraded asphalt around the adjacent, active water tank and not from the abandoned AST; therefore, they were not considered COCs. As a BMP, the empty AST was removed and disposed as sanitary waste. No COCs were present at CAS 12-22-26; therefore, no further action was chosen as the corrective action alternative. Although TPH was present at concentrations that exceeded the PAL, the volatile organic compound and SVOC hazardous constituents of TPH did not exceed the final action levels (FALs); therefore, TPH was not considered a COC. As a BMP, the empty AST was removed and disposed as sanitary waste. Closure activities generated sanitary waste, petroleum hydrocarbon PCB remediation waste, PCB remediation waste, and hazardous waste. Waste was appropriately managed and disposed. Waste that is currently staged on site is being appropriately managed and will be disposed under approved waste profiles in permitted landfills. Waste minimization activities included waste characterization sampling and segregation of waste streams.

  20. Iskuulpa Watershed ProjectIskuulpa Watershed Project BPA Project # 199506001BPA Project # 199506001

    E-Print Network [OSTI]

    Hydroelectric Power Project impacts Improve natural salmonid habitat and production #12;Project ActivitiesProject Activities Land purchaseLand purchase HEP evaluationHEP evaluation Rest from livestockRest from livestock;Project ActivitiesProject Activities Land purchaseLand purchase HEP evaluationHEP evaluation Rest from

  1. Regulatory Framework for Salt Waste Disposal and Tank Closure at the Savannah River Site - 13663

    SciTech Connect (OSTI)

    Thomas, Steve; Dickert, Ginger [Savannah River Remediation LLC, Savannah River Site, Aiken, SC 29808 (United States)] [Savannah River Remediation LLC, Savannah River Site, Aiken, SC 29808 (United States)

    2013-07-01T23:59:59.000Z

    The end of the Cold War has left a legacy of approximately 37 million gallons of radioactive waste in the aging waste tanks at the Department of Energy's Savannah River Site (SRS). A robust program is in place to remove waste from these tanks, treat the waste to separate into a relatively small volume of high-level waste and a large volume of low-level waste, and to actively dispose of the low-level waste on-site and close the waste tanks and associated ancillary structures. To support performance-based, risk-informed decision making and to ensure compliance with all regulatory requirements, the U.S. Department of Energy (DOE) and its current and past contractors have worked closely with the South Carolina Department of Health and Environmental Control (SCDHEC), the U.S. Environmental Protection Agency (EPA) and the Nuclear Regulatory Commission (NRC) to develop and implement a framework for on-site low-level waste disposal and closure of the SRS waste tanks. The Atomic Energy Act of 1954, as amended, provides DOE the authority to manage defense-related radioactive waste. DOE Order 435.1 and its associated manual and guidance documents detail this radioactive waste management process. The DOE also has a requirement to consult with the NRC in determining that waste that formerly was classified as high-level waste can be safely managed as either low-level waste or transuranic waste. Once DOE makes a determination, NRC then has a responsibility to monitor DOE's actions in coordination with SCDHEC to ensure compliance with the Title 10 Code of Federal Regulations Part 61 (10CFR61), Subpart C performance objectives. The management of hazardous waste substances or components at SRS is regulated by SCDHEC and the EPA. The foundation for the interactions between DOE, SCDHEC and EPA is the SRS Federal Facility Agreement (FFA). Managing this array of requirements and successfully interacting with regulators, consultants and stakeholders is a challenging task but ensures thorough and thoughtful processes for disposing of the SRS low-level waste and the closure of the tank farm facilities. (authors)

  2. TRA Closure Plan REV 0-9-20-06 HWMA/RCRA Closure Plan for the TRA/MTR Warm Waste System Voluntary Consent Order SITE-TANK-005 Tank System TRA-007

    SciTech Connect (OSTI)

    Winterholler, K.

    2007-01-31T23:59:59.000Z

    This Hazardous Waste Management Act/Resource Conservation and Recovery Act closure plan was developed for portions of the Test Reactor Area/Materials Test Reactor Warm Waste System located in the Materials Test Reactor Building (TRA-603) at the Reactor Technology Complex, Idaho National Laboratory Site, to meet a further milestone established under Voluntary Consent Order Action Plan SITE-TANK-005 for Tank System TRA-007. The reactor drain tank and canal sump to be closed are included in the Test Reactor Area/Materials Test Reactor Warm Waste System. The reactor drain tank and the canal sump were characterized as having managed hazardous waste. The reactor drain tank and canal sump will be closed in accordance with the interim status requirements of the Hazardous Waste Management Act/Resource Conservation and Recovery Act as implemented by the Idaho Administrative Procedures Act 58.01.05.009 and 40 Code of Federal Regulations 265. This closure plan presents the closure performance standards and methods for achieving those standards.

  3. Post-Closure Inspection and Monitoring Report for Corrective Action Unit 417: Central Nevada Test Area Surface, Hot Creek Valley, Nevada

    SciTech Connect (OSTI)

    None

    2009-10-01T23:59:59.000Z

    This report presents results of data collected during the annual post-closure site inspection conducted at the Central Nevada Test Area, surface Corrective Action Unit (CAU) 417 in June 2009. The annual post-closure site inspection included inspections of the UC-1, UC-3, and UC-4 sites in accordance with the Post-Closure Monitoring Plan provided in the CAU 417 Closure Report (NNSA/NV 2001). The annual inspection conducted at the UC-1 Central Mud Pit (CMP) indicated that the site and soil cover were in good condition. Three new fractures were identified in the soil cover and were filled with bentonite chips during the inspection. The vegetation on the soil cover was adequate but showed signs of the area's ongoing drought. No issues were identified with the CMP fence, gate, or subsidence monuments. No issues were identified with the warning signs and monuments at the other two UC-1 locations

  4. HWMA/RCRA Closure Plan for the CPP-648 Radioactive Solid and Liquid Waste Storage Tank System (VES-SFE-106)

    SciTech Connect (OSTI)

    S. K. Evans

    2006-08-15T23:59:59.000Z

    This Hazardous Waste Management Act/Resource Conservation and Recovery Act closure plan for the Radioactive Solid and Liquid Waste Storage Tank System located in the adjacent to the Sludge Tank Control House (CPP-648), Idaho Nuclear Technology and Engineering Center, Idaho National Laboratory, was developed to meet the interim status closure requirements for a tank system. The system to be closed includes a tank and associated ancillary equipment that were determined to have managed hazardous waste. The CPP-648 Radioactive Solid and Liquid Waste Storage Tank System will be "cleaned closed" in accordance with the requirements of the Hazardous Waste Management Act/Resource Conservation and Recovery Act as implemented by the Idaho Administrative Procedures Act and 40 Code of Federal Regulations 265. This closure plan presents the closure performance standards and methods of acheiving those standards for the CPP-648 Radioactive Solid and Liquid Waste Storage Tank System.

  5. Project Name Project Number Tagging Type

    E-Print Network [OSTI]

    Project Name Project Number Primary Tagging Type Secondary Tagging Type Fish Species Tagging/ Secondary Legal Driver (BiOp, MOA, Accord, etc.) Tagging Purpose Funded Entity Tagging Location Retrieval CWT Recovery Project 2010-036-00 CWT PIT Chinook, coho retrieval, analysis, address PSMFC sampling

  6. Hamiltonian fluid closures of the Vlasov-Amp{č}re equations: from water-bags to N moment models

    E-Print Network [OSTI]

    M. Perin; Cristel Chandre; P. J. Morrison; E. Tassi

    2015-07-02T23:59:59.000Z

    Moment closures of the Vlasov-Amp{\\`e}re system, whereby higher moments are represented as functions of lower moments with the constraint that the resulting fluid system remains Hamiltonian, are investigated by using water-bag theory. The link between the water-bag formalism and fluid models that involve density, fluid velocity, pressure and higher moments is established by introducing suitable thermodynamic variables. The cases of one, two and three water-bags are treated and their Hamiltonian structures are provided. In each case, we give the associated fluid closures and we discuss their Casimir invariants. We show how the method can be extended to an arbitrary number of fields, i.e., an arbitrary number of water-bags and associated moments. The thermodynamic interpretation of the resulting models is discussed. Finally, a general procedure to derive Hamiltonian N-field fluid models is proposed.

  7. Closure Report for Corrective Action Unit 254: Area 25, R-MAD Decontamination Facility, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    G. N. Doyle

    2002-02-01T23:59:59.000Z

    Corrective Action Unit (CAU) 254 is located in Area 25 of the Nevada Test Site (NTS), approximately 100 kilometers (km) (62 miles) northwest of Las Vegas, Nevada. The site is located within the Reactor Maintenance, Assembly and Disassembly (R-MAD) compound and consists of Building 3126, two outdoor decontamination pads, and surrounding areas within an existing fenced area measuring approximately 50 x 37 meters (160 x 120 feet). The site was used from the early 1960s to the early 1970s as part of the Nuclear Rocket Development Station program to decontaminate test-car hardware and tooling. The site was reactivated in the early 1980s to decontaminate a radiologically contaminated military tank. This Closure Report (CR) describes the closure activities performed to allow un-restricted release of the R-MAD Decontamination Facility.

  8. Safer Work Plan for CAUs 452, 454, 456, and 464 Closure of Historical UST Release Sites Nevada Test Site

    SciTech Connect (OSTI)

    Jerry Bonn

    1997-08-01T23:59:59.000Z

    This plan addresses characterization and closure of nine underground storage tank petroleum hydrocarbon release sites. The sites are located at the Nevada Test Site in Areas 2, 9, 12, 23, and 25. The underground storage tanks associated with the release sites and addressed by this plan were closed between 1990 and 1996 by the U. S. Department of Energy, Nevada Operations Office. One underground storage tank was closed in place (23-111-1) while the remaining eight were closed by removal. Hydrocarbon releases were identified at each of the sites based upon laboratory analytical data samples collected below the tank bottoms. The objective of this plan is to provide a method for implementing characterization and closure of historical underground storage tank hydrocarbon release sites.

  9. Closure Report for Corrective Action Unit 408: Bomblet Target Area Tonopah Test Range (TTR), Nevada, Revision 0

    SciTech Connect (OSTI)

    Mark Krauss

    2010-09-01T23:59:59.000Z

    This Closure Report (CR) presents information supporting the closure of Corrective Action Unit (CAU) 408: Bomblet Target Area (TTR), Tonopah Test Range, Nevada. This CR complies with the requirements of the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management. Corrective Action Unit 408 is located at the Tonopah Test Range, Nevada, and consists of Corrective Action Site (CAS) TA-55-002-TAB2, Bomblet Target Areas. This CAS includes the following seven target areas: • Mid Target • Flightline Bomblet Location • Strategic Air Command (SAC) Target Location 1 • SAC Target Location 2 • South Antelope Lake • Tomahawk Location 1 • Tomahawk Location 2 The purpose of this CR is to provide documentation supporting the completed corrective actions and data confirming that the closure objectives for the CAS within CAU 408 were met. To achieve this, the following actions were performed: • Review the current site conditions, including the concentration and extent of contamination. • Implement any corrective actions necessary to protect human health and the environment. • Properly dispose of corrective action and investigation wastes. • Document Notice of Completion and closure of CAU 408 issued by the Nevada Division of Environmental Protection. From July 2009 through August 2010, closure activities were performed as set forth in the Streamlined Approach for Environmental Restoration Plan for CAU 408: Bomblet Target Area, Tonopah Test Range (TTR), Nevada. The purposes of the activities as defined during the data quality objectives process were as follows: • Identify and remove munitions of explosive concern (MEC) associated with DOE activities. • Investigate potential disposal pit locations. • Remove depleted uranium-contaminated fragments and soil. • Determine whether contaminants of concern (COCs) are present. • If COCs are present, determine their nature and extent, implement appropriate corrective actions, and properly dispose of wastes. Analytes detected during the closure activities were evaluated against final action levels to determine COCs for CAU 408. Assessment of the data indicated COCs are not present at CAS TA-55-002-TAB2; therefore, no corrective action is necessary. No use restrictions are required to be placed on this CAU because the investigation showed no evidence of remaining soil contamination or remaining debris/waste upon completion of all investigation activities. The MEC was successfully removed and dispositioned as planned using current best available technologies. As MEC guidance and general MEC standards acknowledge that MEC response actions cannot determine with 100 percent certainty that all MEC and unexploded ordnance (UXO) are removed, the clean closure of CAU 408 will implement a best management practice of posting UXO hazard warning signs near the seven target areas. The signs will warn future land users of the potential for encountering residual UXO hazards. The DOE, National Nuclear Security Administration Nevada Site Office, provides the following recommendations: • A Notice of Completion to the DOE, National Nuclear Security Administration Nevada Site Office, is requested from the Nevada Division of Environmental Protection for closure of CAU 408. • Corrective Action Unit 408 should be moved from Appendix III to Appendix IV of the Federal Facility Agreement and Consent Order.

  10. Projects | Department of Energy

    Office of Environmental Management (EM)

    Projects Projects All 1703 1705 ATVM Current Portfolio 32.4 B in Loans 55 K Jobs Current Portfolio Loans 32.4 B Jobs 55,000 Loan Program Office Projects 1703 1705 ATVM...

  11. CRSP Power Projects

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

    expenses of the project each year, and receive all of the energy it produces. Salt Lake City AreaIntegrated Projects: Power from the Colorado River Storage Project plants was...

  12. Project Selection - Record Keeping

    E-Print Network [OSTI]

    Howard, Jeff W.

    2005-05-10T23:59:59.000Z

    4-H members have many project areas to choose from, depending on where they live. Members should consult with their parents and 4-H leaders when choosing a project. This publication outlines project considerations....

  13. Super Projects (Arkansas)

    Broader source: Energy.gov [DOE]

    A 2004 amendment to the state constitution authorizes the state to attract super projects by issuing bonds to fund a project’s infrastructure, limited to 5% of the net general revenues during the...

  14. C-104 Solid Phase Characterization of Sample 4C-13-1 From Tank 241-C-104 Closure Sampling Event

    SciTech Connect (OSTI)

    Cooke, Gary A.; Pestovich, John A.

    2013-06-12T23:59:59.000Z

    One solid grab sample from closure sampling in Riser 7 of tank 214-C-I04 (C-I04) was examined to determine the solid phases that were present. The sample was analyzed using X-ray diffraction (XRD) and scanning electron microscopy (SEM). The purpose of this analysis was to see if the presence of hydrated phases could provide a possible explanation for the high moisture content obtained from thermogravimetric analysis (TGA).

  15. Closure Report for Corrective Action Unit 544: Cellars, Mud Pits, and Oil Spills, Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Mark Krauss and Catherine Birney

    2011-05-01T23:59:59.000Z

    This Closure Report (CR) presents information supporting the closure of Corrective Action Unit (CAU) 544: Cellars, Mud Pits, and Oil Spills, Nevada National Security Site, Nevada. This CR complies with the requirements of the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management. The corrective action sites (CASs) within CAU 544 are located within Areas 2, 7, 9, 10, 12, 19, and 20 of the Nevada National Security Site. Corrective Action Unit 544 comprises the following CASs: • 02-37-08, Cellar & Mud Pit • 02-37-09, Cellar & Mud Pit • 07-09-01, Mud Pit • 09-09-46, U-9itsx20 PS #1A Mud Pit • 10-09-01, Mud Pit • 12-09-03, Mud Pit • 19-09-01, Mud Pits (2) • 19-09-03, Mud Pit • 19-09-04, Mud Pit • 19-25-01, Oil Spill • 19-99-06, Waste Spill • 20-09-01, Mud Pits (2) • 20-09-02, Mud Pit • 20-09-03, Mud Pit • 20-09-04, Mud Pits (2) • 20-09-06, Mud Pit • 20-09-07, Mud Pit • 20-09-10, Mud Pit • 20-25-04, Oil Spills • 20-25-05, Oil Spills The purpose of this CR is to provide documentation supporting the completed corrective actions and data confirming that the closure objectives for CASs within CAU 544 were met. To achieve this, the following actions were performed: • Review the current site conditions, including the concentration and extent of contamination. • Implement any corrective actions necessary to protect human health and the environment. • Properly dispose of corrective action and investigation wastes. • Document Notice of Completion and closure of CAU 544 issued by the Nevada Division of Environmental Protection.

  16. Closure Strategy for a Waste Disposal Facility with Multiple Waste Types and Regulatory Drivers at the Nevada Test Site

    SciTech Connect (OSTI)

    D. Wieland, V. Yucel, L. Desotell, G. Shott, J. Wrapp

    2008-04-01T23:59:59.000Z

    The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) plans to close the waste and classified material storage cells in the southeast quadrant of the Area 5 Radioactive Waste Management Site (RWMS), informally known as the '92-Acre Area', by 2011. The 25 shallow trenches and pits and the 13 Greater Confinement Disposal (GCD) borings contain various waste streams including low-level waste (LLW), low-level mixed waste (LLMW), transuranic (TRU), mixed transuranic (MTRU), and high specific activity LLW. The cells are managed under several regulatory and permit programs by the U.S. Department of Energy (DOE) and the Nevada Division of Environmental Protection (NDEP). Although the specific closure requirements for each cell vary, 37 closely spaced cells will be closed under a single integrated monolayer evapotranspirative (ET) final cover. One cell will be closed under a separate cover concurrently. The site setting and climate constrain transport pathways and are factors in the technical approach to closure and performance assessment. Successful implementation of the integrated closure plan requires excellent communication and coordination between NNSA/NSO and the regulators.

  17. State Environmental Policy Act (SEPA) Environmental Checklist Form 216-B-3 Expansion Ponds Closure Plan. Revision 1

    SciTech Connect (OSTI)

    Not Available

    1993-12-01T23:59:59.000Z

    The 216-B-3 Expansion Ponds Closure Plan (Revision 1) consists of a Part A Dangerous Waste Permit Application and a Resource Conservation and Recovery Act Closure Plan. An explanation of the Part A submitted with this document is provided at the beginning of the Part A Section. The closure plan consists of nine chapters and five appendices. The 216-B-3 Pond System consists of a series of four earthen, unlined, interconnected ponds and the 216-B-3-3 Ditch that receive waste water from various 200 East Area operating facilities. These four ponds, collectively. Waste water (primarily cooling water, steam condensate, and sanitary water) from various 200 East Area facilities is discharged to the 216-B-3-3 Ditch. Water discharged to the 216-8-3-3 Ditch flows directly into the 216-B-3 Pond. In the past, waste water discharges to B Pond and the 216-B-3-3 Ditch contained mixed waste (radioactive waste and dangerous waste). The radioactive portion of mixed waste has been interpreted by the US Department of Energy (DOE) to be regulated under the Atomic Energy Act of 1954; the nonradioactive dangerous portion of mixed waste is regulated under RCRA. Mixed waste also may be considered a hazardous substance under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) when considering remediation of waste sites.

  18. Closure Report for Corrective Action Unit 143: Area 25 Contaminated Waste Dumps, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    D. S. Tobiason

    2002-03-01T23:59:59.000Z

    This Closure Report (CR) has been prepared for the Area 25 Contaminated Waste Dumps (CWD), Corrective Action Unit (CAU) 143 in accordance with the Federal Facility Agreement and Consent Order [FFACO] (FFACO, 1996) and the Nevada Division of Environmental Protection (NDEP)-approved Corrective Action Plan (CAP) for CAU 143: Area 25, Contaminated Waste Dumps, Nevada Test Site, Nevada. CAU 143 consists of two Corrective Action Sites (CASs): 25-23-09 CWD No.1, and 25-23-03 CWD No.2. The Area 25 CWDs are historic disposal units within the Area 25 Reactor Maintenance, Assembly, and Disassembly (R-MAD), and Engine Maintenance, Assembly, and Disassembly (E-MAD) compounds located on the Nevada Test Site (NTS). The R-MAD and E-MAD facilities originally supported a portion of the Nuclear Rocket Development Station in Area 25 of the NTS. CWD No.1 CAS 25-23-09 received solid radioactive waste from the R-MAD Compound (East Trestle and West Trench Berms) and 25-23-03 CWD No.2 received solid radioactive waste from the E-MAD Compound (E-MAD Trench).

  19. Structure of Sagittarius A* at 86 GHz using VLBI Closure Quantities

    E-Print Network [OSTI]

    S. S. Doeleman; Z. -Q. Shen; A. E. E. Rogers; G. C. Bower; M. C. H. Wright; J. -H. Zhao; D. C. Backer; J. W. Crowley; R. W. Freund; P. T. P. Ho; K. Y. Lo; D. P. Woody

    2001-02-13T23:59:59.000Z

    At radio wavelengths, images of the compact radio source Sagittarius A* (Sgr A*) in the Galactic Center are scatter broadened with a lambda^2 dependence due to an intervening ionized medium. We present VLBI observations of Sgr A* at 86 GHz using a six station array including the VLBA antennas at Pie Town, Fort Davis and Los Alamos, the 12m antenna at Kitt Peak and the millimeter arrays at Hat Creek and Owens Valley. To avoid systematic errors due to imperfect antenna calibration, the data were modeled using interferometric closure information. The data are best modeled by a circular Gaussian brightness distribution of FWHM 0.18 +- 0.02 mas. The data are also shown to be consistent with an elliptical model corresponding to the scattering of a point source. The source structure in the N-S direction, which is less well determined than in the E-W direction due to the limited N-S (u,v) coverage of the array, is constrained to be less than 0.27 mas by these measurements. These results are consistent with extrapolations of intrinsic structure estimates obtained with VLBI at 7mm wavelength assuming the intrinsic size of Sgr A* has a greater dependence than lambda^0.9 with wavelength.

  20. Closure Report for Corrective Action Unit 398: Area 25 Spill Sites, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    K. B. Campbell

    2003-04-01T23:59:59.000Z

    This Closure Report (CR) documents the activities performed to close Corrective Action Unit (CAU) 398: Area 25 Spill Sites, in accordance with the Federal Facility Agreement and Consent Order (FFACO) of 1996, and the Nevada Division of Environmental Protection (NDEP)-approved Streamlined Approach for Environmental Restoration (SA4FER) Plan for CAU 398: Area 25 Spill Sites, Nevada Test Site, Nevada (U.S. Department of Energy, Nevada Operations Office [DOEN], 2001). CAU 398 consists of the following thirteen Corrective Action Sites (CASs) all located in Area 25 of the Nevada Test Site (NTS) (Figure 1): CAS 25-25-02, Oil Spills, CAS 25-25-03, Oil Spills, CAS 25-25-04, Oil Spills, CAS 25-25-05, Oil Spills, CAS 25-25-06, Oil Spills, CAS 25-25-07, Hydraulic Oil Spill(s), CAS 25-25-08, Hydraulic Oil Spill(s), CAS 25-25-16, Diesel Spill (from CAS 25-01-02), CAS 25-25-17, Subsurface Hydraulic Oil Spill, CAS 25-44-0 1, Fuel Spill, CAS 25-44-04, Acid Spill (from CAS 25-01-01), CAS 25-44-02, Spill, and CAS 25-44-03, Spill. Copies of the analytical results for the site verification samples are included in Appendix B. Copies of the CAU Use Restriction Information forms are included in Appendix C.

  1. Planning and Projects

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

    Rates Planning Ten-Year Capital Program Projects Lovell-Yellowtail Transmission Line Rebuild project Studies WACM Wind production summary overview (Oct. 2006)...

  2. Project BETA Cover Page

    E-Print Network [OSTI]

    Cover Page, Project BETA

    2012-01-01T23:59:59.000Z

    and Distribution of the Project BETA articles were funded inproduct is discussed in the BETA articles. Western JournalProject BETA: Best practices in Evaluation and Treatment of

  3. Project Finance and Investments

    Broader source: Energy.gov [DOE]

    Plenary III: Project Finance and Investment Project Finance and Investments Chris Cassidy, National Business Renewable Energy Advisor, U.S. Department of Agriculture

  4. Contract/Project Management

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

    3 rd Quarter Overall Contract and Project Management Performance Metrics and Targets ContractProject Management Performance Metrics FY 2009 Target FY 2009 Actual Comment 1....

  5. Operations Cost Allocation Project

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

    Operations Consolidation Project Operations Consolidation Project (OCP) Cost Allocation Presentation - September 20, 2011 OCP Cost Allocation Customer Presentation List of Acronyms...

  6. Clean Coal Projects (Virginia)

    Broader source: Energy.gov [DOE]

    This legislation directs the Virginia Air Pollution Control Board to facilitate the construction and implementation of clean coal projects by expediting the permitting process for such projects.

  7. Falls Creek Hydroelectric Project

    SciTech Connect (OSTI)

    Gustavus Electric Company; Richard Levitt; DOE Project Officer - Keith Bennett

    2007-06-12T23:59:59.000Z

    This project was for planning and construction of a 700kW hydropower project on the Fall River near Gustavus, Alaska.

  8. CLOSURE REPORT FOR CORRECTIVE ACTION UNIT165: AREA 25 AND 26 DRY WELL AND WASH DOWN AREAS, NEVADA TEST SITE, NEVADA

    SciTech Connect (OSTI)

    BECHTEL NEVADA

    2005-12-01T23:59:59.000Z

    This Closure Report (CR) documents the closure activities for Corrective Action Unit (CAU) 165, Area 25 and 26 Dry Well and Washdown Areas, according to the Federal Facility Agreement and Consent Order (FFACO) of 1996. CAU 165 consists of 8 Corrective Action Sites (CASs) located in Areas 25 and 26 of the Nevada Test Site (NTS). The NTS is located approximately 105 kilometers (65 miles) northwest of Las Vegas, nevada. Site closure activities were performed according to the Nevada Division of Environmental Protection (NDEP)-approved Corrective Action Plan (CAP) for CAU 165. CAU 165 consists of the following CASs: (1) CAS 25-07-06, Train Decontamination Area; (2) CAS 25-07-07, Vehicle Washdown; (3) CAS 25-20-01, Lab Drain Dry Well; (4) CAS 25-47-01, Reservoir and French Drain; (5) CAS 25-51-02, Drywell; (6) CAS 25-59-01, Septic System; (7) CAS 26-07-01, Vehicle Washdown Station; and (8) CAS 26-59-01, Septic System. CAU 165, Area 25 and 26 Dry Well and Washdown Areas, consists of eight CASs located in Areas 25 and 26 of the NTS. The approved closure alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls.

  9. Manhattan Project | Department of Energy

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

    Manhattan Project Manhattan Project Manhattan Project New Manhattan Project Interactive Website The Department of Energy traces its origins to World War II and the Manhattan...

  10. E-Area Vault Concrete Material Property And Vault Durability/Degradation Projection Recommendations

    SciTech Connect (OSTI)

    Phifer, M. A.

    2014-03-11T23:59:59.000Z

    Subsequent to the 2008 E-Area Low-Level Waste Facility (ELLWF) Performance Assessment (PA) (WSRC 2008), two additional E-Area vault concrete property testing programs have been conducted (Dixon and Phifer 2010 and SIMCO 2011a) and two additional E-Area vault concrete durability modeling projections have been made (Langton 2009 and SIMCO 2012). All the information/data from these reports has been evaluated and consolidated herein by the Savannah River National Laboratory (SRNL) at the request of Solid Waste Management (SWM) to produce E-Area vault concrete hydraulic and physical property data and vault durability/degradation projection recommendations that are adequately justified for use within associated Special Analyses (SAs) and future PA updates. The Low Activity Waste (LAW) and Intermediate Level (IL) Vaults structural degradation predictions produced by Carey 2006 and Peregoy 2006, respectively, which were used as the basis for the 2008 ELLWF PA, remain valid based upon the results of the E-Area vault concrete durability simulations reported by Langton 2009 and those reported by SIMCO 2012. Therefore revised structural degradation predictions are not required so long as the mean thickness of the closure cap overlying the vaults is no greater than that assumed within Carey 2006 and Peregoy 2006. For the LAW Vault structural degradation prediction (Carey 2006), the mean thickness of the overlying closure cap was taken as nine feet. For the IL Vault structural degradation prediction (Peregoy 2006), the mean thickness of the overlying closure cap was taken as eight feet. The mean closure cap thicknesses as described here for both E-Area Vaults will be included as a key input and assumption (I&A) in the next revision to the closure plan for the ELLWF (Phifer et al. 2009). In addition, it has been identified as new input to the PA model to be assessed in the ongoing update to the new PA Information UDQE (Flach 2013). Once the UDQE is approved, the SWM Key I&A database will be updated with this new information.

  11. Annual Post-Closure Inspection and Monitoring Report for Corrective Action Unit 329: Area 22 Desert Rock Airstrip Fuel Spill, Nevada Test Site, Nevada, Rev. No.: 0

    SciTech Connect (OSTI)

    Alfred Wickline

    2006-09-01T23:59:59.000Z

    This report presents the data collected during field activities and quarterly soil-gas sampling activities conducted from May 9, 2005, through May 20, 2006, at Corrective Action Unit (CAU) 329, Area 22 Desert Rock Airstrip (DRA) Fuel Spill; Corrective Action Site (CAS) 22-44-01, Fuel Spill. The CAU is located at the DRA, which is located approximately two miles southwest of Mercury, Nevada, as shown in Figure 1-1. Field activities were conducted in accordance with the revised sampling approach outlined in the Addendum to the Closure Report (CR) for CAU 329 (NNSA/NSO, 2005) to support data collection requirements. The previous annual monitoring program for CAU 329 was initiated in August 2000 using soil-gas samples collected from three specific intervals at the DRA-0 and DRA-3 monitoring wells. Results of four sampling events from 2000 through 2003 indicated there is uncertainty in the approach to establish a rate of natural attenuation as specified in ''Streamlined Approach for Environmental Restoration (SAFER) Work Plan for Corrective Action Unit 329: Area 22 Desert Rock Airstrip Fuel Spill, Nevada Test Site, Nevada'' (DOE/NV, 1999). As a result, the Addendum to the CR (NNSA/NSO, 2005) was completed to address this uncertainty by modifying the previous approach. A risk evaluation was added to the scope of the project to determine if the residual concentration of the hazardous constituents of JP4 pose an unacceptable risk to human health or the environment and if a corrective action was required at the site, because the current quarterly monitoring program is not expected to yield a rate constant that could be used effectively to determine a biodegradation rate for total petroleum hydrocarbons (TPH) in less than the initial five years outlined in the CR. Additionally, remediation to the Tier 1 action level for TPH is not practical or technically feasible due to the depth of contamination.

  12. MRIP Operations Team Projects (2012 Funded) Project Name Project Description Project Objectives

    E-Print Network [OSTI]

    MRIP Operations Team Projects (2012 Funded) Project Name Project Description Project Objectives vessel registries to conduct recreational catch and effort surveys. Develop a recreational fishing. Accuracy Funded 2012 Oregon Shore and EstuaryBoat Survey Design Review Develop a new or revised

  13. Western gas sands project. Status report, 1 June-30 June 1980

    SciTech Connect (OSTI)

    Not Available

    1980-01-01T23:59:59.000Z

    Progress of the government-sponsored projects during June 1980, that are directed towards increasing gas production from the low permeability gas sands of the western United States, is summarized. Northwest Exploration declined use of their site for the multi-well experiment; additional sites are being contemplated. Experiments began at Bartlesville Energy Technology Center designed to examine fracture closure and crushing strength of bauxite. At Lawrence Livermore Laboratory, work is progressing on the code to calculate fluid motion in an expanding propagation crack.

  14. Methods of calculating the post-closure performance of high-level waste repositories

    SciTech Connect (OSTI)

    Ross, B. (ed.)

    1989-02-01T23:59:59.000Z

    This report is intended as an overview of post-closure performance assessment methods for high-level radioactive waste repositories and is designed to give the reader a broad sense of the state of the art of this technology. As described here, ''the state of the art'' includes only what has been reported in report, journal, and conference proceedings literature through August 1987. There is a very large literature on the performance of high-level waste repositories. In order to make a review of this breadth manageable, its scope must be carefully defined. The essential principle followed is that only methods of calculating the long-term performance of waste repositories are described. The report is organized to reflect, in a generalized way, the logical order to steps that would be taken in a typical performance assessment. Chapter 2 describes ways of identifying scenarios and estimating their probabilities. Chapter 3 presents models used to determine the physical and chemical environment of a repository, including models of heat transfer, radiation, geochemistry, rock mechanics, brine migration, radiation effects on chemistry, and coupled processes. The next two chapters address the performance of specific barriers to release of radioactivity. Chapter 4 treats engineered barriers, including containers, waste forms, backfills around waste packages, shaft and borehole seals, and repository design features. Chapter 5 discusses natural barriers, including ground water systems and stability of salt formations. The final chapters address optics of general applicability to performance assessment models. Methods of sensitivity and uncertainty analysis are described in Chapter 6, and natural analogues of repositories are treated in Chapter 7. 473 refs., 19 figs., 2 tabs.

  15. Coordinating NRC License Closure/Termination and Army Corps of Engineers FUSRAP Cleanups

    SciTech Connect (OSTI)

    Walter, N. [MACTEC, 511 Congress Street, Portland, ME 04101 (United States); Greene, D. R. [LeBoeuf, Lamb, Greene and MacRae LLP, 225 Asylum Street, Hartford, CT 06103 (United States); Knauerhase, R. K. [Combustion Engineering, 2000 Day Hill Road, CEP 5580-2207, Windsor, CT 06095 (United States)

    2006-07-01T23:59:59.000Z

    Overlapping regulatory cleanup programs present a significant challenge for business entities seeking to close and redevelop properties in an environmentally-appropriate but cost-effective manner. In the nuclear decontamination context, this challenge has been recognized in Memoranda of Understanding ('MOUs') between regulators with overlapping responsibilities seeking to minimize duplicative efforts/costs while fulfilling their respective regulatory obligations. For instance, an MOU between the Army Corps of Engineers (the 'Corps') and the Nuclear Regulatory Commission ('NRC') for coordinating Corps' cleanups under the Formerly Utilized Sites Remedial Action Program ('FUSRAP') and NRC D and D to close and terminate an NRC license was reached in July 2001. Similarly, U.S. Environmental Protection Agency ('EPA') and NRC entered into an MOU in October 2002 addressing the interaction between NRC decontamination and decommissioning ('D and D') oversight and EPA's authority under the Comprehensive Environmental Response, Compensation and Liability Act ('CERCLA') at NRC-licensed sites. Yet, despite these MOU agreements, the simultaneous application of different regulatory programs, differing perspectives on their respective objectives and limited experience in addressing such circumstances often can lead to issues that demand creative solutions. This paper examines the interplay of these regulatory programs, the MOU of the agencies seeking to address their responsibilities under them and the coordination of the cleanups and license closure/termination process under the programs. It also offers technical and practical suggestions and insight to cost-effectively manage such efforts based on experiences with these programs and the regulators and stakeholders involved (at the federal, state and local levels). (authors)

  16. Knowledge based ranking algorithm for comparative assessment of post-closure care needs of closed landfills

    SciTech Connect (OSTI)

    Sizirici, Banu, E-mail: bsy3@case.edu [Case Western Reserve University, Civil Engineering Department, 2104 Adelbert Road, Bingham Bld. Room: 216, Cleveland, OH 44106 (United States); Tansel, Berrin; Kumar, Vivek [Florida International University, Civil and Environmental Engineering Department, Miami, FL (United States)

    2011-06-15T23:59:59.000Z

    Post-closure care (PCC) activities at landfills include cap maintenance; water quality monitoring; maintenance and monitoring of the gas collection/control system, leachate collection system, groundwater monitoring wells, and surface water management system; and general site maintenance. The objective of this study was to develop an integrated data and knowledge based decision making tool for preliminary estimation of PCC needs at closed landfills. To develop the decision making tool, 11 categories of parameters were identified as critical areas which could affect future PCC needs. Each category was further analyzed by detailed questions which could be answered with limited data and knowledge about the site, its history, location, and site specific characteristics. Depending on the existing knowledge base, a score was assigned to each question (on a scale 1-10, as 1 being the best and 10 being the worst). Each category was also assigned a weight based on its relative importance on the site conditions and PCC needs. The overall landfill score was obtained from the total weighted sum attained. Based on the overall score, landfill conditions could be categorized as critical, acceptable, or good. Critical condition indicates that the landfill may be a threat to the human health and the environment and necessary steps should be taken. Acceptable condition indicates that the landfill is currently stable and the monitoring should be continued. Good condition indicates that the landfill is stable and the monitoring activities can be reduced in the future. The knowledge base algorithm was applied to two case study landfills for preliminary assessment of PCC performance.

  17. Advanced recycling and research complexes: A second strategic use for installations on the base closure list

    SciTech Connect (OSTI)

    Walter, D.W.; Kuusinen, T.L.; Beck, J.E.

    1993-05-01T23:59:59.000Z

    Obstacles currently facing the solid waste recycling industry are often related to a lack of public and investor confidence, issues of profitability and liability, and insufficient consumer identification with products made from recycled materials. Resolution of these issues may not be possible without major changes in the way the solid waste recycling business is structured. At the same time, we are faced with opportunities which will not likely recur in our lifetimes: access to educated, well trained work forces; and large tracts of land that are contiguous with metropolitan areas and are developed for heavy industry and transportation. Military installations are being converted to civilian use just in time to serve as important a role in our national resource conservation policy. The future of recycling in North America converges with the future of selected bases on the closure list and takes the form of converting these bases into Advanced Recycling and Research Complexes. The premise is simple: use these strategically-located facilities as industrial parks where a broad range of secondary wastes are separated, refined, or converted and made into new products on site. The wastes would include municipal solid waste (MSW), demolition waste, landscape trimmings, used tires, scrap metal, agricultural waste, food processing waste, and other non-hazardous materials. The park would consist of separation and conversion facilities, research and product standards laboratories, and industries that convert the materials into products and fuels. Energy conversion systems using some waste streams as fuel could be located at the park to supplement energy demands of the industrial operations. The strategic co-location of the resource providers and user industries would minimize transportation costs.

  18. Tank Closure Progress at the Department of Energy's Idaho National Engineering Laboratory Tank Farm Facility

    SciTech Connect (OSTI)

    Lockie, K.A. [U.S. Department of Energy, Idaho Operations Office, Idaho Falls, ID (United States); Suttora, L.C. [U.S. Department of Energy, Washington, D.C. (United States); Quigley, K.D. [CH2M..WG Idaho, LLC, Idaho Falls, ID (United States); Stanisich, N. [Portage Environmental, Inc., Idaho Falls, ID (United States)

    2007-07-01T23:59:59.000Z

    Significant progress has been made at the U.S. Department of Energy (DOE) Idaho National Laboratory (INL) to clean and close emptied radioactive liquid waste storage tanks at the Idaho Nuclear Technology and Engineering Center (INTEC) Tank Farm Facility (TFF). The TFF includes eleven 1,135.6-kL (300,000-gal) underground stainless steel storage tanks and four smaller, 113.5-kL (30,000-gal) stainless steel tanks, along with tank vaults, interconnecting piping, and ancillary equipment. The TFF tanks have historically been used to store a variety of radioactive liquid waste, including wastes associated with past spent nuclear fuel reprocessing. Although four of the large storage tanks remain in use for waste storage, the other seven 1,135.6-kL (300,000-gal) tanks and the four 113.5-kL (30,000-gal) tanks have been emptied of waste and cleaned in preparation of final closure. A water spray cleaning system was developed and deployed to clean internal tank surfaces and remove remaining tank wastes. The cleaning system was effective in removing all but a very small volume of solid residual waste particles. Recent issuance of an Amended Record of Decision (ROD) in accordance with the National Environmental Policy Act, and a Waste Determination complying with Section 3116 of the Ronald W. Reagan National Defense Authorization Act (NDAA) for Fiscal Year 2005, has allowed commencement of grouting activities on the cleaned tanks. In November 2006, three of the 113.5-kL (30,000-gal) tanks were filled with grout to provide long-term stability. It is currently planned that all seven cleaned 1,135.6-kL (300,000-gal) tanks, as well as the four 113.5-kL (30,000-gal) tanks and all associated tank vaults and interconnecting piping, will be stabilized with grout as early as 2008. (authors)

  19. A comparison of LBW and GTAW processes in miniature closure welds

    SciTech Connect (OSTI)

    Knorovsky, G.A.; Fuerschbach, P.W.; Gianoulakis, S.E.; Burchett, S.N.

    1995-07-01T23:59:59.000Z

    When small electronic components with glass-to-metal seals are closure welded, residual stresses developed in the glass are of concern. If these stresses exceed allowable tensile levels` the resulting weld-induced seal failure may cause the entire component to be scrapped or reworked at substantial cost. Conventional wisdom says the best welding process for these applications is that which provides the least heat input, and that Laser Beam Welding (LBW) provides less heat input than Gas Tungsten Arc Welding. (GTAW); however, other concerns such as weld fit-up, part variability, and material weldability can modify the final choice of a welding process. In this paper we compare the characteristic levels of heat input and the residual stresses generated in the glass seals for the two processes (as calculated by 3D Finite Element Analysis) as a function of heat input and travel speed, and contrast some of the other manufacturing decisions that must be made to choose a production process. The geometry chosen is a standing edge corner weld in a cylindrical container about 20 mm diameter by 35 mm tall. Four metal pins are glassed into the part lid. The stresses calculated to result from continuous wave C0{sub 2} LBW are compared with those that result from GTAW. The total energy required by the laser weld is significantly less than for the equivalent size GTA weld. The energy input required for a given size weld is inversely proportional to the travel speed, but approaches a saturation level as the travel speed increases. LBW travel speeds ranging from 10 mm/sec to 50 mm/sec were examined.

  20. Post-Closure Monitoring Report for Corrective Action Unit 339: Area 12 Fleet Operations Steam Cleaning Effluent Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    K. B. Campbell

    2002-09-01T23:59:59.000Z

    The Area 12 Fleet Operations Steam Cleaning Effluent site is located in the southeastern portion of the Area 12 Camp at the Nevada Test Site. This site is identified in the Federal Facility Agreement and Consent Order (1996) as Corrective Action Site (CAS) 12-19-01 and is the only CAS assigned to Corrective Action Unit (CAU) 339. Post-closure sampling and inspection of the site were completed on March 27, 2002. Post-closure monitoring activities were scheduled biennially (every two years) in the Post-Closure Monitoring Plan provided in the Closure Report for CAU 339: Area 12 Fleet Operations Steam Cleaning Effluent, Nevada Test Site (U.S. Department of Energy, Nevada Operations Office [DOEN], 1997). A baseline for the site was established by sampling in 1997. Based on the recommendations from the 1999 post-closure monitoring report (DOE/NV, 1999), samples were collected in 2000, earlier than originally proposed, because the 1999 sample results did not provide the expected decrease in total petroleum hydrocarbon (TPH) concentrations at the site. Sampling results from 2000 (DOE/NV, 2000) and 2001 (DOE/NV, 2001) revealed favorable conditions for natural degradation at the CAU 339 site, but because of differing sample methods and heterogeneity of the soil, data results from 2000 and later were not directly correlated with previous results. Post-closure monitoring activities for 2002 consisted of the following: (1) Soil sample collection from three undisturbed plots (Plots A, B, and C, Figure 2). (2) Sample analysis for TPH as oil and bio-characterization parameters (Comparative Enumeration Assay [CEA] and Standard Nutrient Panel [SNP]). (3) Site inspection to evaluate the condition of the fencing and signs. (4) Preparation and submittal of the Post-Closure Monitoring Report.

  1. Senior projectS corporate Sponsored

    E-Print Network [OSTI]

    Stuart, Josh

    --Professor, Computer Engineering | http://users.soe.ucsc. edu/~larrabee/Site/Professor_Tracy_Larrabee.html Charlie McSenior projectS program corporate Sponsored Partner's Day May 31, 2012 Baskin School of Engineering earning their engineering degree and fulfilling this capstone design sequence. Our students who have

  2. Livingston Campus Geothermal Project The Project

    E-Print Network [OSTI]

    Delgado, Mauricio

    Livingston Campus Geothermal Project The Project: Geothermal power is a cost effective, reliable is a Closed Loop Geothermal System involving the removal and storage of approximately four feet of dirt from the entire Geothermal Field and the boring of 321 vertical holes reaching a depth of 500 feet. These holes

  3. Post-Closure Inspection Report for Corrective Action Unit 407: Roller Coaster RadSafe Area Tonopah Test Range, Nevada, Calendar Year 2001

    SciTech Connect (OSTI)

    K. B. Campbell

    2002-01-01T23:59:59.000Z

    Post-closure monitoring requirements for the Roller Coaster RadSafe Area (Corrective Action Unit [CAU] 407) (Figure 1) are described in Closure Report for Corrective Action Unit 407, Roller Coaster RadSafe Area, Tonopah Test Range, Nevada, report number DOEN-694, October 2001. The Closure Report (CR) was submitted to the Nevada Division of Environmental Protection (NDEP) on April 24,2001. No issues with the post-closure monitoring plan, Section 5 .O, were raised. However, other concerns raised by stakeholders required that the CR be revised. Revision 1 of CR was issued in December of 2001 and was approved by NDEP on January 7,2002. Section 5.2 of the NDEP-approved CR calls for site inspections to be conducted within the first six months following completion of cover construction. Following the first six months, site inspection are to be conducted twice yearly for the next two years. This report provides the results of the six month post-construction site inspection. As stated in Section 5.2 of the CR, Post-closure site inspections at CAU 407 consists of the following: (1) Visual site inspections done twice a year to evaluate the condition of the cover and plant development. (2) Verification that the site is secure and condition of the fence and posted warning signs. (3) Notice of any subsidence, erosion, unauthorized excavation, etc., deficiencies that may compromise the integrity of the unit. (4) Remedy of any deficiencies within 90 days of discovery. (5) Preparation and submittal of an annual report. To meet the fiscal year 2002 post-closure inspection schedule, the first post-closure site inspection was conducted on November 6,2001. The site inspection was conducted after completion of the revegetation activities (October 24,2000) and submittal of revision 0 of the CR (October 31,2001). All site inspections were conducted in accordance with the Post-Closure Inspection requirements stated in revision 0 of the CR. This report includes copies of inspection checklist, photographs, recommendations, and conclusions. The Post-Closure Inspection Checklist is found in Attachment A, a copy of the field notes is found in Attachment By and copies of the inspection photographs are found in Attachment C.

  4. Obesity: An Independent Risk Factor for Insufficient Hemostasis Using the AngioSeal Vascular Closure Device After Antegrade Puncture

    SciTech Connect (OSTI)

    Minko, Peter, E-mail: peterminko@yahoo.com; Katoh, Marcus [University Hospital Saarland, Department of Diagnostic and Interventional Radiology (Germany); Graeber, Stefan [University Hospital Saarland, Institute of Medical Biometry, Epidemiology and Medical Informatics (Germany); Buecker, Arno [University Hospital Saarland, Department of Diagnostic and Interventional Radiology (Germany)

    2012-08-15T23:59:59.000Z

    Purpose: This study was designed to investigate the efficacy of the AngioSeal vascular closure device after antegrade puncture of the femoral artery. Methods: In a prospective study, 120 consecutive patients underwent lower limb vascular intervention by an antegrade access to the common femoral artery (CFA). After intervention, a 6F (n = 88) or an 8F (n = 32) AngioSeal vascular closure device was used to achieve hemostasis. The technical success or the cause of failure was documented. In addition, the coagulation status (platelets, INR, prothrombin time, atrial thromboplastin time (PTT)), hypertonus, locoregional habitus of the groin, body mass index (BMI), presence of calcifications, and history of previous surgical interventions of the CFA were evaluated. Results: Hemostasis was achieved in 97 patients (81%). In 12 patients (10%), persistent bleeding of the puncture site required manual compression. In another nine patients (8%) a kink of the sheath obviated the passage of the collagen plug toward the vessel, and in two patients the anchor dislodged out of the vessel, requiring manual compression. There were no significant differences between the groups of successful and unsuccessful sealing regarding the mean platelets (241 vs. 254 * 10{sup 9}/l; P = 0.86), INR (1.06 vs. 1.02; P = 0.52), prothrombin time (90% vs. 90%; P = 0.86), and PTT (30 vs. 31 s; P = 0.82). However, unsuccessful sealing was more likely in obese patients with an increased BMI (26.6 vs. 28.8 kg/m{sup 2}; P = 0.04). Conclusions: Obesity seems to be an independent risk factor for insufficient sealing using the AngioSeal vascular closure device after antegrade puncture of the CFA. In 8% of our patients, hemostasis could not be achieved due to kink of the flexible sheath.

  5. Theory and Implementation of Nuclear Safety System Codes - Part II: System Code Closure Relations, Validation, and Limitations

    SciTech Connect (OSTI)

    Glenn A Roth; Fatih Aydogan

    2014-09-01T23:59:59.000Z

    This is Part II of two articles describing the details of thermal-hydraulic sys- tem codes. In this second part of the article series, the system code closure relationships (used to model thermal and mechanical non-equilibrium and the coupling of the phases) for the governing equations are discussed and evaluated. These include several thermal and hydraulic models, such as heat transfer coefficients for various flow regimes, two phase pressure correlations, two phase friction correlations, drag coefficients and interfacial models be- tween the fields. These models are often developed from experimental data. The experiment conditions should be understood to evaluate the efficacy of the closure models. Code verification and validation, including Separate Effects Tests (SETs) and Integral effects tests (IETs) is also assessed. It can be shown from the assessments that the test cases cover a significant section of the system code capabilities, but some of the more advanced reactor designs will push the limits of validation for the codes. Lastly, the limitations of the codes are discussed by considering next generation power plants, such as Small Modular Reactors (SMRs), analyz- ing not only existing nuclear power plants, but also next generation nuclear power plants. The nuclear industry is developing new, innovative reactor designs, such as Small Modular Reactors (SMRs), High-Temperature Gas-cooled Reactors (HTGRs) and others. Sub-types of these reactor designs utilize pebbles, prismatic graphite moderators, helical steam generators, in- novative fuel types, and many other design features that may not be fully analyzed by current system codes. This second part completes the series on the comparison and evaluation of the selected reactor system codes by discussing the closure relations, val- idation and limitations. These two articles indicate areas where the models can be improved to adequately address issues with new reactor design and development.

  6. Corrective Action Decision Document/Closure Report for Corrective Action Unit 567: Miscellaneous Soil Sites Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Matthews, Patrick

    2014-12-01T23:59:59.000Z

    This Corrective Action Decision Document/Closure Report presents information supporting the closure of Corrective Action Unit (CAU) 567: Miscellaneous Soil Sites, Nevada National Security Site, Nevada. The purpose of this Corrective Action Decision Document/Closure Report is to provide justification and documentation supporting the recommendation that no further corrective action is needed for CAU 567 based on the implementation of the corrective actions. The corrective actions implemented at CAU 567 were developed based on an evaluation of analytical data from the CAI, the assumed presence of COCs at specific locations, and the detailed and comparative analysis of the CAAs. The CAAs were selected on technical merit focusing on performance, reliability, feasibility, safety, and cost. The implemented corrective actions meet all requirements for the technical components evaluated. The CAAs meet all applicable federal and state regulations for closure of the site. Based on the implementation of these corrective actions, the DOE, National Nuclear Security Administration Nevada Field Office provides the following recommendations: • No further corrective actions are necessary for CAU 567. • The Nevada Division of Environmental Protection issue a Notice of Completion to the DOE, National Nuclear Security Administration Nevada Field Office for closure of CAU 567. • CAU 567 be moved from Appendix III to Appendix IV of the FFACO.

  7. Closure Report for Corrective Action Unit 357: Mud Pits and Waste Dump, Nevada Test Site, Nevada, Rev. No.: 0

    SciTech Connect (OSTI)

    Laura A. Pastor

    2005-04-01T23:59:59.000Z

    This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 357: Mud Pits and Waste Dump, Nevada Test Site (NTS), Nevada. The CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada, U.S. Department of Energy (DOE), and the U.S. Department of Defense (FFACO, 1996). Corrective Action Unit 357 is comprised of 14 Corrective Action Sites (CASs) located in Areas 1, 4, 7, 8, 10, and 25 of the NTS (Figure 1-1). The NTS is located approximately 65 miles (mi) northwest of Las Vegas, Nevada. Corrective Action Unit 357 consists of 11 CASs that are mud pits located in Areas 7, 8, and 10. The mud pits were associated with drilling activities conducted on the NTS in support of the underground nuclear weapons testing. The remaining three CASs are boxes and pipes associated with Building 1-31.2el, lead bricks, and a waste dump. These CAS are located in Areas 1, 4, and 25, respectively. The following CASs are shown on Figure 1-1: CAS 07-09-02, Mud Pit; CAS 07-09-03, Mud Pit; CAS 07-09-04, Mud Pit; CAS 07-09-05, Mud Pit; CAS 08-09-01, Mud Pit; CAS 08-09-02, Mud Pit; CAS 08-09-03, Mud Pit; CAS 10-09-02, Mud Pit; CAS 10-09-04, Mud Pit; CAS 10-09-05, Mud Pit; CAS 10-09-06, Mud Pit, Stains, Material; CAS 01-99-01, Boxes, Pipes; CAS 04-26-03, Lead Bricks; and CAS 25-15-01, Waste Dump. The purpose of the corrective action activities was to obtain analytical data that supports the closure of CAU 357. Environmental samples were collected during the investigation to determine whether contaminants exist and if detected, their extent. The investigation and sampling strategy was designed to target locations and media most likely to be contaminated (biased sampling). A general site conceptual model was developed for each CAS to support and guide the investigation as outlined in the Streamlined Approach for Environmental Restoration (SAFER) Plan (NNSA/NSO, 2003b). This CR summarizes the results of corrective action activities, provides the data confirming the selection of corrective actions, and provides documentation of the completed closure activities conducted in accordance with the SAFER Plan (NNSA/NSO, 2003b). A brief description of the CAU and associated CASs is provided in the following section. A more detailed history of each CAS is provided in the SAFER Plan for CAU 357 (NNSA/NSO, 2003b).

  8. Closure Report for Corrective Action Unit 356: Mud Pits and Disposal Sites, Nevada Test Site, Nevada with Errata Sheet

    SciTech Connect (OSTI)

    NNSA /NV

    2002-11-12T23:59:59.000Z

    This Closure Report (CR) has been prepared for Corrective Action Unit (CAU) 356, Mud Pits and Disposal Sites, in accordance with the Federal Facility Agreement and Consent Order. This CAU is located in Areas 3 and 20 of the Nevada Test Site (NTS) approximately 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 356 consists of seven Corrective Action Sites (CASs): 03-04-01, Area 3 Change House Septic System; 03-09-01, Mud Pit Spill Over; 03-09-03, Mud Pit; 03-09-04, Mud Pit; 03-09-05, Mud Pit; 20-16-01, Landfill; and 20-22-21, Drums. This CR identifies and rationalizes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Operations Office's (NNSA/NV's) recommendation that no further corrective action and closure in place is deemed necessary for CAU 356. This recommendation is based on the results of field investigation/closure activities conducted November 20, 2001, through January 3, 2002, and March 11 to 14, 2002. These activities were conducted in accordance with the Streamlined Approach for Environmental Restoration Plan (SAFER) for CAU 356. For CASs 03-09-01, 03-09-03, 20-16-01, and 22-20-21, analytes detected in soil during the corrective action investigation were evaluated against Preliminary Action Levels (PALs) and it was determined that no Contaminants of Concern (COCs) were present. Therefore, no further action is necessary for the soil at these CASs. For CASs 03-04-01, 03-09-04, and 03-09-05, analytes detected in soil during the corrective action investigation were evaluated against PALs and identifies total petroleum hydrocarbons (TPHs) and radionuclides (i.e., americium-241 and/or plutonium 239/240) as COCs. The nature, extent, and concentration of the TPH and radionuclide COCs were bounded by sampling and shown to be relatively immobile. Therefore, closure in place is recommended for these CASs in CAU 356. Further, use restrictions are not required at this CAU beyond the NTS use restrictions identified in the SAFER Plan. In addition, the septic tank associated with CAU 356 will be closed in accordance with applicable regulations.

  9. Extinction of the N=20 neutron-shell closure for 32Mg examined by direct mass measurements

    E-Print Network [OSTI]

    A. Chaudhuri; C. Andreoiu; T. Brunner; U. Chowdhury; S. Ettenauer; A. T. Gallant; G. Gwinner; A. A. Kwiatkowski; A. Lennarz; D. Lunney; T. D. Macdonald; B. E. Schultz; M. C. Simon; V. V. Simon; J. Dilling

    2013-10-09T23:59:59.000Z

    The 'island of inversion' around $^{32}$Mg is one of the most important paradigm for studying the disappearance of the stabilizing 'magic' of a shell closure. We present the first Penning-trap mass measurements of the exotic nuclides $^{29-31}$Na and $^{30-34}$Mg, which allow a precise determination of the empirical shell gap for $^{32}$Mg. The new value of 1.10(3) MeV is the lowest observed shell gap for any nuclide with a canonical magic number.

  10. UMTRA Surface Project management action process document: Final. Revision 2

    SciTech Connect (OSTI)

    NONE

    1996-06-01T23:59:59.000Z

    Title 1 of the UMTRCA authorized the DOE to undertake remedial actions at these designed sites and associated vicinity properties (VP), which contain uranium mill tailings and other residual radioactive materials (RRM) derived from the processing sites. Title 2 of the UMTRCA addresses uranium mill sites that were licensed at the time the UMTRCA was enacted. Cleanup of these Title 2 sites is the responsibility of the licensees. The cleanup of the Title 1 sites has been split into two separate projects: the Surface Project, which deals with the mill buildings, tailings, and contaminated soils at the sites and VPs; and the Ground Water Project, which is limited to the contaminated ground water at the sites. This management action process (MAP) document discusses the Uranium Mill Tailings Remedial Action (UMTRA) Surface Project. Since its inception through March 1996, the Surface Project (hereinafter called the Project) has cleaned up 16 of the 24 designated processing sites and approximately 5,000 VPs, reducing the risk to human health and the environment posed by the uranium mill tailings. Two of the 24 sites, Belfield and Bowman, North Dakota, will not be remediated at the request of the state, reducing the total number of sites to 22. By the start of FY1998, the remaining 6 processing sites and associated VPs will be cleaned up. The remedial action activities to be funded in FY1998 by the FY1998 budget request are remediation of the remaining Grand Junction, Colorado, VPs; closure of the Cheney disposal cell in Grand Junction, Colorado; and preparation of the completion reports for 4 completed sites.

  11. Cost Estimating for Decommissioning of a Plutonium Facility--Lessons Learned From The Rocky Flats Building 771 Project

    SciTech Connect (OSTI)

    Stevens, J. L.; Titus, R.; Sanford, P. C.

    2002-02-26T23:59:59.000Z

    The Rocky Flats Closure Site is implementing an aggressive approach in an attempt to complete Site closure by 2006. The replanning effort to meet this goal required that the life-cycle decommissioning effort for the Site and for the major individual facilities be reexamined in detail. As part of the overall effort, the cost estimate for the Building 771 decommissioning project was revised to incorporate both actual cost data from a recently-completed similar project and detailed planning for all activities. This paper provides a brief overview of the replanning process and the original estimate, and then discusses the modifications to that estimate to reflect new data, methods, and planning rigor. It provides the new work breakdown structure and discusses the reasons for the final arrangement chosen. It follows with the process used to assign scope, cost, and schedule elements within the new structure, and development of the new code of accounts. Finally, it describes the project control methodology used to track the project, and provides lessons learned on cost tracking in the decommissioning environment.

  12. Information Technology Project Management

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

    2012-12-03T23:59:59.000Z

    The Order provides program and project management direction for the acquisition and management of IT projects, investments, and initiatives. Cancels DOE G 200.1-1. Admin Chg 1, dated 1-16-2013, cancels DOE O 415.1.

  13. The 4-H Project

    E-Print Network [OSTI]

    Howard, Jeff W.

    2005-05-10T23:59:59.000Z

    As a 4-H volunteer, you will find that projects are useful tools for teaching a wide variety of skills to young people. This publication will help you plan and evaluate 4-H learning projects....

  14. Information Technology Project Management

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

    2012-12-03T23:59:59.000Z

    The Order provides program and project management direction for the acquisition and management of IT projects, investments, and initiatives. Cancels DOE G 200.1-1. Admin Chg 1 approved 1-16-2013.

  15. GHPsRUS Project

    SciTech Connect (OSTI)

    Battocletti, Liz

    2013-07-09T23:59:59.000Z

    The GHPsRUS Project's full name is "Measuring the Costs and Benefits of Nationwide Geothermal Heat Pump Deployment." The dataset contains employment and installation price data collected by four economic surveys: (1)GHPsRUS Project Manufacturer & OEM Survey, (2) GHPsRUS Project Geothermal Loop Survey, (3) GHPsRUS Project Mechanical Equipment Installation Survey, and (4) GHPsRUS Geothermal Heat Pump Industry Survey

  16. GHPsRUS Project

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

    Battocletti, Liz

    The GHPsRUS Project's full name is "Measuring the Costs and Benefits of Nationwide Geothermal Heat Pump Deployment." The dataset contains employment and installation price data collected by four economic surveys: (1)GHPsRUS Project Manufacturer & OEM Survey, (2) GHPsRUS Project Geothermal Loop Survey, (3) GHPsRUS Project Mechanical Equipment Installation Survey, and (4) GHPsRUS Geothermal Heat Pump Industry Survey

  17. WIPP Projects Interative Map

    Broader source: Energy.gov [DOE]

    View WIPP Projects in a larger map. To report corrections, please email WeatherizationInnovation@ee.doe.gov.

  18. Bacteria TMDL Projects 

    E-Print Network [OSTI]

    Wythe, Kathy

    2007-01-01T23:59:59.000Z

    of the projects are listed below. ? Peach CreekWater Quality Improvement Project ? Monitoring and Educational Programs Focused on Bacteria and Nutrient Runoff on Dairy Operations in the LeonWatershed ? Development of the Plum CreekWPP ? Impact of Proper... Star Healthy Streams * ? Environmental Management of Grazing Lands * *TWRI-managed projects More information on the initiative is available at www.tsswcb.state.tx.us/managementprogram/ initiatives/bacteria. Bacteria Projects Across the State...

  19. Kansas Advanced Semiconductor Project

    SciTech Connect (OSTI)

    Baringer, P.; Bean, A.; Bolton, T.; Horton-Smith, G.; Maravin, Y.; Ratra, B.; Stanton, N.; von Toerne, E.; Wilson, G.

    2007-09-21T23:59:59.000Z

    KASP (Kansas Advanced Semiconductor Project) completed the new Layer 0 upgrade for D0, assumed key electronics projects for the US CMS project, finished important new physics measurements with the D0 experiment at Fermilab, made substantial contributions to detector studies for the proposed e+e- international linear collider (ILC), and advanced key initiatives in non-accelerator-based neutrino physics.

  20. HWMA/RCRA Closure Plan for the TRA/MTR Warm Waste System Voluntary Consent Order SITE-TANK-005 Tank System TRA-007

    SciTech Connect (OSTI)

    K. Winterholler

    2007-01-30T23:59:59.000Z

    This Hazardous Waste Management Act/Resource Conservation and Recovery Act Closure Plan was developed for portions of the Test Reactor Area/Materials Test Reactor Warm Waste System located in the Materials Test Reactor Building (TRA-603) at the Reactor Technology Complex, Idaho National Laboratory Site, to meet a further milestone established under Voluntary Consent Order Action Plan SITE-TANK-005 for the Tank System TRA-007. The reactor drain tank and canal sump to be closed are included in the Test Reactor Area/Materials Test Reactor Warm Waste System. The reactor drain tank and the canal sump will be closed in accordance with the interim status requirements of the Hazardous Waste Management Act/Resource Conservation and Recovery Act as implemented by the Idaho Administrative Procedures Act 58.01.05.009 and Code of Federal Regulations 265. This closure plan presents the closure performance standards and methods for achieving those standards.

  1. High Performance Zero-Bleed CLSM/Grout Mixes for High-Level Waste Tank Closures Strategic Research and Development - FY99 Report

    SciTech Connect (OSTI)

    Langton, C.A.

    2000-08-11T23:59:59.000Z

    The overall objective of this program, SRD-99-08, was to design and test suitable materials, which can be used to close high-level waste tanks at SRS. Fill materials can be designed to perform several functions including chemical stabilization and/or physical encapsulation of incidental waste so that the potential for transport of contaminants into the environment is reduced. Also they are needed to physically stabilize the void volume in the tanks to prevent/minimize future subsidence and inadvertent intrusion. The intent of this work was to develop a zero-bleed soil CLSM (ZBS-CLSM) and a zero-bleed concrete mix (ZBC) which meet the unique placement and stabilization/encapsulation requirements for high-level waste tank closures. These mixes in addition to the zero-bleed CLSM mixes formulated for closure of Tanks 17-F and 20-F provide design engineers with a suite of options for specifying materials for future tank closures.

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

    SciTech Connect (OSTI)

    Mark Burmeister

    2007-09-01T23:59:59.000Z

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

  3. Corrective Action Decision Document/Closure Report for Corrective Action Unit 370: T-4 Atmospheric Test Site, Nevada Test Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Patrick Matthews

    2009-05-01T23:59:59.000Z

    This Corrective Action Decision Document/Closure Report has been prepared for Corrective Action Unit (CAU) 370, T-4 Atmospheric Test Site, located in Area 4 at the Nevada Test Site, Nevada, in accordance with the Federal Facility Agreement and Consent Order (FFACO). Corrective Action Unit 370 is comprised of Corrective Action Site (CAS) 04-23-01, Atmospheric Test Site T-4. The purpose of this Corrective Action Decision Document/Closure Report is to provide justification and documentation supporting the recommendation that no further corrective action is needed for CAU 370 due to the implementation of the corrective action of closure in place with administrative controls. To achieve this, corrective action investigation (CAI) activities were performed from June 25, 2008, through April 2, 2009, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 370: T-4 Atmospheric Test Site and Record of Technical Change No. 1.

  4. RIVER PROTECTION PROJECT SYSTEM PLAN

    SciTech Connect (OSTI)

    CERTA PJ

    2008-07-10T23:59:59.000Z

    The U.S. Department of Energy (DOE), Office of River Protection (ORP) manages the River Protection Project (RPP). The RPP mission is to retrieve and treat Hanford's tank waste and close the tank farms to protect the Columbia River. As a result, the ORP is responsible for the retrieval, treatment, and disposal of the approximately 57 million gallons of radioactive waste contained in the Hanford Site waste tanks and closure of all the tanks and associated facilities. The previous revision of the System Plan was issued in September 2003. ORP has approved a number of changes to the tank waste treatment strategy and plans since the last revision of this document, and additional changes are under consideration. The ORP has established contracts to implement this strategy to establish a basic capability to complete the overall mission. The current strategy for completion of the mission uses a number of interrelated activities. The ORP will reduce risk to the environment posed by tank wastes by: (1) Retrieving the waste from the single-shell tanks (SST) to double-shell tanks (DST) for treatment and disposal; (2) Constructing and operating the WTP, which will safely treat all of the high-level waste (HLW) and about half of the low-activity waste (LAW) contained in the tank farms, and maximizing its capability and capacity; (3) Developing and deploying supplemental treatment capability or a second WTP LAW Facility that can safely treat about half of the LAW contained in the tank farms; (4) Developing and deploying treatment and packaging capability for transuranic (TRU) tank waste for shipment to and disposal at the Waste Isolation Pilot Plant (WIPP); (5) Deploying interim storage capacity for the immobilized HLW and shipping that waste to Yucca Mountain for disposal; (6) Operating the Integrated Disposal Facility for the disposal of immobilized LAW, along with the associated secondary waste, (7) Closing the SST and DST tank farms, ancillary facilities, and al1 waste management and treatment facilities, (8) Developing and implementing technical solutions to mitigate the impact from substantial1y increased estimates of Na added during the pretreatment of the tank waste solids, This involves a combination of: (1) refining or modifying the flowsheet to reduce the required amount of additional sodium, (2) increasing the overall LAW vitrification capacity, (3) increasing the incorporation of sodium into the LAW glass, or (4) accepting an increase in mission duration, ORP has made and continues to make modifications to the WTP contract as needed to improve projected plant performance and address known or emerging risks, Key elements of the implementation of this strategy are included within the scope of the Tank Operations Contract, currently in procurement Since 2003, the ORP has conducted over 30 design oversight assessments of the Waste Treatment and Immobilization Plant (WTP). The estimated cost at completion has increased and the schedule for construction and commissioning of the WTP has extended, The DOE, Office of Environmental Management (EM), sanctioned a comprehensive review of the WTP flowsheet, focusing on throughput. In 2005, the TFC completed interim stabilization of the SSTs and as of March 2007, has completed the retrieval of seven selected SSTs. Demonstration of supplemental treatment technologies continues. The ongoing tank waste retrieval experience, progress with supplemental treatment technologies, and changes in WTP schedule led to the FY 2007 TFC baseline submittal in November 2006. The TFC baseline submittal was developed before the WTP schedule was fully understood and approved by ORP, and therefore reflects an earlier start date for the WTP facilities. This System Plan is aligned with the current WTP schedule with hot commissioning beginning in 2018 and full operations beginning in 2019. Major decisions regarding the use of supplemental treatment and the associated technology, the ultimate needed capacity, and its relationship to the WTP have not yet been finalized. This System Plan assumes that the outcome of

  5. Product Guide Project Standard and Project Professional

    E-Print Network [OSTI]

    Narasayya, Vivek

    ................................................................................................................................................................6 Manage Projects and Programs, or other intellectual property that are the subject matter of this document. #12;Table of Contents .......................................................................................................9 Make It Yours ­ Personalize the Ribbon

  6. US DOE-AECL cooperative program for development of high-level radioactive waste container fabrication, closure, and inspection techniques

    SciTech Connect (OSTI)

    Russell, E.W.

    1990-06-01T23:59:59.000Z

    The US Department of Energy (DOE) and Atomic Energy of Canada Limited (AECL) plan to initiate a cooperative research program on development of manufacturing processes for high-level radioactive waste containers. This joint program will benefit both countries in the development of processes for the fabrication, final closure in a hot-cell, and certification of the containers. Program activity objectives can be summarized as follows: to support the selection of suitable container fabrication, final closure, and inspection techniques for the candidate materials and container designs that are under development or are being considered in the US and Canadian repository programs; and to investigate these techniques for alternate materials and/or container designs, to be determined in future optimization studies relating to long-term performance of the waste packages. The program participants will carry out this work in a conditional phased approach, and the scope of work for subsequent years will evolve subject to developments in earlier years. The overall term of this cooperative program is planned to run roughly three years. 5 refs., 2 tabs.

  7. Closure Report for Corrective Action Unit 425: Area 9 Main Lake Construction Debris Disposal Area, Tonopah Test Range, Nevada

    SciTech Connect (OSTI)

    K. B. Campbell

    2003-03-01T23:59:59.000Z

    Corrective Action Unit (CAU) 425 is located on the Tonopah Test Range, approximately 386 kilometers (240 miles) northwest of Las Vegas, Nevada. CAU 425 is listed in the Federal Facility Agreement and Consent Order (FFACO, 1996) and is comprised of one Corrective Action Site (CAS). CAS 09-08-001-TA09 consisted of a large pile of concrete rubble from the original Hard Target and construction debris associated with the Tornado Rocket Sled Tests. CAU 425 was closed in accordance with the FFACO and the Nevada Division of Environmental Protection-approved Streamlined Approach for Environmental Restoration Plan for CAU 425: Area 9 Main Lake Construction Debris Disposal Area, Tonopah Test Range, Nevada (U.S. Department of Energy, Nevada Operations Office, 2002). CAU 425 was closed by implementing the following corrective actions: The approved corrective action for this unit was clean closure. Closure activities included: (1) Removal of all the debris from the site. (2) Weighing each load of debris leaving the job site. (3) Transporting the debris to the U.S. Air Force Construction Landfill for disposal. (4) Placing the radioactive material in a U.S. Department of Transportation approved container for proper transport and disposal. (5) Transporting the radioactive material to the Nevada Test Site for disposal. (6) Regrading the job site to its approximate original contours/elevation.

  8. Closure Report for Corrective Action Unit 262: Area 25 Septic Systems and Underground Discharge Point, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    D. S. Tobiason

    2003-07-01T23:59:59.000Z

    This Closure Report (CR) documents the activities undertaken to close Corrective Action Unit (CAU) 262: Area 25 Septic Systems and Underground Discharge Point, in accordance with the Federal Facility Agreement and Consent Order (FFACO) of 1996. Site closure was performed in accordance with the Nevada Division of Environmental Protection (NDEP)-approved Corrective Action Plan (CAP) for CAU 262 (U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office [NNSA/NV, 2002a]). CAU 262 is located at the Nevada Test Site (NTS) approximately 105 kilometers (65 miles) northwest of Las Vegas, Nevada. CAU 262 consists of the following nine Corrective Action Sites (CASs) located in Area 25 of the NTS: CAS 25-02-06, Underground Storage tank CAS 25-04-06, Septic Systems A and B CAS 25-04-07, Septic System CAS 25-05-03, Leachfield CAS 25-05-05, Leachfield CAS 25-05-06, Leachfield CAS 25-05-08, Radioactive Leachfield CAS 25-05-12, Leachfield CAS 25-51-01, Dry Well.

  9. Corrective Action Decision Document/Closure Report for Corrective Action Unit 383: Area E-Tunnel Sites, Nevada Test Site

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2010-03-15T23:59:59.000Z

    This Corrective Action Decision Document/Closure Report (CADD/CR) was prepared by the Defense Threat Reduction Agency (DTRA) for Corrective Action Unit (CAU) 383, Area 12 E-Tunnel Sites, which is the joint responsibility of DTRA and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This CADD/CR is consistent with the requirements of the Federal Facility Agreement and Consent Order (FFACO) agreed to by the State of Nevada, the DOE, and the U.S. Department of Defense. Corrective Action Unit 383 is comprised of three Corrective Action Sites (CASs) and two adjacent areas: • CAS 12-06-06, Muckpile • CAS 12-25-02, Oil Spill • CAS 12-28-02, Radioactive Material • Drainage below the Muckpile • Ponds 1, 2, and 3 The purpose of this CADD/CR is to provide justification and documentation to support the recommendation for closure with no further corrective action, by placing use restrictions at the three CASs and two adjacent areas of CAU 383.

  10. State of the art design: A closure system for the largest hazardous waste landfill at the Savannah River Site

    SciTech Connect (OSTI)

    Bartlett, S.F.; Serrato, M.G.; McMullin, S.R.

    1992-12-31T23:59:59.000Z

    This paper discusses the cover system proposed for a 55-acre, hazardous waste closure of the sanitary landfill at the Savannah River Site, near Aiken, South Carolina. The proposed cover system has been designed to accommodate a significant amount of post-closure settlement while maintaining a permeability of 1 {times} 10{sup {minus}7} cm/s or less throughout its 30-year, regulatory lifetime. A composite cover consisting of a geomembrane (GM) underlain by a geosynthetic clay liner (GCL) was selected because of its extremely low permeability, ability to elongate without tearing, and capacity to ``self-heal`` if punctured. These characteristics will enable the cover system to accommodate differential settlement without cracking or tearing, this providing long-term protection with minimal maintenance. Also, to improve the ability of the cover system to span voids that may develop in the underlying waste, a geogrid has been included in the foundation layer. A gas vent layer has been included to allow for the safe collection and venting of landfill gases.

  11. State of the art design: A closure system for the largest hazardous waste landfill at the Savannah River Site

    SciTech Connect (OSTI)

    Bartlett, S.F.; Serrato, M.G.; McMullin, S.R.

    1992-01-01T23:59:59.000Z

    This paper discusses the cover system proposed for a 55-acre, hazardous waste closure of the sanitary landfill at the Savannah River Site, near Aiken, South Carolina. The proposed cover system has been designed to accommodate a significant amount of post-closure settlement while maintaining a permeability of 1 [times] 10[sup [minus]7] cm/s or less throughout its 30-year, regulatory lifetime. A composite cover consisting of a geomembrane (GM) underlain by a geosynthetic clay liner (GCL) was selected because of its extremely low permeability, ability to elongate without tearing, and capacity to self-heal'' if punctured. These characteristics will enable the cover system to accommodate differential settlement without cracking or tearing, this providing long-term protection with minimal maintenance. Also, to improve the ability of the cover system to span voids that may develop in the underlying waste, a geogrid has been included in the foundation layer. A gas vent layer has been included to allow for the safe collection and venting of landfill gases.

  12. 1-D closure models for slender 3-D viscoelastic free jets: von Karman flow geometry and elliptical cross section

    SciTech Connect (OSTI)

    Bechtel, S.E.; Forest, M.G.; Holm, D.D.; Lin, K.J.

    1988-01-01T23:59:59.000Z

    In this paper we derive one space dimensional, reduced systems of equations (1-D closure models) for viscoelastic free jets. We begin with the three-dimensional system of conservation laws and a Maxwell-Jeffreys constitutive law for an incompressible viscoelastic fluid. First, we exhibit exact truncations to a finite, closed system of 1-D equations based on classical velocity assumptions of von Karman. Next, we demonstrate that the 3-D free surface boundary conditions overconstrain these truncated systems, so that only a very limited class of solutions exist. We then proceed to derive approximate 1-D closure theories through a slender jet asymptotic scaling, combined with appropriate definitions of velocity, pressure and stress unknowns. Our nonaxisymmetric 1-D slender jet models incorporate the physical effects of inertia, viscoelasticity (viscosity, relaxation and retardation), gravity, surface tension, and properties of the ambient fluid, and include shear stresses and time dependence. Previous special 1-D slender jet models correspond to the lowest order equations in the present asymptotic theory by an a posteriori suppression to leading order of some of these effects, and a reduction to axisymmetry. Solutions of the lowest order system of equations in this asymptotic analysis are presented: For the special cases of elliptical inviscid and Newtonian free jets, subject to the effects of surface tension and gravity, our model predicts oscillation of the major axis of the free surface elliptical cross section between perpendicular directions with distance down the jet, and drawdown of the cross section, in agreement with observed behavior. 15 refs.

  13. OREGON STATE UNIVERSITY (OSU) TRAINING RESEARCH ISOTOPE GENERAL ATOMICS (TRIGA) OVERPACK CLOSURE WELDING PROCESS PARAMETER DEVELOPMENT & QUALIFICATION

    SciTech Connect (OSTI)

    CANNELL, G.R.

    2006-09-11T23:59:59.000Z

    Spent Nuclear Fuel (SNF) from the Oregon State University (OSU) TRIGA{reg_sign} Reactor is currently being stored in thirteen 55-gallon drums at the Hanford Site's low-level burial grounds. This fuel is soon to be retrieved from buried storage and packaged into new containers (overpacks) for interim storage at the Hanford Interim Storage Area (ISA). One of the key activities associated with this effort is final closure of the overpack by welding. The OSU fuel is placed into an overpack, a head inserted into the overpack top, and welded closed. Weld quality, for typical welded fabrication, is established through post-weld testing and nondestructive examination (NDE); however, in this case, once the SNF is placed into the overpack, routine testing and NDE are not feasible. An alternate approach is to develop and qualify the welding process/parameters, demonstrate beforehand that they produce the desired weld quality, and then verify parameter compliance during production welding. Fluor engineers have developed a Gas Tungsten Arc Welding (GTAW) technique and parameters, demonstrating that weld quality requirements for closure of packaged SNF overpacks are met, using this alternate approach. The following reviews the activities performed for this development and qualification effort.

  14. On the Zariski closure of a germ of totally geodesic complex submanifold on a subvariety of a

    E-Print Network [OSTI]

    Mok, Ngaiming

    geometry is the Gauss map. Ein [Ei, 1982] proved that the Gauss map of a linearly non-degenerate projective-geometric terms, generic finiteness of the Gauss map on a lin- early non-degenerate projective submanifold W Pn. The projective second fundamental form is on the one hand by definition determined by the canonical projective

  15. Fall Semiannual Report for the HWMA/RCRA Post Closure Permit for the INTEC Waste Calcining Facility at the INL Site

    SciTech Connect (OSTI)

    D. F. Gianotto

    2007-01-12T23:59:59.000Z

    The Waste Calcining Facility (WCF) is located at the Idaho Nuclear Technology and Engineering Center. In 1998, the WCF was closed under an approved Hazardous Waste Management Act/Resource Conservation and Recovery Act (HWMA/RCRA) Closure Plan. Vessels and spaces were grouted and then covered with a concrete cap. The Idaho Department of Environmental Quality issued a final HWMA/RCRA post-closure permit on September 15, 2003, with an effective date of October 16, 2003. This permit sets forth procedural requirements for groundwater characterization and monitoring, maintenance, and inspections of the WCF to ensure continued protection of human health and the environment.

  16. Corrective Action Decision Document/Closure Report for Corrective Action Unit 570: Area 9 Yucca Flat Atmospheric Test Sites, Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Matthews, Patrick

    2013-11-01T23:59:59.000Z

    This Corrective Action Decision Document/Closure Report presents information supporting the closure of Corrective Action Unit (CAU) 570: Area 9 Yucca Flat Atmospheric Test Sites, Nevada National Security Site, Nevada. This complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management. The purpose of the CADD/CR is to provide justification and documentation supporting the recommendation that no further corrective action is needed.

  17. Post-Closure Monitoring Report for Corrective Action Unit 339: Area 12 Fleet Operations Steam Cleaning Discharge Area Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    A. T. Urbon

    2001-08-01T23:59:59.000Z

    The Area 12 Fleet Operations Steam Cleaning site is located in the southeast portion of the Area 12 Camp at the Nevada Test Site (Figure 1). This site is identified in the Federal Facility Agreement and Consent Order (FFACO, 1996) as Corrective Action Site (CAS) 12-19-01 and is the only CAS assigned to Corrective Action Unit (CAU) 339. Post-closure sampling and inspection of the site were completed on March 23, 2001. Because of questionable representativeness and precision of the results, the site was resampled on June 12, 2001. Post-closure monitoring activities were scheduled biennially (every two years) in the Post-Closure Monitoring Plan provided in the December 1997 Closure Report for CAU 339: Area 12 Fleet Operations Steam Cleaning Discharge Area, Nevada Test Site (U.S. Department of Energy, Nevada Operations Office [DOE/NV], 1997). If after six years the rate of degradation appears to be so slow that the greatest concentration of total petroleum hydrocarbons (TPH) present at the site would not decay within 30 years of the site closure, the site will be reevaluated with consideration to enriching the impacted soil at the site to enhance the degradation process. A baseline for the site was established by sampling in 1997. Based on the recommendations from the 1999 post-closure monitoring report, samples were collected in 2000, earlier than originally proposed, because the 1999 sample results did not provide the expected decrease in TPH concentrations at the site. Sampling results from 2000 revealed favorable conditions for natural degradation at the CAU 339 site, but because of differing sample methods and heterogeneity of the soil, the data results from 2000 were not directly correlated with previous results. Post-closure monitoring activities for 2001 consisted of the following: Soil sample collection from three undisturbed plots (Plots A, B, and C, Figure 2); Sample analysis for TPH as oil and bio-characterization parameters (Comparative Enumeration Assay [CEA] and Standard Nutrient Panel [SNP]); Site inspection to evaluate the condition of the fencing and signs; and Preparation and submittal of the Post-Closure Monitoring Report.

  18. Closure Letter Report for Corrective Action Unit 496: Buried Rocket Site - Antelope Lake

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2007-05-01T23:59:59.000Z

    A Streamlined Approach for Environmental Restoration (SAFER) Plan for investigation and closure of CAU 496, Corrective Action Site (CAS) TA-55-008-TAAL (Buried Rocket), at the Tonopah Test Range (TTR), was approved by the Nevada Department of Environmental Protection (NDEP) on July 21,2004. Approval to transfer CAS TA-55-008-TAAL from CAU 496 to CAU 4000 (No Further Action Sites) was approved by NDEP on December 21, 2005, based on the assumption that the rocket did not present any environmental concern. The approval letter included the following condition: ''NDEP understands, from the NNSA/NSO letter dated November 30,2005, that a search will be conducted for the rocket during the planned characterization of other sites at the Tonopah Test Range and, if found, the rocket will be removed as a housekeeping measure''. NDEP and U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office personnel located the rocket on Mid Lake during a site visit to TTR, and a request to transfer CAS TA-55-008-TAAL from CAU 4000 back to CAU 496 was approved by NDEP on September 11,2006. CAS TA-55-008-TAAL was added to the ''Federal Facility Agreement and Consent Order'' of 1996, based on an interview with a retired TTR worker in 1993. The original interview documented that a rocket was launched from Area 9 to Antelope Lake and was never recovered due to the high frequency of rocket tests being conducted during this timeframe. The interviewee recalled the rocket being an M-55 or N-55 (the M-50 ''Honest John'' rocket was used extensively at TTR from the 1960s to early 1980s). A review of previously conducted interviews with former TTR personnel indicated that the interviewees confused information from several sites. The location of the CAU 496 rocket on Mid Lake is directly south of the TTR rocket launch facility in Area 9 and is consistent with information gathered on the lost rocket during recent interviews. Most pertinently, an interview in 2005 with a former TTR range manager recalled a lost rocket that possibly contained a depleted uranium ballast in an inert warhead. The interviewee confirmed that the last tracking coordinate for the rocket indicated it was lost in an area south of Area 9 near the l T R range coordinates X = 6,614.57 feet (ft) and Y = -20,508.79 ft. These coordinates correspond to a location approximately 2,295 ft northeast of the Mid Target, on Mid Lake. CAS TA-55-008-TAAL was removed from CAU 496 before the SAFER investigation could be completed, and before the new information could be evaluated and the conceptual site model assumptions confirmed.

  19. John Day Watershed Restoration Projects, annual report 2003.

    SciTech Connect (OSTI)

    Brown, Linda (Confederated Tribes of the Warm Springs Reservation of Oregon, John Day Basin Office, John Day, OR)

    2004-01-01T23:59:59.000Z

    The John Day is the nation's second longest free-flowing river in the contiguous United States and the longest containing entirely unsupplemented runs of anadromous fish. Located in eastern Oregon, the basin drains over 8,000 square miles, Oregon's fourth largest drainage basin, and incorporates portions of eleven counties. Originating in the Strawberry Mountains near Prairie City, the John Day River flows 284 miles in a northwesterly direction, entering the Columbia River approximately four miles upstream of the John Day dam. With wild runs of spring Chinook salmon and summer steelhead, westslope cutthroat, and redband and bull trout, the John Day system is truly a basin with national significance. The majority of the John Day basin was ceded to the Federal government in 1855 by the Confederated Tribes of the Warm Springs Reservation of Oregon (Tribes). In 1997, the Tribes established an office in the basin to coordinate restoration projects, monitoring, planning and other watershed activities on private and public lands. Once established, the John Day Basin Office (JDBO) formed a partnership with the Grant Soil and Water Conservation District (GSWCD), which contracts the majority of the construction implementation activities for these projects from the JDBO. The GSWCD completes the landowner contact, preliminary planning, engineering design, permitting, construction contracting, and construction implementation phases of most projects. The JDBO completes the planning, grant solicitation/defense, environmental compliance, administrative contracting, monitoring, and reporting portion of the program. Most phases of project planning, implementation, and monitoring are coordinated with the private landowners and basin agencies, such as the Oregon Department of Fish and Wildlife and Oregon Water Resources Department. In 2003, the JDBO and GSWCD proposed continuation of their successful partnership between the two agencies and basin landowners to implement an additional twelve (12) watershed conservation projects. The types of projects include off channel water developments, juniper control, permanent diversions, pump stations, and return-flow cooling systems. Due to funding issues and delays, permitting delays, fire closures and landowner contracting problems, 2 projects were canceled and 7 projects were rescheduled to the 2004 construction season. Project costs in 2003 totaled $115,554.00 with a total amount of $64,981.00 (56%) provided by the Bonneville Power Administration (BPA) and the remainder coming from other sources such as the Bureau of Reclamation (BOR), Oregon Watershed Enhancement Board, the U.S. Fish & Wildlife Service Partners in Wildlife Program and individual landowners.

  20. The CHPRC Columbia River Protection Project Quality Assurance Project Plan

    SciTech Connect (OSTI)

    Fix, N. J.

    2008-11-30T23:59:59.000Z

    Pacific Northwest National Laboratory researchers are working on the CHPRC Columbia River Protection Project (hereafter referred to as the Columbia River Project). This is a follow-on project, funded by CH2M Hill Plateau Remediation Company, LLC (CHPRC), to the Fluor Hanford, Inc. Columbia River Protection Project. The work scope consists of a number of CHPRC funded, related projects that are managed under a master project (project number 55109). All contract releases associated with the Fluor Hanford Columbia River Project (Fluor Hanford, Inc. Contract 27647) and the CHPRC Columbia River Project (Contract 36402) will be collected under this master project. Each project within the master project is authorized by a CHPRC contract release that contains the project-specific statement of work. This Quality Assurance Project Plan provides the quality assurance requirements and processes that will be followed by the Columbia River Project staff.

  1. River Protection Project (RPP) Project Management Plan

    SciTech Connect (OSTI)

    SEEMAN, S.E.

    2000-04-01T23:59:59.000Z

    The U.S. Department of Energy (DOE), in accordance with the Strom Thurmond National Defense Authorization Act for Fiscal Year 1999, established the Office of River Protection (ORP) to successfully execute and manage the River Protection Project (RPP), formerly known as the Tank Waste Remediation System (TWRS). The mission of the RPP is to store, retrieve, treat, and dispose of the highly radioactive Hanford tank waste in an environmentally sound, safe, and cost-effective manner. The team shown in Figure 1-1 is accomplishing the project. The ORP is providing the management and integration of the project; the Tank Farm Contractor (TFC) is responsible for providing tank waste storage, retrieval, and disposal; and the Privatization Contractor (PC) is responsible for providing tank waste treatment.

  2. Battleground Energy Recovery Project

    SciTech Connect (OSTI)

    Daniel Bullock

    2011-12-31T23:59:59.000Z

    In October 2009, the project partners began a 36-month effort to develop an innovative, commercial-scale demonstration project incorporating state-of-the-art waste heat recovery technology at Clean Harbors, Inc., a large hazardous waste incinerator site located in Deer Park, Texas. With financial support provided by the U.S. Department of Energy, the Battleground Energy Recovery Project was launched to advance waste heat recovery solutions into the hazardous waste incineration market, an area that has seen little adoption of heat recovery in the United States. The goal of the project was to accelerate the use of energy-efficient, waste heat recovery technology as an alternative means to produce steam for industrial processes. The project had three main engineering and business objectives: Prove Feasibility of Waste Heat Recovery Technology at a Hazardous Waste Incinerator Complex; Provide Low-cost Steam to a Major Polypropylene Plant Using Waste Heat; and ď?· Create a Showcase Waste Heat Recovery Demonstration Project.

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

    SciTech Connect (OSTI)

    Grant Evenson

    2009-05-01T23:59:59.000Z

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

  4. Addendum to the Closure Report for Corrective Action Unit 326: Areas 6 and 27 Release Sites, Nevada Test Site, Nevada, Revision 1

    SciTech Connect (OSTI)

    Grant Evenson

    2009-05-01T23:59:59.000Z

    This document constitutes an addendum to the Closure Report for Corrective Action Unit 326: Areas 6 and 27 Release Sites, Nevada Test Site, Nevada (Revision 1), December 2002 as described in the document Supplemental Investigation Report for FFACO Use Restrictions, Nevada Test Site, Nevada (SIR) dated November 2008. The SIR document was approved by NDEP on December 5, 2008. The approval of the SIR document constituted approval of each of the recommended UR removals. In conformance with the SIR document, this addendum consists of: • This page that refers the reader to the SIR document for additional information • The cover, title, and signature pages of the SIR document • The NDEP approval letter • The corresponding section of the SIR document This addendum provides the documentation justifying the cancellation of the UR for CAS 06-25-01, CP-1 Heating Oil Release. This UR was established as part of a Federal Facility Agreement and Consent Order (FFACO) corrective action and is based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996). Since this UR was established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, this UR was reevaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006). This re-evaluation consisted of comparing the original data (used to define the need for the UR) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove the UR because contamination is not present at the site above the risk-based FALs. Requirements for inspecting and maintaining this UR will be canceled, and the postings and signage at this site will be removed. Fencing and posting may be present at this site that are unrelated to the FFACO UR such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at this site.

  5. Addendum 2 to the Closure Report for Corrective Action Unit 358: Areas 18, 19, 20 Cellars/Mud Pits, Nevada Test Site, Nevada, Revison 0

    SciTech Connect (OSTI)

    Grant Evenson

    2009-05-01T23:59:59.000Z

    This document constitutes an addendum to the Closure Report for Corrective Action Unit 358: Areas 18, 19, 20 Cellars/Mud Pits, Nevada Test Site, Nevada, January 2004 as described in the document Supplemental Investigation Report for FFACO Use Restrictions, Nevada Test Site, Nevada (SIR) dated November 2008. The SIR document was approved by NDEP on December 5, 2008. The approval of the SIR document constituted approval of each of the recommended UR removals. In conformance with the SIR document, this addendum consists of: • This page that refers the reader to the SIR document for additional information • The cover, title, and signature pages of the SIR document • The NDEP approval letter • The corresponding section of the SIR document This addendum provides the documentation justifying the cancellation of the UR for CAS 19-09-05, Mud Pit. This UR was established as part of a Federal Facility Agreement and Consent Order (FFACO) corrective action and is based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996). Since this UR was established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, this UR was reevaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006). This re-evaluation consisted of comparing the original data (used to define the need for the UR) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove the UR because contamination is not present at the site above the risk-based FALs. Requirements for inspecting and maintaining this UR will be canceled, and the postings and signage at this site will be removed. Fencing and posting may be present at this site that are unrelated to the FFACO UR such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at this site.

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

    SciTech Connect (OSTI)

    Grant Evenson

    2009-05-01T23:59:59.000Z

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

  7. Addendum to the Closure Report for Corrective Action Unit 342: Area 23 Mercury Fire Training Pit Nevada Test Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Lynn Kidman

    2008-10-01T23:59:59.000Z

    This document constitutes an addendum to the April 2000, Closure Report for Corrective Action Unit 342: Area 23 Mercury Fire Training Pit as described in the document Recommendations and Justifications for Modifications for Use Restrictions Established under the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office Federal Facility Agreement and Consent Order (UR Modification document) dated February 2008. The UR Modification document was approved by NDEP on February 26, 2008. The approval of the UR Modification document constituted approval of each of the recommended UR modifications. In conformance with the UR Modification document, this addendum consists of: • This cover page that refers the reader to the UR Modification document for additional information • The cover and signature pages of the UR Modification document • The NDEP approval letter • The corresponding section of the UR Modification document This addendum provides the documentation justifying the cancellation of the UR for CAS 23-56-01, Former Mercury Fire Training Pit. This UR was established as part of a Federal Facility Agreement and Consent Order (FFACO) corrective action and is based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996; as amended August 2006). Since this UR was established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, this UR was re-evaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006c). This re-evaluation consisted of comparing the original data (used to define the need for the UR) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove the UR because contamination is not present at the site above the risk-based FALs. Requirements for inspecting and maintaining this UR will be canceled, and the postings and signage at this site will be removed. Fencing and posting may be present at this site that are unrelated to the FFACO UR such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004f). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at this site.

  8. Addendum to the Closure Report for Corrective Action Unit 335: Area 6 Injection Well and Drain Pit Nevada Test Site, Nevada, Revison 0

    SciTech Connect (OSTI)

    Lynn Kidman

    2008-10-01T23:59:59.000Z

    This document constitutes an addendum to the June 2003, Closure Report for Corrective Action Unit 335: Area 6 Injection Well and Drain Pit as described in the document Recommendations and Justifications for Modifications for Use Restrictions Established under the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office Federal Facility Agreement and Consent Order (UR Modification document) dated February 2008. The UR Modification document was approved by NDEP on February 26, 2008. The approval of the UR Modification document constituted approval of each of the recommended UR modifications. In conformance with the UR Modification document, this addendum consists of: • This cover page that refers the reader to the UR Modification document for additional information • The cover and signature pages of the UR Modification document • The NDEP approval letter • The corresponding section of the UR Modification document This addendum provides the documentation justifying the cancellation of the URs for: • CAS 06-20-02, 20-inch Cased Hole • CAS 06-23-03, Drain Pit These URs were established as part of Federal Facility Agreement and Consent Order (FFACO) corrective actions and were based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996; as amended August 2006). Since these URs were established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, these URs were re-evaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006c). This re-evaluation consisted of comparing the original data (used to define the need for the URs) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove these URs because contamination is not present at these sites above the risk-based FALs. Requirements for inspecting and maintaining these URs will be canceled, and the postings and signage at each site will be removed. Fencing and posting may be present at these sites that are unrelated to the FFACO URs such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004f). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at these sites.

  9. Addendum to the Closure Report for Corrective Action Unit 356: Mud Pits and Disposal Sites Nevada Test Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Lynn Kidman

    2008-10-01T23:59:59.000Z

    This document constitutes an addendum to the November 2002, Closure Report for Corrective Action Unit 356: Mud Pits and Disposal Sites as described in the document Recommendations and Justifications for Modifications for Use Restrictions Established under the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office Federal Facility Agreement and Consent Order (UR Modification document) dated February 2008. The UR Modification document was approved by NDEP on February 26, 2008. The approval of the UR Modification document constituted approval of each of the recommended UR modifications. In conformance with the UR Modification document, this addendum consists of: • This cover page that refers the reader to the UR Modification document for additional information • The cover and signature pages of the UR Modification document • The NDEP approval letter • The corresponding section of the UR Modification document This addendum provides the documentation justifying the cancellation of the URs for: • CAS 03-04-01, Area 3 Change House Septic System • CAS 03-09-04, Mud Pit These URs were established as part of Federal Facility Agreement and Consent Order (FFACO) corrective actions and were based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996; as amended August 2006). Since these URs were established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, these URs were re-evaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006c). This re-evaluation consisted of comparing the original data (used to define the need for the URs) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove these URs because contamination is not present at these sites above the risk-based FALs. Requirements for inspecting and maintaining these URs will be canceled, and the postings and signage at each site will be removed. Fencing and posting may be present at these sites that are unrelated to the FFACO URs such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004f). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at these sites.

  10. Addendum to the Closure Report for Corrective Action Unit 339: Area 12 Fleet Operations Steam Cleaning Discharge Area, Nevada Test Site, Revision 0

    SciTech Connect (OSTI)

    Grant Evenson

    2009-05-01T23:59:59.000Z

    This document constitutes an addendum to the Closure Report for CAU 339: Area 12 Fleet Operations Steam Cleaning Discharge Area Nevada Test Site, December 1997 as described in the document Supplemental Investigation Report for FFACO Use Restrictions, Nevada Test Site, Nevada (SIR) dated November 2008. The SIR document was approved by NDEP on December 5, 2008. The approval of the SIR document constituted approval of each of the recommended UR removals. In conformance with the SIR document, this addendum consists of: • This page that refers the reader to the SIR document for additional information • The cover, title, and signature pages of the SIR document • The NDEP approval letter • The corresponding section of the SIR document This addendum provides the documentation justifying the cancellation of the UR for CAS 12-19-01, A12 Fleet Ops Steam Cleaning Efflu. This UR was established as part of a Federal Facility Agreement and Consent Order (FFACO) corrective action and is based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996). Since this UR was established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, this UR was reevaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006). This re-evaluation consisted of comparing the original data (used to define the need for the UR) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove the UR because contamination is not present at the site above the risk-based FALs. Requirements for inspecting and maintaining this UR will be canceled, and the postings and signage at this site will be removed. Fencing and posting may be present at this site that are unrelated to the FFACO UR such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at this site.

  11. Los Alamos National Laboratory Tritium Technology Deployments Large Scale Demonstration and Deployment Project

    SciTech Connect (OSTI)

    McFee, J.; Blauvelt, D.; Stallings, E.; Willms, S.

    2002-02-26T23:59:59.000Z

    This paper describes the organization, planning and initial implementation of a DOE OST program to deploy proven, cost effective technologies into D&D programs throughout the complex. The primary intent is to accelerate closure of the projects thereby saving considerable funds and at the same time being protective of worker health and the environment. Most of the technologies in the ''toolkit'' for this program have been demonstrated at a DOE site as part of a Large Scale Demonstration and Deployment Project (LSDDP). The Mound Tritium D&D LSDDP served as the base program for the technologies being deployed in this project but other LSDDP demonstrated technologies or ready-for-use commercial technologies will also be considered. The project team will evaluate needs provided by site D&D project managers, match technologies against those needs and rank deployments using a criteria listing. After selecting deployments the project will purchase the equipment and provide a deployment engineer to facilitate the technology implementation. Other cost associated with the use of the technology will be borne by the site including operating staff, safety and health reviews etc. A cost and performance report will be prepared following the deployment to document the results.

  12. Closure Report for Corrective Action Unit 342: Area 23 Mercury Fire Training Pit Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    C. M. Obi

    2000-04-01T23:59:59.000Z

    The purpose of this Closure Report (CR) is to provide documentation of the completed corrective action and to provide data confirming the corrective action. The corrective action was performed following the approved Corrective Action Plan (CAP) (U.S. Department of Energy [DOE], 1999b) and consisted of closure-in-place with partial excavation, disposal, backfilling, administrative controls, and post-closure monitoring. Soil with petroleum hydrocarbon concentrations above the Nevada Division of Environmental Protection (NDEP) Action Level of 100 milligrams per kilogram (mg/kg) (Nevada Administrative Code, 1996) was removed to a depth of 1.5 meters (m) (5 feet [ft]). The excavations were backfilled with clean fill to restore the site and to prevent contact with deeper, closed-in-place soil that exceeded the NDEP Action Level. According to the Corrective Action Investigation Plan (CAIP) (DOE, 1998), the Mercury Fire Training Pit was used from approximately 1965 to the early 1990s to train fire-fighting and emergency response personnel at the NTS and encompasses an area approximately 85 by 115 m (280 by 380 ft). The location of the Mercury Fire Training Pit is shown in Figure 1 and a site plan is shown in Figure 2. The Mercury Fire Training Pit formerly included a bermed bum pit with four small bum tanks; four large above ground storage tanks (ASTS); an overturned bus, a telephone pole storage area; and several areas for burning sheds, pallets, and cables. During the active life of the Mercury Fire Training Pit, training events were conducted at least monthly and sometimes as often as weekly. Fuels burned during these events included off-specification or rust-contaminated gasoline, diesel, and aviation fuel (JP-4). Other items burned during these events included paint, tires, a pond liner, wood, paper, cloth, and copper cable. Approximately 570 liters (L) (150 gallons [gal]) of fuel were used for each training event resulting in an approximate total of 136,000 L (36,000 gal) of fuel used over the life of the Mercury Fire Training Pit. Unburned fuel was allowed to pool on the ground and was left to eventually volatilize or soak into the soil. In addition, fuels from the ASTS and fuels and fluids from the overturned bus leaked or spilled onto the ground. Approximately 19 L to 38 L (5 to 10 gal) of paint were also burned monthly until sometime in the 1970s.

  13. Operational Waste Volume Projection

    SciTech Connect (OSTI)

    STRODE, J.N.

    1999-08-24T23:59:59.000Z

    Waste receipts to the double-shell tank system are analyzed and wastes through the year 2018 are projected based on assumption as of July 1999. A computer simulation of site operations is performed, which results in projections of tank fill schedules, tank transfers, evaporator operations, tank retrieval, and aging waste tank usage. This projection incorporates current budget planning and the clean-up schedule of the Tri-Party Agreement.

  14. Operational Waste Volume Projection

    SciTech Connect (OSTI)

    STRODE, J.N.

    2000-08-28T23:59:59.000Z

    Waste receipts to the double-shell tank system are analyzed and wastes through the year 2015 are projected based on generation trends of the past 12 months. A computer simulation of site operations is performed, which results in projections of tank fill schedules, tank transfers, evaporator operations, tank retrieval, and aging waste tank usage. This projection incorporates current budget planning and the clean-up schedule of the Tri-Party Agreement. Assumptions were current as of June. 2000.

  15. Operational waste volume projection

    SciTech Connect (OSTI)

    Koreski, G.M.

    1996-09-20T23:59:59.000Z

    Waste receipts to the double-shell tank system are analyzed and wastes through the year 2015 are projected based on generation trends of the past 12 months. A computer simulation of site operations is performed, which results in projections of tank fill schedules, tank transfers, evaporator operations, tank retrieval, and aging waste tank usage. This projection incorporates current budget planning and the clean-up schedule of the Tri-Party Agreement. Assumptions were current as of June 1996.

  16. Project: BELLA Bldg. #: 71

    E-Print Network [OSTI]

    TO CONSTRUCTION AS OF 10/4/2011 Current/Approved Projects Project: Solar Energy Research Center Bldg. #:TBD. #: TBD Affected Area: R1 Road & V Road (58) Dates: 8/2011 - 9/2013 6 Small Projects: A. B50 Electrical/1/2014 N3 (58) 42 11/1/2011 2/1/2014 M-1 (35) 12 10/1/2010 11/1/2011 B81 (21) 18 10/1/2010 11/1/2011 V Road

  17. 2015 Technology Innovation Projects

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

    for RTU and Lighting Retrofits Energy Efficiency TIP 140: Energy Efficiency Emerging Technology Assessment and Demonstration Projects TIP 261: Determining and Improving the...

  18. Custom Renewable Energy Projects

    Broader source: Energy.gov [DOE]

    Project development assistance funding is available for a variety of purposes, including grant writing, feasibility studies, or technical assistance with design, permitting, or utility interconne...

  19. Mascoma: Frontier Biorefinery Project

    Broader source: Energy.gov [DOE]

    This project involves the construction and operation of a biorefinery that produces ethanol and other co-products from cellulosic materials through advanced consolidated bioprocessing.

  20. Contract/Project Management

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

    by FY12. 95% Line Item 85% Cleanup 97% Line Item 85% Cleanup EVM represents Earned Value Management. FY2011 Second Quarter Overall Contract and Project Management Improvement...

  1. Contract/Project Management

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

    by FY12. 95% Line Item 85% Cleanup 100% Line Item 88% Cleanup EVM represents Earned Value Management. FY2011 Fourth Quarter Overall Contract and Project Management Improvement...

  2. Contract/Project Management

    Energy Savers [EERE]

    by FY12. 95% Line Item 85% Cleanup 100% Line Item 88% Cleanup EVM represents Earned Value Management. FY2011 First Quarter Overall Contract and Project Management Performance...

  3. Contract/Project Management

    Energy Savers [EERE]

    by FY12. 95% Line Item 85% Cleanup 97% Line Item 89% Cleanup EVM represents Earned Value Management. FY2011 Third Quarter Overall Contract and Project Management Improvement...

  4. Recovery Act Project Stories

    Broader source: Energy.gov [DOE]

    Funded by the American Recovery and Reinvestment Act, these Federal Energy Management Program (FEMP) projects exemplify the range of technical assistance provided to federal agencies.

  5. Project Finance Case Studies

    Broader source: Energy.gov [DOE]

    Presentation covers the Project Finance Case Studies and is given at the Spring 2010 Federal Utility Partnership Working Group (FUPWG) meeting in Rapid City, South Dakota.

  6. Contract/Project Management

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

    capital asset line item projects (less than 50 million) are fully funded in one Fiscal Year (one Appropriation). NA NA Policy memorandum drafted and in review 12. Cost...

  7. TThe {\\sc Majorana} Project

    E-Print Network [OSTI]

    The MAJORANA collaboration

    2009-10-23T23:59:59.000Z

    The {\\sc Majorana} Project, a neutrinoless double-beta decay experiment is described with an emphasis on the choice of Ge-detector configuration.

  8. The MAJORANA project

    SciTech Connect (OSTI)

    Elliott, Steven R [Los Alamos National Laboratory

    2009-01-01T23:59:59.000Z

    The Majorana Project, a neutrinoless double-beta decay experiment is described with an emphasis on the choice of Ge-detector configuration.

  9. Energy Markets and Projections

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

    National Governors Association Governors' Advisors Energy Policy Institute July 24, 2014 | Washington, DC By Adam Sieminski, EIA Administrator Energy Markets and Projections NGA...

  10. Our Project Regional, community,

    E-Print Network [OSTI]

    Minnesota, University of

    City departments -City Engineering and Traffic Engineering Public engagement early in project process modes and all users See.Safe.Smart.Rochester campaign to decrease modal conflict Connection

  11. Barstow Wind Turbine Project

    Broader source: Energy.gov [DOE]

    Presentation covers the Barstow Wind Turbine project for the Federal Utility Partnership Working Group (FUPWG) meeting, held on November 18-19, 2009.

  12. Prison Solar Project

    Broader source: Energy.gov [DOE]

    Presentation covers the Prison Solar Project for the Federal Utility Partnership Working Group (FUPWG) meeting, held on November 18-19, 2009.

  13. Completion of the Operational Closure of Tank 18F and Tank 19F at the Savannah River Site by Grouting - 13236

    SciTech Connect (OSTI)

    Tisler, Andrew J. [Savannah River Remediation, LLC, Aiken, SC 29808 (United States)] [Savannah River Remediation, LLC, Aiken, SC 29808 (United States)

    2013-07-01T23:59:59.000Z

    Radioactive waste is stored in underground waste tanks at the Savannah River Site (SRS). The low-level fraction of the waste is immobilized in a grout waste form, and the high level fraction is disposed of in a glass waste form. Once the waste is removed, the tanks are prepared for closure. Operational closure of the tanks consists of filling with grout for the purpose of chemically stabilizing residual material, filling the tank void space for long-term structural stability, and discouraging future intrusion. Two of the old-style single-shell tanks at the SRS have received regulatory approval confirming waste removal had been completed, and have been stabilized with grout as part of completing operational closure and removal from service. Consistent with the regulatory framework, two types of grout were used for the filling of Tanks 18F and 19F. Reducing grout was used to fill the entire volume of Tanks 18F and 19F (bulk fill grout) and a more flowable grout was used to fill equipment that was left in the tank (equipment fill grout). The reducing grout was added to the tanks using portable grout pumps filled from concrete trucks, and delivered the grout through slick lines to the center riser of each tank. Filling of the two tanks has been completed, and all equipment has been filled. The final capping of riser penetrations brings the operation closure of Tanks 18F and 19F to completion. (authors)

  14. HWMA/RCRA Closure Plan for the Basin Facility Basin Water Treatment System - Voluntary Consent Order NEW-CPP-016 Action Plan

    SciTech Connect (OSTI)

    Evans, S. K.

    2007-11-07T23:59:59.000Z

    This Hazardous Waste Management Act/Resource Conservation and Recovery Act closure plan for the Basin Water Treatment System located in the Basin Facility (CPP-603), Idaho Nuclear Technology and Engineering Center (INTEC), Idaho National Laboratory Site, was developed to meet future milestones established under the Voluntary Consent Order. The system to be closed includes units and associated ancillary equipment included in the Voluntary Consent Order NEW-CPP-016 Action Plan and Voluntary Consent Order SITE-TANK-005 Tank Systems INTEC-077 and INTEC-078 that were determined to have managed hazardous waste. The Basin Water Treatment System will be closed in accordance with the requirements of the Hazardous Waste Management Act/Resource Conservation and Recovery Act, as implemented by the Idaho Administrative Procedures Act 58.01.05.009 and 40 Code of Federal Regulations 265, to achieve "clean closure" of the tank system. This closure plan presents the closure performance standards and methods of achieving those standards for the Basin Water Treatment Systems.

  15. EIS-0356: Retrieval, Treatment and Disposal of Tank Wastes and Closure of Single-Shell Tanks at the Hanford Site, Richland, WA

    Broader source: Energy.gov [DOE]

    This EIS analyzes DOE's proposed retrieval, treatment, and disposal of the waste being managed in the high-level waste (HLW) tank farms at the Hanford Site near Richland, Washington, and closure of the 149 single-shell tanks (SSTs) and associated facilities in the HLW tank farms.

  16. Post-Closure Inspection and Monitoring Report for Corrective Action Unit 417: Central Nevada Test Area Surface, Hot Creek Valley, Nevada

    SciTech Connect (OSTI)

    None

    2013-03-01T23:59:59.000Z

    This report presents results of data collected during the annual post-closure site inspections conducted at the Central Nevada Test Area surface Corrective Action Unit (CAU) 417 in May 2011 and July 2012. The annual post-closure site inspections included inspections of the UC-1, UC-3, and UC-4 sites in accordance with the Post-Closure Monitoring Plan provided in the CAU 417 Closure Report (NNSA/NV 2001). The annual inspections conducted at the UC-1 Central Mud Pit (CMP) indicated that the site and soil cover were in good condition. No new fractures or extension of existing fractures were observed and no issues with the fence or gate were identified. The vegetation on the cover continues to look healthy, but the biennial vegetation survey conducted during the 2012 inspection indicated that the total foliar cover was slightly higher in 2009 than in 2012. This may be indicative of a decrease in precipitation observed during the 2-year monitoring period. The precipitation totaled 9.9 inches from July 1, 2010, through June 30, 2011, and 5 inches from July 1, 2011, through June 30, 2012. This decrease in precipitation is also evident in the soil moisture data obtained from the time domain reflectometry sensors. Soil moisture content data show that the UC-1 cover is performing as designed, and evapotranspiration is effectively removing water from the cover.

  17. Microsoft Word - A5ClosurePlan091708sc.doc

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. Hirsch Project Lead SAMSBIOLOGICAL508-378553

  18. Microsoft Word - EIR-11572- Area 3 Closure Plan-9-25-07.doc

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. Hirsch ProjectLyneis, 1982,Francis,1,

  19. Microsoft Word - Non-RCRA Post Closure Inspection Letter Report.doc

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. Hirsch ProjectLyneis,NevadaNuclear14583TBD3,MAP 1

  20. River Protection Project (RPP) Project Management Plan

    SciTech Connect (OSTI)

    NAVARRO, J.E.

    2001-03-07T23:59:59.000Z

    The Office of River Protection (ORP) Project Management Plan (PMP) for the River Protection Project (RPP) describes the process for developing and operating a Waste Treatment Complex (WTC) to clean up Hanford Site tank waste. The Plan describes the scope of the project, the institutional setting within which the project must be completed, and the management processes and structure planned for implementation. The Plan is written from the perspective of the ORP as the taxpayers' representative. The Hanford Site, in southeastern Washington State, has one of the largest concentrations of radioactive waste in the world, as a result of producing plutonium for national defense for more than 40 years. Approximately 53 million gallons of waste stored in 177 aging underground tanks represent major environmental, social, and political challenges for the U.S. Department of Energy (DOE). These challenges require numerous interfaces with state and federal environmental officials, Tribal Nations, stakeholders, Congress, and the US Department of Energy-Headquarters (DOE-HQ). The cleanup of the Site's tank waste is a national issue with the potential for environmental and economic impacts to the region and the nation.