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Note: This page contains sample records for the topic "national level revisions" from the National Library of EnergyBeta (NLEBeta).
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1

High Level Waste System Plan Revision 9  

SciTech Connect (OSTI)

Revision 9 of the High Level Waste System Plan documents the current operating strategy of the HLW System at SRS to receive, store, treat, and dispose of high-level waste.

Davis, N.R.; Wells, M.N.; Choi, A.S.; Paul, P.; Wise, F.E.

1998-04-01T23:59:59.000Z

2

Brookhaven National Laboratory Number: Revision  

E-Print Network [OSTI]

includes both laser (light) and non-laser hazards. A Nominal Hazard Zone (NHZ) analysis must be completed listed below. All American National Standard Institute (ANSI) Hazard Class 3b and 4 laser systems must description: Pulsed laser deposition system for thin films growth. Location: NSLS-X21 LINE MANAGEMENT

Ohta, Shigemi

3

Hanford Site National Environmental Policy Act (NEPA) Characterization. Revision 5  

SciTech Connect (OSTI)

This fifth revision of the Hanford Site National Environmental Policy (NEPA) Characterization presents current environmental data regarding the Hanford Site and its immediate environs. This information is intended for use in preparing Site-related NEPA documentation. Information is presented on climate and meteorology, geology and hydrology, ecology, history and archaeology, socioeconomics, land use, and noise levels, prepared by Pacific Northwest Laboratory (PNL) staff. Models are described that are to be used in simulating realized or potential impacts from nuclear materials at the Hanford Site. Included are models of radionuclide transport in groundwater and atmospheric pathways, and of radiation dose to populations via all known pathways from known initial conditions. Federal and state regulations, DOE orders and permits, and environmental standards directly applicable for the NEPA documents at the Hanford Site, are provided.

Cushing, C.E. [ed.] [ed.

1992-12-01T23:59:59.000Z

4

Hanford Site National Environmental Policy Act (NEPA) characterization. Revision 7  

SciTech Connect (OSTI)

This seventh revision of the Hanford Site National Environmental Policy (NEPA) Characterization presents current environmental data regarding the Hanford Site and its immediate environs. This information is intended for use in preparing Site-related NEPA documentation. Chapter 4.0 summarizes up-to-date information on climate and meteorology, geology, hydrology, environmental monitoring, ecology, history and archaeology, socioeconomics, land use, and noise levels prepared by Pacific Northwest Laboratory (PNL) staff. More detailed data are available from reference sources cited or from the authors. Chapter 5.0 was not updated from the sixth revision (1994). It describes models, including their principal underlying assumptions, that are to be used in simulating realized or potential impacts from nuclear materials at the Hanford Site. Included are models of radionuclide transport in groundwater and atmospheric pathways, and of radiation dose to populations via all known pathways from known initial conditions. The updated Chapter 6.0 provides the preparer with the federal and state regulations, DOE Orders and permits, and environmental standards directly applicable to the NEPA documents on the Hanford Site, following the structure of Chapter 4.0. No conclusions or recommendations are given in this report. Rather, it is a compilation of information on the Hanford Site environment that can be used directly by Site contractors. This information can also be used by any interested individual seeking baseline data on the Hanford Site and its past activities by which to evaluate projected activities and their impacts.

Cushing, C.E. [ed.] ed.; Baker, D.A.; Chamness, M.A. [and others] and others

1995-09-01T23:59:59.000Z

5

Hanford Site National Environmental Policy Act (NEPA) characterization. Revision 6  

SciTech Connect (OSTI)

This sixth revision of the Hanford Site National Environmental Policy (NEPA) Characterization presents current environmental data regarding the Hanford Site and its immediate environs. This information is intended for use in preparing Site-related NEPA documentation. Chapter 4.0 summarizes up-to-date information on climate and meteorology, geology and hydrology, ecology, history and archaeology, socioeconomics, land use, and noise levels prepared by Pacific Northwest Laboratory (PNL) staff. More detailed data are available from reference sources cited or from the authors; Chapter 5.0 has been significantly updated from the fifth revision. It describes models, including their principal underlying assumptions, that are to be used in simulating realized or potential impacts from nuclear materials at the Hanford Site. Included are models of radionuclide transport in groundwater and atmospheric pathways, and of radiation dose to populations via all known pathways from known initial conditions; The updated Chapter 6.0 provides the preparer with the federal and state regulations, DOE orders and permits, and environmental standards directly applicable to the NEPA documents on the Hanford Site, following the structure of Chapter 4.0. No conclusions or recommendations are given in this report. Rather, it is a compilation of information on the Hanford Site environment that can be utilized directly by Site contractors. This information can also be used by any interested individual seeking baseline data on the Hanford Site and its past activities by which to evaluate projected activities and their impacts.

Cushing, C.E. [ed.; Baker, D.A.; Chamness, M.A. [and others

1994-08-01T23:59:59.000Z

6

Preliminary parametric performance assessment of potential final waste forms for alpha low-level waste at the Idaho National Engineering Laboratory. Revision 1  

SciTech Connect (OSTI)

This report presents a preliminary parametric performance assessment (PA) of potential waste disposal systems for alpha-contaminated, mixed, low-level waste (ALLW) currently stored at the Transuranic Storage Area of INEL. The ALLW, which contains from 10 to 100 nCi/g of transuranic (TRU) radionuclides, is awaiting treatment and disposal. The purpose of this study was to examine the effects of several parameters on the radiological-confinement performance of potential disposal systems for the ALLW. The principal emphasis was on the performance of final waste forms (FWFs). Three categories of FWF (cement, glass, and ceramic) were addressed by evaluating the performance of two limiting FWFs for each category. Performance at five conceptual disposal sites was evaluated to illustrate the effects of site characteristics on the performance of the total disposal system. Other parameters investigated for effects on receptor dose included inventory assumptions, TRU radionuclide concentration, FWF fracture, disposal depth, water infiltration rates, subsurface-transport modeling assumptions, receptor well location, intrusion scenario assumptions, and the absence of waste immobilization. These and other factors were varied singly and in some combinations. The results indicate that compliance of the treated and disposed ALLW with the performance objectives depends on the assumptions made, as well as on the FWF and the disposal site. Some combinations result in compliance, while others do not. The implications of these results for decision making relative to treatment and disposal of the INEL ALLW are discussed. The report compares the degree of conservatism in this preliminary parametric PA against that in four other PAs and one risk assessment. All of the assessments addressed the same disposal site, but different wastes. The report also presents a qualitative evaluation of the uncertainties in the PA and makes recommendations for further study.

Smith, T.H.; Sussman, M.E. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States); Myers, J.; Djordjevic, S.M.; DeBiase, T.A.; Goodrich, M.T.; DeWitt, D. [IT Corp., Albuquerque, NM (United States)

1995-08-01T23:59:59.000Z

7

Reflecting the Revised PM 2.5 National Ambient Air Quality Standard...  

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

Reflecting the Revised PM 2.5 National Ambient Air Quality Standard in NEPA Evaluations Reflecting the Revised PM 2.5 National Ambient Air Quality Standard in NEPA Evaluations This...

8

Hanford Site National Evnironmental Policy Act (NEPA) characterization. Revision 4  

SciTech Connect (OSTI)

This fourth revision of the Hanford Site National Environmental Policy (NEPA) Characterization presents current environmental data regarding the Hanford Site and its immediate environs. This information is intended for use in preparing Site-related NEPA documentation. In Chapter 4.0 are presented summations of up-to-date information about climate and meteorology, geology and hydrology, ecology, history and archaeology, socioeconomics, land use, and noise levels. Chapter 5.0 describes models, including their principal assumptions, that are to be used in simulating realized or potential impacts from nuclear materials at the Hanford Site. Included are models of radionuclides transport in groundwater and atmospheric pathways, and of radiation dose to populations via all known pathways from known initial conditions. Chapter 6.0 provides the preparer with the federal and state regulations, DOE orders and permits, and environmental standards directly applicable for environmental impact statements for the Hanford Site, following the structure Chapter 4.0. NO conclusions or recommendations are given in this report.

Cushing, C.E. [ed.

1991-12-01T23:59:59.000Z

9

Hanford Site National Environmental Policy Act (NEPA) characterization. Revision 9  

SciTech Connect (OSTI)

This ninth revision of the Hanford Site National Environmental Policy Act (NEPA) Characterization presents current environmental data regarding the hanford Site and its immediate environs. This information is intended for use in preparing Chapters 4 and 6 in Hanford Site-related NEPA documents. Chapter 4.0 (Affected Environment) includes information on climate and meteorology, geology, hydrology, ecology, cultural, archaeological and historical resources, socioeconomics, and noise. Chapter 6.0 (Statutory and Regulatory Requirements) provides the preparer with the federal and state regulations, DOE directives and permits, and environmental standards directly applicable to the NEPA documents on the Hanford Site. Not all of the sections have been updated for this revision. The following lists the updated sections: climate and meteorology; ecology (threatened and endangered species section only); culture, archaeological, and historical resources; socioeconomics; all of Chapter 6.

Neitzel, D.A. [ed.] [ed.; Bjornstad, B.N.; Fosmire, C.J. [and others] [and others

1997-08-01T23:59:59.000Z

10

REVISED INDEPENDENT VERIFICATION SURVEY OF A AND B RADIOACTIVE WASTE TRANSFER LINES TRENCH BROOKHAVEN NATIONAL LABORATORY  

SciTech Connect (OSTI)

REVISED INDEPENDENT VERIFICATION SURVEY OF THE A AND B RADIOACTIVE WASTE TRANSFER LINES TRENCH, BROOKHAVEN NATIONAL LABORATORY 5062-SR-01-1

P.C. Weaver

2010-02-10T23:59:59.000Z

11

Hanford Site National Environmental Policy Act (NEPA) characterization. Revision 8  

SciTech Connect (OSTI)

This eighth revision of the Hanford Site National Environmental Policy Act (NEPA) Characterization presents current environmental data regarding the Hanford Site and its immediate environs. This information is intended for use in preparing Chapters 4 and 6 in Hanford Site-related NEPA documents. Chapter 4 (Affected Environment) includes information on climate and meteorology, geology, hydrology, ecology, historical, archaeological and cultural resources, socioeconomics, and noise. Chapter 6 (Statutory and Regulatory Requirements) provides the preparer with the federal and state regulations, DOE directives and permits, and environmental standards directly applicable to the NEPA documents on the Hanford Site. The following sections were updated in this revision: climate and meteorology; ecology (threatened and endangered species section only); historical; archaeological and cultural resources; and all of chapter 6. No conclusions or recommendations are given in this report. Rather, it is a compilation of information on the Hanford Site environment that can be used directly by Site contractors. This information can also be used by any interested individual seeking baseline data on the hanford Site and its past activities by which to evaluate projected activities and their impacts.

Neitzel, D.A. [ed.] [ed.; Bjornstad, B.N.; Fosmire, C.J.; Fowler, R.A. [and others] [and others

1996-08-01T23:59:59.000Z

12

Hanford Site National Environmental Policy Act (NEPA) Characterization, Revision 15  

SciTech Connect (OSTI)

This document describes the U.S. Department of Energy's (DOE) Hanford Site environment. It is updated each year and is intended to provide a consistent description of the Hanford Site environment for the many National Environmental Policy Act (NEPA) documents being prepared by DOE contractors. No statements of significance or environmental consequences are provided. This year's report is the thirteenth revision of the original document published in 1988 and is (until replaced by the fourteenth revision) the only version that is relevant for use in the preparation of Hanford NEPA, State Environmental Policy Act (SEPA), and Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) documents. The two chapters included in this document (Chapters 4 and 6) are numbered to correspond to the chapters where such information is typically presented in environmental impact statements (Weiss) and other Hanford Site NEPA or CERCLA documentation. Chapter 4.0 (Affected Environment) describes Hanford Site climate and meteorology, geology, hydrology, ecology, cultural, archaeological, and historical resources, socioeconomics, occupational safety, and noise. Chapter 6.0 (Statutory and Regulatory Requirements) describes federal and state laws and regulations, DOE directives and permits, and presidential executive orders that are applicable to the NEPA documents prepared for Hanford Site activities.

Neitzel, Duane A.; Bunn, Amoret L.; Burk, Kenneth W.; Cannon, Sandra D.; Duncan, Joanne P.; Fowler, Richard A.; Fritz, Brad G.; Harvey, David W.; Hendrickson, Paul L.; Horton, Duane G.; Last, George V.; Poston, Ted M.; Prendergast-Kennedy, Ellen L.; Reidel, Steve P.; Scott, Michael J.; Thorne, Paul D.; Woody, Dave M.

2003-09-01T23:59:59.000Z

13

NATIONAL RADIO ASTRONOMY OBSERVATORY TITLE: A REVISED VAX FARANT SPLOT ROUTINE AND RELATED APPLE  

E-Print Network [OSTI]

NATIONAL RADIO ASTRONOMY OBSERVATORY TITLE: A REVISED VAX FARANT SPLOT ROUTINE AND RELATED APPLE #12;A REVISED VAX FARANT SPLOT ROUTINE AND RELATED APPLE II PLOTTING PROGRAM. The purpose of this report is to describe some upgrades made to the VAX 1 SPLOT" routine and the related Apple plotting

Groppi, Christopher

14

High level waste tank farm setpoint document. Revision 1  

SciTech Connect (OSTI)

Revision 1 modifies Attachment I of this Technical Report as a result of a meeting which was held Friday, January 27, 1994 between Maintenance, Work Control, and Engineering to discuss report contents. Upon completion of the meeting, the Flow Chart was edited accordingly. Attachment 2 is modified for clerical reasons. Setpoints for nuclear safety-related instrumentation are required for actions determined by the design authorization basis. Minimum requirements need to be established for assuring that setpoints are established and held within specified limits. This document establishes the controlling methodology for changing setpoints of all classifications. The instrumentation under consideration involve the transfer, storage, and volume reduction of radioactive liquid waste in the F- and H-Area High-Level Radioactive Waste Tank Fanns. The setpoint document (Appendix 2) will encompass the PROCESS AREA listed in the Safety Analysis Report (SAR) (DSTSA-200-10 Sup 18) which includes the diversion box HDB-8 facility. In addition to the PROCESS AREAS listed in the SAR, Building 299-H and the Effluent Transfer Facility (ETF) are also included in the scope.

Anthony, J.A. III

1995-01-31T23:59:59.000Z

15

Nevada National Security Site Integrated Groundwater Sampling Plan, Revision 0  

SciTech Connect (OSTI)

The purpose of the Nevada National Security Site (NNSS) Integrated Sampling Plan (referred to herein as the Plan) is to provide a comprehensive, integrated approach for collecting and analyzing groundwater samples to meet the needs and objectives of the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) Underground Test Area (UGTA) Activity. Implementation of this Plan will provide high-quality data required by the UGTA Activity for ensuring public protection in an efficient and cost-effective manner. The Plan is designed to ensure compliance with the UGTA Quality Assurance Plan (QAP). The Plan’s scope comprises sample collection and analysis requirements relevant to assessing the extent of groundwater contamination from underground nuclear testing. This Plan identifies locations to be sampled by corrective action unit (CAU) and location type, sampling frequencies, sample collection methodologies, and the constituents to be analyzed. In addition, the Plan defines data collection criteria such as well-purging requirements, detection levels, and accuracy requirements; identifies reporting and data management requirements; and provides a process to ensure coordination between NNSS groundwater sampling programs for sampling of interest to UGTA. This Plan does not address compliance with requirements for wells that supply the NNSS public water system or wells involved in a permitted activity.

Marutzky, Sam; Farnham, Irene

2014-10-01T23:59:59.000Z

16

Idaho National Engineering Laboratory installation roadmap document. Revision 1  

SciTech Connect (OSTI)

The roadmapping process was initiated by the US Department of Energy`s office of Environmental Restoration and Waste Management (EM) to improve its Five-Year Plan and budget allocation process. Roadmap documents will provide the technical baseline for this planning process and help EM develop more effective strategies and program plans for achieving its long-term goals. This document is a composite of roadmap assumptions and issues developed for the Idaho National Engineering Laboratory (INEL) by US Department of Energy Idaho Field Office and subcontractor personnel. The installation roadmap discusses activities, issues, and installation commitments that affect waste management and environmental restoration activities at the INEL. The High-Level Waste, Land Disposal Restriction, and Environmental Restoration Roadmaps are also included.

Not Available

1993-05-30T23:59:59.000Z

17

National Ignition Facility project acquisition plan revision 1  

SciTech Connect (OSTI)

The purpose of this National Ignition Facility Acquisition Plan is to describe the overall procurement strategy planned for the National Ignition Facility M Project. It was prepared for the NIP Prood Office by the NIF Procurement Manager.

Clobes, A.R.

1996-10-01T23:59:59.000Z

18

National Ignition Facility Quality Assurance Program Plan. Revision 1  

SciTech Connect (OSTI)

The National Ignition Facility (NIF) is a key constituent of the Department of Energy`s Stockpile Stewardship Program. The NIF will use inertial confinement fusion (ICF) to produce ignition and energy gain in ICF targets, and will perform weapons physics and high-energy- density experiments in support of national security and civilian objectives. The NIF Project is a national facility involving the collaboration of several DOE laboratories and subcontractors, including Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Sandia National Laboratory (SNL), and the University of Rochester Laboratory for Laser Energetics (UR/LLE). The primary mission of the NIF Project is the construction and start-up operation of laser-based facilities that will demonstrate fusion ignition in the laboratory to provide nuclear-weapons-related physics data, and secondarily, to propagate fusion burn aimed at developing a potential source of civilian energy. To support the accomplishment of this very important mission, the LLNL Laser Directorate created the NIF Project Office to organize and bring about the Project. The NIF Project Office has established this Quality Assurance Program to ensure its success. This issue of the Quality Assurance Program Plan (QAPP) adds the requirements for the conduct of Title 11 design, construction, procurement, and Title III engineering. This QAPP defines and describes the program-the management system-for specifying, achieving, and assuring the quality of all NIF Project work consistent with the policies of the Laboratory and the Laser Directorate.

Wolfe, C.R.; Yatabe, J.

1996-09-01T23:59:59.000Z

19

Idaho National Engineering Laboratory installation roadmap assumptions document. Revision 1  

SciTech Connect (OSTI)

This document is a composite of roadmap assumptions developed for the Idaho National Engineering Laboratory (INEL) by the US Department of Energy Idaho Field Office and subcontractor personnel as a key element in the implementation of the Roadmap Methodology for the INEL Site. The development and identification of these assumptions in an important factor in planning basis development and establishes the planning baseline for all subsequent roadmap analysis at the INEL.

Not Available

1993-05-01T23:59:59.000Z

20

Oak Ridge National Laboratory Waste Management Plan. Revision 1  

SciTech Connect (OSTI)

The goal of the Oak Ridge National Laboratory (ORNL) Waste Management Program is the protection of workers, the public, and the environment. A vital aspect of this goal is to comply with all applicable state, federal, and DOE requirements. Waste management requirements for DOE radioactive wastes are detailed in DOE Order 5820.2A, and the ORNL Waste Management Program encompasses all elements of this order. The requirements of this DOE order and other appropriate DOE orders, along with applicable Tennessee Department of Environment and Conservation (TDEC) and US Environmental Protection Agency (EPA) rules and regulations, provide the principal source of regulatory guidance for waste management operations at ORNL. The objective of the Oak Ridge National Laboratory Waste Management Plan is to compile and to consolidate information annually on how the ORNL Waste Management is to compile and to consolidate information annually on how the ORNL Waste Management Program is conducted, which waste management facilities are being used to manage wastes, what forces are acting to change current waste management systems, what activities are planned for the forthcoming fiscal year (FY), and how all of the activities are documented.

Not Available

1991-12-01T23:59:59.000Z

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


21

How to Integrate Climate Change Adaptation into National-Level...  

Open Energy Info (EERE)

Integrate Climate Change Adaptation into National-Level Policy and Planning in the Water Sector Jump to: navigation, search Tool Summary LAUNCH TOOL Name: How to Integrate Climate...

22

Underground Test Area Quality Assurance Project Plan Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

This Quality Assurance Project Plan (QAPP) provides the overall quality assurance (QA) program requirements and general quality practices to be applied to the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Underground Test Area (UGTA) Sub-Project (hereafter the Sub-Project) activities. The requirements in this QAPP are consistent with DOE Order 414.1C, Quality Assurance (DOE, 2005); U.S. Environmental Protection Agency (EPA) Guidance for Quality Assurance Project Plans for Modeling (EPA, 2002); and EPA Guidance on the Development, Evaluation, and Application of Environmental Models (EPA, 2009). The QAPP Revision 0 supersedes DOE--341, Underground Test Area Quality Assurance Project Plan, Nevada Test Site, Nevada, Revision 4.

Irene Farnham

2011-05-01T23:59:59.000Z

23

Survey of National Programs for Managing High-Level Radioactive  

E-Print Network [OSTI]

Survey of National Programs for Managing High-Level Radioactive Waste and Spent Nuclear Fuel-Level Radioactive Waste and Spent Nuclear Fuel A Report to Congress and the Secretary of Energy October 2009 #12 Safety (Germany) Peter De Preter: National Agency for Radioactive Waste and Enriched Fissile Materials

24

Sandia National Laboratories: system-level monitoring  

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1developmentturbineredox-activeNational Solar Thermalsslsstudy

25

2013 Idaho National Laboratory Water Use Report and Comprehensive Well Inventory (Revision 22)  

SciTech Connect (OSTI)

This 2013 Idaho National Laboratory Water Use Report and Comprehensive Well Inventory (Revision 22) provides water use information for production and potable water wells at the Idaho National Laboratory for Calendar Year 2013. It also provides detailed information for new, modified, and decommissioned wells and holes. Two new wells were drilled and completed in Calendar Year 2013. No modifications were performed on any wells. Seven wells were decommissioned in Calendar Year 2013. Detailed construction information for the new and decommissioned wells is provided. Location maps are included, provided survey information was available. This report is being submitted in accordance with the Water Rights Agreement between the State of Idaho and the United States, for the United States Department of Energy (dated 1990) and the subsequent Partial Decree for Water Right 34-10901 issued June 20, 2003.

Mike Lewis

2014-06-01T23:59:59.000Z

26

2010 Idaho National Laboratory Water Use Report and Comprehensive Well Inventory (Revision 19)  

SciTech Connect (OSTI)

This 2010 Idaho National Laboratory Water Use Report and Comprehensive Well Inventory (Revision 19) provides water use information (monthly annual average and total annual volume) for production and potable water wells at the Idaho National Laboratory for Calendar Year 2010. It also provides detailed information for new, modified, and abandoned (decommissioned) wells and holes. Five new wells were drilled and completed in the latter part of Calendar Years 2009 and 2010. Two wells were modified in Calendar Year 2010 and 66 wells and boreholes reported as abandoned (decommissioned). Detailed construction information for the new and modified wells, along with abandonment information for older wells, is provided. Location maps are provided if survey information was available. This report is being submitted in accordance with the Water Rights Agreement between the State of Idaho and the United States, for the United States Department of Energy (dated 1990) and the subsequent Partial Decree for Water Right 34-10901 issued June 20, 2003.

Mike Lewis

2011-06-01T23:59:59.000Z

27

2011 Idaho National Laboratory Water Use Report and Comprehensive Well Inventory (Revision 20)  

SciTech Connect (OSTI)

This 2011 Idaho National Laboratory Water Use Report and Comprehensive Well Inventory (Revision 20) provides water use information (monthly annual average and total annual volume) for production and potable water wells at the Idaho National Laboratory for Calendar Year 2011. It also provides detailed information for new, modified, and abandoned (decommissioned) wells and holes. One new well was drilled and completed and one well was modified in Calendar Year 2011. A total of 14 wells and boreholes were reported as decommissioned. Detailed construction information for the new and modified wells is provided. Details are provided for the wells and boreholes that have been decommissioned, and if available, construction diagrams. Location maps are included, provided survey information was available. This report is being submitted in accordance with the Water Rights Agreement between the State of Idaho and the United States, for the United States Department of Energy (dated 1990) and the subsequent Partial Decree for Water Right 34-10901 issued June 20, 2003.

Renee Bowser

2012-06-01T23:59:59.000Z

28

A model for a national low level waste program  

SciTech Connect (OSTI)

A national program for the management of low level waste is essential to the success of environmental clean-up, decontamination and decommissioning, current operations and future missions. The value of a national program is recognized through procedural consistency and a shared set of resources. A national program requires a clear waste definition and an understanding of waste characteristics matched against available and proposed disposal options. A national program requires the development and implementation of standards and procedures for implementing the waste hierarchy, with a specitic emphasis on waste avoidance, minimization and recycling. It requires a common set of objectives for waste characterization based on the disposal facility's waste acceptance criteria, regulatory and license requirements and performance assessments. Finally, a national waste certification program is required to ensure compliance. To facilitate and enhance the national program, a centralized generator services organization, tasked with providing technical services to the generators on behalf of the national program, is necessary. These subject matter experts are the interface between the generating sites and the disposal facility(s). They provide an invaluable service to the generating organizations through their involvement in waste planning prior to waste generation and through championing implementation of the waste hierarchy. Through their interface, national treatment and transportation services are optimized and new business opportunities are identified. This national model is based on extensive experience in the development and on-going management of a national transuranic waste program and management of the national repository, the Waste Isolation Pilot Plant. The Low Level Program at the Savannah River Site also successfully developed and implemented the waste hierarchy, waste certification and waste generator services concepts presented below. The Savannah River Site services over forty generators and has historically managed over 12,000 cubic meters of low level waste annually. The results of the waste minimization program at the site resulted in over 900 initiatives, avoiding over 220,000 cubic meters of waste for a life cycle cost savings of $275 million. At the Los Alamos National Laboratory, the low level waste program services over 20 major generators and several hundred smaller generators that produce over 4,000 cubic meters of low level waste annually. The Los Alamos National Laboratory low level waste program utilizes both on-site and off-site disposal capabilities. Off-site disposal requires the implementation of certification requirements to utilize both federal and commercial options. The Waste Isolation Pilot Plant is the US Department of Energy's first deep geological repository for the permanent disposal of Transuanic waste. Transuranic waste was generated and retrievably stored at 39 sites across the US. Transuranic waste is defined as waste with a radionuclide concentration equal to or greater than 100 nCi/g consisting of radionuclides with half-lives greater than 20 years and with an atomic mass greater than uranium. Combining the lessons learned from the national transuranic waste program, the successful low level waste program at Savannah River Site and the experience of off-site disposal options at Los Alamos National Laboratory provides the framework and basis for developing a viable national strategy for managing low level waste.

Blankenhorn, James A [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

29

Groundwater level status report for 2009, Los Alamos National Laboratory  

SciTech Connect (OSTI)

The status of groundwater level monitoring at Los Alamos National Laboratory in 2009 is provided in this report. This report summarizes groundwater level data for 179 monitoring wells, including 55 regional aquifer wells (including 11 regional/intermediate wells), 26 intermediate wells, 98 alluvial wells, and 12 water supply wells. Pressure transducers were installed in 161 monitoring wells for continuous monitoring of groundwater levels. Time-series hydrographs of groundwater level data are presented along with pertinent construction and location information for each well. The report also summarizes the groundwater temperatures recorded in intermediate and regional aquifer monitoring wells.

Koch, Richard J.; Schmeer, Sarah

2010-03-01T23:59:59.000Z

30

Groundwater level status report for 2010, Los Alamos National Laboratory  

SciTech Connect (OSTI)

The status of groundwater level monitoring at Los Alamos National Laboratory in 2010 is provided in this report. This report summarizes groundwater level data for 194 monitoring wells, including 63 regional aquifer wells (including 10 regional/intermediate wells), 34 intermediate wells, 97 alluvial wells, and 12 water supply wells. Pressure transducers were installed in 162 monitoring wells for continuous monitoring of groundwater levels. Time-series hydrographs of groundwater level data are presented along with pertinent construction and location information for each well. The report also summarizes the groundwater temperatures recorded in intermediate and regional aquifer monitoring wells and seasonal responses to snowmelt runoff observed in intermediate wells.

Koch, Richard J.; Schmeer, Sarah

2011-03-01T23:59:59.000Z

31

Groundwater level status report for 2008, Los Alamos National Laboratory  

SciTech Connect (OSTI)

The status of groundwater level monitoring at Los Alamos National Laboratory in 2008 is provided in this report. This report summarizes groundwater level data for 179 monitoring wells, including 45 regional aquifer wells, 28 intermediate wells, 8 regional/intermediate wells, 106 alluvial wells, and 12 water supply wells. Pressure transducers were installed in 166 monitoring wells for continuous monitoring of groundwater levels. Time-series hydrographs of groundwater level data are presented along with pertinent construction and location information for each well. The report also summarizes the groundwater temperatures recorded in intermediate and regional aquifer monitoring wells.

Koch, Richard J.; Schmeer, Sarah

2009-03-01T23:59:59.000Z

32

The structure and intensity of energy use: Trends in five OECD nations. Revision  

SciTech Connect (OSTI)

This paper examines trends in the structure and intensity of final energy demand in five OECD nations between 1973 and 1988. Our focus is on primary energy use, which weights fuels by their thermal content and multiplies district heat and electricity by factors of 1.15 and 3.24 to approximate the losses that occur in the conversion and distribution of these energy carriers. Grouch in the level of energy-using activities, given 1973 energy intensities (energy use per unit of activity), would have raised primary energy use by 46% in the US, 42% in Norway, 33% in Denmark, 37% in West Germany, and 53% in Japan. Reductions in end-use energy intensities, given 1973 activity levels, would have reduced primary energy use by 19% in the US, 3% in Norway, 20% in Denmark, 15% in West Germany, and l4% in Japan. Growth in national income parallelled increases in a weighted index of energy-using activities in the US, West Germany, and Denmark but substantially outstripped activity growth in Norway and Japan. We conclude that changes in the structure of a nation`s economy may lead to substantial changes in its energy/GDP ratio that are unrelated to changes in the technical efficiency of energy utilization. Similarly, changes in energy intensities may be greater or less than the aggregate change in the energy/GDP ratio of a given country, a further warning that this ratio may be an unreliable indicator of technical efficiency.

Howarth, R.B.; Schipper, L. [Lawrence Berkeley Lab., CA (United States); Andersson, B. [Stockholm School of Economics (Sweden)

1992-09-01T23:59:59.000Z

33

Hanford Site National Environmental Policy Act (NEPA) Characterization Report, Revision 17  

SciTech Connect (OSTI)

This document describes the U.S. Department of Energy’s (DOE) Hanford Site environment. It is updated each year and is intended to provide a consistent description of the Hanford Site environment for the many environmental documents being prepared by DOE contractors concerning the National Environmental Policy Act (NEPA). No statements about significance or environmental consequences are provided. This year’s report is the seventeenth revision of the original document published in 1988 and is (until replaced by the eighteenth revision) the only version that is relevant for use in the preparation of Hanford NEPA, State Environmental Policy Act (SEPA), and Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) documents. The two chapters included in this document (Chapters 4 and 6) are numbered to correspond to the chapters where such information is typically presented in environmental impact statements (EISs) and other Hanford Site NEPA or CERCLA documentation. Chapter 4.0 (Affected Environment) describes Hanford Site climate and meteorology; air quality; geology; hydrology; ecology; cultural, archaeological, and historical resources; socioeconomics; noise; and occupational health and safety. Sources for extensive tabular data related to these topics are provided in the chapter. Most subjects are divided into a general description of the characteristics of the Hanford Site, followed by site-specific information, where available, of the 100, 200, 300, and other areas. This division allows the reader to go directly to those sections of particular interest. When specific information on each of these separate areas is not complete or available, the general Hanford Site description should be used. Chapter 6.0 (Statutory and Regulatory Requirements) describes federal and state laws and regulations, DOE directives and permits, and presidential executive orders that are applicable to the NEPA documents prepared for Hanford Site activities. Information in Chapter 6 of this document can be adapted and supplemented with specific information for a chapter covering statutory and regulatory requirements in an environmental assessment or environmental impact statement. When preparing environmental assessments and EISs, authors should also be cognizant of the document titled Recommendations for the Preparation of Environmental Assessments and Environmental Impact Statements published by the DOE Office of NEPA Oversight (DOE 2004). Additional guidance on preparing DOE NEPA documents can be found at http://tis.eh.doe.gov/nepa/guidance.html. Any interested individual seeking baseline data on the Hanford Site and its past activities may also use the information contained in this document to evaluate projected activities and their impacts. For this 2005 revision, the following sections of the document were reviewed by the authors and updated with the best available information through May 2005: Climate and Meteorology Air Quality Geology – Seismicity section only Hydrology – Flow charts for the Columbia and Yakima rivers only Ecology – Threatened and Endangered Species subsection only Socioeconomics Occupational Safety All of Chapter 6.

Neitzel, Duane A.; Bunn, Amoret L.; Cannon, Sandra D.; Duncan, Joanne P.; Fowler, Richard A.; Fritz, Brad G.; Harvey, David W.; Hendrickson, Paul L.; Hoitink, Dana J.; Horton, Duane G.; Last, George V.; Poston, Ted M.; Prendergast-Kennedy, Ellen L.; Reidel, Steve P.; Rohay, Alan C.; Sackschewsky, Michael R.; Scott, Michael J.; Thorne, Paul D.

2005-09-30T23:59:59.000Z

34

The Usefulness of Bi-Level Switching; Original Technical Note: November 1998. Revised August, 1999  

SciTech Connect (OSTI)

California's Title 24 Energy Efficiency Building Standard requires multiple lighting level control in all individual offices. Usually, this requirement is fulfilled using bi-level switching. With bi-level switching, each office occupant is provided with two wall switches near the doorway to control their lights. In a typical installation, one switch would control 1/3 of the fluorescent lamps in the ceiling lighting system, while the other switch would control the remaining 2/3 of the lamps. This allows four possible light levels: OFF, 1/3, 2/3 and FULL lighting. Because it has been required by building code since 1983, bi-level switching is common in California office buildings. However, there is no published evidence showing that occupants sometimes use just one switch rather than just switching on both switches when entering the room. Consequently, some have questioned whether bi-level switching is a necessary or desirable requirement for typical office buildings. In fact, the draft national standard, ASHRAE Standard 90.1-1989K apparently does not require bi-level switching at all.

Building Technologies Department

1998-11-01T23:59:59.000Z

35

Underground Test Area Fiscal Year 2012 Annual Quality Assurance Report Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

This report is mandated by the Underground Test Area (UGTA) Quality Assurance Project Plan (QAPP) and identifies the UGTA quality assurance (QA) activities for fiscal year (FY) 2012. All UGTA organizations—U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO); Desert Research Institute (DRI); Lawrence Livermore National Laboratory (LLNL); Los Alamos National Laboratory (LANL); Navarro-Intera, LLC (N-I); National Security Technologies, LLC (NSTec); and the U.S. Geological Survey (USGS)—conducted QA activities in FY 2012. The activities included conducting assessments, identifying findings and completing corrective actions, evaluating laboratory performance, revising the QAPP, and publishing documents. In addition, processes and procedures were developed to address deficiencies identified in the FY 2011 QAPP gap analysis.

Farnham, Irene; Marutzky, Sam

2013-01-01T23:59:59.000Z

36

Waste certification program plan for Oak Ridge National Laboratory. Revision 2  

SciTech Connect (OSTI)

This document defines the waste certification program (WCP) developed for implementation at Oak Ridge National Laboratory (ORNL). The document describes the program structure, logic, and methodology for certification of ORNL wastes. The purpose of the WCP is to provide assurance that wastes are properly characterized and that the Waste Acceptance Criteria (WAC) for receiving facilities are met. The program meets the waste certification requirements for mixed (both radioactive and hazardous) and hazardous [including polychlorinated biphenyls (PCB)] waste. Program activities will be conducted according to ORNL Level 1 document requirements.

Not Available

1997-09-01T23:59:59.000Z

37

Lesson Learned by Lawrence Livermore National Laboratory Activity-level Work Planning and Control  

Broader source: Energy.gov [DOE]

Slide Presentation by Donna J. Governor, Lawrence Livermore National Laboratory. Lessons Learned by Lawrence Livermore National Laboratory Activity-Level Work Planning & Control.

38

National Low-Level Waste Management Program Radionuclide Report Series  

SciTech Connect (OSTI)

This volume serves as an introduction to the National Low-Level Radioactive Waste Management Program Radionuclide Report Series. This report includes discussions of radionuclides listed in Title 10 of the Code of Federal Regulations Part 61.55, Tables 1 and 2 (including alpha-emitting transuranics with half-lives greater than five years). Each report includes information regarding radiological and chemical characteristics of specific radionuclides. Information is also included discussing waste streams and waste forms that may contain each radionuclide, and radionuclide behavior in the environment and in the human body. Not all radionuclides commonly found at low-level radioactive waste sites are included in this report. The discussion in this volume explains the rationale of the radionuclide selection process.

Rudin, M.J.; Garcia, R.S.

1992-02-01T23:59:59.000Z

39

Waste certification program plan for Oak Ridge National Laboratory. Revision 1  

SciTech Connect (OSTI)

This document defines the waste certification program developed for implementation at Oak Ridge National Laboratory (ORNL). The document describes the program structure, logic, and methodology for certification of ORNL wastes. The purpose of the waste certification program is to provide assurance that wastes are properly characterized and that the Waste Acceptance Criteria (WAC) for receiving facilities are met. The program meets the waste certification requirements outlined in US Department of Energy (DOE) Order 5820.2A, Radioactive Waste Management, and ensures that 40 CFR documentation requirements for waste characterization are met for mixed (both radioactive and hazardous) and hazardous (including polychlorinated biphenyls) waste. Program activities will be conducted according to ORNL Level 1 document requirements.

Orrin, R.C.

1997-05-01T23:59:59.000Z

40

Standard testing procedures for optical fiber and unshielded twisted pair at Sandia National Laboratories. Revision  

SciTech Connect (OSTI)

This revision updates Sandia`s working standard for testing optical fiber and unshielded twisted pair cables included in the Lab-wide telecommunications cabling infrastructure. The purpose of these standard testing procedures is to deliver to all Sandians a reliable, low-maintenance, state-of-the-art, ubiquitous telecommunications cabling infrastructure capable of satisfying all current and future telecommunication needs.

Adams, R.L. [Sandia National Labs., Albuquerque, NM (United States). Communications Dept.

1994-09-01T23:59:59.000Z

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


41

Likely social impacts of proposed national-level policy initiatives  

SciTech Connect (OSTI)

The results are described of an investigation of likely social effects of enacting nine proposed national-level policy initiatives to accelerate development and use of solar energy. This study is part of the Technology Assessment of Solar Energy Systems (TASE) project supported by the US Department of Energy. The report presents general social impact information about the variety of ways in which the American people could be affected by enactment of these initiatives. It identifies the effects of each initiative on individuals, groups, organizations, communities, and society as a whole. In addition, it provides a framework for organizing a myriad of impact information into a set of conceptually exclusive impact categories. It illustrates that social impacts means effects on people as individuals, groups, organizations, and communities as well as on the infrastructure of society. Finally, it demonstrates the importance of specifying an audience of impact with a case example from the residential rental market.

Piernot, C.A.; Rothweiler, M.A.; Levine, A.; Crews, R.

1981-03-01T23:59:59.000Z

42

Report on waste burial charges. Escalation of decommissioning waste disposal costs at low-level waste burial facilities, Revision 4  

SciTech Connect (OSTI)

One of the requirements placed upon nuclear power reactor licensees by the U.S. Nuclear Regulatory Commission (NRC) is for the licensees to periodically adjust the estimate of the cost of decommissioning their plants, in dollars of the current year, as part of the process to provide reasonable assurance that adequate funds for decommissioning will be available when needed. This report, which is scheduled to be revised periodically, contains the development of a formula for escalating decommissioning cost estimates that is acceptable to the NRC. The sources of information to be used in the escalation formula are identified, and the values developed for the escalation of radioactive waste burial costs, by site and by year, are given. The licensees may use the formula, the coefficients, and the burial escalation factors from this report in their escalation analyses, or they may use an escalation rate at least equal to the escalation approach presented herein. This fourth revision of NUREG-1307 contains revised spreadsheet results for the disposal costs for the reference PWR and the reference BWR and the ratios of disposal costs at the Washington, Nevada, and South Carolina sites for the years 1986, 1988, 1991 and 1993, superseding the values given in the May 1993 issue of this report. Burial cost surcharges mandated by the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) have been incorporated into the revised ratio tables for those years. In addition, spreadsheet results for the disposal costs for the reference reactors and ratios of disposal costs at the two remaining burial sites in Washington and South Carolina for the year 1994 are provided. These latter results do not include any LLRWPAA surcharges, since those provisions of the Act expired at the end of 1992. An example calculation for escalated disposal cost is presented, demonstrating the use of the data contained in this report.

Not Available

1994-06-01T23:59:59.000Z

43

Report on waste burial charges: Escalation of decommissioning waste disposal costs at Low-Level Waste Burial facilities. Revision 5  

SciTech Connect (OSTI)

One of the requirements placed upon nuclear power reactor licensees by the US Nuclear Regulatory Commission (NRC) is for the licensees to periodically adjust the estimate of the cost of decommissioning their plants, in dollars of the current year, as part of the process to provide reasonable assurance that adequate funds for decommissioning will be available when needed. This report, which is scheduled to be revised periodically, contains the development of a formula for escalating decommissioning cost estimates that is acceptable to the NRC. The sources of information to be used in the escalation formula are identified, and the values developed for the escalation of radioactive waste burial costs, by site and by year, are given. The licensees may use the formula, the coefficients, and the burial escalation factors from this report in their escalation analyses, or they may use an escalation rate at least equal to the escalation approach presented herein. This fifth revision of NUREG-1307 contains revised spreadsheet results for the disposal costs for the reference PWR and the reference BWR and the ratios of disposal costs at the Washington, Nevada, and South Carolina sites for the years 1986, 1988, 1991, 1993, and 1994, superseding the values given in the June 1994 issue of this report. Burial cost surcharges mandated by the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) have been incorporated into the revised ratio tables for those years. In addition, spreadsheet results for the disposal costs for the reference reactors and ratios of disposal costs at the two remaining burial sites in Washington and South Carolina for the year 1995 are provided. These latter results do not include any LLRWPAA surcharges, since those provisions of the Act expired at the end of 1992. An example calculation for escalated disposal cost is presented, demonstrating the use of the data contained in this report.

NONE

1995-08-01T23:59:59.000Z

44

Working with the National Center of Photovoltaics (NCPV) (Revised) (Fact Sheet)  

SciTech Connect (OSTI)

Capabilities fact sheet for the National Center for Photovoltaics: Working with the National Center for Photovoltaics. One-sided sheet that includes projects in various areas: Technology Pathway Partnerships, CRADAs, Incubator Program, Pre-Incubator Program, Universities, Next-Generation Program, and NREL T&E.

Not Available

2011-06-01T23:59:59.000Z

45

Assessment of Inundation Risk from Sea Level Rise and Storm Surge in Northeastern Coastal National Parks  

E-Print Network [OSTI]

Assessment of Inundation Risk from Sea Level Rise and Storm Surge in Northeastern Coastal National of inundation risk from sea level rise and storm surge in northeastern coastal national parks. Journal of Coastal Research, 00(0), 000­000. Coconut Creek (Florida), ISSN 0749-0208. Sea level rise and an increase

Wang, Y.Q. "Yeqiao"

46

National Fuel Cell Technology Evaluation Center (NFCTEC) (Revised) (Fact Sheet), Energy Systems Integration Facility (ESIF), NREL (National Renewable Energy Laboratory)  

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the Contributions andData andFleetEngineeringAnnual Report ThisNational Environmental

47

Sandia National Laboratories/New Mexico Environmental Baseline update--Revision 1.0  

SciTech Connect (OSTI)

This report provides a baseline update to provide the background information necessary for personnel to prepare clear and consise NEPA documentation. The environment of the Sandia National Laboratories is described in this document, including the ecology, meteorology, climatology, seismology, emissions, cultural resources and land use, visual resources, noise pollution, transportation, and socioeconomics.

NONE

1996-07-01T23:59:59.000Z

48

Idaho National Engineering Laboratory (INEL) Environmental Restoration Program (ERP), Baseline Safety Analysis File (BSAF). Revision 1  

SciTech Connect (OSTI)

This document was prepared to take the place of a Safety Evaluation Report since the Baseline Safety Analysis File (BSAF)and associated Baseline Technical Safety Requirements (TSR) File do not meet the requirements of a complete safety analysis documentation. Its purpose is to present in summary form the background of how the BSAF and Baseline TSR originated and a description of the process by which it was produced and approved for use in the Environmental Restoration Program.The BSAF is a facility safety reference document for INEL environmental restoration activities including environmental remediation of inactive waste sites and decontamination and decommissioning (D&D) of surplus facilities. The BSAF contains safety bases common to environmental restoration activities and guidelines for performing and documenting safety analysis. The common safety bases can be incorporated by reference into the safety analysis documentation prepared for individual environmental restoration activities with justification and any necessary revisions. The safety analysis guidelines in BSAF provide an accepted method for hazard analysis; analysis of normal, abnormal, and accident conditions; human factors analysis; and derivation of TSRS. The BSAF safety bases and guidelines are graded for environmental restoration activities.

Not Available

1994-06-20T23:59:59.000Z

49

Background Information for the Nevada National Security Site Integrated Sampling Plan, Revision 0  

SciTech Connect (OSTI)

This document describes the process followed to develop the Nevada National Security Site (NNSS) Integrated Sampling Plan (referred to herein as the Plan). It provides the Plan’s purpose and objectives, and briefly describes the Underground Test Area (UGTA) Activity, including the conceptual model and regulatory requirements as they pertain to groundwater sampling. Background information on other NNSS groundwater monitoring programs—the Routine Radiological Environmental Monitoring Plan (RREMP) and Community Environmental Monitoring Program (CEMP)—and their integration with the Plan are presented. Descriptions of the evaluations, comments, and responses of two Sampling Plan topical committees are also included.

Farnham, Irene; Marutzky, Sam

2014-12-01T23:59:59.000Z

50

Overview of groundwater and surface water standards pertinent to the Idaho National Engineering Laboratory. Revision 3  

SciTech Connect (OSTI)

This document presents an overview of groundwater- and surface water-related laws, regulations, agreements, guidance documents, Executive Orders, and DOE orders pertinent to the Idaho National Engineering Laboratory. This document is a summary and is intended to help readers understand which regulatory requirements may apply to their particular circumstances. However, the document is not intended to be used in lieu of applicable regulations. Unless otherwise noted, the information in this report reflects a summary and evaluation completed July 1, 1995. This document is considered a Living Document, and updates on changing laws and regulations will be provided.

Lundahl, A.L.; Williams, S.; Grizzle, B.J.

1995-09-01T23:59:59.000Z

51

Ethanol Vehicle and Infrastructure Codes and Standards Chart (Revised) (Fact Sheet), NREL (National Renewable Energy Laboratory)  

Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative Fuels Data CenterEnergyAuthorization for(EV) Road User AssessmentNREL is a national

52

Los Alamos National Laboratory transuranic waste quality assurance project plan. Revision 1  

SciTech Connect (OSTI)

This Transuranic (TRU) Waste Quality Assurance Project Plan (QAPjP) serves as the quality management plan for the characterization of transuranic waste in preparation for certification and transportation. The Transuranic Waste Characterization/Certification Program (TWCP) consists of personnel who sample and analyze waste, validate and report data; and provide project management, quality assurance, audit and assessment, and records management support, all in accordance with established requirements for disposal of TRU waste at the Waste Isolation Pilot Plant (WIPP) facility. This QAPjP addresses how the TWCP meets the quality requirements of the Carlsbad Area Office (CAO) Quality Assurance Program Description (QAPD) and the technical requirements of the Transuranic Waste Characterization Quality Assurance Program Plan (QAPP). The TWCP characterizes and certifies retrievably stored and newly generated TRU waste using the waste selection, testing, sampling, and analytical techniques and data quality objectives (DQOs) described in the QAPP, the Los Alamos National Laboratory Transuranic Waste Certification Plan (Certification Plan), and the CST Waste Management Facilities Waste Acceptance Criteria and Certification [Los Alamos National Laboratory (LANL) Waste Acceptance Criteria (WAC)]. At the present, the TWCP does not address remote-handled (RH) waste.

NONE

1997-04-14T23:59:59.000Z

53

Evaluation of Conservation Voltage Reduction (CVR) on a National Level  

SciTech Connect (OSTI)

Conservation Voltage Reduction (CVR) is a reduction of energy consumption resulting from a reduction of feeder voltage. While there have been numerous CVR systems deployed in North America there has been little substantive analytic analysis of the effect; the majority of the published results are based on empirical field measurements. Since these results are based on empirical measurements it is difficult to extrapolate how this technology will behave on the various types of distribution feeders found throughout the nation. This report has utilized the Taxonomy of Prototypical feeder developed under the Modern Grid Initiative (MGI), now the Modern Grid Strategy (MGS), in order to estimate the benefits of CVR on multiple distribution feeder types. This information will then be used to determine an estimate of the national benefits of a wide scale deployment of CVR.

Schneider, Kevin P.; Fuller, Jason C.; Tuffner, Francis K.; Singh, Ruchi

2010-09-29T23:59:59.000Z

54

Sandia National Laboratories: understand the atomic-level processes of  

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1developmentturbineredox-activeNational SolartSSLPVinteractionhydrocarbonshydrogen

55

Closure Report for Corrective Action Unit 465: Hydronuclear Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

The corrective action sites (CASs) within CAU 465 are located within Areas 6 and 27 of the NNSS. CAU 465 comprises the following CASs: • 00-23-01, Hydronuclear Experiment, located in Area 27 of the NNSS and known as the Charlie site. • 00-23-02, Hydronuclear Experiment, located in Area 27 of the NNSS and known as the Dog site. • 00-23-03, Hydronuclear Experiment, located in Area 27 of the NNSS and known as the Charlie Prime and Anja sites. • 06-99-01, Hydronuclear, located in Area 6 of the NNSS and known as the Trailer 13 site. The purpose of this CR is to provide documentation supporting the completed corrective actions and provide data confirming that the closure objectives for CASs within CAU 465 were met. From September 2011 through July 2012, closure activities were performed as set forth in the Streamlined Approach for Environmental Restoration Plan for CAU 465: Hydronuclear, Nevada National Security Site, Nevada.

Mark Burmeister and Patrick Matthews

2012-11-01T23:59:59.000Z

56

National Synchrotron Light Source Facility Manual Maintenance Management Program. Revision 1  

SciTech Connect (OSTI)

The purpose of this program s to meet the policy and objectives for the management and performance of cost-effective maintenance and repair of the National Synchrotron Light Source, as required by the US Department of Energy order DOE 433O.4A. It is the DOE`s policy that: The maintenance management program for the NSLS be consistent with this Order and that NSLS property is maintained in a manner which promotes operational safety, worker health, environmental protection and compliance, property preservation, and cost-effectiveness while meeting the NSLS`s programmatic mission. Structures, components and systems (active and passive) that are imporant to safe operation of the NSLS shall be subject to a maintenance program to ensure that they meet or exceed their design requirements throughout the life of the NSLS. Periodic examination of structures, systems components and equipment be performed to determine deterioration or technical obsolescence which may threaten performance and/or safety. Primary responsibility, authority, and accountability for the direction and management of the maintenance program at the NSLS reside with the line management assigned direct programmatic responsibility. Budgeting and accounting for maintenance programs are consistent with DOE Orders guidance.

Fewell, N.

1993-12-01T23:59:59.000Z

57

Site safety plan for Lawrence Livermore National Laboratory CERCLA investigations at site 300. Revision 2  

SciTech Connect (OSTI)

Various Department of Energy Orders incorporate by reference, health and safety regulations promulgated by the Occupational Safety and Health Administration (OSHA). One of the OSHA regulations, 29 CFR 1910.120, Hazardous Waste Operations and Emergency Response, requires that site safety plans are written for activities such as those covered by work plans for Site 300 environmental investigations. Based upon available data, this Site Safety Plan (Plan) for environmental restoration has been prepared specifically for the Lawrence Livermore National Laboratory Site 300, located approximately 15 miles east of Livermore, California. As additional facts, monitoring data, or analytical data on hazards are provided, this Plan may need to be modified. It is the responsibility of the Environmental Restoration Program and Division (ERD) Site Safety Officer (SSO), with the assistance of Hazards Control, to evaluate data which may impact health and safety during these activities and to modify the Plan as appropriate. This Plan is not `cast-in-concrete.` The SSO shall have the authority, with the concurrence of Hazards Control, to institute any change to maintain health and safety protection for workers at Site 300.

Kilmer, J.

1997-08-01T23:59:59.000Z

58

Fermilab Engineering Manual Appendices Revision 1.0  

E-Print Network [OSTI]

Fermilab Engineering Manual Appendices Revision 1.0 Page 1 FERMI NATIONAL ACCELERATOR LABORATORY:__________________________ DATE:_________ REVISION NO.________ REVISION ISSUE DATE:____________ #12;Fermilab Engineering Manual ..................................... 166 #12;Fermilab Engineering Manual Appendices Revision 1.0 Page 3 A. REQUIREMENTS AND SPECIFICATIONS

Quigg, Chris

59

Oak Ridge National Laboratory Waste Management Plan, fiscal year 1994. Revision 3  

SciTech Connect (OSTI)

US Department of Energy (DOE) Order 5820.2A was promulgated in final form on September 26, 1988. The order requires heads of field organizations to prepare and to submit updates on the waste management plans for all operations under their purview according to the format in Chap. 6, {open_quotes}Waste Management Plan Outline.{close_quotes} These plans are to be submitted by the DOE Oak Ridge Operations Office (DOE-ORO) in December of each year and distributed to the DP-12, ES&H-1, and other appropriate DOE Headquarters (DOE-HQ) organizations for review and comment. This document was prepared in response to this requirement for fiscal year (FY) 1994. The Oak Ridge National Laboratory (ORNL) waste management mission is reduction, collection, storage, treatment, and disposal of DOE wastes, generated primarily in pursuit of ORNL missions, in order to protect human health and safety and the environment. In carrying out this mission, waste management staff in the Waste Management and Remedial Action Division (WMRAD) will (1) guide ORNL in optimizing waste reduction and waste management capabilities and (2) conduct waste management operations in a compliant, publicly acceptable, technically sound, and cost-efficient manner. Waste management requirements for DOE radioactive wastes are detailed in DOE Order 5820.2A, and the ORNL Waste Management Program encompasses all elements of this order. The requirements of this DOE order and other appropriate DOE orders, along with applicable Tennessee Department of Environment and Conservation and US Environmental Protection Agency (EPA) rules and regulations, provide the principal source of regulatory guidance for waste management operations at ORNL. The objective of this document is compilation and consolidation of information on how the ORNL Waste Management Program is conducted, which waste management facilities are being used to manage wastes, what activities are planned for FY 1994, and how all of the activities are documented.

Turner, J.W. [ed.

1993-12-01T23:59:59.000Z

60

Implementation plan for liquid low-level radioactive waste systems under the FFA for fiscal years 1996 and 1997 at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

This document is the fourth annual revision of the plans and schedules for implementing the Federal Facility Agreement (FFA) compliance program, originally submitted in 1992 as ES/ER-17&D1, Federal Facility Agreement Plans and Schedules for Liquid Low-Level Radioactive Waste Tank Systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee. This document summarizes the progress that has been made to date implementing the plans and schedules for meeting the FFA commitments for the Liquid Low-Level Waste (LLLW) System at Oak Ridge National Laboratory (ORNL). In addition, this document lists FFA activities planned for FY 1997. Information presented in this document provides a comprehensive summary to facilitate understanding of the FFA compliance program for LLLW tank systems and to present plans and schedules associated with remediation, through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) process, of LLLW tank systems that have been removed from service.

NONE

1996-06-01T23:59:59.000Z

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


61

How El Nino affects energy consumption: a study at national and regional levels  

E-Print Network [OSTI]

for home heating purposes. Hydroelectricity may also be affected by ENSO in the southeastern US but the results at this time are inconclusive. At the national level, ENSO influences the consumption of nuclear electricity....

Collins, Kathleen Jo

2009-06-02T23:59:59.000Z

62

EA-0843: Idaho National Engineering Laboratory Low-Level and Mixed Waste Processing, Idaho Falls, Idaho  

Broader source: Energy.gov [DOE]

This EA evaluates the environmental impacts of a proposal to (1) reduce the volume of the U.S. Department of Energy's Idaho National Engineering Laboratory's (INEL) generated low-level waste (LLW)...

63

Entry-Level Positions | National Nuclear Security Administration  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-Series toESnet4: Networking for37EnergyNuclearEnterprise-WideEconomicEntry-Level

64

Waste minimization for commercial radioactive materials users generating low-level radioactive waste. Revision 1  

SciTech Connect (OSTI)

The objective of this document is to provide a resource for all states and compact regions interested in promoting the minimization of low-level radioactive waste (LLW). This project was initiated by the Commonwealth of Massachusetts, and Massachusetts waste streams have been used as examples; however, the methods of analysis presented here are applicable to similar waste streams generated elsewhere. This document is a guide for states/compact regions to use in developing a system to evaluate and prioritize various waste minimization techniques in order to encourage individual radioactive materials users (LLW generators) to consider these techniques in their own independent evaluations. This review discusses the application of specific waste minimization techniques to waste streams characteristic of three categories of radioactive materials users: (1) industrial operations using radioactive materials in the manufacture of commercial products, (2) health care institutions, including hospitals and clinics, and (3) educational and research institutions. Massachusetts waste stream characterization data from key radioactive materials users in each category are used to illustrate the applicability of various minimization techniques. The utility group is not included because extensive information specific to this category of LLW generators is available in the literature.

Fischer, D.K.; Gitt, M.; Williams, G.A.; Branch, S. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Otis, M.D.; McKenzie-Carter, M.A.; Schurman, D.L. [Science Applications International Corp., Idaho Falls, ID (United States)

1991-07-01T23:59:59.000Z

65

National low-level waste management program radionuclide report series, Volume 15: Uranium-238  

SciTech Connect (OSTI)

This report, Volume 15 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of uranium-238 ({sup 238}U). The purpose of the National Low-Level Waste Management Program Radionuclide Report Series is to provide information to state representatives and developers of low-level radioactive waste disposal facilities about the radiological, chemical, and physical characteristics of selected radionuclides and their behavior in the waste disposal facility environment. This report also includes discussions about waste types and forms in which {sup 238}U can be found, and {sup 238}U behavior in the environment and in the human body.

Adams, J.P.

1995-09-01T23:59:59.000Z

66

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

SciTech Connect (OSTI)

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.

Mark Krauss

2011-06-01T23:59:59.000Z

67

Mixed Waste Management Options: 1995 Update. National Low-Level Waste Management Program  

SciTech Connect (OSTI)

In the original mixed Waste Management Options (DOE/LLW-134) issued in December 1991, the question was posed, ``Can mixed waste be managed out of existence?`` That study found that most, but not all, of the Nation`s mixed waste can theoretically be managed out of existence. Four years later, the Nation is still faced with a lack of disposal options for commercially generated mixed waste. However, since publication of the original Mixed Waste Management Options report in 1991, limited disposal capacity and new technologies to treat mixed waste have become available. A more detailed estimate of the Nation`s mixed waste also became available when the US Environmental Protection Agency (EPA) and the US Nuclear Regulatory Commission (NRC) published their comprehensive assessment, titled National Profile on Commercially Generated Low-Level Radioactive Mixed Waste (National Profile). These advancements in our knowledge about mixed waste inventories and generation, coupled with greater treatment and disposal options, lead to a more applied question posed for this updated report: ``Which mixed waste has no treatment option?`` Beyond estimating the volume of mixed waste requiring jointly regulated disposal, this report also provides a general background on the Atomic Energy Act (AEA) and the Resource Conservation and Recovery Act (RCRA). It also presents a methodical approach for generators to use when deciding how to manage their mixed waste. The volume of mixed waste that may require land disposal in a jointly regulated facility each year was estimated through the application of this methodology.

Kirner, N.; Kelly, J.; Faison, G.; Johnson, D. [Foster Wheeler Environmental Corp. (United States)

1995-05-01T23:59:59.000Z

68

Long-Term National Impacts of State-Level Policies: Preprint  

SciTech Connect (OSTI)

This paper presents analysis conducted with the Wind Deployment System Model (WinDS) -- a model of capacity expansion in the U.S. electric sector. With 358 regions covering the United States, detailed transmission system representation, and an explicit treatment of wind intermittency and ancillary services, WinDS is uniquely positioned to evaluate the market impacts of specific state-level policies. This paper provides analysis results regarding the impact of existing state-level policies designed to promote wind-capacity expansion, including state portfolio standards, mandates, and tax credits. The results show the amount of wind deployment due to current state-level incentives as well as examine their lasting impact on the national wind industry. For example, state-level mandates increase industry size and lower costs, which result in wind capacity increases in states without mandates and greater market growth even after the policies expire. Although these policies are enacted by individual states, the cumulative effect must be examined at a national level. Finally, this paper examines the impact on wind-capacity growth by increasing the penalty associated with the state-level renewable portfolio standards (RPS). The results show national and regional wind energy deployment and generation through 2050.

Blair, N.; Short, W.; Denholm, P.; Heimiller, D.

2006-06-01T23:59:59.000Z

69

National Low-Level Waste Management Program radionuclide report series. Volume 13, Curium-242  

SciTech Connect (OSTI)

This report, Volume 13 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of curium-242 ({sup 242}Cm). This report also includes discussions about waste types and forms in which {sup 242}Cm can be found and {sup 242}Cm behavior in the environment and in the human body.

Adams, J.P.

1995-08-01T23:59:59.000Z

70

National Low-Level Waste Management Program Radionuclide Report Series, Volume 17: Plutonium-239  

SciTech Connect (OSTI)

This report, Volume 17 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of plutonium-239 (Pu-239). This report also discusses waste types and forms in which Pu-239 can be found, waste and disposal information on Pu-239, and Pu-239 behavior in the environment and in the human body.

J. P. Adams; M. L. Carboneau

1999-03-01T23:59:59.000Z

71

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

SciTech Connect (OSTI)

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

Grant Evenson

2012-05-01T23:59:59.000Z

72

Derived concentration guideline levels for Argonne National Laboratory's building 310 area.  

SciTech Connect (OSTI)

The derived concentration guideline level (DCGL) is the allowable residual radionuclide concentration that can remain in soil after remediation of the site without radiological restrictions on the use of the site. It is sometimes called the single radionuclide soil guideline or the soil cleanup criteria. This report documents the methodology, scenarios, and parameters used in the analysis to support establishing radionuclide DCGLs for Argonne National Laboratory's Building 310 area.

Kamboj, S., Dr.; Yu, C ., Dr. (Environmental Science Division)

2011-08-12T23:59:59.000Z

73

Underground Test Area Fiscal Year 2013 Annual Quality Assurance Report Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

This report is required by the Underground Test Area (UGTA) Quality Assurance Plan (QAP) and identifies the UGTA quality assurance (QA) activities for fiscal year (FY) 2013. All UGTA organizations—U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO); Desert Research Institute (DRI); Lawrence Livermore National Laboratory (LLNL); Los Alamos National Laboratory (LANL); Navarro-Intera, LLC (N-I); National Security Technologies, LLC (NSTec); and the U.S. Geological Survey (USGS)—conducted QA activities in FY 2013. The activities included conducting assessments, identifying findings and completing corrective actions, evaluating laboratory performance, and publishing documents. In addition, integrated UGTA required reading and corrective action tracking was instituted.

Krenzien, Susan; Marutzky, Sam

2014-01-01T23:59:59.000Z

74

National profile on commercially generated low-level radioactive mixed waste  

SciTech Connect (OSTI)

This report details the findings and conclusions drawn from a survey undertaken as part of a joint US Nuclear Regulatory Commission and US Environmental Protection Agency-sponsored project entitled ``National Profile on Commercially Generated Low-Level Radioactive Mixed Waste.`` The overall objective of the work was to compile a national profile on the volumes, characteristics, and treatability of commercially generated low-level mixed waste for 1990 by five major facility categories-academic, industrial, medical, and NRC-/Agreement State-licensed goverment facilities and nuclear utilities. Included in this report are descriptions of the methodology used to collect and collate the data, the procedures used to estimate the mixed waste generation rate for commercial facilities in the United States in 1990, and the identification of available treatment technologies to meet applicable EPA treatment standards (40 CFR Part 268) and, if possible, to render the hazardous component of specific mixed waste streams nonhazardous. The report also contains information on existing and potential commercial waste treatment facilities that may provide treatment for specific waste streams identified in the national survey. The report does not include any aspect of the Department of Energy`s (DOES) management of mixed waste and generally does not address wastes from remedial action activities.

Klein, J.A.; Mrochek, J.E.; Jolley, R.L.; Osborne-Lee, I.W.; Francis, A.A.; Wright, T. [Oak Ridge National Lab., TN (United States)

1992-12-01T23:59:59.000Z

75

Low-level radioactive waste disposal operations at Los Alamos National Laboratory  

SciTech Connect (OSTI)

Los Alamos National Laboratory (LANL) generates Low-Level Radioactive Waste (LLW) from various activities: research and development, sampling and storage of TRU wastes, decommissioning and decontamination of facilities, and from LANL`s major role in stockpile stewardship. The Laboratory has its own active LLW disposal facility located at Technical Area 54, Area G. This paper will identify the current operations of the facility and the issues pertaining to operating a disposal facility in today`s compliance and cost-effective environment.

Stanford, A.R.

1997-02-01T23:59:59.000Z

76

Lead-acid load-leveling battery testing at Argonne National Laboratory  

SciTech Connect (OSTI)

Argonne National Laboratory (ANL) has conducted an extensive evaluation of an advanced lead-acid battery development for load-leveling applications. The battery technology was developed by the Exide Corporation under a DOE-sponsored cost-shared R and D contract with ANL during 1979-1982. The objective of that program was to increase battery life from 2000 to 4000 deep discharge cycles while maintaining or reducing initial battery cost. Full-size, 3100-Ah cells were fabricated by Exide and assembled into one 6-cell and two 3-cell batteries. These 36-kWh and 18-kWh batteries were delivered to ANL in April 1982 for testing and evaluation. Southern California Edison is currently installing a 10-MW, 40-MWh load-leveling facility comprised of batteries based on this design.

Miller, J.F.; Mulcahey, T.P.; Christianson, C.C.; Marr, J.J.; Smaga, J.A.

1987-01-01T23:59:59.000Z

77

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

SciTech Connect (OSTI)

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.

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

2002-02-27T23:59:59.000Z

78

Corrective Action Investigation Plan for Corrective Action Unit 573: Alpha Contaminated Sites, Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 573 is located in Area 5 of the Nevada National Security Site, which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 573 is a grouping of sites where there has been a suspected release of contamination associated with non-nuclear experiments and nuclear testing. This document describes the planned investigation of CAU 573, which comprises the following corrective action sites (CASs): • 05-23-02, GMX Alpha Contaminated Area • 05-45-01, Atmospheric Test Site - Hamilton These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives.

Matthews, Patrick

2014-05-01T23:59:59.000Z

79

Navajo Generating Station and Air Visibility Regulations: Alternatives and Impacts (Revised), Energy Analysis, NREL (National Renewable Energy Laboratory)  

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the Contributions andDataNational Library of1, 2007 (nextNauru Island Effect StudyEnergy

80

Louis Stokes Laboratories, Building 50, National Institutes of Health, Bethesda, Maryland: Laboratories for the 21st Century Case Studies (Revision)  

SciTech Connect (OSTI)

This case study was prepared by participants in the Laboratories for the 21st Century program, a joint endeavor of the U.S. Environmental Protection Agency and the U.S. Department of Energy's Federal Energy Management Program. The goal of this program is to foster greater energy efficiency in new laboratory buildings for both the public and the private sectors. Retrofits of existing laboratories are also encouraged. The energy-efficient features of the new laboratories in Building 50 at the National Institutes of Health in Bethesda, Maryland, include extensive use of daylighting, variable-air-volume control of the ventilation air supply and exhaust air system, and a unique energy recovery system that makes use of large desiccant energy wheels. With nearly 300,000 gross square feet, the building is estimated to use much less energy than traditional research facilities consume because of its energy-efficient design and features.

Not Available

2002-03-01T23:59:59.000Z

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


81

Safety Basis Requirements for Nonnuclear Facilities at Lawrence Livermore National Laboratory Site-Specific Work Smart Standards Revision 1  

SciTech Connect (OSTI)

This standard establishes requirements that, when coupled with Lawrence Livermore National Laboratory's (LLNL's) Integrated Safety Management System (ISMS) methods and other Work Smart Standards for assuring worker safety, assure that the impacts of nonnuclear operations authorized in LLNL facilities are well understood and controlled in a manner that protects the health of workers, the public, and the environment. All LLNL facilities shall be classified based on potential for adverse impact of operations to the health of co-located (i.e., nearby) workers and the public in accordance with this standard, Title 10 Code of Federal Regulations (10 CFR) 830, Subpart B, and Department of Energy Order (DOE O) 420.2A. This standard provides information on: Objectives; Applicability; Safety analysis requirements; Control selection and maintenance; Documentation requirements; Safety basis review, approval, and renewal; and Safety basis implementation.

Beach, R; Brereton, S; Failor, R; Hildum, S; Spagnolo, S; Van Warmerdam, C

2003-02-24T23:59:59.000Z

82

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

SciTech Connect (OSTI)

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.

Mark Krauss and Catherine Birney

2011-05-01T23:59:59.000Z

83

Vitrification as a low-level radioactive mixed waste treatment technology at Argonne National Laboratory  

SciTech Connect (OSTI)

Argonne National Laboratory-East (ANL-E) is developing plans to use vitrification to treat low-level radioactive mixed wastes (LLMW) generated onsite. The ultimate objective of this project is to install a full-scale vitrification system at ANL-E capable of processing the annual generation and historic stockpiles of selected LLMW streams. This project is currently in the process of identifying a range of processible glass compositions that can be produced from actual mixed wastes and additives, such as boric acid or borax. During the formulation of these glasses, there has been an emphasis on maximizing the waste content in the glass (70 to 90 wt %), reducing the overall final waste volume, and producing a stabilized low-level radioactive waste glass. Crucible glass studies with actual mixed waste streams have produced alkali borosilicate glasses that pass the Toxic Characteristic Leaching Procedure (TCLP) test. These same glass compositions, spiked with toxic metals well above the expected levels in actual wastes, also pass the TCLP test. These results provide compelling evidence that the vitrification system and the glass waste form will be robust enough to accommodate expected variations in the LLMW streams from ANL-E. Approximately 40 crucible melts will be studied to establish a compositional envelope for vitrifying ANL-E mixed wastes. Also being determined is the identity of volatilized metals or off-gases that will be generated.

Mazer, J.J.; No, Hyo J.

1995-08-01T23:59:59.000Z

84

Performance Assessment for the Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Facility  

SciTech Connect (OSTI)

This performance assessment for the Remote-Handled Low-Level Radioactive Waste Disposal Facility at the Idaho National Laboratory documents the projected radiological dose impacts associated with the disposal of low-level radioactive waste at the facility. This assessment evaluates compliance with the applicable radiological criteria of the U.S. Department of Energy and the U.S. Environmental Protection Agency for protection of the public and the environment. The calculations involve modeling transport of radionuclides from buried waste to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses are calculated for both offsite receptors and individuals who inadvertently intrude into the waste after site closure. The results of the calculations are used to evaluate the future performance of the low-level radioactive waste disposal facility and to provide input for establishment of waste acceptance criteria. In addition, one-factor-at-a-time, Monte Carlo, and rank correlation analyses are included for sensitivity and uncertainty analysis. The comparison of the performance assessment results to the applicable performance objectives provides reasonable expectation that the performance objectives will be met

Annette L. Schafer; A. Jeffrey Sondrup; Arthur S. Rood

2012-05-01T23:59:59.000Z

85

Commercial disposal options for Idaho National Engineering Laboratory low-level radioactive waste  

SciTech Connect (OSTI)

The Idaho National Engineering Laboratory (INEL) is a Department of Energy (DOE)-owned, contractor-operated site. Significant quantities of low-level radioactive waste (LLW) have been generated and disposed of onsite at the Radioactive Waste Management Complex (RWMC). The INEL expects to continue generating LLW while performing its mission and as aging facilities are decommissioned. An on-going Performance Assessment process for the RWMC underscores the potential for reduced or limited LLW disposal capacity at the existing onsite facility. In order to properly manage the anticipated amount of LLW, the INEL is investigating various disposal options. These options include building a new facility, disposing the LLW at other DOE sites, using commercial disposal facilities, or seeking a combination of options. This evaluation reports on the feasibility of using commercial disposal facilities.

Porter, C.L.; Widmayer, D.A.

1995-09-01T23:59:59.000Z

86

Lawrence Berkeley National Laboratory Facilities Division- Optimizing Activity-level Work Planning and Control Lessons Learned  

Broader source: Energy.gov [DOE]

Presenter: Ken Fletcher, Deputy Division Director for Facilities, Lawrence Berkeley National Laboratory

87

Corrective Action Investigation Plan for Corrective Action Unit 365: Baneberry Contamination Area, Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit 365 comprises one corrective action site (CAS), CAS 08-23-02, U-8d Contamination Area. This site is being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for the CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The site will be investigated based on the data quality objectives (DQOs) developed on July 6, 2010, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for the Baneberry site. The primary release associated with Corrective Action Unit 365 was radiological contamination from the Baneberry nuclear test. Baneberry was an underground weapons-related test that vented significant quantities of radioactive gases from a fissure located in close proximity to ground zero. A crater formed shortly after detonation, which stemmed part of the flow from the fissure. The scope of this investigation includes surface and shallow subsurface (less than 15 feet below ground surface) soils. Radionuclides from the Baneberry test with the potential to impact groundwater are included within the Underground Test Area Subproject. Investigations and corrective actions associated with the Underground Test Area Subproject include the radiological inventory resulting from the Baneberry test.

Patrick Matthews

2010-12-01T23:59:59.000Z

88

Low-level waste certification plan for the Lawrence Berkeley Laboratory Hazardous Waste Handling Facility. Revision 1  

SciTech Connect (OSTI)

The purpose of this plan is to describe the organization and methodology for the certification of low-level radioactive waste (LLW) handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan is composed to meet the requirements found in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and follows the suggested outline provided by WHC in the letter of April 26, 1990, to Dr. R.H. Thomas, Occupational Health Division, LBL. LLW is to be transferred to the WHC Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington.

NONE

1995-01-10T23:59:59.000Z

89

Evaluation of Department of Energy-Held Potential Greater-Than-Class C Low-Level Radioactive Waste. Revision 1  

SciTech Connect (OSTI)

A number of commercial facilities have generated potential greater-than-Class C low-level radioactive waste (GTCC LLW), and, through contractual arrangements with the US Department of Energy (DOE) or for health and safety reasons, DOE is storing the waste. This report presents the results of an assessment conducted by the GTCC LLW Management Program to consider specific circumstances under which DOE accepted the waste, and to determine whether disposal in a facility licensed by the US Nuclear Regulatory Commission, or by DOE in a nonlicensed facility, is appropriate. Input from EG&G Idaho, Inc., and DOE Idaho Operations Office legal departments concerning the disposal requirements of this waste were the basis for the decision process used in this report.

NONE

1994-09-01T23:59:59.000Z

90

Progress in High-Level Waste Tank Cleaning at the Idaho National Environmental and Engineering Laboratory  

SciTech Connect (OSTI)

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 (DOE) 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). Design, development, and deployment of a remotely operated tank cleaning system were completed in August 2001. The system incorporates many commercially available components, which have been adapted for application in cleaning high-level waste tanks. The system also uses existing waste transfer technology (steam-jets) to remove tank heel solids from the tank bottoms during the cleaning operations. By using this existing transfer system and commercially available equipment, the cost of developing custom designed cleaning equipment can be avoided. 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. This system is also compliant with operational and safety performance requirements at INTEC. Through the deployment of the tank cleaning system, the INEEL High Level Waste Program has demonstrated the capability to clean tanks to meet RCRA clean closure standards and DOE closure performance measures. The tank cleaning system deployed at the INTEC offers unique advantages over other approaches evaluated at the INEEL and throughout the DOE Complex. The system's ability to agitate and homogenize the tank heel sludge will simplify verification-sampling techniques and reduce the total quantity of samples required to demonstrate compliance with the performance standards. This will reduce tank closure budget requirements and improve closure-planning schedules.

Lockie, K. A.; McNaught, W. B.

2002-02-26T23:59:59.000Z

91

Application of spectral summing to suspect low level debris drums at Los Alamos National Laboratory  

SciTech Connect (OSTI)

The spectral summing technique developed by Pajarito Scientific Corporation (PSC) is a unique modeling technique that is being employed by the Waste Disposition Project - Low Level Waste Disposal (WDP-LLWD) Group at Los Alamos National Laboratory (LANL). This technique is being used to disposition low-level radioactive waste that has dropped out of the transuranic (TRU) category and has no place to go unless it can be proven to be LLW and not TRU. The TRU program at LANL run by Mobile Characterization Services (MCS) employs two High Efficiency Neutron Counters (HENC) with built-in gamma assay systems to assay radioactive waste for shipment and disposal as TRU waste at the Waste Isolation Pilot Plant (WIPP) at Carlsbad, New Mexico. As well as being certified for WIPP assays, the HENC systems can also be used for low-level waste assays for disposal at LANL or off-site disposal facilities, such as the Nevada Test Site (NTS). Some of the waste processed through the HENC systems cannot be confirmed TRU due to the absence of detected TRU alpha emitters above the TRU cutoff of 100 nCi/g. This waste becomes suspect low-level waste (SLLW). In many cases, the waste also can't be classified as LLW because the minimum detectable activity (MDA) of TRU radionuclides is above the 100 nCi/g level. These wastes that do not have enough detectable TRU activity to be classified as TRU waste and have too high a MDA to be classified as LLW enter a radioactive waste characterization limbo that prevents their dispositioning as either TRU waste or LLW. Spectral summing allows an experienced gamma spectroscopy analyst to add the HENC gamma spectra of a number of similar waste items together to form a consolidated (summed) spectrum. This summed spectrum contains the assay results of the group of items rather than the individual item, and gamma peaks that were not discernable in the individual spectra become quantifiable in the summed spectrum. The group of waste items can then be properly classified as LLW based on the summed spectrum and valid assay values can be assigned for disposal. This technique is being successfully used to dispose of LLW debris drums from LANL.

Gruetzmacher, Kathleen M [Los Alamos National Laboratory; Veilleux, John M [Los Alamos National Laboratory; Lucero, Randy P [PAJARITO SCIENTIFIC CORPORATION; Seamans, Jr, James V [PAJARITO SCIENTIFIC CORPORATION; Clapham, Martin J [PAJARITO SCIENTIFIC CORPORATION

2010-01-01T23:59:59.000Z

92

Application of spectral summing to indeterminate suspect low-level drums at Los Alamos National Laboratory  

SciTech Connect (OSTI)

The spectral summing technique developed by Pajarito Scientific Corporation (PSC) is a unique modeling technique that is being employed by the Waste Disposition Project - Low Level Waste Disposition (WDP-LLWD) Group at Los Alamos National Laboratory (LANL). This technique has been used to disposition low-level radioactive waste that has dropped out of the transuranic (TRU) category and has no disposal path unless it can be proven to be LLW and not TRU. The TRU program at LANL run by Mobile Characterization Services (MCS) employs High Efficiency Neutron Counters (HENC) with built-in gamma assay systems to assay radioactive waste for shipment and disposal as TRU waste at the Waste Isolation Pilot Plant (WIPP) at Carlsbad, New Mexico. As well as being certified for WIPP assays, the HENC systems can also be used for low-level waste assays for disposal at LANL or off-site disposal facilities, such as the Nevada Test Site (NTS). Some of the waste processed through the HENC systems cannot be confirmed TRU due to the absence of detected TRU alpha emitters above the TRU cutoff of 100 nCi/g. This waste becomes suspect low-level waste (SLLW). In many cases, the waste also can't be classified as LLW because the minimum detectable activity (MDA) of TRU radionuclides is above the 100 nCi/g level. These wastes that do not have enough detectable TRU activity to be classified as TRU waste and have TRU MDAs > 100nCi/g enter a radioactive waste characterization indeterminate state that prevents their dispositioning as either TRU waste or LLW. Spectral summing allows an experienced gamma spectroscopy analyst to add the HENC gamma spectra of a number of similar waste items together to form a consolidated (summed) spectrum. This summed spectrum contains the assay results of the group of items rather than the individual item, and gamma peaks that were not discemable in the individual spectra become quantifiable in the summed spectrum and the MDA for the group sum is reduced. The group of waste items can then be properly classified as LLW waste on the summed spectrum and valid assay values can be assigned for disposal. This technique has been successfully applied to a set of 52 debris drums - with individual MDA > 100nCi/g - with a resulting group total TRU alpha activity concentration below 40nCi/g. Further application of the technique at LANL to other debris drums and sludge drums that were measured on a WIPP certified HENe is planned and good candidate drum sets are being evaluated.

Gruetzmacher, Kathleen M [Los Alamos National Laboratory; Veilleux, John M [Los Alamos National Laboratory; Lucero, Randy P [PAJARITO SCIENTIFIC CORPORATION; Seamans, Jr, J. V. [PAJARITO SCIENTIFIC CORPATION; Clapham, M. J. [PAJARITO SCIENTIFIC CORPORATION

2011-01-27T23:59:59.000Z

93

Application of spectral summing to indeterminate suspect low-level drums at Los Alamos National Laboratory  

SciTech Connect (OSTI)

An analytical technique developed by Pajarito Scientific Corporation (PSC), utilizing spectral summing of spectra from groups of drums of similar waste type, is being employed by the Waste Disposition Project - Low Level Waste Disposal (WDP-LLWD) Group at Los Alamos National Laboratory (LANL). This technique has been used to disposition low-level radioactive waste that has dropped out of the transuranic (TRU) category and has no place to go unless it can be proven to be LLW and not TRU. The TRU program at LANL run by Mobile Characterization Services (MCS) employs two High Efficiency Neutron Counters (HENC) with built-in gamma assay systems to assay radioactive waste for shipment and disposal as TRU waste at the Waste Isolation Pilot Plant (WIPP) at Carlsbad, New Mexico. As well as being certified for WIPP assays, the HENC systems can also be used for low-level waste assays for disposal at LANL or off-site disposal facilities, such as the Nevada Test Site (NTS). Some of the waste processed through the HENC systems cannot be confinned TRU due to the absence of detected TRU alpha emitters above the TRU cutoff of 100 nCi/g. This waste becomes suspect low-level waste (SLLW). In many cases, the waste also can't be classified as LLW because the minimum detectable activity (MDA) of TRU radio nuclides is above the 100 nCi/g level. These wastes that do not have enough detectable TRU activity to be classified as TRU waste and have too high a MDA to be classified as LLW enter a radioactive waste characterization indetenninate status that prevents their dispositioning as either TRU waste or LLW. Spectral summing allows an experienced ganuna spectroscopy analyst to add the HENC gamma spectra of a number of similar waste items together to form a consolidated (summed) spectrum. This summed spectrum contains the assay results of the group of items rather than the individual item, and gamma peaks that were not discernable in the individual spectra can become quantifiable in the summed spectrum and the MDA for group sum is reduced. The group of waste items can then be properly classified as LLW based on the summed spectrum and valid assay values can be assigned for disposal. This technique has been successfully applied to a set of 52 debris drums - with individual MDA > 100 nCi/g - with a resulting group total TRU alpha activity concentration below 40nCi/g. Further application of the technique at LANL to other waste drums that are measured on a WIPP certified HENC system is planned and good candidate drum sets are being evaluated as indeterminate situations develop.

Gruetzmacher, Kathleen M [Los Alamos National Laboratory; Veilleux, John M [Los Alamos National Laboratory; Lucero, Randy P [PAJARITO SCIENTIFIC CORAPTION; Seamans, Jr., James V [PAJARITO SCIENTIFIC CORPORATION; Clapham, Martin J [PAJARITO SCIENTIFIC CORPORATION

2010-11-09T23:59:59.000Z

94

On the integration of technology readiness levels at Sandia National Laboratories.  

SciTech Connect (OSTI)

Integrating technology readiness levels (TRL) into the management of engineering projects is critical to the mitigation of risk and improved customer/supplier communications. TRLs provide a common framework and language with which consistent comparisons of different technologies and approaches can be made. At Sandia National Laboratories, where technologies are developed, integrated and deployed into high consequence systems, the use of TRLs may be transformational. They are technology independent and span the full range of technology development including scientific and applied research, identification of customer requirements, modeling and simulation, identification of environments, testing and integration. With this report, we provide a reference set of definitions for TRLs and a brief history of TRLs at Sandia National Laboratories. We then propose and describe two approaches that may be used to integrate TRLs into the NW SMU business practices. In the first approach, we analyze how TRLs can be integrated within concurrent qualification as documented in TBP-100 [1]. In the second approach we take a look at the product realization process (PRP) as documented in TBP-PRP [2]. Both concurrent qualification and product realization are fundamental to the way weapons engineering work is conducted at this laboratory and the NWC (nuclear weapons complex) as a whole. Given the current structure and definitions laid out in the TBP-100 and TBP-PRP, we believe that integrating TRLs into concurrent qualification (TBP-100) rather than TBP-PRP is optimal. Finally, we note that our charter was to explore and develop ways of integrating TRLs into the NW SMU and therefore we do not significantly cover the development and history of TRLs. This work was executed under the auspices and direction of Sandia's Weapon Engineering Program. Please contact Gerry Sleefe, Deputy Program Director, for further information.

Bailey, Beatriz R.; Mitchell, John Anthony

2006-09-01T23:59:59.000Z

95

Greater-than-Class C low-level radioactive waste characterization: Estimated volumes, radionuclide activities, and other characteristics. Revision 1  

SciTech Connect (OSTI)

The Department of Energy`s (DOE`s) planning for the disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) requires characterization of the waste. This report estimates volumes, radionuclide activities, and waste forms of GTCC LLW to the year 2035. It groups the waste into four categories, representative of the type of generator or holder of the waste: Nuclear Utilities, Sealed Sources, DOE-Held, and Other Generator. GTCC LLW includes activated metals (activation hardware from reactor operation and decommissioning), process wastes (i.e., resins, filters, etc.), sealed sources, and other wastes routinely generated by users of radioactive material. Estimates reflect the possible effect that packaging and concentration averaging may have on the total volume of GTCC LLW. Possible GTCC mixed LLW is also addressed. Nuclear utilities will probably generate the largest future volume of GTCC LLW with 65--83% of the total volume. The other generators will generate 17--23% of the waste volume, while GTCC sealed sources are expected to contribute 1--12%. A legal review of DOE`s obligations indicates that the current DOE-Held wastes described in this report will not require management as GTCC LLW because of the contractual circumstances under which they were accepted for storage. This report concludes that the volume of GTCC LLW should not pose a significant management problem from a scientific or technical standpoint. The projected volume is small enough to indicate that a dedicated GTCC LLW disposal facility may not be justified. Instead, co-disposal with other waste types is being considered as an option.

Not Available

1994-09-01T23:59:59.000Z

96

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

SciTech Connect (OSTI)

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.

Quigley, K.D.; Wessman, D

2003-02-27T23:59:59.000Z

97

Low-Level Plutonium Bioassay Measurements at the Lawrence Livermore National Laboratory  

SciTech Connect (OSTI)

Plutonium-239 ({sup 239}Pu) and plutonium-240 ({sup 240}Pu) are important alpha emitting radionuclides contained in radioactive debris from nuclear weapons testing. {sup 239}Pu and {sup 240}Pu are long-lived radionuclides with half-lives of 24,400 years and 6580 years, respectively. Concerns over human exposure to plutonium stem from knowledge about the persistence of plutonium isotopes in the environment and the high relative effectiveness of alpha-radiation to cause potential harm to cells once incorporated into the human body. In vitro bioassay tests have been developed to assess uptakes of plutonium based on measured urinary excretion patterns and modeled metabolic behaviors of the absorbed radionuclides. Systemic plutonium absorbed by the deep lung or from the gastrointestinal tract after ingestion is either excreted or distributed to other organs, primarily to the liver and skeleton, where it is retained for biological half-times of around 20 and 50 years, respectively. Dose assessment and atoll rehabilitation programs in the Marshall Islands have historically given special consideration to residual concentrations of plutonium in the environment even though the predicted dose from inhalation and/or ingestion of plutonium accounts for less than 5% of the annual effective dose from exposure to fallout contamination. Scientists from the Lawrence Livermore National Laboratory (LLNL) have developed a state-of-the-art bioassay test to assess urinary excretion rates of plutonium from Marshallese populations. This new heavy-isotope measurement system is based on Accelerator Mass Spectrometry (AMS). The AMS system at LLNL far exceeds the standard measurement requirements established under the latest United States Department of Energy (DOE) regulation, 10CFR 835, for occupational monitoring of plutonium, and offers several advantages over classical as well as competing new technologies for low-level detection and measurement of plutonium isotopes. The United States National Institute of Standards and Technology (NIST) has independently verified the accuracy and precision of the AMS detection system for low-level bioassay measurements of plutonium isotopes through participation in an intercomparison exercise whereby performance evaluation samples were prepared in a synthetic urine matrix and submitted to participating laboratories for blind analysis. The results of the analyses were then sent to the NIST to independently evaluate the performance of laboratory participants. At LLNL, the AMS measurements of {sup 239}Pu and {sup 240}Pu met ANSI 13.30 criteria for both precision and accuracy at all sample test levels. Livermore scientists continue to test the performance of the Marshall Islands Plutonium Urinalysis Program by routine blind analysis of externally prepared quality control test samples, and through the rigorous implementation of standardized methods and procedures. Although not addressed directly in the report, AMS measurements show that the urinary excretion of plutonium by selected Marshallese populations fall into a low and reproducible range. Moreover, there appears to be no evidence of small incremental intakes of plutonium associated with resettlement activities - past or present. The improved quality, reliability and detection sensitivity of AMS for low-level plutonium isotope measurements will enable DOE to develop high-quality, baseline urinary excretion data for Marshallese populations, and accurately assess and track potential uptakes of plutonium. associated with resettlement activities and/or from long-term changes in plutonium exposure conditions in the Marshall Islands.

Hamilton, T; Brown, T; Hickman, D; Marchetti, A; Williams, R; Kehl, S

2007-06-18T23:59:59.000Z

98

Level 3 baseline risk evaluation for Building 3506 at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

This report presents the results of the Level 3 Baseline Risk Evaluation (BRE) performed on Building 3506 located at the Oak Ridge National Laboratory (ORNL). This BRE is intended to provide an analysis of the potential for adverse health effects (current or future) posed by contaminants at the facility. The decision was made to conduct a Level 3 (least rigorous) BRE because only residual contamination exists in the building. Future plans for the facility (demolition) also preclude a rigorous analysis. Site characterization activities for Building 3506 were conducted in fall of 1993. Concrete core samples were taken from the floors and walls of both the cell and the east gallery. These cores were analyzed for radionuclides and organic and inorganic chemicals. Smear samples and direct radiation measurements were also collected. Sediment exists on the floor of the cell and was also analyzed. To adequately characterize the risks posed by the facility, receptors for both current and potential future land uses were evaluated. For the current land use conditions, two receptors were evaluated. The first receptor is a hypothetical maintenance worker who spends 250 days (8 hours/day) for 25 years working in the facility. The remaining receptor evaluated is a hypothetical S and M worker who spends 2 days (8 hours/day) per year for 25 years working within the facility. This particular receptor best exemplifies the current worker scenario for the facility. The two current exposure scenarios and parameters of exposure (e.g., inhalation and ingestion rates) have been developed to provide a conservative (i.e. health protective) estimate of potential exposure.

Golden, K.M.; Robers, S.K.; Cretella, F.M.

1994-12-01T23:59:59.000Z

99

A Megawatt-level 28z GHz Heating System For The National Spherical Torus Experiment Upgrade  

SciTech Connect (OSTI)

The National Spherical Torus Experiment Upgrade (NSTX-U) will operate at axial toroidal fields of < 1 T and plasma currents, Ip < 2 MA. The development of non-inductive (NI) plasmas is a major long-term research goal for NSTX-U. Time dependent numerical simulations of 28 GHz electron cyclotron (EC) heating of low density NI start-up plasmas generated by Coaxial Helicity Injection (CHI) in NSTX-U predict a significant and rapid increase of the central electron temperature (Te(0)) before the plasma becomes overdense. The increased Te(0) will significantly reduce the Ip decay rate of CHI plasmas, allowing the coupling of fast wave heating and neutral beam injection. A megawatt-level, 28 GHz electron heating system is planned for heating NI start-up plasmas in NSTX-U. In addition to EC heating of CHI start-up discharges, this system will be used for electron Bernstein wave (EBW) plasma start-up, and eventually for EBW heating and current drive during the Ip flattop.

Taylor, Gary [PPPL

2014-04-01T23:59:59.000Z

100

Brookhaven National Laboratory Number: Revision  

E-Print Network [OSTI]

of the beam distribution system. The analysis includes both laser (light) and non- laser hazards. A Nominal (ANSI) Hazard Class 3B and 4 laser systems must be documented, reviewed, and approved through use will be addressed in heating operations. Location: The lasers are located in the X17B3 hutch of Building 725. LINE

Ohta, Shigemi

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101

Brookhaven National Laboratory Number: Revision  

E-Print Network [OSTI]

circumstance. System description: Time-resolved light scattering Location: X20C Hutch LINE MANAGEMENT. The analysis includes both laser (light) and non-laser hazards. A Nominal Hazard Zone (NHZ) analysis must) Hazard Class 3B and 4 laser systems must be documented, reviewed, and approved through use of this form

Ohta, Shigemi

102

Brookhaven National Laboratory Number: Revision  

E-Print Network [OSTI]

of the beam distribution system. The analysis includes both laser (light) and non-laser hazards. A Nominal (ANSI) Hazard Class 3B and 4 laser systems must be documented, reviewed, and approved through use particular circumstance. System description: Raman fiber optic system with class 3B laser source Location

Ohta, Shigemi

103

Brookhaven National Laboratory Number: Revision  

E-Print Network [OSTI]

of the beam distribution system. The analysis includes both laser (light) and non-laser hazards. A Nominal) Hazard Class 3B and 4 laser systems must be documented, reviewed, and approved through use of this form circumstance. System description: Pico second pulsed laser Location: Building 740, C30 SLM hutch LINE

Homes, Christopher C.

104

Brookhaven National Laboratory Number: Revision  

E-Print Network [OSTI]

includes both laser (light) and non-laser hazards. A Nominal Hazard Zone (NHZ) analysis must be completed (ANSI) Hazard Class 3B and 4 laser systems must be documented, reviewed, and approved through use Lab Location: 703, E2/E4 LINE MANAGEMENT RESPONSIBILITIES The Owner/Operator(s) for this laser is

Ohta, Shigemi

105

Brookhaven National Laboratory Number: Revision  

E-Print Network [OSTI]

and the configuration of the beam distribution system. The analysis includes both laser (light) and non-laser hazards (ANSI) Hazard Class 3B and 4 laser systems must be documented, reviewed, and approved through use diode lasers Location: Associated with beamline X26-C at the NSLS LINE MANAGEMENT RESPONSIBILITIES

Ohta, Shigemi

106

National Environmental Policy Act Compliance Strategy for the Remote-Handled Low-level Waste Disposal Facility  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) needs to have disposal capability for remote-handled low level waste (LLW) generated at the Idaho National Laboratory (INL) at the time the existing disposal facility is full or must be closed in preparation for final remediation of the INL Subsurface Disposal Area in approximately the year 2017.

Peggy Hinman

2010-10-01T23:59:59.000Z

107

Los Alamos National Laboratory's Sister Laboratory Collaborations on Low and Intermediate Level Radioactive Waste Management  

SciTech Connect (OSTI)

The DOE/National Nuclear Security Administration's (NNSA) ''Sister Laboratory'' program allows for bilateral technical cooperation in peaceful uses of nuclear energy for developing nations. The program establishes a direct line of communication between U.S. scientists and the nuclear research and scientific communities in participating countries.

Newell, D. L.; Sinkule, B. J.; Apt, K. E.

2003-02-25T23:59:59.000Z

108

Mission Need Statement for the Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Project  

SciTech Connect (OSTI)

The Idaho National Laboratory proposes to establish replacement remote-handled low-level waste disposal capability to meet Nuclear Energy and Naval Reactors mission-critical, remote-handled low-level waste disposal needs beyond planned cessation of existing disposal capability at the end of Fiscal Year 2015. Remote-handled low-level waste is generated from nuclear programs conducted at the Idaho National Laboratory, including spent nuclear fuel handling and operations at the Naval Reactors Facility and operations at the Advanced Test Reactor. Remote-handled low-level waste also will be generated by new programs and from segregation and treatment (as necessary) of remote-handled scrap and waste currently stored in the Radioactive Scrap and Waste Facility at the Materials and Fuels Complex. Replacement disposal capability must be in place by Fiscal Year 2016 to support uninterrupted Idaho operations. This mission need statement provides the basis for the laboratory’s recommendation to the Department of Energy to proceed with establishing the replacement remote-handled low-level waste disposal capability, project assumptions and constraints, and preliminary cost and schedule information for developing the proposed capability. Without continued remote-handled low-level waste disposal capability, Department of Energy missions at the Idaho National Laboratory would be jeopardized, including operations at the Naval Reactors Facility that are critical to effective execution of the Naval Nuclear Propulsion Program and national security. Remote-handled low-level waste disposal capability is also critical to the Department of Energy’s ability to meet obligations with the State of Idaho.

Lisa Harvego

2009-06-01T23:59:59.000Z

109

How to Integrate Climate Change Adaptation into National-Level Policy and  

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 on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revision hasInformation Earth's Heat Jump to:PhotonHolyName HousingIII Wind FarmWould You Rebuild

110

Legal Frameworks for REDD: Design and Implementation at the National Level  

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 on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revision hasInformation Earth's Heat JumpInc Place:Keystone CleanLaton,Learn Gapminder Jump3. ItInformation|

111

Selection of liquid-level monitoring method for the Oak Ridge National Laboratory inactive liquid low-level waste tanks, remedial investigation/feasibility study  

SciTech Connect (OSTI)

Several of the inactive liquid low-level waste (LLLW) tanks at Oak Ridge National Laboratory contain residual wastes in liquid or solid (sludge) form or both. A plan of action has been developed to ensure that potential environmental impacts from the waste remaining in the inactive LLLW tank systems are minimized. This document describes the evaluation and selection of a methodology for monitoring the level of the liquid in inactive LLLW tanks. Criteria are established for comparison of existing level monitoring and leak testing methods; a preferred method is selected and a decision methodology for monitoring the level of the liquid in the tanks is presented for implementation. The methodology selected can be used to continuously monitor the tanks pending disposition of the wastes for treatment and disposal. Tanks that are empty, are scheduled to be emptied in the near future, or have liquid contents that are very low risk to the environment were not considered to be candidates for installing level monitoring. Tanks requiring new monitoring equipment were provided with conductivity probes; tanks with existing level monitoring instrumentation were not modified. The resulting data will be analyzed to determine inactive LLLW tank liquid level trends as a function of time.

Not Available

1994-11-01T23:59:59.000Z

112

Solar Position Algorithm for Solar Radiation Applications (Revised...  

Office of Scientific and Technical Information (OSTI)

Revised January 2008 * NRELTP-560-34302 Solar Position Algorithm for Solar Radiation Applications Ibrahim Reda and Afshin Andreas National Renewable Energy Laboratory 1617 Cole...

113

EIS-0305: Treating Transuranic (TRU)/Alpha Low-Level at the Oak Ridge National Laboratory, Oak Ridge, Tennessee  

Broader source: Energy.gov [DOE]

Treating Transuranic (TRU)/Alpha Low-Level Waste at the Oak Ridge National Laboratory, Oak Ridge, Tennessee)This EIS evaluates DOE's proposal to construct, operate, and decontaminate/decommission a Transuranic (TRU) Waste Treatment Facility in Oak Ridge, Tennessee. The four waste types that would be treated at the proposed facility would be remote-handled TRU mixed waste sludge, liquid low-level waste associated with the sludge, contact-handled TRU/alpha low-level waste solids, and remote-handled TRU/alpha low-level waste solids. The mixed waste sludge and some of the solid waste contain metals regulated under the Resource Conservation and Recovery Act and may be classified as mixed waste.

114

Estimating Economic and Environmental Impacts At the National, Regional, and Watershed Levels  

E-Print Network [OSTI]

: The Linked ASM/HUMUS Modeling Systema By Jay D. Atwoodb Verel Benson Chi-Chung Chen Bruce McCarl R Consequences into National Agricultural Policy Analysis: A Regional Perspective" held at the Annual Meeting for the paper and EPIC, respectively); Chi-Chung Chen, chen@scout.tamu.edu, is a Research Associate and Bruce Mc

McCarl, Bruce A.

115

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

SciTech Connect (OSTI)

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

Mark Kauss

2011-06-01T23:59:59.000Z

116

SAFETY PROCEDURE SP-19 Revision 02  

E-Print Network [OSTI]

SAFETY PROCEDURE SP-19 Page 1 Revision 02 August 6, 2007 NATIONAL HIGH MAGNETIC FIELD LABORATORY NHMFL FLORIDA STATE UNIVERSITY SAFETY PROCEDURE SP-19 MAGNETIC FIELD SAFETY DIRECTOR, ENVIRONMENTAL, HEALTH, SAFETY & SECURITY Angela Sutton

Weston, Ken

117

The French national program for spent fuel and high-level waste management  

SciTech Connect (OSTI)

From its very beginning, the French national program for spent fuel and HLW management is aimed at the recycling of energetic materials and the safe disposal of nuclear waste. Spent fuel reprocessing is the cornerstone of this program, since it directly opens the way to energetic material recycling, waste minimization and safe conditioning. It is complemented by the HLW management program which is defined by the HLW disposal regulation and the Waste Act issued in 1991.

Giraud, J.P.; Demontalembert, J.A. [COGEMA, Velizy-Villacoublay (France)

1993-12-31T23:59:59.000Z

118

Waste Management Program management plan. Revision 1  

SciTech Connect (OSTI)

As the prime contractor to the Department of Energy Idaho Operations Office (DOE-ID), Lockheed Martin Idaho Technologies Company (LMITCO) provides comprehensive waste management services to all contractors at the Idaho National Engineering and Environmental Laboratory (INEEL) through the Waste Management (WM) Program. This Program Management Plan (PMP) provides an overview of the Waste Management Program objectives, organization and management practices, and scope of work. This document will be reviewed at least annually and updated as needed to address revisions to the Waste Management`s objectives, organization and management practices, and scope of work. Waste Management Program is managed by LMITCO Waste Operations Directorate. The Waste Management Program manages transuranic, low-level, mixed low-level, hazardous, special-case, and industrial wastes generated at or transported to the INEEL.

NONE

1997-02-01T23:59:59.000Z

119

Hanford High-Level Waste Vitrification Program at the Pacific Northwest National Laboratory: technology development - annotated bibliography  

SciTech Connect (OSTI)

This report provides a collection of annotated bibliographies for documents prepared under the Hanford High-Level Waste Vitrification (Plant) Program. The bibliographies are for documents from Fiscal Year 1983 through Fiscal Year 1995, and include work conducted at or under the direction of the Pacific Northwest National Laboratory. The bibliographies included focus on the technology developed over the specified time period for vitrifying Hanford pretreated high-level waste. The following subject areas are included: General Documentation; Program Documentation; High-Level Waste Characterization; Glass Formulation and Characterization; Feed Preparation; Radioactive Feed Preparation and Glass Properties Testing; Full-Scale Feed Preparation Testing; Equipment Materials Testing; Melter Performance Assessment and Evaluations; Liquid-Fed Ceramic Melter; Cold Crucible Melter; Stirred Melter; High-Temperature Melter; Melter Off-Gas Treatment; Vitrification Waste Treatment; Process, Product Control and Modeling; Analytical; and Canister Closure, Decontamination, and Handling

Larson, D.E.

1996-09-01T23:59:59.000Z

120

Corrective Action Investigation Plan for Corrective Action Unit 567: Miscellaneous Soil Sites, Nevada National Security Site, Nevada, with ROTC 1 Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 567 is located in Areas 1, 3, 5, 20, and 25 of the Nevada National Security Site, which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 567 is a grouping of sites where there has been a suspected release of contamination associated with nuclear testing. This document describes the planned investigation of CAU 567, which comprises the following corrective action sites (CASs): • 01-23-03, Atmospheric Test Site T-1 • 03-23-25, Seaweed E Contamination Area • 05-23-07, A5b RMA • 20-23-08, Colby Mud Spill • 25-23-23, J-11 Soil RMA These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the investigation report. The sites will be investigated based on the data quality objectives (DQOs) developed on May 6, 2013, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 567. The site investigation process will also be conducted in accordance with the Soils Activity Quality Assurance Plan, which establishes requirements, technical planning, and general quality practices to be applied to this activity. The potential contamination sources associated with CAU 567 releases are nuclear test operations and other NNSS operations. The DQO process resulted in an assumption that total effective dose (TED) within a default contamination boundary at Atmospheric Test Site T-1 exceeds the final action level (FAL) and requires corrective action. The presence and nature of contamination outside the default contamination boundary at Atmospheric Test Site T-1 and all other CAU 567 CASs will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the TED at sample locations to the dose-based FAL. The TED will be calculated as the total of separate estimates of internal and external dose. Results from the analysis of soil samples will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at the center of each sample location will be used to measure external radiological dose. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS.

Matthews, Patrick K.

2013-07-01T23:59:59.000Z

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


121

REVISION POLICY  

U.S. Energy Information Administration (EIA) 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 CenterFranconia, Virginia:FAQ <Information Administration (EIA) 10 MECS Survey Data 2010Feet) Year Jan Feb: Shale0a.REVISION

122

Corrective Action Decision Document/Closure Report for Corrective Action Unit 372: Area 20 Cabriolet/Palanquin Unit Craters, Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

This Corrective Action Decision Document (CADD)/Closure Report (CR) has been prepared for Corrective Action Unit (CAU) 372, Area 20 Cabriolet/Palanquin Unit Craters, located within Areas 18 and 20 at the Nevada National Security Site, Nevada, in accordance with the Federal Facility Agreement and Consent Order (FFACO). Corrective Action Unit 372 comprises four corrective action sites (CASs): • 18-45-02, Little Feller I Surface Crater • 18-45-03, Little Feller II Surface Crater • 20-23-01, U-20k Contamination Area • 20-45-01, U-20L Crater (Cabriolet) The purpose of this CADD/CR is to provide justification and documentation supporting the recommendation that no further corrective action is needed for CAU 372 based on the implementation of the corrective action of closure in place with administrative controls at all CASs. Corrective action investigation (CAI) activities were performed from November 9, 2009, through December 10, 2010, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 372: Area 20 Cabriolet/Palanquin Unit Craters. The approach for the CAI was divided into two facets: investigation of the primary release of radionuclides and investigation of other releases (migration in washes and chemical releases). The purpose of the CAI was to fulfill data needs as defined during the data quality objective (DQO) process. The CAU 372 dataset of investigation results was evaluated based on a data quality assessment. This assessment demonstrated the dataset is acceptable for use in fulfilling the DQO data needs. Investigation results were evaluated against final action levels (FALs) established in this document. A radiological dose FAL was established of 25 millirem per year based on the Remote Work Area exposure scenario (336 hours of annual exposure). Radiological doses exceeding the FAL were found to be present at all four CASs. It is assumed that radionuclide levels present within the Little Feller I and Cabriolet high contamination areas and within the craters at Palanquin and Cabriolet exceed the FAL. It is also assumed that potential source material in the form of lead bricks at Little Feller I and lead-acid batteries at Palanquin and Cabriolet exceed the FAL. Therefore, corrective actions were undertaken that consist of removing potential source material, where present, and implementing a use restriction and posting warning signs at each CAS. These use restrictions were recorded in the FFACO database; the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Facility Information Management System; and the NNSA/NSO CAU/CAS files. Therefore, NNSA/NSO provides the following recommendations: • No further corrective actions are necessary for CAU 372. • A Notice of Completion to NNSA/NSO is requested from the Nevada Division of Environmental Protection for closure of CAU 372. • Corrective Action Unit 372 should be moved from Appendix III to Appendix IV of the FFACO.

Matthews, Patrick and Sloop, Christy

2011-04-01T23:59:59.000Z

123

Corrective Action Investigation Plan for Corrective Action Unit 569: Area 3 Yucca Flat Atmospheric Test Sites Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 569 is located in Area 3 of the Nevada National Security Site, which is approximately 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 569 comprises the nine numbered corrective action sites (CASs) and one newly identified site listed below: (1) 03-23-09, T-3 Contamination Area (hereafter referred to as Annie, Franklin, George, and Moth); (2) 03-23-10, T-3A Contamination Area (hereafter referred to as Harry and Hornet); (3) 03-23-11, T-3B Contamination Area (hereafter referred to as Fizeau); (4) 03-23-12, T-3S Contamination Area (hereafter referred to as Rio Arriba); (5) 03-23-13, T-3T Contamination Area (hereafter referred to as Catron); (6) 03-23-14, T-3V Contamination Area (hereafter referred to as Humboldt); (7) 03-23-15, S-3G Contamination Area (hereafter referred to as Coulomb-B); (8) 03-23-16, S-3H Contamination Area (hereafter referred to as Coulomb-A); (9) 03-23-21, Pike Contamination Area (hereafter referred to as Pike); and (10) Waste Consolidation Site 3A. Because CAU 569 is a complicated site containing many types of releases, it was agreed during the data quality objectives (DQO) process that these sites will be grouped. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each study group. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the DQOs developed on September 26, 2011, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 569. The presence and nature of contamination at CAU 569 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the total effective dose (TED) at sample locations to the dose-based final action level (FAL). The TED will be calculated as the total of separate estimates of internal and external dose. Results from the analysis of soil samples will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at the center of each sample location will be used to measure external radiological dose. A field investigation will be performed to define any areas where TED exceeds the FAL and to determine whether contaminants of concern are present at the site from other potential releases. The presence and nature of contamination from other types of releases (e.g., excavation, migration, and any potential releases discovered during the investigation) will be evaluated using soil samples collected from biased locations indicating the highest levels of contamination. Appendix A provides a detailed discussion of the DQO methodology and the objectives specific to each study group.

Patrick Matthews; Christy Sloop

2012-02-01T23:59:59.000Z

124

Corrective Action Decision Document/Closure Report for Corrective Action Unit 365: Baneberry Contamination Area, Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit 365 comprises one corrective action site (CAS), CAS 08-23-02, U-8d Contamination Area. The purpose of this CADD/CR is to provide justification and documentation supporting the recommendation that no further corrective action is needed for CAU 365 based on the implementation of the corrective action of closure in place with a use restriction (UR). Corrective action investigation (CAI) activities were performed from January 18, 2011, through August 2, 2011, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 365: Baneberry Contamination Area. The purpose of the CAI was to fulfill data needs as defined during the data quality objective (DQO) process. The CAU 365 dataset of investigation results was evaluated based on a data quality assessment. This assessment demonstrated the dataset is complete and acceptable for use in supporting the DQO decisions. Investigation results were evaluated against final action levels (FALs) established in this document. A radiological dose FAL of 25 millirem per year was established based on the Remote Work Area exposure scenario (336 hours of annual exposure). Radiological doses exceeding the FAL were found to be present to the southwest of the Baneberry crater. It was also assumed that radionuclide levels present within the crater and fissure exceed the FAL. Corrective actions were undertaken that consisted of establishing a UR and posting warning signs for the crater, fissure, and the area located to the southwest of the crater where soil concentrations exceeded the FAL. These URs were recorded in the FFACO database; the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Facility Information Management System; and the NNSA/NSO CAU/CAS files. Therefore, NNSA/NSO provides the following recommendations: (1) No further corrective actions beyond what are described in this document are necessary for CAU 365. (2) A Notice of Completion to NNSA/NSO is requested from the Nevada Division of Environmental Protection for closure of CAU 365. (3) Corrective Action Unit 365 should be moved from Appendix III to Appendix IV of the FFACO.

Patrick Matthews

2011-09-01T23:59:59.000Z

125

Preliminary Waste Form Compliance Plan for the Idaho National Engineering and Environmental Laboratory High-Level Waste  

SciTech Connect (OSTI)

The Department of Energy (DOE) has specific technical and documentation requirements for high-level waste (HLW) that is to be placed in a federal repository. This document describes in general terms the strategy to be used at the Idaho National Engineering and Environmental Laboratory (INEEL) to demonstrate that vitrified HLW, if produced at the INEEL, meets these requirements. Waste form, canister, quality assurance, and documentation specifications are discussed. Compliance strategy is given, followed by an overview of how this strategy would be implemented for each specification.

B. A. Staples; T. P. O'Holleran

1999-05-01T23:59:59.000Z

126

Evaluation of Low-Level Waste Disposal Receipt Data for Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility - Fiscal Year 2011  

SciTech Connect (OSTI)

The Los Alamos National Laboratory (LANL or the Laboratory) generates radioactive waste as a result of various activities. Operational or institutional waste is generated from a wide variety of research and development activities including nuclear weapons development, energy production, and medical research. Environmental restoration (ER), and decontamination and decommissioning (D and D) waste is generated as contaminated sites and facilities at LANL undergo cleanup or remediation. The majority of this waste is low-level radioactive waste (LLW) and is disposed of at the Technical Area 54 (TA-54), Area G disposal facility. U.S. Department of Energy (DOE) Order 435.1 (DOE, 2001) requires that radioactive waste be managed in a manner that protects public health and safety, and the environment. To comply with this order, DOE field sites must prepare and maintain site-specific radiological performance assessments for LLW disposal facilities that accept waste after September 26, 1988. Furthermore, sites are required to conduct composite analyses that account for the cumulative impacts of all waste that has been (or will be) disposed of at the facilities and other sources of radioactive material that may interact with the facilities. Revision 4 of the Area G performance assessment and composite analysis was issued in 2008 (LANL, 2008). These analyses estimate rates of radionuclide release from the waste disposed of at the facility, simulate the movement of radionuclides through the environment, and project potential radiation doses to humans for several on-site and off-site exposure scenarios. The assessments are based on existing site and disposal facility data and on assumptions about future rates and methods of waste disposal. The accuracy of the performance assessment and composite analysis depends upon the validity of the data used and assumptions made in conducting the analyses. If changes in these data and assumptions are significant, they may invalidate or call into question certain aspects of the analyses. For example, if the volumes and activities of waste disposed of during the remainder of the disposal facility's lifetime differ significantly from those projected, the doses projected by the analyses may no longer apply. DOE field sites are required to implement a performance assessment and composite analysis maintenance program. The purpose of this program is to ensure the continued applicability of the analyses through incremental improvement of the level of understanding of the disposal site and facility. Site personnel are required to conduct field and experimental work to reduce the uncertainty in the data and models used in the assessments. Furthermore, they are required to conduct periodic reviews of waste receipts, comparing them to projected waste disposal rates. The radiological inventory for Area G was updated in conjunction with Revision 4 of the performance assessment and composite analysis (Shuman, 2008). That effort used disposal records and other sources of information to estimate the quantities of radioactive waste that have been disposed of at Area G from 1959, the year the facility started receiving waste on a routine basis, through 2007. It also estimated the quantities of LLW that will require disposal from 2008 through 2044, the year in which it is assumed that disposal operations at Area G will cease. This report documents the fourth review of Area G disposal receipts since the inventory was updated and examines information for waste placed in the ground during fiscal years (FY) 2008 through 2011. The primary objective of the disposal receipt review is to ensure that the future waste inventory projections developed for the performance assessment and composite analysis are consistent with the actual types and quantities of waste being disposed of at Area G. Toward this end, the disposal data that are the subject of this review are used to update the future waste inventory projections for the disposal facility. These projections are compared to the future inventory projections that were develope

French, Sean B. [Los Alamos National Laboratory; Shuman, Robert [WPS: WASTE PROJECTS AND SERVICES

2012-04-17T23:59:59.000Z

127

Low-Level Radio Frequency System Development for the National Synchrotron Light Source II  

SciTech Connect (OSTI)

The National Synchrotron Light Source-II (NSLS-II) is a new ultra-bright 3GeV 3rd generation synchrotron radiation light source. The performance goals require operation with a beam current of 500mA and a bunch current of at least 0.5mA. The position and timing specifications of the ultra-bright photon beam imposes a set of stringent requirements on the performance of radio frequency (RF) control. In addition, commissioning and staged installation of damping wigglers and insertion devices requires the flexibility of handling varying beam conditions. To meet these requirements, a digital implementation of the LLRF is chosen, and digital serial links are planned for the system integration. The first prototype of the controller front-end hardware has been built, and is currently being tested.

Ma,H.; Rose, J.

2009-05-04T23:59:59.000Z

128

Transmission Design at the National Level: Benefits, Risks and Possible Paths Forward  

E-Print Network [OSTI]

James Bushnell University of California, Davis PSERC Publication 12-01 May 2012 #12;Information about to move electric energy interregionally is limited to the capacity of the existing transmission system, the levelized cost of energy production for renewables (e.g., wind, solar, and deep geoth

129

Radiological, physical, and chemical characterization of low-level alpha contaminated wastes stored at the Idaho National Engineering Laboratory  

SciTech Connect (OSTI)

This document provides radiological, physical, and chemical characterization data for low-level alpha-contaminated radioactive and low-level alpha-contaminated radioactive and hazardous (i.e., mixed) wastes stored at the Idaho National Engineering Laboratory and considered for treatment under the Private Sector Participation Initiative Program. Waste characterization data are provided in the form of INEL Waste Profile Sheets. These documents provide, for each content code, information on waste identification, waste description, waste storage configuration, physical/chemical waste composition, radionuclide and associated alpha activity waste characterization data, and hazardous constituents present in the waste. Information is provided for 97 waste streams which represent an estimated total volume of 25,450 m 3 corresponding to a total mass of approximately 12,000,000 kg. In addition, considerable information concerning alpha, beta, gamma, and neutron source term data specific to Rocky Flats-generated waste forms stored at the INEL are provided to assist in facility design specification.

Apel, M.L.; Becker, G.K.; Ragan, Z.K.; Frasure, J.; Raivo, B.D.; Gale, L.G.; Pace, D.P.

1994-03-01T23:59:59.000Z

130

Corrective Action Investigation Plan for Corrective Action Unit 105: Area 2 Yucca Flat Atmospheric Test Sites Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 105 is located in Area 2 of the Nevada National Security Site, which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 105 is a geographical grouping of sites where there has been a suspected release of contamination associated with atmospheric nuclear testing. This document describes the planned investigation of CAU 105, which comprises the following corrective action sites (CASs): • 02-23-04, Atmospheric Test Site - Whitney • 02-23-05, Atmospheric Test Site T-2A • 02-23-06, Atmospheric Test Site T-2B • 02-23-08, Atmospheric Test Site T-2 • 02-23-09, Atmospheric Test Site - Turk These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on April 30, 2012, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 105. The site investigation process will also be conducted in accordance with the Soils Activity Quality Assurance Plan, which establishes requirements, technical planning, and general quality practices to be applied to this activity. The potential contamination sources associated with all CAU 105 CASs are from atmospheric nuclear testing activities. The presence and nature of contamination at CAU 105 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the total effective dose at sample locations to the dose-based final action level. The total effective dose will be calculated as the total of separate estimates of internal and external dose. Results from the analysis of soil samples will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at the center of each sample location will be used to measure external radiological dose. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. This Corrective Action Investigation Plan has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; DOE, Environmental Management; U.S. Department of Defense; and DOE, Legacy Management. Under the Federal Facility Agreement and Consent Order, this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Fieldwork will be conducted after the plan is approved.

Patrick Matthews

2012-09-01T23:59:59.000Z

131

EIS-0074: Long-Term Management of Defense High-Level Radioactive Wastes Idaho Chemical Processing Plant, Idaho National Engineering Lab, Idaho  

Broader source: Energy.gov [DOE]

The U.S. Department of Energy prepared this statement to analyze the environmental implications of the proposed selection of a strategy for long- term management of the high- level radioactive wastes generated as part of the national defense effort at the Department's Idaho Chemical Processing Plant a t the Idaho National Engineering Laboratory.

132

Brookhaven National Laboratory National Synchrotron Light Source  

E-Print Network [OSTI]

Brookhaven National Laboratory National Synchrotron Light Source Number: Revision: LS-ESH-0027 06 copy of this file is the one on-line in the NSLS ESH website. Before using a printed copy, verify that it is the most current version by checking the document issue date on the NSLS ESH website. BROOKHAVEN NATIONAL

Ohta, Shigemi

133

Corrective Action Decision Document/Closure Report for Corrective Action Unit 106: Area 5, 11 Frenchman Flat Atmospheric Sites, Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit 106 comprises four corrective action sites (CASs): (1) 05-20-02, Evaporation Pond; (2) 05-23-05, Atmospheric Test Site - Able; (3) 05-45-04, 306 GZ Rad Contaminated Area; (4) 05-45-05, 307 GZ Rad Contaminated Area. The purpose of this CADD/CR is to provide justification and documentation supporting the recommendation that no further corrective action is needed for CAU 106 based on the implementation of corrective actions. The corrective action of clean closure was implemented at CASs 05-45-04 and 05-45-05, while no corrective action was necessary at CASs 05-20-02 and 05-23-05. Corrective action investigation (CAI) activities were performed from October 20, 2010, through June 1, 2011, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 106: Areas 5, 11 Frenchman Flat Atmospheric Sites. The approach for the CAI was divided into two facets: investigation of the primary release of radionuclides, and investigation of other releases (mechanical displacement and chemical releases). The purpose of the CAI was to fulfill data needs as defined during the data quality objective (DQO) process. The CAU 106 dataset of investigation results was evaluated based on a data quality assessment. This assessment demonstrated the dataset is complete and acceptable for use in fulfilling the DQO data needs. Investigation results were evaluated against final action levels (FALs) established in this document. A radiological dose FAL of 25 millirem per year was established based on the Industrial Area exposure scenario (2,250 hours of annual exposure). The only radiological dose exceeding the FAL was at CAS 05-45-05 and was associated with potential source material (PSM). It is also assumed that additional PSM in the form of depleted uranium (DU) and DU-contaminated debris at CASs 05-45-04 and 05-45-05 exceed the FAL. Therefore, corrective actions were undertaken at these CASs that consisted of removing PSM and collecting verification samples. Results of verification samples show that remaining soil does not contain contamination exceeding the FALs. Therefore, the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) provides the following recommendations: (1) No further corrective actions are necessary for CAU 106. (2) A Notice of Completion to NNSA/NSO is requested from the Nevada Division of Environmental Protection for closure of CAU 106. (3) Corrective Action Unit 106 should be moved from Appendix III to Appendix IV of the FFACO.

Patrick Matthews and Dawn Peterson

2011-09-01T23:59:59.000Z

134

Corrective Action Investigation Plan for Corrective Action Unit 570: Area 9 Yucca Flat Atmospheric Test Sites Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

CAU 570 comprises the following six corrective action sites (CASs): • 02-23-07, Atmospheric Test Site - Tesla • 09-23-10, Atmospheric Test Site T-9 • 09-23-11, Atmospheric Test Site S-9G • 09-23-14, Atmospheric Test Site - Rushmore • 09-23-15, Eagle Contamination Area • 09-99-01, Atmospheric Test Site B-9A These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on April 30, 2012, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 570. The site investigation process will also be conducted in accordance with the Soils Activity Quality Assurance Plan, which establishes requirements, technical planning, and general quality practices to be applied to this activity. The presence and nature of contamination at CAU 570 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the total effective dose at sample locations to the dose-based final action level. The total effective dose will be calculated as the total of separate estimates of internal and external dose. Results from the analysis of soil samples will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed near the center of each sample location will be used to measure external radiological dose. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS.

Patrick Matthews

2012-08-01T23:59:59.000Z

135

Corrective Action Investigation Plan for Corrective Action Unit 571: Area 9 Yucca Flat Plutonium Dispersion Sites, Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

CAU 571 is a grouping of sites where there has been a suspected release of contamination associated with nuclear testing. This document describes the planned investigation of CAU 571, which comprises the following corrective action sites (CASs): • 09-23-03, Atmospheric Test Site S-9F • 09-23-04, Atmospheric Test Site T9-C • 09-23-12, Atmospheric Test Site S-9E • 09-23-13, Atmospheric Test Site T-9D • 09-45-01, Windrows Crater These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the investigation report. The sites will be investigated based on the data quality objectives (DQOs) developed on March 6, 2013, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (now the Nevada Field Office). The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 571. The site investigation process will also be conducted in accordance with the Soils Activity Quality Assurance Plan, which establishes requirements, technical planning, and general quality practices to be applied to this activity. The potential contamination sources associated with CAU 571 CASs are from nuclear testing activities. The DQO process resulted in an assumption that total effective dose (TED) within a default contamination boundary exceeds the final action level (FAL) and requires corrective action. The presence and nature of contamination outside the default contamination boundaries at CAU 571 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the TED at sample locations to the dose-based FAL. The TED will be calculated as the total of separate estimates of internal and external dose. Results from the analysis of soil samples will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at the center of each sample location will be used to measure external radiological dose. Chemical contamination will be evaluated by comparing soil sample results to the FAL. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS.

Bailey, Bernadine; Matthews, Patrick

2013-07-01T23:59:59.000Z

136

Corrective Action Decision Document/Closure Report for Corrective Action Unit 374: Area 20 Schooner Unit Crater, Nevada National Security Site, Nevada with ROTC 1, Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit 374 comprises five corrective action sites (CASs): • 18-22-05, Drum • 18-22-06, Drums (20) • 18-22-08, Drum • 18-23-01, Danny Boy Contamination Area • 20-45-03, U-20u Crater (Schooner) 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 374 based on the implementation of corrective actions. The corrective action of closure in place with administrative controls was implemented at CASs 18-23-01 and 20-45-03, and a corrective action of removing potential source material (PSM) was conducted at CAS 20-45-03. The other CASs require no further action; however, best management practices of removing PSM and drums at CAS 18-22-06, and removing drums at CAS 18-22-08 were performed. Corrective action investigation (CAI) activities were performed from May 4 through October 6, 2010, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 374: Area 20 Schooner Unit Crater, Nevada Test Site, Nevada. The approach for the CAI was divided into two facets: investigating the primary release of radionuclides and investigating other releases (migration in washes and chemical releases). The purpose of the CAI was to fulfill data needs as defined during the data quality objective (DQO) process. The CAU 374 dataset of investigation results was evaluated based on the data quality indicator parameters. This evaluation demonstrated the dataset is acceptable for use in fulfilling the DQO data needs. Analytes detected during the CAI were evaluated against final action levels (FALs) established in this document. Radiological doses exceeding the FAL of 25 millirem per year were found to be present in the surface soil that was sampled. It is assumed that radionuclide levels present in subsurface media within the craters and ejecta fields (default contamination boundaries) at the Danny Boy and Schooner sites exceed the FAL. It is also assumed that PSM in the form of lead-acid batteries at Schooner exceeds the FAL. Therefore, corrective actions were undertaken that consist of removing PSM, where present, and implementing a use restriction and posting warning signs at the Danny Boy and Schooner sites. These use restrictions were recorded in the FFACO database; the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Facility Information Management System; and the NNSA/NSO CAU/CAS files. Therefore, NNSA/NSO provides the following recommendations: • No further corrective actions are necessary for CAU 374. • A Notice of Completion to NNSA/NSO is requested from the Nevada Division of Environmental Protection for closure of CAU 374. • Corrective Action Unit 374 should be moved from Appendix III to Appendix IV of the FFACO.

Patrick Matthews

2011-07-01T23:59:59.000Z

137

National Low-Level Waste Management Program Radionuclide Report Series. Volume 10, Nickel-63  

SciTech Connect (OSTI)

This report outlines the basic radiological, chemical, and physical characteristics of nickel-63 ({sup 63}Ni) and examines how these characteristics affect the behavior of {sup 63}Ni in various environmental media, such as soils, groundwater, plants, animals, the atmosphere, and the human body. Discussions also include methods of {sup 63}Ni production, waste types, and waste forms that contain {sup 63}Ni. The primary source of {sup 63}Ni in the environment has been low-level radioactive waste material generated as a result of neutron activation of stable {sup 62}Ni that is present in the structural components of nuclear reactor vessels. {sup 63}Ni enters the environment from the dismantling activities associated with nuclear reactor decommissioning. However, small amounts of {sup 63}Ni have been detected in the environment following the testing of thermonuclear weapons in the South Pacific. Concentrations as high as 2.7 Bq{sup a} per gram of sample (or equivalently 0.0022 parts per billion) were observed on Bikini Atoll (May 1954). {sup 63}Ni was not created as a fission product species (e.g., from {sup 235}U or {sup 239}Pu fissions), but instead was produced as a result of neutron capture in {sup 63}Ni, a common nickel isotope present in the stainless steel components of nuclear weapons (e.g., stainless-304 contains {approximately}9% total Ni or {approximately}0.3% {sup 63}Ni).

Carboneau, M.L.; Adams, J.P.

1995-02-01T23:59:59.000Z

138

Level III baseline risk evaluation for Building 3505 at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

The Level III Baseline Risk Evaluation (BRE) for Building 3505, the ORNL Metal Recovery Facility, provides an analysis of the potential for adverse health effects, current or future, associated with the presence of hazardous substances in the building. The Metal Recovery Facility was used from 1952 through 1960 to process large quantities of radioactive material using the PUREX process for the recovery of uranium-238, plutonium-239, neptunium-237, and americium-241. The facility consists of seven process cells (A through G), a canal, a dissolver room, a dissolver pit, an office, locker room, storage area, control room, electrical gallery, shop, and makeup area. The cells were used to house the nuclear fuel reprocessing equipment, and the canal was constructed to be used as a water-shielded transfer canal. Currently, there are no known releases of radioactive contaminants from Building 3505. To perform the BRE, historical radiological survey data were used to estimate the concentration of alpha- and beta/gamma emitting radionuclides in the various cells, rooms, and other areas in Building 3505. Data from smear surveys were used to estimate the amount of transferable contamination (to which receptors can be exposed via inhalation and ingestion), and data from probe surveys were used to estimate the amount of both fixed and transferable contamination (from which receptors can receive external exposure). Two land use scenarios, current and future, and their subsequent exposure scenarios were explored in the BRE. Under the current land use scenario, two exposure scenarios were evaluated. The first was a worst-case industrial exposure scenario in which the receptor is a maintenance worker who works 8 hours/day, 350 days/year in the building for 25 years. In the second, more realistic exposure scenario, the receptor is a surveillance and maintenance (S&M) worker who spends two 8-hour days/year in the building for 25 years.

Mostella, W.B. Jr.

1994-12-01T23:59:59.000Z

139

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

SciTech Connect (OSTI)

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

Patrick Matthews

2011-06-01T23:59:59.000Z

140

Corrective Action Investigation Plan for Corrective Action Unit 104: Area 7 Yucca Flat Atmospheric Test Sites, Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

CAU 104 comprises the 15 CASs listed below: (1) 07-23-03, Atmospheric Test Site T-7C; (2) 07-23-04, Atmospheric Test Site T7-1; (3) 07-23-05, Atmospheric Test Site; (4) 07-23-06, Atmospheric Test Site T7-5a; (5) 07-23-07, Atmospheric Test Site - Dog (T-S); (6) 07-23-08, Atmospheric Test Site - Baker (T-S); (7) 07-23-09, Atmospheric Test Site - Charlie (T-S); (8) 07-23-10, Atmospheric Test Site - Dixie; (9) 07-23-11, Atmospheric Test Site - Dixie; (10) 07-23-12, Atmospheric Test Site - Charlie (Bus); (11) 07-23-13, Atmospheric Test Site - Baker (Buster); (12) 07-23-14, Atmospheric Test Site - Ruth; (13) 07-23-15, Atmospheric Test Site T7-4; (14) 07-23-16, Atmospheric Test Site B7-b; (15) 07-23-17, Atmospheric Test Site - Climax These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on April 28, 2011, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 104. The releases at CAU 104 consist of surface-deposited radionuclides from 30 atmospheric nuclear tests. The presence and nature of contamination at CAU 104 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the total effective dose (TED) to the dose-based final action level (FAL). The presence of TED exceeding the FAL is considered a radiological contaminant of concern (COC). Anything identified as a COC will require corrective action. The TED will be calculated as the total of separate estimates of internal and external dose. Results from the analysis of soil samples will be used to calculate internal radiological dose. Thermoluminescent dosimeters will be used to measure external radiological dose. Based on process knowledge of the releases associated with the nuclear tests and radiological survey information about the location and shape of the resulting contamination plume, it was determined that the releases from the nuclear tests are co-located and will be investigated concurrently. A field investigation will be performed to define areas where TED exceeds the FAL and to determine whether other COCs are present at the site. The investigation will also collect information to determine the presence and nature of contamination associated with migration and excavation, as well as any potential releases discovered during the investigation. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS.

Patrick Matthews

2011-08-01T23:59:59.000Z

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141

Corrective Action Investigation Plan for Corrective Action Unit 366: Area 11 Plutonium Valley Dispersion Sites, Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit 366 comprises the six corrective action sites (CASs) listed below: (1) 11-08-01, Contaminated Waste Dump No.1; (2) 11-08-02, Contaminated Waste Dump No.2; (3) 11-23-01, Radioactively Contaminated Area A; (4) 11-23-02, Radioactively Contaminated Area B; (5) 11-23-03, Radioactively Contaminated Area C; and (6) 11-23-04, Radioactively Contaminated Area D. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed July 6, 2011, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 366. The presence and nature of contamination at CAU 366 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the total effective dose (TED) at sample locations to the dose-based final action level (FAL). The TED will be calculated by summing the estimates of internal and external dose. Results from the analysis of soil samples collected from sample plots will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at each sample location will be used to measure external radiological dose. Based on historical documentation of the releases associated with the nuclear tests, it was determined that CASs 11-23-02, 11-23-03, and 11-23-04 will be investigated as one release site. The three test areas associated with these CASs are in close proximity; the devices tested were all composed of plutonium and enriched uranium; and the ground zeroes are all posted high contamination areas (HCAs). Because the device tested at CAS 11-23-01 was composed primarily of enriched uranium and the ground zero is not a posted HCA, the CAS will be investigated as a separate release. The DQO process also resulted in an assumption that TED within the HCAs and contaminated waste dumps exceeds the FAL and requires corrective action. A field investigation will be performed to define where TED exceeds the FAL and to determine whether other contaminants of concern are present at the site associated with other activities that took place at the site or from spills or waste discovered during the investigation. The presence and nature of contamination from other types of releases (such as migration and any potential releases discovered during the investigation) will be evaluated using soil samples collected from the locations most likely containing contamination, if present. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS.

Patrick Matthews

2011-09-01T23:59:59.000Z

142

Corrective Action Decision Document/Closure Report for Corrective Action Unit 375: Area 30 Buggy Unit Craters, Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit 375 comprises three corrective action sites (CASs): (1) 25-23-22, Contaminated Soils Site; (2) 25-34-06, Test Cell A Bunker; and (3) 30-45-01, U-30a, b, c, d, e Craters. The purpose of this CADD/CR is to provide justification and documentation supporting the recommendation that no further corrective action is needed for CAU 375 based on the implementation of corrective action of closure in place with administrative controls at CAS 25-23-22, no further action at CAS 25-34-06, and closure in place with administrative controls and removal of potential source material (PSM) at CAS 30-45-01. Corrective action investigation (CAI) activities were performed from July 28, 2010, through April 4, 2011, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 375: Area 30 Buggy Unit Craters. The approach for the CAI was divided into two facets: investigation of the primary release of radionuclides, and investigation of other releases (migration in washes and chemical releases). The purpose of the CAI was to fulfill data needs as defined during the data quality objective (DQO) process. The CAU 375 dataset of investigation results was evaluated based on the data quality assessment. This assessment demonstrated the dataset is acceptable for use in fulfilling the DQO data needs. Investigation results were evaluated against final action levels (FALs) established in this document. A radiological dose FAL of 25 millirem per year was established based on the Remote Work Area exposure scenario (336 hours of annual exposure). Radiological doses exceeding the FAL were assumed to be present within the default contamination boundaries at CASs 25-23-22 and 30-45-01. No contaminants were identified at CAS 25-34-06, and no corrective action is necessary. Potential source material in the form of lead plate, lead-acid batteries, and oil within an abandoned transformer were identified at CAS 30-45-01, and corrective actions were undertaken that consisted of removing the PSM. Use restrictions and warning signs were implemented for the remaining radiological contamination at CASs 25-23-22 and 30-45-01. These use restrictions were recorded in the FFACO database; the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Facility Information Management System; and the NNSA/NSO CAU/CAS files. Therefore, NNSA/NSO provides the following recommendations: (1) No further corrective actions are necessary for CAU 375; (2) A Notice of Completion to NNSA/NSO is requested from the Nevada Division of Environmental Protection for closure of CAU 375; and (3) Move CAU 375 from Appendix III to Appendix IV of the FFACO.

Patrick Matthews

2011-08-01T23:59:59.000Z

143

National survey of crystalline rocks and recommendations of regions to be explored for high-level radioactive waste repository sites  

SciTech Connect (OSTI)

A reconnaissance of the geological literature on large regions of exposed crystalline rocks in the United States provides the basis for evaluating if any of those regions warrant further exploration toward identifying potential sites for development of a high-level radioactive waste repository. The reconnaissance does not serve as a detailed evaluation of regions or of any smaller subunits within the regions. Site performance criteria were selected and applied insofar as a national data base exists, and guidelines were adopted that relate the data to those criteria. The criteria include consideration of size, vertical movements, faulting, earthquakes, seismically induced ground motion, Quaternary volcanic rocks, mineral deposits, high-temperature convective ground-water systems, hydraulic gradients, and erosion. Brief summaries of each major region of exposed crystalline rock, and national maps of relevant data provided the means for applying the guidelines and for recommending regions for further study. It is concluded that there is a reasonable likelihood that geologically suitable repository sites exist in each of the major regions of crystalline rocks. The recommendation is made that further studies first be conducted of the Lake Superior, Northern Appalachian and Adirondack, and the Southern Appalachian Regions. It is believed that those regions could be explored more effectively and suitable sites probably could be found, characterized, verified, and licensed more readily there than in the other regions.

Smedes, H.W.

1983-04-01T23:59:59.000Z

144

Low-level radioactive waste management: transitioning to off-site disposal at Los Alamos National Laboratory  

SciTech Connect (OSTI)

Facing the closure of nearly all on-site management and disposal capability for low-level radioactive waste (LLW), Los Alamos National Laboratory (LANL) is making ready to ship the majority of LLW off-site. In order to ship off-site, waste must meet the Treatment, Storage, and Disposal Facility's (TSDF) Waste Acceptance Criteria (WAC). In preparation, LANL's waste management organization must ensure LANL waste generators characterize and package waste compliantly and waste characterization documentation is complete and accurate. Key challenges that must be addressed to successfully make the shift to off-site disposal of LLW include improving the detail, accuracy, and quality of process knowledge (PK) and acceptable knowledge (AK) documentation, training waste generators and waste management staff on the higher standard of data quality and expectations, improved WAC compliance for off-site facilities, and enhanced quality assurance throughout the process. Certification of LANL generators will allow direct off-site shipping of LLW from their facilities.

Dorries, Alison M [Los Alamos National Laboratory

2010-11-09T23:59:59.000Z

145

Corrective Action Decision Document/Closure Report for Corrective Action Unit 567: Miscellaneous Soil Sites Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

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.

Matthews, Patrick

2014-12-01T23:59:59.000Z

146

THE Low-level Radio Frequency System for the superconducting cavities of National Synchrotron Light Source II  

SciTech Connect (OSTI)

A digital low-level radio frequency (LLRF) field controller has been developed for the storage ring of The National Synchrotron Light Source-II (NSLS-II). The primary performance goal for the LLRF is to support the required RF operation of the superconducting cavities with a beam current of 500mA and a 0.14 degree or better RF phase stability. The digital field controller is FPGA-based, in a standard format 19-inch/I-U chassis. It has an option of high-level control support with MATLAB running on a local host computer through a USB2.0 port. The field controller has been field tested with the high-power superconducting RF (SRF) at Canadian light Source, and successfully stored a high beam current of 250 mA. The test results show that required specifications for the cavity RF field stability are met. This digital field controller is also currently being used as a development platform for other functional modules in the NSLS-II RF systems.

Ma, H.; Rose, J.; Holub, B.; Cupolo, J.; Oliva, J.; Sikora, R.; Yeddulla, M.

2011-03-28T23:59:59.000Z

147

Status Update on Action 2b: Revision of DOE G 226.1-2 with new Guidance for Activity-level Work Planning and Control  

Broader source: Energy.gov [DOE]

Slide Presentation by Roger Claycomb, Work Control Program Manager, DOE Idaho Operations Office. Strengthen guidance and formality associated with contractor implementation and Federal monitoring of activity-level WP&C. Develop a DOE Guide on Federal oversight and evaluation of the effectiveness of Activity-Level WP&C.

148

Journal of Machine Learning Research 11 (2010) 491-516 Submitted 3/09; Revised 8/09; Published 2/10 Classification Using Geometric Level Sets  

E-Print Network [OSTI]

classification, an efficient scheme is developed using a logarithmic number of decision functions in the number/10 Classification Using Geometric Level Sets Kush R. Varshney KRV@MIT.EDU Alan S. Willsky WILLSKY@MIT.EDU Laboratory: Ulrike von Luxburg Abstract A variational level set method is developed for the supervised classification

Willsky, Alan S.

149

Level: National Data;  

U.S. Energy Information Administration (EIA) 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 CenterFranconia,(Million Barrels) Crude Oil Reserves in Nonproducing Reservoirs Year in Review1,213 136,422 133,442 140,9488

150

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)

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.

Matthews, Patrick

2013-11-01T23:59:59.000Z

151

Lessons Learned at the Nevada National Security Site Implementing the EFCOG Activity-level Work Planning and Control Guide  

Broader source: Energy.gov [DOE]

Slide Presentation by Steele Coddington, Work Planning Manager, National Security Technologies, Nevada National Security Site. Lessons Learned Implementing Work Planning & Control. 6 Step Process for improving WP&C.

152

Safety Basis Requirements for Nonnuclear Facilities at Lawrence Livermore National Laboratory Site-Specific Work Smart Standard Revision 3 December 2006  

SciTech Connect (OSTI)

This standard establishes requirements that, when coupled with Lawrence Livermore National Laboratory's (LLNL's) Integrated Safety Management System (ISMS) methods and other Work Smart Standards for assuring worker safety, assure that the impacts of nonnuclear operations authorized in LLNL facilities are well understood and controlled in a manner that protects the health of workers, the public, and the environment. All LLNL facilities shall be classified based on potential for adverse impact of operations to the health of co-located (i.e., nearby) workers and the public in accordance with this standard, Title 10 Code of Federal Regulations (10 CFR) 830, Subpart B, and Department of Energy Order (DOE O) 420.2A.

Beach, D; Brereton, S; Failor, R; Hildum, J; Ingram, C; Spagnolo, S; van Warmerdam, C

2007-06-07T23:59:59.000Z

153

Environmental, Safety, and Health Plan for the remedial investigation/feasibility study at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Revision 1, Environmental Restoration Program  

SciTech Connect (OSTI)

This Environmental, Safety, and Health (ES&H) Plan presents the concepts and methodologies to be followed during the remedial investigation/feasibility study (RI/FS) for Oak Ridge National Laboratory (ORNL) to protect the health and safety of employees, the public, and the environment. This ES&H Plan acts as a management extension for ORNL and Martin Marietta Energy Systems, Inc. (Energy Systems) to direct and control implementation of the project ES&H program. The subsections that follow describe the program philosophy, requirements, quality assurance measures, and methods for applying the ES&H program to individual waste area grouping (WAG) remedial investigations. Hazardous work permits (HWPs) will be used to provide task-specific health and safety requirements.

Not Available

1993-05-01T23:59:59.000Z

154

This volume contains revised and extended versions of selected papers presented at the Ninth Inter national Symposium on Temporal Representation and Reasoning (TIME) held in Manchester, UK,  

E-Print Network [OSTI]

. The papers in this edition represent a broad spectrum of current research work relating to the use of time different levels of detail, representing and reasoning about time granularities using linear­time temporal results for propositional and first­order branching­time temporal logics, local search methods for solving

Franconi, Enrico

155

Brookhaven National Laboratory National Synchrotron Light Source  

E-Print Network [OSTI]

Brookhaven National Laboratory National Synchrotron Light Source Number: Revision: LS-ESH-0026 4 (ANSI) Hazard Class 3B and 4 laser systems must be documented, reviewed, and approved through use) CrystaLaser Compact Solid State Laser (Class 3B) Location: All four lasers are located in the U2A

Ohta, Shigemi

156

High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 7. Revision 1  

SciTech Connect (OSTI)

The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 7) presents the standards and requirements for the following sections: Occupational Safety and Health, and Environmental Protection.

Burt, D.L.

1994-04-01T23:59:59.000Z

157

revision:20090902 modified:20090903  

E-Print Network [OSTI]

871 revision:2009­09­02 modified:2009­09­03 A trichotomy of countable, stable, unsuperstable and DMS 0600940 and Israel Science Foundation Grant no. 242/03. Publica­ tion 871. 1 #12; 871 revision of formulas (see Definition 2.3). The origins of these 2 #12; 871 revision:2009­09­02 modified:2009

Shelah, Saharon

158

Restrained Revision Richard Booth  

E-Print Network [OSTI]

another, newer, piece of information comes along, Boutilier's natural revision [4, 5] being a caseRestrained Revision Richard Booth School of IT and Computer Science University of Wollongong of their proposed framework for iterated belief revision Darwiche and Pearl advanced a convincing argument against

Booth, Richard

159

Revision Level: 03 Revision Date: 10/21/13  

E-Print Network [OSTI]

required for all collector types. However, the form is generic in nature so many fields will not apply to your particular collector. Therefore not all fields in this application will be filled out. Where): The information submitted with this application has been reviewed by me and is true and correct to the best of my

160

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)

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.

Matthews, Patrick

2013-09-01T23:59:59.000Z

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


161

?Framework for a Risk-Informed Groundwater Compliance Strategy for Corrective Action Unit 98: Frenchman Flat, Nevada National Security Site, Nye County, Nevada, Revision 1  

SciTech Connect (OSTI)

Note: This document was prepared before the NTS was renamed the Nevada National Security Site (August 23, 2010); thus, all references to the site herein remain NTS. Corrective Action Unit (CAU) 98, Frenchman Flat, at the Nevada Test Site (NTS) was the location of ten underground nuclear tests between 1965 and 1971. As a result, radionuclides were released in the subsurface in the vicinity of the test cavities. Corrective Action Unit 98 and other CAUs at the NTS and offsite locations are being investigated. The Frenchman Flat CAU is one of five Underground Test Area (UGTA) CAUs at the NTS that are being evaluated as potential sources of local or regional impact to groundwater resources. For UGTA sites, including Frenchman Flat, contamination in and around the test cavities will not be remediated because it is technologically infeasible due to the depth of the test cavities (150 to 2,000 feet [ft] below ground surface) and the volume of contaminated groundwater at widely dispersed locations on the NTS. Instead, the compliance strategy for these sites is to model contaminant flow and transport, estimate the maximum spatial extent and volume of contaminated groundwater (over a period of 1,000 years), maintain institutional controls, and restrict access to potentially contaminated groundwater at areas where contaminants could migrate beyond the NTS boundaries.

Sam Marutzky

2010-09-01T23:59:59.000Z

162

Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 575: Area 15 Miscellaneous Sites, Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the actions needed to achieve closure for Corrective Action Unit (CAU) 575, Area 15 Miscellaneous Sites, identified in the Federal Facility Agreement and Consent Order (FFACO). CAU 575 comprises the following four corrective action sites (CASs) located in Area 15 of the Nevada National Security Site: • 15-19-02, Waste Burial Pit • 15-30-01, Surface Features at Borehole Sites • 15-64-01, Decontamination Area • 15-99-03, Aggregate Plant This plan provides the methodology for field activities needed to gather the necessary information for closing each CAS. There is sufficient information and process knowledge from historical documentation and investigations of similar sites regarding the expected nature and extent of potential contaminants to recommend closure of CAU 575 using the SAFER process. Additional information will be obtained by conducting a field investigation to document and verify the adequacy of existing information, to affirm the predicted corrective action decisions, and to provide sufficient data to implement the corrective actions. This will be presented in a closure report that will be prepared and submitted to the Nevada Division of Environmental Protection (NDEP) for review and approval.

Matthews, Patrick

2014-12-01T23:59:59.000Z

163

Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory. Part 1, Waste streams and treatment technologies  

SciTech Connect (OSTI)

This report describes health and safety concerns associated with the Mixed and Low-level Waste Treatment Facility at the Idaho National Engineering Laboratory. Various hazards are described such as fire, electrical, explosions, reactivity, temperature, and radiation hazards, as well as the potential for accidental spills, exposure to toxic materials, and other general safety concerns.

Neupauer, R.M.; Thurmond, S.M.

1992-09-01T23:59:59.000Z

164

Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory  

SciTech Connect (OSTI)

This report describes health and safety concerns associated with the Mixed and Low-level Waste Treatment Facility at the Idaho National Engineering Laboratory. Various hazards are described such as fire, electrical, explosions, reactivity, temperature, and radiation hazards, as well as the potential for accidental spills, exposure to toxic materials, and other general safety concerns.

Neupauer, R.M.; Thurmond, S.M.

1992-09-01T23:59:59.000Z

165

National Level Co-Control Study of the Targets for Energy Intensity and Sulfur Dioxide in China  

E-Print Network [OSTI]

David Kline of the National Renewable Energy Laboratory foralong with hydropower, renewable and nuclear capacityCapacity Accelerated Renewable Generation Power Sector CO2

Zhou, Nan

2013-01-01T23:59:59.000Z

166

Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 465: Hydronuclear Nevada National Security Site, Nevada, with ROTC 1, Revision 0  

SciTech Connect (OSTI)

This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the actions needed to achieve closure for Corrective Action Unit (CAU) 465, Hydronuclear, identified in the Federal Facility Agreement and Consent Order (FFACO). Corrective Action Unit 465 comprises the following four corrective action sites (CASs) located in Areas 6 and 27 of the Nevada National Security Site: (1) 00-23-01, Hydronuclear Experiment; (2) 00-23-02, Hydronuclear Experiment; (3) 00-23-03, Hydronuclear Experiment; (4) 06-99-01, Hydronuclear. The sites will be investigated based on the data quality objectives (DQOs) developed on July 6, 2011, by representatives of the Nevada Division of Environmental Protection (NDEP) and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to determine and implement appropriate corrective actions for each CAS in CAU 465. For CAU 465, two potential release components have been identified. The subsurface release component includes potential releases of radiological and nonradiological contaminants from the subsurface hydronuclear experiments and disposal boreholes. The surface release component consists of other potential releases of radiological and nonradiological contaminants to surface soils that may have occurred during the pre- and post-test activities. This plan provides the methodology for collection of the necessary information for closing each CAS component. There is sufficient information and process knowledge from historical documentation, contaminant characteristics, existing regional and site groundwater models, and investigations of similar sites regarding the expected nature and extent of potential contaminants to recommend closure of CAU 465 using the SAFER process. For potential subsurface releases, flow and transport models will be developed to integrate existing data into a conservative description of contaminant migration in the unsaturated zone from the hydronuclear experiments and disposal boreholes. For the potential surface releases, additional information will be obtained by conducting a field investigation before selecting the appropriate corrective action for each CAS component. It is anticipated that results of the flow and transport models, the field investigation, and implementation of the corrective action of closure in place will support a defensible recommendation that no further corrective action is necessary. This will be presented in a closure report that will be prepared and submitted to NDEP for review and approval. The following text summarizes the SAFER activities that will support the closure of CAU 465: (1) Perform site preparation activities (e.g., utilities clearances, and radiological and visual surveys). (2) Move or remove and dispose of debris at various CASs, as required. (3) Collect environmental samples from designated target populations (e.g., stained soil) to confirm or disprove the presence of contaminants of concern as necessary to supplement existing information. (4) Evaluate and analyze existing data to develop conservative flow and transport models to simulate the potential for contaminant migration from the hydronuclear experiments and disposal boreholes to the water table within 1,000 years. (5) Confirm the preferred closure option (closure in place with use restrictions) is sufficient to protect human health and the environment.

Patrick Matthews

2011-11-01T23:59:59.000Z

167

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

SciTech Connect (OSTI)

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

Mark Krauss

2011-09-01T23:59:59.000Z

168

External Peer Review Team Report for Corrective Action Unit 97: Yucca Flat/Climax Mine, Nevada National Security Site, Nye County, Nevada, Revision 0  

SciTech Connect (OSTI)

The peer review team commends the Navarro-Intera, LLC (N-I), team for its efforts in using limited data to model the fate of radionuclides in groundwater at Yucca Flat. Recognizing the key uncertainties and related recommendations discussed in Section 6.0 of this report, the peer review team has concluded that U.S. Department of Energy (DOE) is ready for a transition to model evaluation studies in the corrective action decision document (CADD)/corrective action plan (CAP) stage. The DOE, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) clarified the charge to the peer review team in a letter dated October 9, 2014, from Bill R. Wilborn, NNSA/NFO Underground Test Area (UGTA) Activity Lead, to Sam J. Marutzky, N-I UGTA Project Manager: “The model and supporting information should be sufficiently complete that the key uncertainties can be adequately identified such that they can be addressed by appropriate model evaluation studies. The model evaluation studies may include data collection and model refinements conducted during the CADD/CAP stage. One major input to identifying ‘key uncertainties’ is the detailed peer review provided by independent qualified peers.” The key uncertainties that the peer review team recognized and potential concerns associated with each are outlined in Section 6.0, along with recommendations corresponding to each uncertainty. The uncertainties, concerns, and recommendations are summarized in Table ES-1. The number associated with each concern refers to the section in this report where the concern is discussed in detail.

Marutzky, Sam J.; Andrews, Robert

2015-01-01T23:59:59.000Z

169

Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada National Security Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site  

SciTech Connect (OSTI)

The Nevada National Security Site (NNSS) is located approximately 105 km (65 mi) northwest of Las Vegas, Nevada. The U.S. Department of Energy National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is the federal lands management authority for the NNSS and National Security Technologies, LLC (NSTec) is the Management and Operations contractor. Access on and off the NNSS is tightly controlled, restricted, and guarded on a 24-hour basis. The NNSS is posted with signs along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NNSS. The Area 5 Radioactive Waste Management Site (RWMS) is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NNSS (Figure 1), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. The site will be used for the disposal of regulated Asbestiform Low-Level Waste (ALLW), small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains Polychlorinated Biphenyl (PCB) Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. Waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM) and PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water. The term asbestiform is used throughout this document to describe RACM. The disposal site will be used as a depository of permissible waste generated both on site and off site. All generators designated by NNSA/NSO will be eligible to dispose regulated ALLW at the Asbestiform Low-Level Waste Disposal Site in accordance with the DOE/NV-325, Nevada National Security Site Waste Acceptance Criteria (NNSSWAC, current revision). Approval will be given by NNSA/NSO to generators that have successfully demonstrated through process knowledge (PK) and/or sampling and analysis that the waste is low-level, contains asbestiform material, or contains PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, or small quantities of LLHB demolition and construction waste and does not contain prohibited waste materials. Each waste stream will be approved through the Radioactive Waste Acceptance Program (RWAP), which ensures that the waste meets acceptance requirements outlined in the NNSSWAC.

NSTec Environmental Programs

2010-10-04T23:59:59.000Z

170

Revised Spring 2008 NIH Public Access Policy  

E-Print Network [OSTI]

Revised Spring 2008 NIH Public Access Policy Notice Number: NOT-OD-08-033 - (See Notice NOT-OD-08-161 (Consolidated Appropriations Act, 2008), the NIH voluntary Public Access Policy (NOT-OD-05-022) is now mandatory funded by the NIH submit or have submitted for them to the National Library of Medicine's PubMed Central

171

Anomalies of Nuclear Criticality, Revision 6  

SciTech Connect (OSTI)

This report is revision 6 of the Anomalies of Nuclear Criticality. This report is required reading for the training of criticality professionals in many organizations both nationally and internationally. This report describes many different classes of nuclear criticality anomalies that are different than expected.

Clayton, E. D.; Prichard, Andrew W.; Durst, Bonita E.; Erickson, David; Puigh, Raymond J.

2010-02-19T23:59:59.000Z

172

EA-1442: Final Environmental Assessment, Revised  

Broader source: Energy.gov [DOE]

Proposed Construction and Operation of a Biosafety Level 3 Facility at Lawrence Livermore National Laboratory, Livermore, California

173

Corrective Action Decision Document/Corrective Action Plan for Corrective Action Unit 104: Area 7 Yucca Flat Atmospheric Test Sites Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

CAU 104 comprises the following corrective action sites (CASs): • 07-23-03, Atmospheric Test Site T-7C • 07-23-04, Atmospheric Test Site T7-1 • 07-23-05, Atmospheric Test Site • 07-23-06, Atmospheric Test Site T7-5a • 07-23-07, Atmospheric Test Site - Dog (T-S) • 07-23-08, Atmospheric Test Site - Baker (T-S) • 07-23-09, Atmospheric Test Site - Charlie (T-S) • 07-23-10, Atmospheric Test Site - Dixie • 07-23-11, Atmospheric Test Site - Dixie • 07-23-12, Atmospheric Test Site - Charlie (Bus) • 07-23-13, Atmospheric Test Site - Baker (Buster) • 07-23-14, Atmospheric Test Site - Ruth • 07-23-15, Atmospheric Test Site T7-4 • 07-23-16, Atmospheric Test Site B7-b • 07-23-17, Atmospheric Test Site - Climax These 15 CASs include releases from 30 atmospheric tests conducted in the approximately 1 square mile of CAU 104. Because releases associated with the CASs included in this CAU overlap and are not separate and distinguishable, these CASs are addressed jointly at the CAU level. The purpose of this CADD/CAP is to evaluate potential corrective action alternatives (CAAs), provide the rationale for the selection of recommended CAAs, and provide the plan for implementation of the recommended CAA for CAU 104. Corrective action investigation (CAI) activities were performed from October 4, 2011, through May 3, 2012, as set forth in the CAU 104 Corrective Action Investigation Plan.

Patrick Matthews

2012-10-01T23:59:59.000Z

174

WIPP WAC Equivalence Support Measurements for Low-Level Sludge Waste at Los Alamos National Laboratory - 12242  

SciTech Connect (OSTI)

Los Alamos National Laboratory (LANL) uses the Nevada National Security Site (NNSS) as an off-site disposal facility for low-level waste (LLW), including sludge waste. NNSS has issued a position paper that indicates that systems that are not certified by the Carlsbad Field Office (CBFO) for Waste Isolation Pilot Plant (WIPP) disposal of Transuranic (TRU) waste must demonstrate equivalent practices to the CBFO certified systems in order to assign activity concentration values to assayed items without adding in the Total Measurement Uncertainty (TMU) when certifying waste for NNSS disposal. Efforts have been made to meet NNSS requirements to accept sludge waste for disposal at their facility. The LANL LLW Characterization Team uses portable high purity germanium (HPGe) detector systems for the nondestructive assay (NDA) of both debris and sludge LLW. A number of performance studies have been conducted historically by LANL to support the efficacy and quality of assay results generated by the LANL HPGe systems, and, while these detector systems are supported by these performance studies and used with LANL approved procedures and processes, they are not certified by CBFO for TRU waste disposal. Beginning in 2009, the LANL LLW Characterization Team undertook additional NDA measurements of both debris and sludge simulated waste containers to supplement existing studies and procedures to demonstrate full compliance with the NNSS position paper. Where possible, Performance Demonstration Project (PDP) drums were used for the waste matrix and PDP sources were used for the radioactive sources. Sludge drums are an example of a matrix with a uniform distribution of contaminants. When attempting to perform a gamma assay of a sludge drum, it is very important to adequately simulate this uniform distribution of radionuclides in order to accurately model the assay results. This was accomplished by using a spiral radial source tube placement in a sludge drum rather than the standard three source tubes seen in debris PDP drums. Available line sources (Eu-152) were placed in the spiral tubes to further accomplish the desired uniform distribution of radionuclides. The standard PDP drum (PDP matrix drum 005) and PDP sources were used to determine the lower limits of detection (LLD) and TMU. Analysis results for the sludge drum matrix case for two HPGe detectors were tabulated and evaluated. NNSS has accepted the methodology and results of the measurements towards demonstrating equivalence to CBFO certified systems. In conclusion, the WES-WGS and CMR-OPS gamma spectroscopy teams at LANL have defined and performed measurements that serve to establish and demonstrate equivalency with the processes used by CBFO certified NDA systems. The supplemental measurements address four key areas in Appendix A of DOE/WIPP-02-3122: Annual Calibration Confirmation and Performance Check measurements; LLD determination; and TMU definition. For these measurements the containers, matrices and activity loadings are selected to represent items being assayed in real LLW cases. The LLD and the TMU bounding measurements are to be performed one time and will not be required to be repeated in future campaigns. The annual calibration and performance check measurements were performed initially and planned to repeat in annual campaigns in order to maintain NNSS certification. PDP sources and a PDP sludge drum as well as Eu-152 line sources and a spiral sludge drum were used for the measurements. In all cases, the results for accuracy and precision (%R and %RSD, respectively) were within allowable ranges as defined by the WIPP PDP program. LLD (or MDC) results were established for all the ten WIPP reportable radionuclides and U-235, and the MDC for Pu-239 was established in all cases to be well under 100 nCi/g. Useful results for reducing estimated uncertainties were established and an interesting unexpected case of high bias was observed and will be applied toward this end. (authors)

Gruetzmacher, Kathleen M.; Bustos, Roland M.; Ferran, Scott G.; Gallegos, Lucas E. [Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States); Lucero, Randy P. [Pajarito Scientific Corporation, Santa Fe, New Mexico 87507 (United States)

2012-07-01T23:59:59.000Z

175

Corrective Action Decision Document/Closure Report for Corrective Action Unit 561: Waste Disposal Areas, Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

CAU 561 comprises 10 CASs: (1) 01-19-01, Waste Dump; (2) 02-08-02, Waste Dump and Burn Area; (3) 03-19-02, Debris Pile; (4) 05-62-01, Radioactive Gravel Pile; (5) 12-23-09, Radioactive Waste Dump; (6) 22-19-06, Buried Waste Disposal Site; (7) 23-21-04, Waste Disposal Trenches ; (8) 25-08-02, Waste Dump; (9) 25-23-21, Radioactive Waste Dump; and (10) 25-25-19, Hydrocarbon Stains and Trench. The purpose of this CADD/CR is to provide justification and documentation supporting the recommendation for closure of CAU 561 with no further corrective action. The purpose of the CAI was to fulfill the following data needs as defined during the DQO process: (1) Determine whether COCs are present; (2) If COCs are present, determine their nature and extent; and (3) Provide sufficient information and data to complete appropriate corrective actions. The following contaminants were determined to be present at concentrations exceeding their corresponding FALs: (1) No contamination exceeding FALs was identified at CASs 01-19-01, 03-19-02, 05-62-01, 12-23-09, and 22-19-06. (2) The surface and subsurface soil within the burn area at CAS 02-08-02 contains arsenic and lead above the FALs of 23 milligrams per kilogram (mg/kg) and 800 mg/kg, respectively. The surface and subsurface soil within the burn area also contains melted lead slag (potential source material [PSM]). The soil within the waste piles contains polyaromatic hydrocarbons (PAHs) above the FALs. The contamination within the burn area is spread throughout the area, as it was not feasible to remove all the PSM (melted lead), while at the waste piles, the contamination is confined to the piles. (3) The surface and subsurface soils within Trenches 3 and 5 at CAS 23-21-04 contain arsenic and polychlorinated biphenyls (PCBs) above the FALs of 23 mg/kg and 0.74 mg/kg, respectively. The soil was removed from both trenches, and the soil that remains at this CAS does not contain contamination exceeding the FALs. Lead bricks and counterweights were also removed, and the soil below these items does not contain contamination that exceeds the FAL for lead. (4) The concrete-like material at CAS 25-08-02 contains arsenic above the FAL of 23 mg/kg. This concrete-like material was removed, and the soil that remains at this CAS does not contain contamination exceeding the FALs. Lead-acid batteries were also removed, and the soil below the batteries does not contain contamination that exceeds the FAL for lead. (5) The surface soils within the main waste dump at the posted southern radioactive material area (RMA) at CAS 25-23-21 contain cesium (Cs)-137 and PCBs above the FALs of 72.9 picocuries per gram (pCi/g) and 0.74 mg/kg, respectively. The soil was removed from the RMA, and the soil that remains at this CAS does not contain contamination exceeding the FALs. (6) The surface and subsurface soils at CAS 25-25-19 do not contain contamination exceeding the FALs. In addition, lead bricks were removed, and the soil below these items does not contain contamination that exceeds the FAL for lead. The following best management practices were implemented: (1) Housekeeping debris at CASs 02-08-02, 23-21-04, 25-08-02, 25-23-21, and 25-25-19 was removed and disposed of; (2) The open trenches at CAS 23-21-04 were backfilled; (3) The waste piles at CAS 25-08-02 were removed and the area leveled to ground surface; and (4) The remaining waste piles at the main waste dump at CAS 25-23-21 were leveled to ground surface. Therefore, NNSA/NSO provides the following recommendations: (1) No further action for CASs 01-19-01, 03-19-02, 05-62-01, 12-23-09, and 22-19-06; (2) Closure in place with an FFACO use restriction (UR) at CAS 02-08-02 for the remaining PAH-, arsenic-, and lead-contaminated soil, and the melted lead PSM. The UR form and map have been filed in the NNSA/NSO Facility Information Management System, the FFACO database, and the NNSA/NSO CAU/CAS files; (3) No further corrective action at CAS 23-21-04, as the lead bricks and counterweights (PSM) have been removed, and the COCs of arsenic and PCBs in soil have be

Mark Krauss

2011-08-01T23:59:59.000Z

176

DWPF waste form compliance plan (Draft Revision)  

SciTech Connect (OSTI)

The Department of Energy currently has over 100 million liters of high-level radioactive waste in storage at the Savannah River Site (SRS). In the late 1970`s, the Department of Energy recognized that there were significant safety and cost advantages associated with immobilizing the high-level waste in a stable solid form. Several alternative waste forms were evaluated in terms of product quality and reliability of fabrication. This evaluation led to a decision to build the Defense Waste Processing Facility (DWPF) at SRS to convert the easily dispersed liquid waste to borosilicate glass. In accordance with the NEPA (National Environmental Policy Act) process, an Environmental Impact Statement was prepared for the facility, as well as an Environmental Assessment of the alternative waste forms, and issuance of a Record of Decision (in December, 1982) on the waste form. The Department of Energy, recognizing that start-up of the DWPF would considerably precede licensing of a repository, instituted a Waste Acceptance Process to ensure that these canistered waste forms would be acceptable for eventual disposal at a federal repository. This report is a revision of the DWPF compliance plan.

Plodinec, M.J.; Marra, S.L.

1991-12-31T23:59:59.000Z

177

DWPF waste form compliance plan (Draft Revision)  

SciTech Connect (OSTI)

The Department of Energy currently has over 100 million liters of high-level radioactive waste in storage at the Savannah River Site (SRS). In the late 1970's, the Department of Energy recognized that there were significant safety and cost advantages associated with immobilizing the high-level waste in a stable solid form. Several alternative waste forms were evaluated in terms of product quality and reliability of fabrication. This evaluation led to a decision to build the Defense Waste Processing Facility (DWPF) at SRS to convert the easily dispersed liquid waste to borosilicate glass. In accordance with the NEPA (National Environmental Policy Act) process, an Environmental Impact Statement was prepared for the facility, as well as an Environmental Assessment of the alternative waste forms, and issuance of a Record of Decision (in December, 1982) on the waste form. The Department of Energy, recognizing that start-up of the DWPF would considerably precede licensing of a repository, instituted a Waste Acceptance Process to ensure that these canistered waste forms would be acceptable for eventual disposal at a federal repository. This report is a revision of the DWPF compliance plan.

Plodinec, M.J.; Marra, S.L.

1991-01-01T23:59:59.000Z

178

revision:19970323 modified:19970323  

E-Print Network [OSTI]

596 revision:1997­03­23 modified:1997­03­23 Some independence results on reflection James Cummings. Publication number 596. 1 #12; 596 revision:1997­03­23 modified:1997­03­23 Baumgartner proved in [1­reflection principle captures 2 #12; 596 revision:1997­03­23 modified:1997­03­23 exactly that part of # which is useful

Shelah, Saharon

179

Addendum to the Corrective Action Decision Document/Closure Report for Corrective Action Unit 372: Area 20 Cabriolet/Palanquin Unit Craters Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

This document constitutes an addendum to the Corrective Action Decision Document/Closure Report for Corrective Action Unit 372: Area 20 Cabriolet/Palanquin Unit Craters, Nevada Test Site, Nevada (Revision 0), April 2011.

Patrick Matthews and Christy Sloop

2012-01-01T23:59:59.000Z

180

Statement on New Mexico Science Education and the 2003 Revisions to New Mexico Science Standards  

E-Print Network [OSTI]

Statement on New Mexico Science Education and the 2003 Revisions to New Mexico Science Standards is unlimited. August 21, 2003 Summary Many workers in New Mexico's national laboratories, industries National Laboratory have examined the proposed 2003 revisions to the New Mexico Science Standards2 and find

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


181

Greater-than-Class C low-level radioactive waste shipping package/container identification and requirements study. National Low-Level Waste Management Program  

SciTech Connect (OSTI)

This report identifies a variety of shipping packages (also referred to as casks) and waste containers currently available or being developed that could be used for greater-than-Class C (GTCC) low-level waste (LLW). Since GTCC LLW varies greatly in size, shape, and activity levels, the casks and waste containers that could be used range in size from small, to accommodate a single sealed radiation source, to very large-capacity casks/canisters used to transport or dry-store highly radioactive spent fuel. In some cases, the waste containers may serve directly as shipping packages, while in other cases, the containers would need to be placed in a transport cask. For the purpose of this report, it is assumed that the generator is responsible for transporting the waste to a Department of Energy (DOE) storage, treatment, or disposal facility. Unless DOE establishes specific acceptance criteria, the receiving facility would need the capability to accept any of the casks and waste containers identified in this report. In identifying potential casks and waste containers, no consideration was given to their adequacy relative to handling, storage, treatment, and disposal. Those considerations must be addressed separately as the capabilities of the receiving facility and the handling requirements and operations are better understood.

Tyacke, M.

1993-08-01T23:59:59.000Z

182

Parallel programming with PCN. Revision 2  

SciTech Connect (OSTI)

PCN is a system for developing and executing parallel programs. It comprises a high-level programming language, tools for developing and debugging programs in this language, and interfaces to Fortran and Cthat allow the reuse of existing code in multilingual parallel programs. Programs developed using PCN are portable across many different workstations, networks, and parallel computers. This document provides all the information required to develop parallel programs with the PCN programming system. It includes both tutorial and reference material. It also presents the basic concepts that underlie PCN, particularly where these are likely to be unfamiliar to the reader, and provides pointers to other documentation on the PCN language, programming techniques, and tools. PCN is in the public domain. The latest version of both the software and this manual can be obtained by anonymous ftp from Argonne National Laboratory in the directory pub/pcn at info.mcs. ani.gov (cf. Appendix A). This version of this document describes PCN version 2.0, a major revision of the PCN programming system. It supersedes earlier versions of this report.

Foster, I.; Tuecke, S.

1993-01-01T23:59:59.000Z

183

Revised NIH Model M-CRADA Monday, October 22, 2007  

E-Print Network [OSTI]

Revised NIH Model M-CRADA Monday, October 22, 2007 Page 1 of 10 NATIONAL INSTITUTES OF HEALTH Agreement ("M-CRADA") has been adopted for use by the Institutes and Centers of the National Institutes are collected in Appendix B. Appendices A and B are incorporated herein by reference. This M-CRADA involves

Baker, Chris I.

184

Final Environmental Impact Statement for Treating Transuranic (TRU)/Alpha Low-level Waste at the Oak Ridge National Laboratory Oak Ridge, Tennessee  

SciTech Connect (OSTI)

The DOE proposes to construct, operate, and decontaminate/decommission a TRU Waste Treatment Facility in Oak Ridge, Tennessee. The four waste types that would be treated at the proposed facility would be remote-handled TRU mixed waste sludge, liquid low-level waste associated with the sludge, contact-handled TRU/alpha low-level waste solids, and remote-handled TRU/alpha low-level waste solids. The mixed waste sludge and some of the solid waste contain metals regulated under the Resource Conservation and Recovery Act and may be classified as mixed waste. This document analyzes the potential environmental impacts associated with five alternatives--No Action, the Low-Temperature Drying Alternative (Preferred Alternative), the Vitrification Alternative, the Cementation Alternative, and the Treatment and Waste Storage at Oak Ridge National Laboratory (ORNL) Alternative.

N /A

2000-06-30T23:59:59.000Z

185

Belief Revision Revisited Thoughts on the Scope of Belief Revision  

E-Print Network [OSTI]

Belief Revision Revisited or: Thoughts on the Scope of Belief Revision James Delgrande Simon Fraser University Canada NMR 2006 Windermere, UK, May 31, 2006 1 #12;Belief Revision · Current interest in belief revision is regarded as going back to the seminal work of Alchourr´on, G¨ardenfors, and Makinson (e.g. [AGM

Hunter, Anthony

186

Greater-than-Class C low-level radioactive waste transportation regulations and requirements study. National Low-Level Waste Management Program  

SciTech Connect (OSTI)

The purpose of this report is to identify the regulations and requirements for transporting greater-than-Class C (GTCC) low-level radioactive waste (LLW) and to identify planning activities that need to be accomplished in preparation for transporting GTCC LLW. The regulations and requirements for transporting hazardous materials, of which GTCC LLW is included, are complex and include several Federal agencies, state and local governments, and Indian tribes. This report is divided into five sections and three appendices. Section 1 introduces the report. Section 2 identifies and discusses the transportation regulations and requirements. The regulations and requirements are divided into Federal, state, local government, and Indian tribes subsections. This report does not identify the regulations or requirements of specific state, local government, and Indian tribes, since the storage, treatment, and disposal facility locations and transportation routes have not been specifically identified. Section 3 identifies the planning needed to ensure that all transportation activities are in compliance with the regulations and requirements. It is divided into (a) transportation packaging; (b) transportation operations; (c) system safety and risk analysis, (d) route selection; (e) emergency preparedness and response; and (f) safeguards and security. This section does not provide actual planning since the details of the Department of Energy (DOE) GTCC LLW Program have not been finalized, e.g., waste characterization and quantity, storage, treatment and disposal facility locations, and acceptance criteria. Sections 4 and 5 provide conclusions and referenced documents, respectively.

Tyacke, M.; Schmitt, R.

1993-07-01T23:59:59.000Z

187

Implementation Plan for Liquid Low-Level Radioactive Waste tank systems at Oak Ridge National Laboratory under the Federal Facility Agreement, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

This document summarizes the progress that has been made to date in implementing the plans and schedules for meeting the Federal Facility Agreement (FFA) commitments for the Liquid Low-Level Waste (LLLW) System at Oak Ridge National Laboratory (ORNL). These commitments were initially submitted in ES/ER-17&Dl, Federal Facility Agreement Plans and Schedules for Liquid Low-Level Radioactive Waste Tank Systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Information presented in this document provides a comprehensive summary to facilitate understanding of the FFA compliance program for LLLW tank systems and to present plans and schedules associated with remediation, through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) process, of LLLW tank systems that have been removed from service. ORNL has a comprehensive program underway to upgrade the LLLW system as necessary to meet the FFA requirements. The tank systems that are removed from service are being investigated and remediated through the CERCLA process. Waste and risk characterizations have been submitted. Additional data will be prepared and submitted to EPA/TDEC as tanks are taken out of service and as required by the remedial investigation/feasibility study (RI/FS) process. The plans and schedules for implementing the FFA compliance program that were submitted in ES/ER-17&Dl, Federal Facility Agreement Plans and Schedules for Liquid Low-Level Radioactive Waste tanks Systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee, are updated in this document. Chapter 1 provides general background information and philosophies that lead to the plans and schedules that appear in Chaps. 2 through 5.

Not Available

1994-09-01T23:59:59.000Z

188

BIOLOGICAL SAFETY MANUAL Revised April 2004  

E-Print Network [OSTI]

BIOLOGICAL SAFETY MANUAL Revised April 2004 #12;TABLE OF CONTENTS Emergency Numbers iv Awareness: Biological Safety Cabinets 31 Appendix D: Working Safely in a Biological Safety Cabinet 33 Ultraviolet and Tissue Culture Systems 50 Classification of Cell and/or Tissue Cultures According to Containment Level

Holland, Jeffrey

189

Radiological control manual. Revision 1  

SciTech Connect (OSTI)

This Lawrence Berkeley National Laboratory Radiological Control Manual (LBNL RCM) has been prepared to provide guidance for site-specific additions, supplements and interpretation of the DOE Radiological Control Manual. The guidance provided in this manual is one methodology to implement the requirements given in Title 10 Code of Federal Regulations Part 835 (10 CFR 835) and the DOE Radiological Control Manual. Information given in this manual is also intended to provide demonstration of compliance to specific requirements in 10 CFR 835. The LBNL RCM (Publication 3113) and LBNL Health and Safety Manual Publication-3000 form the technical basis for the LBNL RPP and will be revised as necessary to ensure that current requirements from Rules and Orders are represented. The LBNL RCM will form the standard for excellence in the implementation of the LBNL RPP.

Kloepping, R.

1996-05-01T23:59:59.000Z

190

Screening level model for ecological risk assessment at EF-Site Los Alamos National Laboratory, New Mexico. Final report  

SciTech Connect (OSTI)

In response to a paucity of data on the chemical toxicity of uranium to plants, a factorial experiment employing five uranium concentrations (0, 50, 500, 5000, 25000 ppm) and three moisture regimes (low, medium, high) was performed using three native grasses. Buchloe dactyloides (buffalograss-mid/late seral), Schizachyrium scoparium (little bluestem-late seral), and Aristida longiseta (purple threeawn-early/mid seral) were grown in monocultures and every mixture of two species under all combinations of uranium and moisture levels. This design allows for the analysis of uranium effects, as well as possible compound effects due to moisture stress. Several measures of plant health and viability were made, including: percent emergence, survivability of seedlings and mature plants, root and shoot biomass, and the number and mass of inflorescences. No significant differences between uranium levels were observed in terms of emergence and seedling survival. Effects are evident for plant biomass, fecundity, and long-term survivability.

Alldredge, A.W.; Kirchner, T.B.; McLendon, T. [and others

1995-12-01T23:59:59.000Z

191

Completion report for the Inactive Liquid Low-Level Waste Tank Remediation Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

This report documents the results of the Inactive Liquid Low-Level Waste Tank Remediation Project at Oak Ridge National Laboratory (ORNL). The work performed is compared with that proposed in the statement of work and the service contract specification for the maintenance action to remediate tanks 3013, 3004-B, T-30, and 3001-B. The Federal Facility Agreement (FFA) among the U.S. Environmental Protection Agency (EPA), the Tennessee Department of Environment and Conservation (TDEC), and the U.S. Department of Energy (DOE) requires that all tanks, which have been removed from service and are designated in the FFA as Category D, must be remediated in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) requirements. The Environmental Restoration Program`s inactive tank removal program strategy and plans for remediating the inactive LLLW tanks were documented in a report issued in January 1995 (Inactive Tanks Remediation Program Strategy and Plans for Oak Ridge National Laboratory, Oak Ridge, Tennessee, ORNL/ER-297). The inactive (Category D) tanks were initially screened for remediation according to risk, remediation technology required, level of instrumentation available, interferences with other piping and equipment, location, and available sludge removal techniques and storage requirements. On the basis of this preliminary screening, the tanks were assigned to one of five batches (I through V) for consideration of remedial action alternatives, and these batches were tentatively scheduled for remedial actions. The eight links tentatively assigned to Batch I were divided into two groups (Series I and Series II).

NONE

1996-02-01T23:59:59.000Z

192

Implementation plan for liquid low-level radioactive waste systems under the FFA for Fiscal years 1996 and 1997 at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

The Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) requires a Federal Facility Agreement (FFA) for federal facilities placed on the National Priorities List. The Oak Ridge Reservation was placed on that list on December 21, 1989, and the agreement was signed in November 1991 by the Department of Energy Oak Ridge Operations Office (DOE-ORO), the U.S. Environmental Protection Agency (EPA)-Region IV, and the Tennessee Department of Environment and Conservation (TDEC). The effective date of the FFA was January 1, 1992. Section IX and Appendix F of the agreement impose design and operating requirements on the Oak Ridge National Laboratory (ORNL) liquid low-level radioactive waste (LLLW) tank systems and identify several plans, schedules, and assessments that must be submitted to EPA/TDEC for review of approval. The issue of ES/ER-17&D1 Federal Facility Agreement Plans and Schedules for Liquid Low-Level Radioactive Waste Tank Systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee in March 1992 transmitted to EPA/TDEC those plans and schedules that were required within 60 to 90 days of the FFA effective date. This document updates the plans, schedules, and strategy for achieving compliance with the FFA as presented in ES/ER-17&D I and summarizes the progress that has been made to date. This document supersedes all updates of ES/ER- 17&D 1. Chapter 1 describes the history and operation of the ORNL LLLW System and the objectives of the FFA. Chapters 2 through 5 contain the updated plans and schedules for meeting FFA requirements. This document will continue to be periodically reassessed and refined to reflect newly developed information and progress.

NONE

1996-10-01T23:59:59.000Z

193

A Revision of the Leafhopper Genus Xyphon (Hemiptera: Cicadellidae)  

E-Print Network [OSTI]

in the past and their identification has been difficult using published keys. The genus is revised here based on a new species level phylogenetic assessment that incorporates both morphological and molecular data. The genus Xyphon was erected to contain...

Catanach, Therese A.

2012-02-14T23:59:59.000Z

194

Supplemental design requirements document, Project W026. Revision 3  

SciTech Connect (OSTI)

This document supplements and extends the Functional Design Criteria, SP-W026-FDC-001, for the Waste Receiving and Processing Facility (WRAP), Module 1. It provides additional detailed requirements, summarizes key Westinghouse Hanford Company design guidance, and establishes baseline technical agreements to be used in definitive design of the WRAP-1 facility. Revision 3 of the Supplemental Design Requirements Document has been assigned an Impact Level of 3ESQ based on the content of the entire revision. The actual changes made from Revision 2 have an Impact Level of 3S and the basis for these changes was previously reviewed and approved per WHC correspondence No. 9355770.

Weidert, J.R.

1993-10-08T23:59:59.000Z

195

Surveillance and maintenance plan for the inactive liquid low-level waste tanks at Oak Ridge National Laboratory  

SciTech Connect (OSTI)

ORNL has a total of 54 inactive liquid low-level waste (ILLLW) tanks. In the past, these tanks were used to contain radioactive liquid wastes from various research programs, decontamination operations, and reactor operations. The tanks have since been removed from service for various reasons; the majority were retired because of their age, some due to integrity compromises, and others because they did not meet the current standards set by the Federal Facilities Agreement (FFA). Many of the tanks contain residual radioactive liquids and/or sludges. Plans are to remediate all tanks; however, until remediation of each tank, this Surveillance and Maintenance (S&M) Plan will be used to monitor the safety and inventory containment of these tanks.

Not Available

1994-11-01T23:59:59.000Z

196

High Level Waste Tank Farm Replacement Project for the Idaho Chemical Processing Plant at the Idaho National Engineering Laboratory. Environmental Assessment  

SciTech Connect (OSTI)

The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0831, for the construction and operation of the High-Level Waste Tank Farm Replacement (HLWTFR) Project for the Idaho Chemical Processing Plant located at the Idaho National Engineering Laboratory (INEL). The HLWTFR Project as originally proposed by the DOE and as analyzed in this EA included: (1) replacement of five high-level liquid waste storage tanks with four new tanks and (2) the upgrading of existing tank relief piping and high-level liquid waste transfer systems. As a result of the April 1992 decision to discontinue the reprocessing of spent nuclear fuel at INEL, DOE believes that it is unlikely that the tank replacement aspect of the project will be needed in the near term. Therefore, DOE is not proposing to proceed with the replacement of the tanks as described in this-EA. The DOE`s instant decision involves only the proposed upgrades aspect of the project described in this EA. The upgrades are needed to comply with Resource Conservation and Recovery Act, the Idaho Hazardous Waste Management Act requirements, and the Department`s obligations pursuant to the Federal Facilities Compliance Agreement and Consent Order among the Environmental Protection Agency, DOE, and the State of Idaho. The environmental impacts of the proposed upgrades are adequately covered and are bounded by the analysis in this EA. If DOE later proposes to proceed with the tank replacement aspect of the project as described in the EA or as modified, it will undertake appropriate further review pursuant to the National Environmental Policy Act.

Not Available

1993-06-01T23:59:59.000Z

197

E-Print Network 3.0 - anxiety inventory-2 revised Sample Search...  

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

Robbie M. Cooper... in revised form 22 November 2007; accepted 26 November 2007 Abstract Previous work has suggested... that elevated levels of trait anxiety are...

198

National Level Co-Control Study of the Targets for Energy Intensity and Sulfur Dioxide in China  

SciTech Connect (OSTI)

Since 2006, China has set goals of reducing energy intensity, emissions, and pollutants in multiple guidelines and in the Five Year Plans. Various strategies and measures have then been taken to improve the energy efficiency in all sectors and to reduce pollutants. Since controlling energy, CO{sub 2} emissions, and pollutants falls under the jurisdiction of different government agencies in China, many strategies are being implemented to fulfill only one of these objectives. Co-controls or integrated measures could simultaneously reduce greenhouse gas (GHG) emissions and criteria air pollutant emissions. The targets could be met in a more cost effective manner if the integrated measures can be identified and prioritized. This report provides analysis and insights regarding how these targets could be met via co-control measures focusing on both CO{sub 2} and SO{sub 2} emissions in the cement, iron &steel, and power sectors to 2030 in China. An integrated national energy and emission model was developed in order to establish a baseline scenario that was used to assess the impact of actions already taken by the Chinese government as well as planned and expected actions. In addition, CO{sub 2} mitigation scenarios and SO{sub 2} control scenarios were also established to evaluate the impact of each of the measures and the combined effects. In the power sector, although the end of pipe SO{sub 2} control technology such as flue gas desulfurization (FGD) has the largest reduction potential for SO{sub 2} emissions, other CO{sub 2} control options have important co-benefits in reducing SO{sub 2} emissions of 52.6 Mt of SO{sub 2} accumulatively. Coal efficiency improvements along with hydropower, renewable and nuclear capacity expansion will result in more than half of the SO{sub 2} emission reductions as the SO{sub 2} control technology through 2016. In comparison, the reduction from carbon capture and sequestration (CCS) is much less and has negative SO{sub 2} reductions potential. The expanded biomass generation scenario does not have significant potential for reducing SO{sub 2} emissions, because of its limited availability. For the cement sector, the optimal co-control strategy includes accelerated adoption of energy efficiency measures, decreased use of clinker in cement production, increased use of alternative fuels, and fuel-switching to biomass. If desired, additional SO{sub 2} mitigation could be realized by more fully adopting SO{sub 2} abatement mitigation technology measures. The optimal co-control scenario results in annual SO{sub 2} emissions reductions in 2030 of 0.16 Mt SO{sub 2} and annual CO{sub 2} emissions reductions of 76 Mt CO{sub 2}. For the iron and steel sector, the optimal co-control strategy includes accelerated adoption of energy efficiency measures, increased share of electric arc furnace steel production, and reduced use of coal and increased use of natural gas in steel production. The strategy also assumes full implementation of sinter waste gas recycling and wet desulfurization. This strategy results in annual SO{sub 2} emissions reductions in 2030 of 1.3 Mt SO{sub 2} and annual CO{sub 2} emissions reductions of 173 Mt CO{sub 2}.

Zhou, Nan; Price, Lynn; Zheng, Nina; Ke, Jing; Hasanbeigi, Ali

2011-10-15T23:59:59.000Z

199

Parallel Belief Revision: Revising by Sets of Formulas  

E-Print Network [OSTI]

Parallel Belief Revision: Revising by Sets of Formulas James Delgrande and Yi Jin School of Computing Science Simon Fraser University Burnaby, B.C. V5A 1S6 Canada {jim,yij}@cs.sfu.ca March 15, 2012 Abstract The area of belief revision studies how a rational agent may incorporate new information about

Delgrande, James P.

200

Beaver Monitoring Protocol for Forest Service Region 2 Revised May 2008 1 USDA FOREST SERVICE REGION 2  

E-Print Network [OSTI]

HILLS NATIONAL FORESTS (Photo from Nature of New England Website ­ http Black Hills National Forest, USDA Forest Service, Custer, SD Revised May 2008 #12;Beaver MonitoringBeaver Monitoring Protocol for Forest Service Region 2 ­ Revised May 2008 1 USDA FOREST SERVICE

Beck, Jeffrey L.

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


201

Radiation Safety (Revised March 2010)  

E-Print Network [OSTI]

Radiation Safety Manual (Revised March 2010) Updated December 2012 Stanford University, Stanford California #12; #12; Radiation Safety Manual (Revised March 2010) Updated Environmental Health and Safety, Stanford University, Stanford California #12; CREDITS This Radiation Safety

Kay, Mark A.

202

SOFA Component Revision Identification 1 Premysl Brada  

E-Print Network [OSTI]

SOFA Component Revision Identification 1 Premysl Brada Department of Computer Science versions, component revision numbers and change indications are derived as a well- founded version called "component revisions" and the basic fine-grained "type revisions", can subsequently be used

203

Initial performance assessment of the disposal of spent nuclear fuel and high-level waste stored at Idaho National Engineering Laboratory. Volume 1, Methodology and results  

SciTech Connect (OSTI)

This performance assessment characterized plausible treatment options conceived by the Idaho National Engineering Laboratory (INEL) for its spent fuel and high-level radioactive waste and then modeled the performance of the resulting waste forms in two hypothetical, deep, geologic repositories: one in bedded salt and the other in granite. The results of the performance assessment are intended to help guide INEL in its study of how to prepare wastes and spent fuel for eventual permanent disposal. This assessment was part of the Waste Management Technology Development Program designed to help the US Department of Energy develop and demonstrate the capability to dispose of its nuclear waste. Although numerous caveats must be placed on the results, the general findings were as follows: Though the waste form behavior depended upon the repository type, all current and proposed waste forms provided acceptable behavior in the salt and granite repositories.

Rechard, R.P. [ed.

1993-12-01T23:59:59.000Z

204

Feasibility study on the solidification of liquid low-level radioactive mixed waste in the inactive tank system at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

A literature survey was conducted to help determine the feasibility of solidifying a liquid low-level radioactive mixed waste in the inactive tank system at Oak Ridge National Laboratory (ORNL). The goal of this report is to facilitate a decision on the disposition of these wastes by identifying any waste constituents that might (1) compromise the strength or stability of the waste form or (2) be highly leachable. Furthermore, its goal is to identify ways to circumvent interferences and to decrease the leachability of the waste constituents. This study has sought to provide an understanding of inhibition of cement set by identifying the fundamental chemical mechanisms by which this inhibition takes place. From this fundamental information, it is possible to draw some conclusions about the potential effects of waste constituents, even in the absence of particular studies on specific compounds.

Trussell, S. (Texas A and M Univ., College Station, TX (United States). Dept. of Civil Engineering); Spence, R.D. (Oak Ridge National Lab., TN (United States))

1993-01-01T23:59:59.000Z

205

Computer Science Revised Edition  

E-Print Network [OSTI]

Computer Science Revised Edition December 2004 #12;Quality Assurance Netherlands Universities (QANU of the Assessment Aspects 11 2 Structure and Funding of Computer Science in the Netherlands 13 2.1 Flow of Funds 13 2.2 Graduate Schools 13 2.3 Societal Relevance of Computer Science 14 3 Comments on Computer Science

van Rooij, Robert

206

revision:19960317 modified:19960317  

E-Print Network [OSTI]

restrict our­ self to certain concrete classes then we may be able to retain compactness. In this paper we375 revision:1996­03­17 modified:1996­03­17 Some Compact Logics ­ Results in ZFC Alan H. Mekler order logic is so strong that it fails to have nice model theoretic properties such as compactness

Shelah, Saharon

207

Evaluation of Groundwater Impacts to Support the National Environmental Policy Act Environmental Assessment for the INL Remote-Handled Low-Level Waste Disposal Project  

SciTech Connect (OSTI)

Groundwater impacts have been analyzed for the proposed remote-handled low-level waste disposal facility. The analysis was prepared to support the National Environmental Policy Act environmental assessment for the top two ranked sites for the proposed disposal facility. A four-phase screening and analysis approach was documented and applied. Phase I screening was site independent and applied a radionuclide half-life cut-off of 1 year. Phase II screening applied the National Council on Radiation Protection analysis approach and was site independent. Phase III screening used a simplified transport model and site-specific geologic and hydrologic parameters. Phase III neglected the infiltration-reducing engineered cover, the sorption influence of the vault system, dispersion in the vadose zone, vertical dispersion in the aquifer, and the release of radionuclides from specific waste forms. These conservatisms were relaxed in the Phase IV analysis which used a different model with more realistic parameters and assumptions. Phase I screening eliminated 143 of the 246 radionuclides in the inventory from further consideration because each had a half-life less than 1 year. An additional 13 were removed because there was no ingestion dose coefficient available. Of the 90 radionuclides carried forward from Phase I, 57 radionuclides had simulated Phase II screening doses exceeding 0.4 mrem/year. Phase III and IV screening compared the maximum predicted radionuclide concentration in the aquifer to maximum contaminant levels. Of the 57 radionuclides carried forward from Phase II, six radionuclides were identified in Phase III as having simulated future aquifer concentrations exceeding maximum contaminant limits. An additional seven radionuclides had simulated Phase III groundwater concentrations exceeding 1/100th of their respective maximum contaminant levels and were also retained for Phase IV analysis. The Phase IV analysis predicted that none of the thirteen remaining radionuclides would exceed the maximum contaminant levels for either site location. The predicted cumulative effective dose equivalent from all 13 radionuclides also was less than the dose criteria set forth in Department of Energy Order 435.1 for each site location. An evaluation of composite impacts showed one site is preferable over the other based on the potential for commingling of groundwater contamination with other facilities.

Annette Schafer, Arthur S. Rood, A. Jeffrey Sondrup

2011-12-23T23:59:59.000Z

208

Initial performance assessment of the disposal of spent nuclear fuel and high-level waste stored at Idaho National Engineering Laboratory. Volume 2: Appendices  

SciTech Connect (OSTI)

This performance assessment characterized plausible treatment options conceived by the Idaho National Engineering Laboratory (INEL) for its spent fuel and high-level radioactive waste and then modeled the performance of the resulting waste forms in two hypothetical, deep, geologic repositories: one in bedded salt and the other in granite. The results of the performance assessment are intended to help guide INEL in its study of how to prepare wastes and spent fuel for eventual permanent disposal. This assessment was part of the Waste Management Technology Development Program designed to help the US Department of Energy develop and demonstrate the capability to dispose of its nuclear waste, as mandated by the Nuclear Waste Policy Act of 1982. The waste forms comprised about 700 metric tons of initial heavy metal (or equivalent units) stored at the INEL: graphite spent fuel, experimental low enriched and highly enriched spent fuel, and high-level waste generated during reprocessing of some spent fuel. Five different waste treatment options were studied; in the analysis, the options and resulting waste forms were analyzed separately and in combination as five waste disposal groups. When the waste forms were studied in combination, the repository was assumed to also contain vitrified high-level waste from three DOE sites for a common basis of comparison and to simulate the impact of the INEL waste forms on a moderate-sized repository, The performance of the waste form was assessed within the context of a whole disposal system, using the U.S. Environmental Protection Agency`s Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes, 40 CFR 191, promulgated in 1985. Though the waste form behavior depended upon the repository type, all current and proposed waste forms provided acceptable behavior in the salt and granite repositories.

Rechard, R.P. [ed.

1993-12-01T23:59:59.000Z

209

ANSI/ASA S3.2-2009 (Revision of ANSI S3.2-1999)  

E-Print Network [OSTI]

ANSI/ASA S3.2-2009 (Revision of ANSI S3.2-1999) AMERICAN NATIONAL STANDARD Method for Measuring Secretariat Acoustical Society of America 35 Pinelawn Road, Suite 114 E Melville, NY 11747-3177 ANSI/ASAS3:48:02 #12;The American National Standards Institute, Inc. (ANSI) is the national coordinator of voluntary

Allen, Jont

210

A report documenting the completion of the Los Alamos National Laboratory portion of the ASC level II milestone ""Visualization on the supercomputing platform  

SciTech Connect (OSTI)

This report provides documentation for the completion of the Los Alamos portion of the ASC Level II 'Visualization on the Supercomputing Platform' milestone. This ASC Level II milestone is a joint milestone between Sandia National Laboratory and Los Alamos National Laboratory. The milestone text is shown in Figure 1 with the Los Alamos portions highlighted in boldfaced text. Visualization and analysis of petascale data is limited by several factors which must be addressed as ACES delivers the Cielo platform. Two primary difficulties are: (1) Performance of interactive rendering, which is the most computationally intensive portion of the visualization process. For terascale platforms, commodity clusters with graphics processors (GPUs) have been used for interactive rendering. For petascale platforms, visualization and rendering may be able to run efficiently on the supercomputer platform itself. (2) I/O bandwidth, which limits how much information can be written to disk. If we simply analyze the sparse information that is saved to disk we miss the opportunity to analyze the rich information produced every timestep by the simulation. For the first issue, we are pursuing in-situ analysis, in which simulations are coupled directly with analysis libraries at runtime. This milestone will evaluate the visualization and rendering performance of current and next generation supercomputers in contrast to GPU-based visualization clusters, and evaluate the perfromance of common analysis libraries coupled with the simulation that analyze and write data to disk during a running simulation. This milestone will explore, evaluate and advance the maturity level of these technologies and their applicability to problems of interest to the ASC program. In conclusion, we improved CPU-based rendering performance by a a factor of 2-10 times on our tests. In addition, we evaluated CPU and CPU-based rendering performance. We encourage production visualization experts to consider using CPU-based rendering solutions when it is appropriate. For example, on remote supercomputers CPU-based rendering can offer a means of viewing data without having to offload the data or geometry onto a CPU-based visualization system. In terms of comparative performance of the CPU and CPU we believe that further optimizations of the performance of both CPU or CPU-based rendering are possible. The simulation community is currently confronting this reality as they work to port their simulations to different hardware architectures. What is interesting about CPU rendering of massive datasets is that for part two decades CPU performance has significantly outperformed CPU-based systems. Based on our advancements, evaluations and explorations we believe that CPU-based rendering has returned as one viable option for the visualization of massive datasets.

Ahrens, James P [Los Alamos National Laboratory; Patchett, John M [Los Alamos National Laboratory; Lo, Li - Ta [Los Alamos National Laboratory; Mitchell, Christopher [Los Alamos National Laboratory; Mr Marle, David [KITWARE INC.; Brownlee, Carson [UNIV OF UTAH

2011-01-24T23:59:59.000Z

211

Nevada National Security Site Radiological Control Manual  

SciTech Connect (OSTI)

This document supersedes DOE/NV/25946--801, 'Nevada Test Site Radiological Control Manual,' Revision 1 issued in February 2010. Brief Description of Revision: A complete revision to reflect a recent change in name for the NTS; changes in name for some tenant organizations; and to update references to current DOE policies, orders, and guidance documents. Article 237.2 was deleted. Appendix 3B was updated. Article 411.2 was modified. Article 422 was re-written to reflect the wording of DOE O 458.1. Article 431.6.d was modified. The glossary was updated. This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE) and the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection.' Programs covered by this manual are located at the Nevada National Security Site (NNSS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Livermore, California; and Andrews Air Force Base, Maryland. In addition, fieldwork by NNSA/NSO at other locations is covered by this manual. Current activities at NNSS include operating low-level radioactive and mixed waste disposal facilities for United States defense-generated waste, assembly and execution of subcritical experiments, assembly/disassembly of special experiments, the storage and use of special nuclear materials, performing criticality experiments, emergency responder training, surface cleanup and site characterization of contaminated land areas, environmental activity by the University system, and nonnuclear test operations, such as controlled spills of hazardous materials at the Hazardous Materials Spill Center. Currently, the major potential for occupational radiation exposure is associated with the burial of low-level radioactive waste and the handling of radioactive sources. Remediation of contaminated land areas may also result in radiological exposures.

Radiological Control Managers’ Council

2012-03-26T23:59:59.000Z

212

National Level Computing at UTK  

E-Print Network [OSTI]

at NICS q NSF TeraGrid XD center: Remote Data Analysis & Visualization (RDAV). $10M/3-year award to UT) Computing hardware Computing infrastructure (space, network, power, cooling) Community organization cluster · 4200 processors, 8TB RAM, 40 Gbit/sec network · 50 TB High-performance storage · Remote data

Tennessee, University of

213

ELECTRICAL AREA CONTROLLED ACCESS PROCEDURE SP-18 Revision 01  

E-Print Network [OSTI]

ELECTRICAL AREA CONTROLLED ACCESS PROCEDURE SP-18 Page 1 Revision 01 April 17, 2007 NATIONAL HIGH ______________________________________________________ ASSOCIATE DIRECTOR for MANAGEMENT & ADMINISTRATION Brian Fairhurst #12;ELECTRICAL AREA CONTROLLED ACCESS TITLE: ELECTRICAL AREA CONTROLLED ACCESS PROCEDURE 1.0 PURPOSE 1.1 This document establishes policy

Weston, Ken

214

Revisions to the Proposal and Award Policies & Procedures Guide  

E-Print Network [OSTI]

Revisions to the Proposal and Award Policies & Procedures Guide Effective January 14, 2013 National Description should outline the general plan of work, including the broad design of activities to be undertaken;Project Description - Changed Language OLD The Project Description must describe, as an integral part

He, Chuan

215

Solid waste integrated forecast technical (SWIFT) report: FY1997 to FY 2070, Revision 1  

SciTech Connect (OSTI)

This web site provides an up-to-date report on the radioactive solid waste expected to be managed by Hanford's Waste Management (WM) Project from onsite and offsite generators. It includes: an overview of Hanford-wide solid waste to be managed by the WM Project; program-level and waste class-specific estimates; background information on waste sources; and comparisons with previous forecasts and with other national data sources. This web site does not include: liquid waste (current or future generation); waste to be managed by the Environmental Restoration (EM-40) contractor (i.e., waste that will be disposed of at the Environmental Restoration Disposal Facility (ERDF)); or waste that has been received by the WM Project to date (i.e., inventory waste). The focus of this web site is on low-level mixed waste (LLMW), and transuranic waste (both non-mixed and mixed) (TRU(M)). Some details on low-level waste and hazardous waste are also provided. Currently, this web site is reporting data th at was requested on 10/14/96 and submitted on 10/25/96. The data represent a life cycle forecast covering all reported activities from FY97 through the end of each program's life cycle. Therefore, these data represent revisions from the previous FY97.0 Data Version, due primarily to revised estimates from PNNL. There is some useful information about the structure of this report in the SWIFT Report Web Site Overview.

Valero, O.J.; Templeton, K.J.; Morgan, J.

1997-01-07T23:59:59.000Z

216

Sexual harassment levels 'alarming' in rural Australia http://www.theage.com.au/national/sexual-harassment-levels-alarming-in-rural-australia-20131030-2whaj.html#ixzz2jdxUVnCG[8/11/2013 5:55:19 PM  

E-Print Network [OSTI]

Sexual harassment levels 'alarming' in rural Australia http://www.theage.com.au/national/sexual-harassment-levels-alarming-in-rural-australia done on domestic violence and crime in rural Australia, but little done before now on sexual harassment studies of its kind, has looked at the prevalence of sexual harassment in regional Australia. Based

Botea, Adi

217

Microsoft Word - SAR 536 Revised  

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

SITE INSPECTION REPORT AND SWMU ASSESSMENT REPORT UNIT NUMBER: 536 UNIT NAME: Concrete Truck Washout Area DATE: 060302 Revised 071502 REGULATORY STATUS: SWMU LOCATION:...

218

BCBST PDC --EOC Revised 1/2013  

E-Print Network [OSTI]

BCBST ­ PDC -- EOC Revised 1/2013 Vanderbilt University 89508 January 1, 2014 #12;BCBST ­ PDC -- EOC Revised 1/2013 #12;BCBST ­ PDC -- EOC Revised 1/2013 DENTAL EVIDENCE OF COVERAGE BlueCross Blue ­ PDC -- EOC Revised 1/2013 #12;BCBST ­ PDC -- EOC Revised 1/2013 TABLE OF CONTENTS INTRODUCTION

Simaan, Nabil

219

Exam revision Database Systems Lecture 18  

E-Print Network [OSTI]

,B) and (A,C), fd B C. #12;3 Exam revision Example (coursework 5) · Relation Listing is not in 2NF because1 Exam revision Database Systems Lecture 18 Natasha Alechina Exam revision In This Lecture · Exam format · Main topics · How to revise Exam revision Exam format · Answer three questions out of five

Alechina, Natasha

220

Cumulative Revision Map  

E-Print Network [OSTI]

Unlike static documents, version-controlled documents are edited by one or more authors over a certain period of time. Examples include large scale computer code, papers authored by a team of scientists, and online discussion boards. Such collaborative revision process makes traditional document modeling and visualization techniques inappropriate. In this paper we propose a new visualization technique for version-controlled documents that reveals interesting authoring patterns in papers, computer code and Wikipedia articles. The revealed authoring patterns are useful for the readers, participants in the authoring process, and supervisors.

Kim, Seungyeon; Lebanon, Guy

2012-01-01T23:59:59.000Z

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


221

Proposed Revisions for Regents Policy  

E-Print Network [OSTI]

Proposed Revisions for Regents Policy: Faculty Tenure Arlene Carney Vice Provost for Faculty family friendliness for probationary period #12;Basis for Revisions of Faculty Tenure Policy · Changed definitions of Academic Freedom and Responsibility required changes in the tenure policy. · As more untenured

Amin, S. Massoud

222

Miscellaneous States Coalbed Methane Proved Reserves Revision...  

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

Revision Decreases (Billion Cubic Feet) Miscellaneous States Coalbed Methane Proved Reserves Revision Decreases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4...

223

Proposed Rule To Implement the 1997 8-Hour Ozone National Ambient Air Quality Standard: Revision on Subpart 1 Area Reclassification and Anti-Backsliding Provisions Under Former 1-Hour Ozone Standard; Proposed Deletion of Obsolete 1-Hour Ozone Standard Provision  

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart of the Review ofElectronicNORTH LAS VEGASEly District Record

224

Generalized Test Plan for the Vitrification of Simulated High-Level -Waste Calcine in the Idaho National Laboratory‘s Bench -Scale Cold Crucible Induction Melter  

SciTech Connect (OSTI)

This Preliminary Idaho National Laboratory (INL) Test Plan outlines the chronological steps required to initially evaluate the validity of vitrifying INL surrogate (cold) High-Level-Waste (HLW) solid particulate calcine in INL's Cold Crucible Induction Melter (CCIM). Its documentation and publication satisfies interim milestone WP-413-INL-01 of the DOE-EM (via the Office of River Protection) sponsored work package, WP 4.1.3, entitled 'Improved Vitrification' The primary goal of the proposed CCIM testing is to initiate efforts to identify an efficient and effective back-up and risk adverse technology for treating the actual HLW calcine stored at the INL. The calcine's treatment must be completed by 2035 as dictated by a State of Idaho Consent Order. A final report on this surrogate/calcine test in the CCIM will be issued in May 2012-pending next fiscal year funding In particular the plan provides; (1) distinct test objectives, (2) a description of the purpose and scope of planned university contracted pre-screening tests required to optimize the CCIM glass/surrogate calcine formulation, (3) a listing of necessary CCIM equipment modifications and corresponding work control document changes necessary to feed a solid particulate to the CCIM, (4) a description of the class of calcine that will be represented by the surrogate, and (5) a tentative tabulation of the anticipated CCIM testing conditions, testing parameters, sampling requirements and analytical tests. Key FY -11 milestones associated with this CCIM testing effort are also provided. The CCIM test run is scheduled to be conducted in February of 2012 and will involve testing with a surrogate HLW calcine representative of only 13% of the 4,000 m3 of 'hot' calcine residing in 6 INL Bin Sets. The remaining classes of calcine will have to be eventually tested in the CCIM if an operational scale CCIM is to be a feasible option for the actual INL HLW calcine. This remaining calcine's make-up is HLW containing relatively high concentrations of zirconium and aluminum, representative of the cladding material of the reprocessed fuel that generated the calcine. A separate study to define the CCIM testing needs of these other calcine classifications in currently being prepared under a separate work package (WP-0) and will be provided as a milestone report at the end of this fiscal year.

Vince Maio

2011-08-01T23:59:59.000Z

225

Corrective Action Decision Document/Closure Report for Corrective Action Unit 569: Area 3 Yucca Flat Atmospheric Test Sites Nevada National Security Site, Nevada with ROTC 1, Revision 0  

SciTech Connect (OSTI)

This Corrective Action Decision Document/Closure Report presents information supporting the closure of Corrective Action Unit (CAU) 569: Area 3 Yucca Flat Atmospheric Test Sites, Nevada National Security Site, Nevada. CAU 569 comprises the following nine corrective action sites (CASs): • 03-23-09, T-3 Contamination Area • 03-23-10, T-3A Contamination Area • 03-23-11, T-3B Contamination Area • 03-23-12, T-3S Contamination Area • 03-23-13, T-3T Contamination Area • 03-23-14, T-3V Contamination Area • 03-23-15, S-3G Contamination Area • 03-23-16, S-3H Contamination Area • 03-23-21, Pike Contamination Area 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 569 based on the implementation of the corrective actions listed in Table ES-2.

Sloop, Christy

2013-04-01T23:59:59.000Z

226

Exam revision Database Systems Lecture 18  

E-Print Network [OSTI]

revision Example (coursework 5) · {Film} {Certificate} is a non-trivial functional dependency · {Cinema(A,B,C), candidate keys (A,B) and (A,C), fd B C. #12;Exam revision Example (coursework 5) · Relation ListingExam revision Database Systems Lecture 18 Natasha Alechina #12;Exam revision In This Lecture · Exam

Alechina, Natasha

227

FOR OFFICERS REVISED AND PUBLISHED  

E-Print Network [OSTI]

Council 2007 Revision HANOVER, NEW HAMPSHIRE #12;To Dartmouth Club Officers: The development) 646-2253 Career Services (603) 646-2215 Club Mailings, Lists, Changes (603) 646-3497 Club Scholarships ............................................................................................................................ 8 Public Information Chair

Lotko, William

228

Answers to the set revision exercise 1 Answers to the set revision exercise  

E-Print Network [OSTI]

to the set revision exercise 5 Answers to the set revision exercise · If A has k elements, how many different1 Answers to the set revision exercise 1 Answers to the set revision exercise · Are A = {1 in which they are listed does not matter. Answers to the set revision exercise 2 Answers to the set

Alechina, Natasha

229

Revision of ASCE 4  

SciTech Connect (OSTI)

The original version of ASCE Standard 4, ``Seismic Analysis of Safety-Related Nuclear Structures`` was published in September 1986. It is ASCE policy to update its standards on a five year interval and the Working Group on Seismic Analysis of Safety Related Nuclear Structures was reconvened to formulate the revisions. The goal in updating the standard is to make sure that it is still relevant and that it incorporates the state of the practice in seismic engineering or, in some cases, where it has been demonstrated that state-of-the-art improvements need to be made to standard practice; new improvements are included. The contents of the new standard cover the same areas as the original version, with some additions. The contents are as follows: Input - response spectra and time histories; modeling of structures; analysis of structures; soil-structure interaction; input for subsystem analysis; special structures - buried pipes and conduits, earth-retaining walls, above-ground vertical tanks, raceways, and base-isolated structures; and an appendix providing seismic probabilistic risk assessment and margin assessment.

Nelson, T.A.; Murray, R.C. [Lawrence Livermore National Lab., CA (United States); Short, S.A. [EQE Engineering Consultants, Inc. (United States)

1995-01-24T23:59:59.000Z

230

Phase I Flow and Transport Model Document for Corrective Action Unit 97: Yucca Flat/Climax Mine, Nevada National Security Site, Nye County, Nevada, Revision 1 with ROTC 1  

SciTech Connect (OSTI)

The Underground Test Area (UGTA) Corrective Action Unit (CAU) 97, Yucca Flat/Climax Mine, in the northeast part of the Nevada National Security Site (NNSS) requires environmental corrective action activities to assess contamination resulting from underground nuclear testing. These activities are necessary to comply with the UGTA corrective action strategy (referred to as the UGTA strategy). The corrective action investigation phase of the UGTA strategy requires the development of groundwater flow and contaminant transport models whose purpose is to identify the lateral and vertical extent of contaminant migration over the next 1,000 years. In particular, the goal is to calculate the contaminant boundary, which is defined as a probabilistic model-forecast perimeter and a lower hydrostratigraphic unit (HSU) boundary that delineate the possible extent of radionuclide-contaminated groundwater from underground nuclear testing. Because of structural uncertainty in the contaminant boundary, a range of potential contaminant boundaries was forecast, resulting in an ensemble of contaminant boundaries. The contaminant boundary extent is determined by the volume of groundwater that has at least a 5 percent chance of exceeding the radiological standards of the Safe Drinking Water Act (SDWA) (CFR, 2012).

Andrews, Robert

2013-09-01T23:59:59.000Z

231

Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory  

SciTech Connect (OSTI)

This report contains health and safety information relating to the chemicals that have been identified in the mixed waste streams at the Waste Treatment Facility at the Idaho National Engineering Laboratory. Information is summarized in two summary sections--one for health considerations and one for safety considerations. Detailed health and safety information is presented in material safety data sheets (MSDSs) for each chemical.

Neupauer, R.M.; Thurmond, S.M.

1992-09-01T23:59:59.000Z

232

Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory. Part 2, Chemical constituents  

SciTech Connect (OSTI)

This report contains health and safety information relating to the chemicals that have been identified in the mixed waste streams at the Waste Treatment Facility at the Idaho National Engineering Laboratory. Information is summarized in two summary sections--one for health considerations and one for safety considerations. Detailed health and safety information is presented in material safety data sheets (MSDSs) for each chemical.

Neupauer, R.M.; Thurmond, S.M.

1992-09-01T23:59:59.000Z

233

Revised August 2, 2013 ELECTRICAL ENGINEERING CURRICULUM GUIDE  

E-Print Network [OSTI]

of Engineering ­ 2.00 GPA in all required engineering, math, chemistry and physics courses ECE Department ­ 2Revised August 2, 2013 ELECTRICAL ENGINEERING CURRICULUM GUIDE Ending Spring 2014 ACADEMIC Engineering Degree, 125126 credits A minimum of 42 upperdivision semester credits (300400 level) is required

234

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, Revision 0  

SciTech Connect (OSTI)

This document is part of an effort to re-evaluate all FFACO URs against the current RBCA criteria (referred to in this document as the Industrial Sites [IS] RBCA process) as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006c). Based on this evaluation, the URs were sorted into the following categories: 1. Where sufficient information exists to determine that the current UR is consistent with the RCBA criteria 2. Where sufficient information exists to determine that the current UR may be removed or downgraded based on RCBA criteria. 3. Where sufficient information does not exist to evaluate the current UR against the RCBA criteria. After reviewing all the existing FFACO URs, the 49 URs addressed in this document have sufficient information to determine that these current URs may be removed or downgraded based on RCBA criteria. This document presents recommendations on modifications to existing URs that will be consistent with the RCBA criteria.

Lynn Kidman

2008-02-01T23:59:59.000Z

235

Revised Edition Edited by  

E-Print Network [OSTI]

As cultural studies powers ahead to new intellectual horizons, it becomes increas-ingly important to chart the discipline’s controversial history. This is the object of an exciting new series, KeyWorks in Cultural Studies. By showcasing the best that has been thought and written on the leading themes and topics constituting the discip-line, KeyWorks in Cultural Studies provides an invaluable genealogy for students striving to better understand the contested space in which cultural studies takes place and is practiced. 1 Nations and Identities: Classic Readings edited by Vincent P. Pecora

Ii Douglas M. Kellner; Meenakshi Gigi Durham; Gigi Durham; Douglas M. Kellner; Meenakshi Gigi Durham; Douglas M. Kellner; Iv Douglas M. Kellner; Meenakshi Gigi Durham; Douglas M. Kellner

236

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 with ROTC 1, Revision No. 0  

SciTech Connect (OSTI)

Many Federal Facility Agreement and Consent Order (FFACO) Use Restrictions (URs) have been established at various corrective action sites (CASs) as part of FFACO corrective actions (FFACO, 1996; as amended January 2007). Since the signing of the FFACO in 1996, practices and procedures relating to the implementation of risk-based corrective action (RBCA) have evolved. This document is part of an effort to re-evaluate all FFACO URs against the current RBCA criteria (referred to in this document as the Industrial Sites [IS] RBCA process) as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006c). Based on this evaluation, the URs were sorted into the following categories: 1. Where sufficient information exists to determine that the current UR is consistent with the RCBA criteria 2. Where sufficient information exists to determine that the current UR may be removed or downgraded based on RCBA criteria. 3. Where sufficient information does not exist to evaluate the current UR against the RCBA criteria. After reviewing all the existing FFACO URs, the 49 URs addressed in this document have sufficient information to determine that these current URs may be removed or downgraded based on RCBA criteria. This document presents recommendations on modifications to existing URs that will be consistent with the RCBA criteria.

Lynn Kidman

2008-02-01T23:59:59.000Z

237

Local public document room directory. Revision 7  

SciTech Connect (OSTI)

This directory (NUREG/BR-0088, Revision 7) lists local public document rooms (LPDRs) for commercial nuclear power plants with operating or possession-only licenses or under construction, plus the LPDRs for potential high-level radioactive waste repository sites, gaseous diffusion plants, certain fuel cycle facilities, certain low-level waste disposal facilities, and any temporary LPDRs established for the duration of licensing proceedings. In some instances, the LPDR libraries maintain document collections for more than one licensed facility. The library staff members listed are the persons most familiar with the LPDR collections. Reference librarians in the NRC Headquarters Public Document Room (PDR) are also available to assist the public in locating NRC documents.

NONE

1998-04-01T23:59:59.000Z

238

Environmental, Safety, and Health Plan for the remedial investigation of the liquid low-level waste tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program  

SciTech Connect (OSTI)

The Environmental, Safety, and Health (ES&H) Plan presents the concepts and methodologies to be used during the Oak Ridge National Laboratory (ORNL) RI/FS project to protect the health and safety of employees, the public, and the environment. The ES&H Plan acts as a management extension for ORNL and Energy Systems to direct and control implementation of the project ES&H program. This report describes the program philosophy, requirements, quality assurance measures, and methods for applying the ES&H program to individual task remedial investigations, project facilities, and other major tasks assigned to the project.

Not Available

1991-09-01T23:59:59.000Z

239

Environmental, Safety, and Health Plan for the remedial investigation of the liquid low-level waste tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

The Environmental, Safety, and Health (ES H) Plan presents the concepts and methodologies to be used during the Oak Ridge National Laboratory (ORNL) RI/FS project to protect the health and safety of employees, the public, and the environment. The ES H Plan acts as a management extension for ORNL and Energy Systems to direct and control implementation of the project ES H program. This report describes the program philosophy, requirements, quality assurance measures, and methods for applying the ES H program to individual task remedial investigations, project facilities, and other major tasks assigned to the project.

Not Available

1991-09-01T23:59:59.000Z

240

COMMITTEE FINAL REPORT REVISED SHORTTERM PEAK  

E-Print Network [OSTI]

COMMITTEE FINAL REPORT REVISED SHORTTERM PEAK DEMAND FORECAST (20112012) MARCH 2011 CEC. #12; i ABSTRACT This report presents revised shortterm peak demand forecasts for the California, and San Diego Gas & Electric transmission access charge areas. Keywords: Forecast, peak demand

Note: This page contains sample records for the topic "national level revisions" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
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We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

5(b)/9(c) Final Revised Policy  

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

Revised Policy on Determining Net Requirements of Pacific Northwest Utility Customers Under Sections 5(b)(1) and 9(c) of the Northwest Power Act (First revision. Issued March 19,...

242

Distributed Belief Revision vs. Belief Revision in a MultiAgent environment  

E-Print Network [OSTI]

belief revision in a multi­source enviroment (MSBR) [5], we realized that three relevant items are1 Distributed Belief Revision vs. Belief Revision in a Multi­Agent environment: first results propose a distributed architecture for belief revision­ integration, where each element is conceived like

243

Revising partial pre-orders with partial pre-orders: A unit-based revision framework  

E-Print Network [OSTI]

Revising partial pre-orders with partial pre-orders: A unit-based revision framework Jianbing Ma1, Queen's University Belfast, Belfast BT9 5BN, UK, email: {jma03, w.liu}@qub.ac.uk 2 CRIL-CNRS, UMR 8188@cril.fr Abstract Belief revision studies strategies about how agents revise their belief states when receiving new

Liu, Weiru

244

REVISED NATURAL GAS MARKET ASSESSMENT  

E-Print Network [OSTI]

CALIFORNIA ENERGY COMMISSION REVISED NATURAL GAS MARKET ASSESSMENT In Support of the 2007's natural gas market. It covers natural gas demand, supply, infrastructure, price, and possible alternative and the related Scenarios Project, and additional updated information. California natural gas demand growth

245

Storage Ring Revised March 1994  

E-Print Network [OSTI]

.5.4.3. Ground Plane Epoxy #12; 136 Storage Ring #12; Storage Ring 137 8.5.5. Coil Winding Process #12; 138Chapter 8. Storage Ring Revised March 1994 8.1. Introduction -- 107 -- #12; 108 Storage Ring 8.2. Magnetic Design and Field Calculations 8.2.1. Conceptual Approach #12; Storage Ring 109 #12; 110 Storage

Brookhaven National Laboratory - Experiment 821

246

(Revised May 25, 2012) Radioactivity  

E-Print Network [OSTI]

(Revised May 25, 2012) Radioactivity GOALS (1) To gain a better understanding of naturally-occurring. (3) To measure the amount of "background radiation" from natural sources. (4) To test whether and man-made radiation sources. (2) To use a Geiger-Mueller tube to detect both beta and gamma radiation

Collins, Gary S.

247

BELIEF REVISION AND UPDATE a dissertation  

E-Print Network [OSTI]

computational problems (chapters 5 and 6). A review of some of the most important proposals on revisionBELIEF REVISION AND UPDATE a dissertation submitted to the department of philosophy. In this study we focus on two of them, revision and update. For each of them, we attempt to ground them

del Val, Alvaro

248

A Revision of the Genera Pelomyia Williston  

E-Print Network [OSTI]

A Revision of the Genera Pelomyia Williston and Masoniella Vockeroth (Diptera: Tethinidae) GEORGE A O G Y · N U M B E R 6 1 9 A Revision of the Genera Pelomyia Williston and Masoniella Vockeroth. Mathis. A Revision of the Genera Pelomyia Williston and Masoniella Vockeroth (Diptera: Tethinidae

Mathis, Wayne N.

249

Los Alamos National Laboratory emergency management plan. Revision 1  

SciTech Connect (OSTI)

The Laboratory has developed this Emergency Management Plan (EMP) to assist in emergency planning, preparedness, and response to anticipated and actual emergencies. The Plan establishes guidance for ensuring safe Laboratory operation, protection of the environment, and safeguarding Department of Energy (DOE) property. Detailed information and specific instructions required by emergency response personnel to implement the EMP are contained in the Emergency Management Plan Implementing Procedure (EMPIP) document, which consists of individual EMPIPs. The EMP and EMPIPs may be used to assist in resolving emergencies including but not limited to fires, high-energy accidents, hazardous material releases (radioactive and nonradioactive), security incidents, transportation accidents, electrical accidents, and natural disasters.

Ramsey, G.F.

1998-07-15T23:59:59.000Z

250

IAEA Information Circular 225 Revision 5: Fact Sheet | National Nuclear  

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickr FlickrGuidedCH2MLLCBasics HydropowerI/O LibraryIACT EnergySecurity

251

Ris National Laboratory's revised strategy entails focusing and directing research  

E-Print Network [OSTI]

impact on the environment. Risø has a special role as a knowledge centre for nuclear matters. Compared Programme area 6 14 ­ Wind energy and atmospheric processes Programme area 7 15 ­ Nuclear safety Risø applications that contribute to the competitiveness of Danish industry and reduce the adverse impacts

252

Hanford Site National Environmental Policy Act (NEPA) characterization. Revision 10  

SciTech Connect (OSTI)

This document describes the US Department of Energy`s (DOE) Hanford Site environment and is numbered to correspond to the chapters where such information is presented in Hanford Site NEPA related documents. The document is intended to provide a consistent description of the Hanford Site environment for the many NEPA documents that are being prepared by contractors. The two chapters in this document (Chapters 4 and 6) are numbered this way to correspond to the chapters where such information is presented in environmental impact statements (EISs) and other Site-related NEPA or CERCLA documentation. Chapter 4.0 (Affected Environment) describes the Hanford Site environment, and includes information on climate and meteorology, geology, hydrology, ecology, cultural, archaeological and historical resources, socioeconomics, and noise. Chapter 6.0 (Statutory and Regulatory Requirements) describes applicable federal and state laws and regulations, DOE directives and permits, and environmental standards directly applicable to the NEPA documents on the Hanford Site.

Neitzel, D.A. [ed.; Fosmire, C.J.; Fowler, R.A. [and others

1998-09-01T23:59:59.000Z

253

Revised Propane Stock Levels for 6/7/13  

Annual Energy Outlook 2013 [U.S. Energy Information Administration (EIA)]

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) " ,"ClickPipelines AboutDecemberSteamYear Jan FebThousand Cubic Feet) CokersJanuary403,972

254

Perspectives on the National  

E-Print Network [OSTI]

Perspectives on the National Electrical Code ® John Wiles Sponsored by the Photovoltaic Systems systems. Representatives from the photovoltaic (PV) industry, academic institutions, the inspector requirements does not guarantee high levels of performance, higher performance and reliability frequently

Johnson, Eric E.

255

Clean Air Act. Revision 5  

SciTech Connect (OSTI)

This Reference Book contains a current copy of the Clean Air Act, as amended, and those regulations that implement the statute and appear to be most relevant to DOE activities. The document is provided to DOE and contractor staff for informational purposes only and should not be interpreted as legal guidance. This Reference Book has been completely revised and is current through February 15, 1994.

Not Available

1994-02-15T23:59:59.000Z

256

REVISED CATALOG OF SECURITY CONTROLS FOR FEDERAL INFORMATION SYSTEMS AND ORGANIZATIONS: FOR USE IN BOTH  

E-Print Network [OSTI]

REVISED CATALOG OF SECURITY CONTROLS FOR FEDERAL INFORMATION SYSTEMS AND ORGANIZATIONS: FOR USE's information systems. The uniform approach to describing controls for both national security and nonnational, implement, and assess their security controls most effectively when the process is carried out as part

257

Laser Safety Policy Procedure: 6.15 Version: 2.0 Revised: 09/15/2013  

E-Print Network [OSTI]

Laser Safety Policy Procedure: 6.15 Version: 2.0 Revised: 09/15/2013 Page 1 of 18 A. Purpose The purpose of this policy is to establish safe procedures for working with Class 3b and Class 4 lasers used that lasers and laser systems be operations in accordance with the American National Standards Institute (ANSI

Jia, Songtao

258

Notice of Intent to Revise DOE O 331.1C Chg 3, Employee Performance Management and Recognition Program  

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

The revision incorporates recommendations from the FY12 National Council on Federal Labor-Management Relation's "Goals-Engagement-Accountability-Results (GEAR)" report and program requirements currently contained in the DOE Supervisory/Non-Supervisory Employee Performance Management and Recognition Desk Reference (Desk Reference) such as the DOE Monetary Awards Scale, as well as program requirements that have been established via memoranda since the Order was revised in October 2010.

2015-03-20T23:59:59.000Z

259

Identification of permit and waste acceptance criteria provisions requiring modification for acceptance of commercial mixed waste. National Low-Level Waste Management Program  

SciTech Connect (OSTI)

In October 1990, representatives of States and compact regions requested that the US Department of Energy (DOE) explore an agreement with host States and compact regions under which DOE would accept commercial mixed low-level radioactive waste (LLW) at DOE`s own treatment and disposal facilities. A program for DOE management of commercial mixed waste is made potentially more attractive in light of the low commercial mixed waste volumes, high regulatory burdens, public opposition to new disposal sites, and relatively high cost of constructing commercial disposal facilities. Several studies were identified as essential in determining the feasibility of DOE accepting commercial mixed waste for disposal. The purpose of this report is to identify any current or proposed waste acceptance criteria (WAC) or Resource Conservation and Recovery Act (RCRA) provisions that would have to be modified for commercial mixed waste acceptance at specified DOE facilities. Following the introduction, Section 2 of this report (a) provides a background summary of existing and proposed mixed waste disposal facilities at each DOE site, and (b) summarizes the status of any RCRA Part B permit and WAC provisions relating to the disposal of mixed waste, including provisions relating to acceptance of offsite waste. Section 3 provides overall conclusions regarding the current status and permit modifications that must be implemented in order to grant DOE sites authority under their permits to accept commercial mixed waste for disposal. Section 4 contains a list of references.

Not Available

1994-03-01T23:59:59.000Z

260

NRC comprehensive records disposition schedule. Revision 3  

SciTech Connect (OSTI)

Title 44 US Code, ``Public Printing and Documents,`` regulations issued by the General Service Administration (GSA) in 41 CFR Chapter 101, Subchapter B, ``Management and Use of Information and Records,`` and regulations issued by the National Archives and Records Administration (NARA) in 36 CFR Chapter 12, Subchapter B, ``Records Management,`` require each agency to prepare and issue a comprehensive records disposition schedule that contains the NARA approved records disposition schedules for records unique to the agency and contains the NARA`s General Records Schedules for records common to several or all agencies. The approved records disposition schedules specify the appropriate duration of retention and the final disposition for records created or maintained by the NRC. NUREG-0910, Rev. 3, contains ``NRC`s Comprehensive Records Disposition Schedule,`` and the original authorized approved citation numbers issued by NARA. Rev. 3 incorporates NARA approved changes and additions to the NRC schedules that have been implemented since the last revision dated March, 1992, reflects recent organizational changes implemented at the NRC, and includes the latest version of NARA`s General Records Schedule (dated August 1995).

NONE

1998-02-01T23:59:59.000Z

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


261

Evaluations of 1990 PRISM design revisions  

SciTech Connect (OSTI)

Analyses of the 1990 version of the PRISM Advanced Liquid Metal Reactor (ALMR) design are presented and discussed. Most of the calculations were performed using BNL computer codes, particularly SSC and MINET. In many cases, independent BNL calculations were compared against analyses presented by General Electric when they submitted the PRISM design revisions for evaluation by the Nuclear Regulatory Commission (NRC). The current PRISM design utilizes the metallic fuel developed by Argonne National Laboratory (ANL) which facilitates the passive/``inherent`` shutdown mechanism that acts to shut down reactor power production whenever the system overheats. There are a few vulnerabilities in the passive shutdown, with the most worrisome being the positive feedback from sodium density decreases or sodium voiding. Various postulated unscrammed events were examined by GE and/or BNL, and much of the analysis discussed in this report is focused on this category of events. For the most part, the BNL evaluations confirm the information submitted by General Electric. The principal areas of concern are related to the performance of the ternary metal fuel, and may be resolved as ANL continues with its fuel development and testing program.

Van Tuyle, G.J.; Slovik, G.C.; Chan, B.C.; Aronson, A.L.; Kennett, R.J. [Brookhaven National Lab., Upton, NY (United States)

1992-03-01T23:59:59.000Z

262

Hanford Site National Environmental Policy Act (NEPA) Characterization  

SciTech Connect (OSTI)

This fifth revision of the Hanford Site National Environmental Policy (NEPA) Characterization presents current environmental data regarding the Hanford Site and its immediate environs. This information is intended for use in preparing Site-related NEPA documentation. Information is presented on climate and meteorology, geology and hydrology, ecology, history and archaeology, socioeconomics, land use, and noise levels, prepared by Pacific Northwest Laboratory (PNL) staff. Models are described that are to be used in simulating realized or potential impacts from nuclear materials at the Hanford Site. Included are models of radionuclide transport in groundwater and atmospheric pathways, and of radiation dose to populations via all known pathways from known initial conditions. Federal and state regulations, DOE orders and permits, and environmental standards directly applicable for the NEPA documents at the Hanford Site, are provided.

Cushing, C.E. (ed.)

1992-12-01T23:59:59.000Z

263

Feasibility study on the solidification of liquid low-level radioactive mixed waste in the inactive tank system at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program  

SciTech Connect (OSTI)

A literature survey was conducted to help determine the feasibility of solidifying a liquid low-level radioactive mixed waste in the inactive tank system at Oak Ridge National Laboratory (ORNL). The goal of this report is to facilitate a decision on the disposition of these wastes by identifying any waste constituents that might (1) compromise the strength or stability of the waste form or (2) be highly leachable. Furthermore, its goal is to identify ways to circumvent interferences and to decrease the leachability of the waste constituents. This study has sought to provide an understanding of inhibition of cement set by identifying the fundamental chemical mechanisms by which this inhibition takes place. From this fundamental information, it is possible to draw some conclusions about the potential effects of waste constituents, even in the absence of particular studies on specific compounds.

Trussell, S. [Texas A and M Univ., College Station, TX (United States). Dept. of Civil Engineering; Spence, R.D. [Oak Ridge National Lab., TN (United States)

1993-01-01T23:59:59.000Z

264

On the Dynamics of Total Preorders: Revising Abstract Interval Orders  

E-Print Network [OSTI]

of iterated belief revision [5­7]. In the problem of belief set revision, the tpo can be thought of as extraOn the Dynamics of Total Preorders: Revising Abstract Interval Orders Richard Booth1 and Thomas) are often used in belief revision to encode an agent's strategy for revising its belief set in response

Meyer, Tommie

265

Coal Data Publication Revision Policy  

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-Series to User Group and Userof aChristinaCliffPublication Revision Policy IF

266

Ris-R-1291(EN) Revised Cost Estimate for the  

E-Print Network [OSTI]

-R-1250(EN) "Decommissioning of the Nuclear Facilities at Risø National Laboratory" Edited by Kurt 3 in the report Risø-R-1250(EN) "Decommission- ing of the Nuclear Facilities at Risø National), a decommissioning project is carried out at three levels: Initial, On- going and Final. For a given nuclear

267

USER'S MANUAL Revision 1.0c  

E-Print Network [OSTI]

to correct the interference at your own expense. California Best Management Practices RegulationsH8QM3-2 H8QMi-2 USER'S MANUAL Revision 1.0c SUPER ® #12;Manual Revision 1.0c Release Date: November in the United States of America The information in this User's Manual has been carefully reviewed

van Hemmen, J. Leo

268

COMPUTER SECURITY revision list Subject Notes  

E-Print Network [OSTI]

COMPUTER SECURITY revision list Subject Notes AES DES 3-DES CBC Diffie-Hellman Elgaml RSA KeyCrypt Electronic Signatures PGP Access Control Matrix Access Control Lists #12;COMPUTER SECURITY revision list for Linux Confused Deputy Problem MD5 SHA1 SHA2 / SHA256 / SHA512 SHA3 Collision attacks MAC Password

Chothia, Tom

269

Belief Revision with Unreliable Observations Craig Boutilier  

E-Print Network [OSTI]

Belief Revision with Unreliable Observations Craig Boutilier Dept. Computer Science University of British Columbia Vancouver, British Columbia Canada, V6T 1W5 cebly@cs.ubc.ca Nir Friedman ¡£¢ Computer Research in belief revision has been dominated by work that lies firmly within the classic AGM paradigm

Halpern, Joseph Y.

270

NEW SOLAR HOMES PARTNERSHIP REVISED SECONDTHIRD EDITION  

E-Print Network [OSTI]

CALIFORNIA ENERGY COMMISSION NEW SOLAR HOMES PARTNERSHIP REVISED SECONDTHIRD EDITION of 15 Attachment 1 ERRATA TO THE NEW SOLAR HOMES PARTNERSHIP COMMITTEE DRAFT GUIDEBOOK The following list of Errata was adopted as part of the proposed revisions to the New Solar Homes Partnership

271

Sandia National Laboratories: high PV deployment level  

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1development Sandia,evaluatingfull moduleresources gridstandby positionshigh PV

272

Sandia National Laboratories: high PV penetration levels  

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1development Sandia,evaluatingfull moduleresources gridstandby positionshigh

273

Future scientists advance to national level  

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickr Flickr Editor's note:ComputingFusion roadmapping SubscribeFuture

274

Revised Draft Guidance on Consideration of Greenhouse Gas Emissions...  

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

Revised Draft Guidance on Consideration of Greenhouse Gas Emissions and Climate Change in NEPA Reviews Revised Draft Guidance on Consideration of Greenhouse Gas Emissions and...

275

CEQ Issues Revised Draft Guidance on Consideration of Greenhouse...  

Office of Environmental Management (EM)

Revised Draft Guidance on Consideration of Greenhouse Gas Emissions and the Effects of Climate Change in NEPA Reviews CEQ Issues Revised Draft Guidance on Consideration of...

276

After Wordsworth: Global Revisions of the English Poet  

E-Print Network [OSTI]

Revisions of the English Poet A dissertation submitted inRevisions of the English Poet by Katherine Lillian Bergrenbetween the English poet and his global Anglophone audience,

Bergren, Katherine Lillian

2013-01-01T23:59:59.000Z

277

PG&E Reconductoring Project Biological Assessment (Revised) ...  

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

PG&E Reconductoring Project Biological Assessment (Revised) PG&E Reconductoring Project Biological Assessment (Revised) PG&E Reconductoring Project Biological Assessment (1216...

278

Attachment 2: Solicitation for Offers with New and Revised Green...  

Office of Environmental Management (EM)

2: Solicitation for Offers with New and Revised Green Lease Text Attachment 2: Solicitation for Offers with New and Revised Green Lease Text Solicitation for Offers Paragraphs with...

279

Revised Davis-Bacon Wage Determinations for the Weatherization...  

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

Revised Davis-Bacon Wage Determinations for the Weatherization Assistance Program Revised Davis-Bacon Wage Determinations for the Weatherization Assistance Program U.S. Department...

280

Pancreaticoportal Fistula and Disseminated Fat Necrosis After Revision of a Transjugular Intrahepatic Portosystemic Shunt  

SciTech Connect (OSTI)

A 59-year old man with alcohol related cirrhosis and portal hypertension was referred for transjugular intrahepatic portosystemic shunt (TIPS) to treat his refractory ascites. Ten years later, two sequential TIPS revisions were performed for shunt stenosis and recurrent ascites. After these revisions, he returned with increased serum pancreatic enzyme levels and disseminated superficial fat necrosis; an iatrogenic pancreaticoportal vein fistula caused by disruption of the pancreatic duct was suspected. The bare area of the TIPS was subsequently lined with a covered stent-graft, and serum enzyme levels returned to baseline. In the interval follow-up period, the patient has clinically improved.

Klein, Seth J., E-mail: kleins@mir.wustl.edu; Saad, Nael [Washington University School of Medicine, Interventional Radiology Section, Mallinckrodt Institute of Radiology (United States)] [Washington University School of Medicine, Interventional Radiology Section, Mallinckrodt Institute of Radiology (United States); Korenblat, Kevin [Washington University School of Medicine, Division of Gastroenterology, Department of Internal Medicine (United States)] [Washington University School of Medicine, Division of Gastroenterology, Department of Internal Medicine (United States); Darcy, Michael D. [Washington University School of Medicine, Interventional Radiology Section, Mallinckrodt Institute of Radiology (United States)] [Washington University School of Medicine, Interventional Radiology Section, Mallinckrodt Institute of Radiology (United States)

2013-04-15T23:59:59.000Z

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


281

The IRAS Revised Bright Galaxy Sample (RBGS)  

E-Print Network [OSTI]

IRAS flux densities, redshifts, and infrared luminosities are reported for all sources identified in the IRAS Revised Bright Galaxy Sample (RBGS), a complete flux-limited survey of all extragalactic objects with total 60 micron flux density greater than 5.24 Jy, covering the entire sky surveyed by IRAS at Galactic latitude |b| > 5 degrees. The RBGS includes 629 objects, with a median (mean) sample redshift of 0.0082 (0.0126) and a maximum redshift of 0.0876. The RBGS supersedes the previous two-part IRAS Bright Galaxy Samples, which were compiled before the final ("Pass 3") calibration of the IRAS Level 1 Archive in May 1990. The RBGS also makes use of more accurate and consistent automated methods to measure the flux of objects with extended emission. Basic properties of the RBGS sources are summarized, including estimated total infrared luminosities, as well as updates to cross-identifications with sources from optical galaxy catalogs established using the NASA/IPAC Extragalactic Database (NED). In addition...

Sanders, D B; Kim, D C; Surace, J A; Soifer, B T

2003-01-01T23:59:59.000Z

282

How Hard is it to Revise a Belief Base? Bernhard Nebel  

E-Print Network [OSTI]

. . . . . . . . . . . . . . . . . . . . 5 2.4 Cut Revision Scheme . . . . . . . . . . . . . . . . . . . . . . . . . 6 2.5 Safe Revision Schemes 19 4.5 Full Meet Revision Scheme . . . . . . . . . . . . . . . . . . . . . . 20 5 Meet Base Revision Schemes 21 5.1 Full Meet Base Revision . . . . . . . . . . . . . . . . . . . . . . . 22 5

Nebel, Bernhard

283

Enterprise Assessments Review of the Y-12 National Security Complex...  

Office of Environmental Management (EM)

Enterprise Assessments Review of the Y-12 National Security Complex 2014 Site-Level Exercise - January 2015 Enterprise Assessments Review of the Y-12 National Security Complex 2014...

284

National Green Building Standard Analysis  

SciTech Connect (OSTI)

DOE's Building America Program is a research and development program to improve the energy performance of new and existing homes. The ultimate goal of the Building America Program is to achieve examples of cost-effective, energy efficient solutions for all U.S. climate zones. Periodic maintenance of an ANSI standard by review of the entire document and action to revise or reaffirm it on a schedule not to exceed five years is required by ANSI. In compliance, a consensus group has once again been formed and the National Green Building Standard is currently being reviewed to comply with the periodic maintenance requirement of an ANSI standard.

NAHB Research Center, Upper Marlboro, Maryland

2012-07-01T23:59:59.000Z

285

CTBT | National Nuclear Security Administration  

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNational NuclearhasAdministration77 SandiaGuidance to the RevisedLinks(. ForCTBT

286

Number: Revision: ESH-0002 03  

E-Print Network [OSTI]

program for the laser system listed below. All American National Standard Institute (ANSI) Hazard Class 3b) Signature: Date: AUTHORIZATION Work with all ANSI Class 3b and 4 laser systems must be planned (Argon, CO2, etc) Wavelengths ANSI Class Maximum Power of Energy/Pulse Pulse Length Repetition Rate

McDonald, Kirk

287

Revision control in the Grid era: The Unmet challenge  

SciTech Connect (OSTI)

As we move to distribute High Energy Physics computing tasks throughout the global Grid, they are encountering ever more severe difficulties installing and selecting appropriate versions of the supporting products. Problems show up at every level: the base operating systems and tools, general purpose utilities like root, and specific releases of application code. The author discusses some specific examples, including what we've learned in commissioning the SAM software for use by CDF. The author also shows why revision control can be a truly difficult problem, and will discuss what we've been doing to measure and control the situation.

Arthur Kreymer

2003-10-01T23:59:59.000Z

288

Introduction Wikipedia Revision History Applications Conclusions References Mining Wikipedia's  

E-Print Network [OSTI]

Revision History Revision History Plots Figure: RH plots for articles 2005 (5,714 rev.) and 2007 (11,494 rev.) Mihai Grigore Mining Wikipedia's Article Revision History 5/24 #12;Introduction WikipediaIntroduction Wikipedia Revision History Applications Conclusions References Mining Wikipedia

Neumann, GĂĽnter

289

Belief Revision through Forgetting Conditionals in Conditional Probabilistic Logic Programs  

E-Print Network [OSTI]

of probabilistic belief revising, most research focuses on revising a single probabilistic distribution [5, 1, 8, 4Belief Revision through Forgetting Conditionals in Conditional Probabilistic Logic Programs Anbu Yue 1 and Weiru Liu 1 Abstract. In this paper, we present a revision strategy of revis- ing

Liu, Weiru

290

Semistructured Merge: Rethinking Merge in Revision Control Systems  

E-Print Network [OSTI]

Semistructured Merge: Rethinking Merge in Revision Control Systems Sven Apel, Jörg Liebig, Benjamin, Germany ABSTRACT An ongoing problem in revision control systems is how to resolve conflicts in a merge of independently developed revisions. Un- structured revision control systems are purely text-based and solve

Apel, Sven

291

New and revised standards for coke production  

SciTech Connect (OSTI)

The need for new and revised standards for coke production in Ukraine and Russia is outlined. Such standards should address improvements in plant operation, working conditions, environmental protection, energy conservation, fire and explosion safety, and economic indices.

G.A. Kotsyuba; M.I. Alpatov; Y.G. Shapoval [Giprokoks, the State Institute for the Design of Coke-Industry Enterprises, Kharkov (Ukraine)

2009-07-15T23:59:59.000Z

292

Revised June 2014 Training Management System (TMS)  

E-Print Network [OSTI]

Revised June 2014 Training Management System (TMS) User Manual Contents Accessing the TMS.................................................................................................................15 #12;2 Accessing the TMS Before accessing the Training Management System you must know your Harvard...........................................................................................................................................2 Training Director, Training Manager, and Course Director Access

Heller, Eric

293

Safe Operating Procedure (Revised 11/11)  

E-Print Network [OSTI]

Generators Definition and Visual Determination of Opacity With regards to stack emissions, opacitySafe Operating Procedure (Revised 11/11) OPACITY OF EMISSIONS FROM COMBUSTION SOURCES (opacity) from combustion sources. Opacity monitoring & measurements are taken in accordance

Farritor, Shane

294

Status of Revisions to ASHRAE Standard 62  

E-Print Network [OSTI]

occupancies. This standard has also been cited in court to help demonstrate compliance with state-of the- art indoor environmental design. In August 1996, ASHRAE released for public review Standard 62-1989R, the highly controversial proposed revisions...

Gallo, F. M.

1998-01-01T23:59:59.000Z

295

Pennsylvania Coalbed Methane Proved Reserves Revision Decreases...  

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

Decreases (Billion Cubic Feet) Pennsylvania Coalbed Methane Proved Reserves Revision Decreases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7...

296

Colorado Coalbed Methane Proved Reserves Revision Increases ...  

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

Increases (Billion Cubic Feet) Colorado Coalbed Methane Proved Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7...

297

Pennsylvania Coalbed Methane Proved Reserves Revision Increases...  

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

Increases (Billion Cubic Feet) Pennsylvania Coalbed Methane Proved Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7...

298

Virginia Coalbed Methane Proved Reserves Revision Decreases ...  

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

Decreases (Billion Cubic Feet) Virginia Coalbed Methane Proved Reserves Revision Decreases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7...

299

Oklahoma Coalbed Methane Proved Reserves Revision Decreases ...  

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

Decreases (Billion Cubic Feet) Oklahoma Coalbed Methane Proved Reserves Revision Decreases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7...

300

Arkansas Coalbed Methane Proved Reserves Revision Increases ...  

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

Increases (Billion Cubic Feet) Arkansas Coalbed Methane Proved Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7...

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


301

Oklahoma Coalbed Methane Proved Reserves Revision Increases ...  

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

Increases (Billion Cubic Feet) Oklahoma Coalbed Methane Proved Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7...

302

Colorado Coalbed Methane Proved Reserves Revision Decreases ...  

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

Decreases (Billion Cubic Feet) Colorado Coalbed Methane Proved Reserves Revision Decreases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7...

303

Arkansas Coalbed Methane Proved Reserves Revision Decreases ...  

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

Decreases (Billion Cubic Feet) Arkansas Coalbed Methane Proved Reserves Revision Decreases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7...

304

Virginia Coalbed Methane Proved Reserves Revision Increases ...  

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

Increases (Billion Cubic Feet) Virginia Coalbed Methane Proved Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7...

305

CALIFORNIA ENERGY DEMAND 20142024 REVISED FORECAST  

E-Print Network [OSTI]

CALIFORNIA ENERGY DEMAND 20142024 REVISED FORECAST Volume 2: Electricity Demand Robert P. Oglesby Executive Director #12;i ACKNOWLEDGEMENTS The demand forecast is the combined provided estimates for demand response program impacts and contributed to the residential forecast. Mitch

306

Revised 01-14 DATE: _____________________________  

E-Print Network [OSTI]

of Diagnoses Heart attack Yes No Transient ischemic attack Yes No Angina (chest pain) Yes No Stroke Yes Level _________________ Year Diagnosed with Diabetes:_________ Family history of heart attack

de Lijser, Peter

307

HLW system plan - revision 2  

SciTech Connect (OSTI)

The projected ability of the Tank Farm to support DWPF startup and continued operation has diminished somewhat since revision 1 of this Plan. The 13 month delay in DWPF startup, which actually helps the Tank Farm condition in the near term, was more than offset by the 9 month delay in ITP startup, the delay in the Evaporator startups and the reduction to Waste Removal funding. This Plan does, however, describe a viable operating strategy for the success of the HLW System and Mission, albeit with less contingency and operating flexibility than in the past. HLWM has focused resources from within the division on five near term programs: The three evaporator restarts, DWPF melter heatup and completion of the ITP outage. The 1H Evaporator was restarted 12/28/93 after a 9 month shutdown for an extensive Conduct of Operations upgrade. The 2F and 2H Evaporators are scheduled to restart 3/94 and 4/94, respectively. The RHLWE startup remains 11/17/97.

Not Available

1994-01-14T23:59:59.000Z

308

Special Analysis for the Disposal of the Idaho National Laboratory Unirradiated Light Water Breeder Reactor Rods and Pellets Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada  

SciTech Connect (OSTI)

The purpose of this special analysis (SA) is to determine if the Idaho National Laboratory (INL) Unirradiated Light Water Breeder Reactor (LWBR) Rods and Pellets waste stream (INEL103597TR2, Revision 2) is suitable for disposal by shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS). The INL Unirradiated LWBR Rods and Pellets waste stream consists of 24 containers with unirradiated fabricated rods and pellets composed of uranium oxide (UO2) and thorium oxide (ThO2) fuel in zirconium cladding. The INL Unirradiated LWBR Rods and Pellets waste stream requires an SA because the 229Th, 230Th, 232U, 233U, and 234U activity concentrations exceed the Nevada National Security Site (NNSS) Waste Acceptance Criteria (WAC) Action Levels.

Shott, Gregory [NSTec

2014-08-31T23:59:59.000Z

309

Revision of the DELFIC Particle Activity Module  

SciTech Connect (OSTI)

The Defense Land Fallout Interpretive Code (DELFIC) was originally released in 1968 as a tool for modeling fallout patterns and for predicting exposure rates. Despite the continual advancement of knowledge of fission yields, decay behavior of fission products, and biological dosimetry, the decay data and logic of DELFIC have remained mostly unchanged since inception. Additionally, previous code revisions caused a loss of conservation of radioactive nuclides. In this report, a new revision of the decay database and the Particle Activity Module is introduced and explained. The database upgrades discussed are replacement of the fission yields with ENDF/B-VII data as formatted in the Oak Ridge Isotope Generation (ORIGEN) code, revised decay constants, revised exposure rate multipliers, revised decay modes and branching ratios, and revised boiling point data. Included decay logic upgrades represent a correction of a flaw in the treatment of the fission yields, extension of the logic to include more complex decay modes, conservation of nuclides (including stable nuclides) at all times, and conversion of key variables to double precision for nuclide conservation. Finally, recommended future work is discussed with an emphasis on completion of the overall radiation physics upgrade, particularly for dosimetry, induced activity, decay of the actinides, and fractionation.

Hooper, David A [ORNL; Jodoin, Vincent J [ORNL

2010-09-01T23:59:59.000Z

310

LA-UR-96-3440 Revised 2/11/97 THE ATLAS PROJECT  

E-Print Network [OSTI]

, and S.M. Younger Los Alamos National Laboratory Los Alamos, NM. 87545 Abstract Atlas is a facility being and Management Program2. Atlas will be the first of several new facilities constructed to support this ProgramLA-UR-96-3440 Revised 2/11/97 1 THE ATLAS PROJECT W.M. Parsons, E.O. Ballard, R.R. Bartsch, J

311

Transuranic waste baseline inventory report. Revision No. 3  

SciTech Connect (OSTI)

The Transuranic Waste Baseline Inventory Report (TWBIR) establishes a methodology for grouping wastes of similar physical and chemical properties from across the U.S. Department of Energy (DOE) transuranic (TRU) waste system into a series of {open_quotes}waste profiles{close_quotes} that can be used as the basis for waste form discussions with regulatory agencies. The purpose of Revisions 0 and 1 of this report was to provide data to be included in the Sandia National Laboratories/New Mexico (SNL/NM) performance assessment (PA) processes for the Waste Isolation Pilot Plant (WIPP). Revision 2 of the document expanded the original purpose and was also intended to support the WIPP Land Withdrawal Act (LWA) requirement for providing the total DOE TRU waste inventory. The document included a chapter and an appendix that discussed the total DOE TRU waste inventory, including nondefense, commercial, polychlorinated biphenyls (PCB)-contaminated, and buried (predominately pre-1970) TRU wastes that are not planned to be disposed of at WIPP.

NONE

1996-06-01T23:59:59.000Z

312

National Institute for Global Environmental Change  

SciTech Connect (OSTI)

This document is the Semi-Annual Report of the National Institute for Global Environmental Change for the reporting period July 1 to December 31, 1991. The report is in two parts. Part I presents the mission of the Institute, examples of progress toward that mission, a brief description of the revised management plan, and the financial report. Part II presents the statements of the Regional Center Directors along with progress reports of the projects written by the researchers themselves.

Werth, G.C.

1992-04-01T23:59:59.000Z

313

Federal Agency Hazardous Waste Compliance Docket (docket). Revision 1  

SciTech Connect (OSTI)

The Federal Facilities Hazardous Waste Compliance Docket (``docket``) identifies Federal facilities that may be contaminated with hazardous substances and that must be evaluated to determine if they pose a risk to public health or the environment The docket, required by Section 120(c) of the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA), as amended by the Superfund Amendments and Reauthorization Act of 1986 (SARA), also provides a vehicle for making information about potentially contaminated facilities available to the public. Facilities listed on the docket must complete site assessments that provide the Environmental Protection Agency (EPA) with information needed to determine whether or not the facility should be included on he National Priorities List (NPL). This Information Brief, which revises the previous Federal Agency Hazardous Waste Compiliance Docket Information Brief, provides updated information on the docket listing process, the implications of listing, and facility status after listing.

Not Available

1994-01-01T23:59:59.000Z

314

NATIONAL LABORATORY  

Office of Scientific and Technical Information (OSTI)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinan antagonist Journal Article: CrystalFG36-08GO18149 Revision: - Date: 06/15/10 ABENGOA SOLAREnergy

315

CFTB 04/22/2010 Revisions to the 2008 Census of Fatal Occupational Injuries (CFOI) counts  

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart of the Review of theOFFICEACME | NationalTbilisi08 to 2028Revisions

316

National Spent Nuclear Fuel Program  

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

need to safely and efficiently manage all DOE-owned spent nuclear fuel and high level waste and prepare it for disposal. The National Spent Nuclear Fuel Program is addressing...

317

Revised Economic andRevised Economic and Demand ForecastsDemand Forecasts  

E-Print Network [OSTI]

Revised Economic andRevised Economic and Demand ForecastsDemand Forecasts April 14, 2009 Massoud,000 MW #12;6 Demand Forecasts Price Effect (prior to conservation) - 5,000 10,000 15,000 20,000 25,000 30 Jourabchi #12;2 Changes since the Last Draft ForecastChanges since the Last Draft Forecast Improved

318

Development of the Office of Civilian Radioactive Waste Management National Transportation Plan  

SciTech Connect (OSTI)

The Director of the Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) designated development of the National Transportation Plan (NTP) as one of his four strategic objectives for the program. The Office of Logistics Management (OLM) within OCRWM was tasked to develop the plan, which will accommodate state, local, and tribal concerns and input to the greatest extent practicable. The plan will describe each element of the national transportation system that OCRWM is developing for shipping spent nuclear fuel and high-level radioactive waste to the proposed geologic repository at Yucca Mountain, Nevada. The plan will bring together OCRWM's approach for acquiring capital assets (casks, rail cars, and a rail line in Nevada) and its operational planning efforts in a single, comprehensive document. It will also provide a timetable for major transportation decisions and milestones needed to support a 2017 start date for shipments to the Yucca Mountain repository. The NTP will be revised to incorporate new developments and decisions as they are finalized. This paper will describe the elements of the NTP, its importance in providing a comprehensive overview of the national transportation system, and the role of stakeholders in providing input on the NTP and the national transportation system. (authors)

Macaluso, C. [U.S. Department of Energy, Office of Civilian Radioactive Waste Management, Washington, DC (United States); Offner, J.; Patric, J. [Booz Allen Hamilton, Washington, DC (United States)

2008-07-01T23:59:59.000Z

319

Program Plan for Revision of the Z-Area Saltstone Disposal Facility Performance Assessment  

SciTech Connect (OSTI)

Savannah River National Laboratory (SRNL) and the Saltstone Project, are embarking on the next revision to the Saltstone Disposal Facility (SDF) performance assessment (PA). This program plan has been prepared to outline the general approach, scope, schedule and resources for the PA revision. The plan briefly describes the task elements of the PA process. It discusses critical PA considerations in the development of conceptual models and interpretation of results. Applicable quality assurance (QA) requirements are identified and the methods for implementing QA for both software and documentation are described. The plan identifies project resources supporting the core team and providing project oversight. Program issues and risks are identified as well as mitigation of those risks. Finally, a preliminary program schedule has been developed and key deliverables identified. A number of significant changes have been implemented since the last PA revision resulting in a new design for future SDF disposal units. This revision will encompass the existing and planned disposal units, PA critical radionuclides and exposure pathways important to SDF performance. An integrated analysis of the overall facility layout, including all disposal units, will be performed to assess the impact of plume overlap on PA results. Finally, a rigorous treatment of uncertainty will be undertaken using probabilistic simulations. This analysis will be reviewed and approved by DOE-SR, DOE-HQ and potentially the Nuclear Regulatory Commission (NRC). This revision will be completed and ready for the start of the DOE review at the end of December 2006. This work supports a Saltstone Vault 2 fee-bearing milestone. This milestone includes completion of the Vault 2 module of the PA revision by the end of FY06.

Cook, James R.

2005-12-07T23:59:59.000Z

320

BSL-3 Links | National Nuclear Security Administration  

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNational NuclearhasAdministration77 SandiaGuidance to the RevisedLinks | National

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While these samples are representative of the content of NLEBeta,
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We encourage you to perform a real-time search of NLEBeta
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321

Notice of Intent to Revise DOE G 226.1-2, Federal Line Management Oversight of Department of Energy Nuclear Facilities  

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

This revision will incorporate new content devoted to Federal oversight and evaluation of effectiveness of activity-level work planning and control (WP&C) at Hazard Category 1, 2, and 3 nuclear facilities.

2013-04-04T23:59:59.000Z

322

First Responders | National Nuclear Security Administration  

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

specialized national-level first responder technical and operational capabilities, and conduct specialized operations, during the initial phases of a response to a radiological...

323

Parallel programming with PCN. Revision 1  

SciTech Connect (OSTI)

PCN is a system for developing and executing parallel programs. It comprises a high-level programming language, tools for developing and debugging programs in this language, and interfaces to Fortran and C that allow the reuse of existing code in multilingual parallel programs. Programs developed using PCN are portable across many different workstations, networks, and parallel computers. This document provides all the information required to develop parallel programs with the PCN programming system. In includes both tutorial and reference material. It also presents the basic concepts that underly PCN, particularly where these are likely to be unfamiliar to the reader, and provides pointers to other documentation on the PCN language, programming techniques, and tools. PCN is in the public domain. The latest version of both the software and this manual can be obtained by anonymous FTP from Argonne National Laboratory in the directory pub/pcn at info.mcs.anl.gov (c.f. Appendix A).

Foster, I.; Tuecke, S.

1991-12-01T23:59:59.000Z

324

From: National Science Foundation TO: All IPAs by BCC  

E-Print Network [OSTI]

From: National Science Foundation TO: All IPAs by BCC Dear NSF Intergovernmental Personnel Act (IPA of the information you received yesterday. The revised document removes information not applicable to IPA assignees and Fellows and describes a number of actions and responsibilities for NSF employees, IPA assignees

Herr, Amy E.

325

Exceptional service in the national interest www.sandia.gov  

E-Print Network [OSTI]

Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE) and the International, Homeland & Nuclear Security Strategic Management Unit Revised July 2012 Jill Hruby is the Vice as the corporate strategic thrust on Nuclear Security (in all, about $274M in funding during FY10). The Nuclear

326

Vision and revision in Coleridge's dramas  

E-Print Network [OSTI]

to repentance with the aid of a foil, and then punished him for his evil deeds. But Coleridge went further in his revision of the dramatic vision of the day; he rewrote Remorse as a romance, ~2a ol a. While he shifted the emphasis from the punishment... is that they are attempts to revise Shakespeare, to offer a modern, romantic version of Shakespearean tragedy in Remorse and Shakespearean romance 1n ~2a ol a. Little work has been done on these dramas, and only a small fraction of those studies that have been written...

Tveten, Janet Elaine Hesler

2012-06-07T23:59:59.000Z

327

U.S. Geological Survey National Produced Waters Geochemical Database v2.0 (PROVISIONAL)  

E-Print Network [OSTI]

U.S. Geological Survey National Produced Waters Geochemical Database v2.0 (PROVISIONAL (USGS) National Produced Waters Geochemical Database v2.0 are provisional and subject to revision Produced Waters Geochemical Database v2.0 should be used with careful consideration of its limitations

Torgersen, Christian

328

Final Environmental Impact Statement and Environmental Impact Report for continued operation of Lawrence Livermore National Laboratory and Sandia National Laboratories, Livermore. Volume 3, Appendices F--M  

SciTech Connect (OSTI)

This Environmental Impact Statement/Environmental Impact Report (EIS/EIR) is prepared pursuant to the National Environmental Policy Act (NEPA) and the California Environmental Quality Act (CEQA). This document analyzes the potential environmental impacts of the proposed action: continued operation, including near-term (within 5 to 10 years) proposed projects, of Lawrence Livermore National Laboratory (LLNL) and Sandia National Laboratories, Livermore (SNL, Livermore). Additionally, this document analyzes a no action alternative involving continuing operations at FY 1992 funding levels without further growth, a modification of operations alternative to reduce adverse environmental impacts of operations or facilities, and a shutdown and decommissioning alternative of UC discontinuing its management of LLNL after the current contract expires on September 30, 1992. This document assesses the environmental impacts of the Laboratories` operations on air and water quality, geological and ecological systems, occupational and public health risks, prehistoric and historic resources, endangered species, floodplains and wetlands, socioeconomic resources, hazardous waste management, site contamination, and other environmental issues. The EIS/EIR is divided into five volumes and two companion reports. This volume contains the Final EIS/EIR technical appendices F through M. Appendix L has been revised to reflect public information activities since publication of the Draft EIS/EIR. These appendices provide technical support for the analyses in Volume 1 and also provide additional information and references.

Not Available

1992-08-01T23:59:59.000Z

329

Psychometric properties of the revised marital satisfaction inventory  

E-Print Network [OSTI]

This study examines the psychometric properties of the Revised marital Satisfaction Inventory (MSI-R) using archival data from previous validation studies of the original instrument. Normalized T-scores were identified for each of the 11 revised...

Aikman, Grace Glass

2012-06-07T23:59:59.000Z

330

Ohio Coalbed Methane Proved Reserves Revision Decreases (Billion...  

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

Revision Decreases (Billion Cubic Feet) Ohio Coalbed Methane Proved Reserves Revision Decreases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7...

331

Policy Flash 2015 Revision to the Federal Assistance Reporting...  

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

Revision to the Federal Assistance Reporting Checklist, DOE F 4600.2 (102014). Policy Flash 2015 Revision to the Federal Assistance Reporting Checklist, DOE F 4600.2 (102014)....

332

Revision of DOE Manual 460.2-1  

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

, 2005 TECWG 1 Revision of DOE M 460.2-1, Radioactive Material Transportation Practices Manual Revision of DOE M 460.2-1, Radioactive Material Transportation Practices Manual Ella...

333

Oak Ridge National Laboratory National Security Programs  

E-Print Network [OSTI]

Oak Ridge National Laboratory National Security Programs Dr. Michael A. Kuliasha, Chief Scientist National Security Technologies Oak Ridge National Laboratory #12;2 OAK RIDGE NATIONAL LABORATORY U. S Security Challenges #12;3 OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY How Will Our Enemies

334

Special Analysis for the Disposal of the Neutron Products Incorporated Sealed Source Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada  

SciTech Connect (OSTI)

The purpose of this special analysis (SA) is to determine if the Neutron Products Incorporated (NPI) Sealed Sources waste stream (DRTK000000056, Revision 0) is suitable for disposal by shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS). The NPI Sealed Sources waste stream consists of 850 60Co sealed sources (Duratek [DRTK] 2013). The NPI Sealed Sources waste stream requires a special analysis (SA) because the waste stream 60Co activity concentration exceeds the Nevada National Security Site (NNSS) Waste Acceptance Criteria (WAC) Action Levels.

Shott, Gregory

2014-08-31T23:59:59.000Z

335

Southeast Regional Clean Energy Policy Analysis (Revised)  

SciTech Connect (OSTI)

More than half of the electricity produced in the southeastern states is fuelled by coal. Although the region produces some coal, most of the states depend heavily on coal imports. Many of the region's aging coal power facilities are planned for retirement within the next 20 years. However, estimates indicate that a 20% increase in capacity is needed over that time to meet the rapidly growing demand. The most common incentives for energy efficiency in the Southeast are loans and rebates; however, total public spending on energy efficiency is limited. The most common state-level policies to support renewable energy development are personal and corporate tax incentives and loans. The region produced 1.8% of the electricity from renewable resources other than conventional hydroelectricity in 2009, half of the national average. There is significant potential for development of a biomass market in the region, as well as use of local wind, solar, methane-to-energy, small hydro, and combined heat and power resources. Options are offered for expanding and strengthening state-level policies such as decoupling, integrated resource planning, building codes, net metering, and interconnection standards to support further clean energy development. Benefits would include energy security, job creation, insurance against price fluctuations, increased value of marginal lands, and local and global environmental paybacks.

McLaren, J.

2011-04-01T23:59:59.000Z

336

Curriculum Vitae | ANTHONY FAIOLA Revised 3/3/20141 CURRICULUM VITAE  

E-Print Network [OSTI]

Vitae | ANTHONY FAIOLA Revised 3/3/20141 CURRICULUM VITAE ANTHONY FAIOLA;___________________________________________________________________________________________________________________________________________________________________________________ Curriculum Vitae | ANTHONY FAIOLA Revised 3___________________________________________________________________________________________________________________________________________________________________________________ Curriculum

Zhou, Yaoqi

337

Revised 2006 UNDERGRADUATE MINOR IN MECHANICAL ENGINEERING  

E-Print Network [OSTI]

Revised 2006 UNDERGRADUATE MINOR IN MECHANICAL ENGINEERING Instructions for declaring the ME Services Office (Building 530, room 125) · Submit the form to Student Services and the login to Axess students to the breadth of Mechanical Engineering topics and analytic design activities. Prerequisites

Prinz, Friedrich B.

338

USER'S MANUAL Revision 1.1b  

E-Print Network [OSTI]

Best Management Practices Regulations for Perchlorate Materials: This Perchlorate warning applies onlySUPER ® X7DB3 USER'S MANUAL Revision 1.1b #12;Unless you request and receive written permission in this User's Manual has been carefully reviewed and is believed to be accurate. The vendor assumes

Maccabe, Barney

339

Safe Operating Procedure (Revised 9/10)  

E-Print Network [OSTI]

ingestion is 0.04 mCi. Waste Disposal EHS procedures for disposal of hazardous and/or radioactive wastesSafe Operating Procedure (Revised 9/10) SAFETY PROTOCOL: I-125://ehs.unl.edu/) Use of radioactive materials requires a safety protocol be submitted to the UNL Radiation Safety

Farritor, Shane

340

Revised 4/12 Computer Science  

E-Print Network [OSTI]

Revised 4/12 Computer Science The Computer Science Minor is primarily designed for students background in computer science to complement their major beyond the requirements of their major department. To receive a minor in computer science, students must complete a minimum of six courses with the following

Massachusetts at Lowell, University of

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


341

Revised 5/14 Computer Science  

E-Print Network [OSTI]

Revised 5/14 Computer Science The Computer Science Minor is primarily designed for students background in computer science to complement their major beyond the requirements of their major department. To receive a minor in computer science, students must complete a minimum of six courses with the following

Massachusetts at Lowell, University of

342

Application Note (A9) Revision: A  

E-Print Network [OSTI]

measurements of light falling onto a flat surface. Such studies vary from solar UV exposure limitsApplication Note (A9) Revision: A AUGUST 1995 OPTRONIC LABORATORIES, INC. 4632 36TH STREET Orlando on the wavelength of light so the bluer wavelengths are scattered more strongly than redder. This leads

Johnsen, Sönke

343

Revised April, 2013 IIT Dining Services  

E-Print Network [OSTI]

Revised April, 2013 IIT Dining Services Request to Serve or Sell Food on Campus Program Information and Food Provider Information Before any person or organization operates a temporary food service establishment where food is served or sold, approval must be secured by the Director of Sodexo Dining Services

Heller, Barbara

344

FTCP Corrective Action Plan- Revision 1  

Broader source: Energy.gov [DOE]

January 2007 FTCP Corrective Action Plan, Revision 1, which is Deliverable B for Commitment 13 in the Department of Energy (DOE) Implementation Plan to Improve Oversight of Nuclear Operations, issued in response to Defense Nuclear Facilities Safety Board Recommendation 2004- 1, Oversight of Complex, High-Hazard Nuclear Operations

345

January 8, 2002 Revised March 2010  

E-Print Network [OSTI]

January 8, 2002 Revised March 2010 Facilities Management Department Policy Statement #3 Utility of interruptions in utility service on campus. 2. Responsibility: The Director of Facilities Operations activities. E. Emergency Call List i. An emergency call list of the building representatives and other key

Howitt, Ivan

346

Revised Nov. 2013 Contracting and Procurement Services  

E-Print Network [OSTI]

Revised Nov. 2013 Contracting and Procurement Services Contract and Purchase Order Cover Sheet Procedures The Contract and Purchase Order Cover Sheet is an internal document utilized by Contracting the business purpose of the proposed purchase or contract; 2) Identify courses offered for credit at off campus

Caughman, John

347

REVISED HYDROGEN SULFIDE DRILLING CONTINGENCY PLAN  

E-Print Network [OSTI]

REVISED HYDROGEN SULFIDE DRILLING CONTINGENCY PLAN OCEAN DRILLING PROGRAM TEXAS A&M UNIVERSITY Technical Note 19 Gien N. Foss Ocean Drilling Program Texas A&M University 1000 Discovery Drive College Station, TX 77845-9547 Bradley D. Julson Ocean Drilling Program Texas A&M University 1000 Discovery Drive

348

Revised: June 14, 2013 UNIVERSITY OF MICHIGAN  

E-Print Network [OSTI]

Revised: June 14, 2013 UNIVERSITY OF MICHIGAN University Travel Warning Destination Liability/College/Business Unit: Destination: Travel Start Date: Travel End Date: I understand that the University of Michigan the Regents of the University of Michigan, ("University"), and all of its employees and agents from any claim

Eustice, Ryan

349

REVISED CALIFORNIA ENERGY DEMAND FORECAST 20122022  

E-Print Network [OSTI]

REVISED CALIFORNIA ENERGY DEMAND FORECAST 20122022 Volume 2: Electricity Demand by Utility ACKNOWLEDGEMENTS The staff demand forecast is the combined product of the hard work and expertise of numerous the residential forecast. Mitch Tian prepared the peak demand forecast. Ravinderpal Vaid provided the projections

350

REVISED CALIFORNIA ENERGY DEMAND FORECAST 20122022  

E-Print Network [OSTI]

REVISED CALIFORNIA ENERGY DEMAND FORECAST 20122022 Volume 1: Statewide Electricity Demand in this report. #12;i ACKNOWLEDGEMENTS The staff demand forecast is the combined product of the hard work Sheridan provided the residential forecast. Mitch Tian prepared the peak demand forecast. Ravinderpal Vaid

351

CALIFORNIA ENERGY DEMAND 20142024 REVISED FORECAST  

E-Print Network [OSTI]

CALIFORNIA ENERGY DEMAND 2014­2024 REVISED FORECAST Volume 1: Statewide Electricity Demand in this report. #12;i ACKNOWLEDGEMENTS The demand forecast is the combined product of the hard work provided estimates for demand response program impacts and contributed to the residential forecast. Mitch

352

Last revised July 2008 Harvard University  

E-Print Network [OSTI]

Last revised July 2008 Harvard University Purchasing Card Individual Cardholder Application, Part 1 Harvard Office Mailing Address City, State, Zip Code Harvard Phone Number ( ) - 33-Digit Default General") are pleased to offer you the Purchasing Card. The Purchasing Card represents Harvard's trust in you

Chen, Yiling

353

OPTIMIZATION TOPICS LIST Revised April 2012  

E-Print Network [OSTI]

1 OPTIMIZATION TOPICS LIST Revised April 2012 For Fall 2012 and Spring 2013 we will adopt. Bertsimas and J. Tsitsiklis, Introduction to Linear Optimization, Athena Scientific, 1997 2. M. C. Ferris, O and mixed integer models · Existence of optimal solutions, optimality conditions · Branch and bound methods

Radeloff, Volker C.

354

Revised: May 2011 Fraud Prevention Policy  

E-Print Network [OSTI]

Revised: May 2011 Fraud Prevention Policy #12;Fraud Prevention Policy March 2011 1 Contents Page 1. Introduction 2 2. Basis of the Policy 3 3. Purpose and Definitions 3 4. Management and Staff Responsibilities 4 5. Adherence to University Regulations, Policies and Procedures 4 6. Code of Conduct on Commercial

Mottram, Nigel

355

Revised 4/9/13 Columbia University  

E-Print Network [OSTI]

Revised 4/9/13 Columbia University Research Financial Operations Studebaker Building 615 West 131st Giscombe Anita Accountant University-Wide (212) 854-1062 adg9@columbia.edu 499P Hamdan Tamara Director University-Wide (212) 854-1071 jk2740@columbia.edu 457 Lee-Johnson Seran Project Manager I CUMC (212) 851

Hone, James

356

Stephen Johnson Last revised November 2010  

E-Print Network [OSTI]

Stephen Johnson fonds Last revised November 2010 University of British Columbia Archives #12;Table Stephen Johnson fonds. ­ 1974-1984. 13 cm of textual records. Biographical Sketch Stephen Johnson of the projects with which Johnson was associated include Canadian Serial Directory, Journal of Canadian Library

Handy, Todd C.

357

Technical support document for proposed 1994 revision of the MEC thermal envelope requirements  

SciTech Connect (OSTI)

This report documents the development of the proposed revision of the Council of American Building Officials` (CABO) 1994 supplement to the 1993 Model Energy Code (MEC) building thermal envelope requirements for maximum component U{sub 0}-value. The 1994 amendments to the 1993 MEC were established in last year`s code change cycle and did not change the envelope requirements. The research underlying the proposed MEC revision was conducted by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE) Building Energy Standards program. The goal of this research was to develop revised guidelines based on an objective methodology that determines the most cost-effective (least total cost) combination of energy conservation measures (ECMs) (insulation levels and window types) for residential buildings. This least-cost set of ECMs was used as a basis for proposing revised MEC maximum U{sub 0}-values (thermal transmittances). ECMs include window types (for example, double-pane vinyl) and insulation levels (for example, R-19) for ceilings, walls, and floors.

Conner, C.C.; Lucas, R.G.

1994-03-01T23:59:59.000Z

358

More Opportunities for Success with the GRE revised General Test  

E-Print Network [OSTI]

More Opportunities for Success with the GRE® revised General Test University of Memphis 10/27/11 Michelle Hampton Global Client Relations ETS-Princeton, NJ #12;The GRE® revised General Test Better by DesignTM What we will cover today · Overview of the GRE® revised General Test ­ Content and Structure

Dasgupta, Dipankar

359

Firstorder belief revision Samir Chopra and Eric Martin  

E-Print Network [OSTI]

. The theories that are the target of the revisions could easily be propositional, modal S 5 , firstFirst­order belief revision Samir Chopra and Eric Martin School of Computer Science and Engineering present a model for first­order belief revision that is character­ ized by an underlying relevance

Chopra, Samir

360

Revising Specifications with CTL Properties using Bounded Model Checking  

E-Print Network [OSTI]

Revising Specifications with CTL Properties using Bounded Model Checking No Author Given that inconsistencies arise between the formal specification and some desired property. Belief Revision deals. In this paper, we propose the use of belief revision techniques in order to deal with inconsistencies in formal

Finger, Marcelo

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


361

Theory Revision in Equation Discovery Ljupco Todorovski and Saso Dzeroski  

E-Print Network [OSTI]

. Section 5 presents the experiments with revising the earth-science equation model. The last sectionTheory Revision in Equation Discovery Ljupco Todorovski and Saso Dzeroski Department of Intelligent than from an initial hypothesis in the space of equations. On the other hand, theory revision systems

Dzeroski, Saso

362

Revising by an Inconsistent Set of Formulas James Delgrande  

E-Print Network [OSTI]

Revising by an Inconsistent Set of Formulas James Delgrande School of Computing Science Simon Fraser University Burnaby, B.C. V5A 1S6 Canada jim@cs.sfu.ca Abstract This paper presents an approach to belief revision in which revision is a function from a belief state and a finite set of formulas to a new

Delgrande, James P.

363

A General Model for Epistemic State Revision using Plausibility Measures  

E-Print Network [OSTI]

A General Model for Epistemic State Revision using Plausibility Measures Jianbing Ma 1 and Weiru Liu1 Abstract. In this paper, we present a general revision model on epistemic states based on plausibility measures proposed by Fried- man and Halpern. We propose our revision strategy and give some

Liu, Weiru

364

A Conditional Logic for Iterated Belief Revision Laura Giordano  

E-Print Network [OSTI]

A Conditional Logic for Iterated Belief Revision Laura Giordano DSTA ­ Universitâ?? a del Piemonte Abstract. In this paper we propose a conditional logic IBC to rep­ resent iterated belief revision. We define an iterated belief revision system by strengthening the postulates proposed by Darwiche and Pearl

Giordano, Laura

365

Revising Beliefs on the Basis of Evidence James P. Delgrande  

E-Print Network [OSTI]

Fraser University Burnaby, B.C., Canada V5A 1S6 jim@cs.sfu.ca Abstract Approaches to belief revision mostRevising Beliefs on the Basis of Evidence James P. Delgrande School of Computing Science Simon is not categorical. In revision, one may circumvent this fact by assuming that, in some fashion or other, an agent

Delgrande, James P.

366

Workshop on Revisions to SE 2004 Mark Ardis David Budgen  

E-Print Network [OSTI]

Workshop on Revisions to SE 2004 Mark Ardis David Budgen Stevens Institute of Technology University-day workshop on needed revisions to Software Engineering 2004: Curriculum Guidelines for Undergraduate Degree Programs in Software Engineering (SE 2004). A brief overview of the current guidelines and their revision

Ardis, Mark

367

Properties of Iterated Multiple Belief Revision Dongmo Zhang  

E-Print Network [OSTI]

in the community of belief revision[2][5][9][10][13][17]. The major concern in the research is the reducibilityProperties of Iterated Multiple Belief Revision Dongmo Zhang School of Computing and Information investigate the properties of iterated multiple belief revision. We examine several typical assumptions

Zhang, Dongmo

368

Iterated Belief Revision and Conditional Logic Laura Giordano  

E-Print Network [OSTI]

/01/2001; 17:22; p.1 #12; 2 well known Triviality Result [5], that claims that no signi#12;cant belief revisionIterated Belief Revision and Conditional Logic Laura Giordano DSTA - Universit#18;a del Piemonte a conditional logic called IBC to represent iterated belief revision systems. We propose a set of postulates

Torino, UniversitĂ  di

369

Revision of Qualitative Multi-Attribute Decision Models Martin Znidarsic*  

E-Print Network [OSTI]

881 Revision of Qualitative Multi-Attribute Decision Models Martin Znidarsic* Marko Bohanec** Jozef.znidarsic@ijs.si **Email: marko.bohanec@ijs.si Abstract Data-driven revision of decision models is defined as follows: given an existing model and a set of data items, revise the model to match the data items. In this paper

Bohanec, Marko

370

Reasoning about Plan Revision in Agent Programs Natasha Alechina  

E-Print Network [OSTI]

and executing a plan a b p Plan(a;b) Natasha Alechina Reasoning about plan revision TIME 2012 5 / 46 #12;WhatReasoning about Plan Revision in Agent Programs Natasha Alechina University of Nottingham, UK TIME 2012, Leicester 14 September 2012 Natasha Alechina Reasoning about plan revision TIME 2012 1 / 46 #12

Fisher, Michael

371

On the Revision of Probabilistic Belief States Craig Boutilier  

E-Print Network [OSTI]

) and the author's 5, 7] proposal for minimal conditional (MC) revision. Spohn's model imposes additional structureOn the Revision of Probabilistic Belief States Craig Boutilier Department of Computer Science two approaches to the revision of probability functions. We assume that a probabilistic state

Boutilier, Craig

372

Nationalities of China Province of China  

E-Print Network [OSTI]

Outline Nationalities of China Province of China Language of China #12;Nationalities of China 56 of China A province is an administrative division of China. 33 province level divisions. 22 Provinces 4-level cities in China direct- controlled by the central government Beijing Tianjin Shanghai Chongqing #12

Li, Xiang

373

DWPF Development Plan. Revision 1  

SciTech Connect (OSTI)

The DWPF Development Plan is based on an evaluation process flowsheet and related waste management systems. The scope is shown in Figure 1 entitled ``DWPF Process Development Systems.`` To identify the critical development efforts, each system has been analyzed to determine: The identification of unresolved technology issues. A technology issue (TI) is one that requires basic development to resolve a previously unknown process or equipment problem and is managed via the Technology Assurance Program co-chaired by DWPF and SRTC. Areas that require further work to sufficiently define the process basis or technical operating envelop for DWPF. This activity involves the application of sound engineering and development principles to define the scope of work required to complete the technical data. The identification of the level of effort and expertise required to provide process technical consultation during the start-up and demonstration of this first of a kind plant.

Holtzscheiter, E.W.

1994-05-09T23:59:59.000Z

374

Environmental Monitoring Plan, Revision 6  

SciTech Connect (OSTI)

The purpose of environmental monitoring is to promote the early identification of, and response to, potential adverse environmental impacts associated with Lawrence Livermore National Laboratory (LLNL) operations. Environmental monitoring supports the Integrated Safety Management System (ISMS), International Organization for Standardization (ISO) 14001 Environmental Management Systems standard, and U. S. Department of Energy (DOE) Order 458.1, Radiation Protection of the Public and the Environment. Specifically, environmental monitoring enables LLNL to detect, characterize, and respond to releases from LLNL activities; assess impacts; estimate dispersal patterns in the environment; characterize the pathways of exposure to members of the public; characterize the exposures and doses to individuals and to the population; and to evaluate the potential impacts to the biota in the vicinity of LLNL. Environmental monitoring is also a major component of compliance demonstration for permits and other regulatory requirements. The Environmental Monitoring Plan (EMP) addresses the sample collection and analytical work supporting environmental monitoring to ensure the following: (1) A consistent system for collecting, assessing, and documenting environmental data of known and documented quality; (2) A validated and consistent approach for sampling and analysis of samples to ensure laboratory data meets program-specific needs and requirements within the framework of a performance-based approach for analytical laboratory work; and (3) An integrated sampling approach to avoid duplicative data collection. LLNL prepares the EMP because it provides an organizational framework for ensuring that environmental monitoring work, which is integral to the implementation of LLNL's Environmental Management System, is conducted appropriately. Furthermore, the Environmental Monitoring Plan helps LLNL ensure compliance with DOE Order 231.1 Change 2, Environment, Safety and Health Reporting, which require the publication of an annual report that characterizes the site's environmental management performance. To summarize, the general regulatory drivers for this environmental monitoring plan are ISO 14001, DOE Order 458.1, and DOE Order 231.1. The environmental monitoring addressed by this plan includes preoperational characterization and assessment, effluent and surveillance monitoring, and permit and regulatory compliance monitoring. Additional environmental monitoring is conducted at LLNL as part of compliance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA, also known as Superfund). LLNL coordinates its ground water surveillance monitoring program with the CERCLA monitoring program to gain sampling efficiencies.

Gallegos, G M; Bertoldo, N A; Blake, R G; Campbell, C G; Grayson, A R; Nelson, J C; Revelli, M A; Rosene, C A; Wegrecki, T; Williams, R A; Wilson, K R; Jones, H E

2012-03-02T23:59:59.000Z

375

Environmental Monitoring Plan, Revision 5  

SciTech Connect (OSTI)

The purpose of environmental monitoring is to promote the early identification of, and response to, potential adverse environmental impacts associated with Lawrence Livermore National Laboratory (LLNL) operations. Environmental monitoring supports the Integrated Safety Management System (ISMS), International Organization for Standardization (ISO) 14001 Environmental Management Systems standard, and U. S. Department of Energy (DOE) Order 450.1A, Environmental Protection Program. Specifically, in conformance with DOE Order 450.1A, Attachment 1, paragraph 1(b)(5), environmental monitoring enables LLNL to detect, characterize, and respond to releases from LLNL activities; assess impacts; estimate dispersal patterns in the environment; characterize the pathways of exposure to members of the public; characterize the exposures and doses to individuals and to the population; and to evaluate the potential impacts to the biota in the vicinity of LLNL. Environmental monitoring also serves to demonstrate compliance with permits and other regulatory requirements. The Environmental Monitoring Plan (EMP) addresses the sample collection and analytical work supporting environmental monitoring to ensure the following: (1) A consistent system for collecting, assessing, and documenting environmental data of known and documented quality. (2) A validated and consistent approach for sampling and analysis of samples to ensure laboratory data meets program-specific needs and requirements within the framework of a performance-based approach for analytical laboratory work. (3) An integrated sampling approach to avoid duplicative data collection. Until its cancellation in January 2003, DOE Order 5400.1 required the preparation of an environmental monitoring plan. Neither DOE Order 450.1A nor the ISO 14001 standard are as prescriptive as DOE Order 5400.1, in that neither expressly requires an EMP. However, LLNL continues to prepare the EMP because it provides an organizational framework for ensuring that this work, which is integral to the implementation of LLNL's Environmental Management System, is conducted appropriately. Furthermore, the Environmental Monitoring Plan helps LLNL ensure compliance with DOE Order 5400.5, Radiation Protection of the Public and the Environment, and DOE Order 231.1 Change 2, Environment, Safety and Health Reporting, which require the publication of an annual report that characterizes the site's environmental management performance. To summarize, the general regulatory drivers for this environmental monitoring plan are ISO 14001, DOE Order 450.1A, DOE Order 5400.5, and DOE Order 231.1. The environmental monitoring addressed by this plan includes preoperational characterization and assessment, effluent and surveillance monitoring, and permit and regulatory compliance monitoring. Additional environmental monitoring is conducted at LLNL as part of compliance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA, also known as Superfund). LLNL coordinates its ground water surveillance monitoring program with the CERCLA monitoring program to gain sampling efficiencies. (See LLNL [1992] and LLNL [2008] for information about LLNL's CERCLA activities).

Gallegos, G M; Blake, R G; Bertoldo, N A; Campbell, C G; Coty, J; Folks, K; Grayson, A R; Jones, H E; Nelson, J C; Revelli, M A; Wegrecki, T; Williams, R A; Wilson, K

2010-01-27T23:59:59.000Z

376

Guidance document for revision of DOE Order 5820.2A, Radioactive Waste Technical Support Program. Revision 1  

SciTech Connect (OSTI)

This document provides guidance for the revision of DOE Order 5820.2A, ``Radioactive Waste Management.`` Technical Working Groups have been established and are responsible for writing the revised order. The Technical Working Groups will use this document as a reference for polices and procedures that have been established for the revision process. The overall intent of this guidance is to outline how the order will be revised and how the revision process will be managed. In addition, this document outlines technical issues considered for inclusion by a Department of Energy Steering Committee.

Kudera, D.E.; McMurtrey, C.D.; Meagher, B.G.

1993-04-01T23:59:59.000Z

377

The mixed waste management facility. Project baseline revision 1.2  

SciTech Connect (OSTI)

Revision 1.2 to the Project Baseline (PB) for the Mixed Waste Management Facility (MWMF) is in response to DOE directives and verbal guidance to (1) Collocate the Decontamination and Waste Treatment Facility (DWTF) and MWMF into a single complex, integrate certain and overlapping functions as a cost-saving measure; (2) Meet certain fiscal year (FY) new-BA funding objectives ($15.3M in FY95) with lower and roughly balanced funding for out years; (3) Reduce Total Project Cost (TPC) for the MWMF Project; (4) Include costs for all appropriate permitting activities in the project TPC. This baseline revision also incorporates revisions in the technical baseline design for Molten Salt Oxidation (MSO) and Mediated Electrochemical Oxidation (MEO). Changes in the WBS dictionary that are necessary as a result of this rebaseline, as well as minor title changes, at WBS Level 3 or above (DOE control level) are approved as a separate document. For completeness, the WBS dictionary that reflects these changes is contained in Appendix B. The PB, with revisions as described in this document, were also the basis for the FY97 Validation Process, presented to DOE and their reviewers on March 21-22, 1995. Appendix C lists information related to prior revisions to the PB. Several key changes relate to the integration of functions and sharing of facilities between the portion of the DWTF that will house the MWMF and those portions that are used by the Hazardous Waste Management (HWM) Division at LLNL. This collocation has been directed by DOE as a cost-saving measure and has been implemented in a manner that maintains separate operational elements from a safety and permitting viewpoint. Appendix D provides background information on the decision and implications of collocating the two facilities.

Streit, R.D.; Throop, A.L.

1995-04-01T23:59:59.000Z

378

Common occupational classification system - revision 3  

SciTech Connect (OSTI)

Workforce planning has become an increasing concern within the DOE community as the Office of Environmental Restoration and Waste Management (ER/WM or EM) seeks to consolidate and refocus its activities and the Office of Defense Programs (DP) closes production sites. Attempts to manage the growth and skills mix of the EM workforce while retaining the critical skills of the DP workforce have been difficult due to the lack of a consistent set of occupational titles and definitions across the complex. Two reasons for this difficulty may be cited. First, classification systems commonly used in industry often fail to cover in sufficient depth the unique demands of DOE`s nuclear energy and research community. Second, the government practice of contracting the operation of government facilities to the private sector has introduced numerous contractor-specific classification schemes to the DOE complex. As a result, sites/contractors report their workforce needs using unique classification systems. It becomes difficult, therefore, to roll these data up to the national level necessary to support strategic planning and analysis. The Common Occupational Classification System (COCS) is designed to overcome these workforce planning barriers. The COCS is based on earlier workforce planning activities and the input of technical, workforce planning, and human resource managers from across the DOE complex. It provides a set of mutually-exclusive occupation titles and definitions that cover the broad range of activities present in the DOE complex. The COCS is not a required record-keeping or data management guide. Neither is it intended to replace contractor/DOE-specific classification systems. Instead, the system provides a consistent, high- level, functional structure of occupations to which contractors can crosswalk (map) their job titles.

Stahlman, E.J.; Lewis, R.E.

1996-05-01T23:59:59.000Z

379

Bicyclic graphs with maximal revised Szeged index  

E-Print Network [OSTI]

The revised Szeged index $Sz^*(G)$ is defined as $Sz^*(G)=\\sum_{e=uv \\in E}(n_u(e)+ n_0(e)/2)(n_v(e)+ n_0(e)/2),$ where $n_u(e)$ and $n_v(e)$ are, respectively, the number of vertices of $G$ lying closer to vertex $u$ than to vertex $v$ and the number of vertices of $G$ lying closer to vertex $v$ than to vertex $u$, and $n_0(e)$ is the number of vertices equidistant to $u$ and $v$. Hansen used the AutoGraphiX and made the following conjecture about the revised Szeged index for a connected bicyclic graph $G$ of order $n \\geq 6$:

Li, Xueliang

2011-01-01T23:59:59.000Z

380

Coal within a revised energy perspective  

SciTech Connect (OSTI)

The author considers the use of coal within a revised energy perspective, focusing on the factors that will drive which fuels are used to generate electricity going forward. He looks at the world markets for fossil fuels and the difficulties of predicting oil and natural gas supply and prices, as demonstrated by the variability in projections from one year to another in the EIA's Annual Energy Outlook. 4 refs., 1 tab.

Darmstadter, J. [Resources for the Future (RFF), Washington, DC (United States)

2006-07-15T23:59:59.000Z

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


381

Revision Date: 2/4/03  

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 RankCombustion | Department ofT ib l LPROJECTS IN RENEWABLEOperated inFebruaryReviewingEnergy Revised

382

National Laboratory Impact Initiative  

Broader source: Energy.gov [DOE]

The National Laboratory Impact Initiative supports the relationship between the Office of Energy Efficiency & Renewable Energy and the national laboratory enterprise.  The national laboratories...

383

National System Templates: Building Sustainable National Inventory...  

Open Energy Info (EERE)

Templates: Building Sustainable National Inventory Management Systems Jump to: navigation, search Tool Summary LAUNCH TOOL Name: National System Templates: Building Sustainable...

384

National Security  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation Desert Southwest Regionat Cornell Batteries &NST DivisionNationalEnergy

385

National Laboratory  

Office of Scientific and Technical Information (OSTI)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart ofMeasuringInformationOffice ofEnergy, OfficeUS Dept

386

National Laboratory  

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the Contributions andData andFleetEngineeringAnnual ReportNational Lab Day -

387

National Laboratory  

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the Contributions andData andFleetEngineeringAnnual ReportNational Lab Day -draws more

388

Extended and Revised Analysis of Singly Ionized Tin: Sn II  

E-Print Network [OSTI]

The electronic structure of singly ionized tin (SnII) is partly a one-electron and partly a three-electron system with ground configuration 5s25p. The excited configurations are of the type 5s2nl in the one-electron part, and 5s5p2, 5p3 and 5s5pnl (nl = 6s, 5d) in the three-electron system with quartet and doublet levels. The spectrum analyzed in this work was recorded on a 3 m normal incidence vacuum spectrograph of the Antigonish laboratory (Canada) in the wavelength region 300 - 2080 {\\AA} using a triggered spark source. The existing interpretation of the one-electron level system was confirmed in this paper, while the 2S1/2 level of the 5s5p2 configuration has been revised. The analysis has been extended to include new configurations 5p3, 5s5p5d and 5s5p6s with the aid of superposition-of-configurations Hartree-Fock calculations with relativistic corrections. The ionization potential obtained from the ng series was found to be 118023.7(5) 1/cm (14.63307(6) eV). We give a complete set of critically evaluat...

Haris, K; Tauheed, A

2013-01-01T23:59:59.000Z

389

Environmental Baseline File: National Transportation  

SciTech Connect (OSTI)

This Environmental Baseline File summarizes and consolidates information related to the national-level transportation of commercial spent nuclear fuel. Topics address include: shipmnents of commercial spent nuclear fuel based on mostly truck and mostly rail shipping scenarios; transportation routing for commercial spent nuclear fuel sites and DOE sites; radionuclide inventories for various shipping container capacities; transportation routing; populations along transportation routes; urbanized area population densities; the impacts of historical, reasonably foreseeable, and general transportation; state-level food transfer factors; Federal Guidance Report No. 11 and 12 radionuclide dose conversion factors; and national average atmospheric conditions.

NONE

1999-05-22T23:59:59.000Z

390

E-Print Network 3.0 - aviation national defense Sample Search...  

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

of a nation striving... aviation emissions from EU nations within the EU's emissions trading scheme should be investigated... '. Achieving such levels demands industrialised...

391

Hanford Site National Evnironmental Policy Act (NEPA) characterization  

SciTech Connect (OSTI)

This fourth revision of the Hanford Site National Environmental Policy (NEPA) Characterization presents current environmental data regarding the Hanford Site and its immediate environs. This information is intended for use in preparing Site-related NEPA documentation. In Chapter 4.0 are presented summations of up-to-date information about climate and meteorology, geology and hydrology, ecology, history and archaeology, socioeconomics, land use, and noise levels. Chapter 5.0 describes models, including their principal assumptions, that are to be used in simulating realized or potential impacts from nuclear materials at the Hanford Site. Included are models of radionuclides transport in groundwater and atmospheric pathways, and of radiation dose to populations via all known pathways from known initial conditions. Chapter 6.0 provides the preparer with the federal and state regulations, DOE orders and permits, and environmental standards directly applicable for environmental impact statements for the Hanford Site, following the structure Chapter 4.0. NO conclusions or recommendations are given in this report.

Cushing, C.E. (ed.)

1991-12-01T23:59:59.000Z

392

National Marine Fisheries Service | 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 on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revision hasInformation Earth's HeatMexico: EnergyMithun JumpMuscoy,Jump9 CaseNatEl JumpGypsumIranianNational

393

National Telecommunications and Information Administration | Open Energy  

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 on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revision hasInformation Earth's HeatMexico: EnergyMithun JumpMuscoy,Jump9Information National

394

BSL-3 Documents | National Nuclear Security Administration  

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNational NuclearhasAdministration77 SandiaGuidance to the Revised PartDocuments |

395

Change Request Forms | National Nuclear Security Administration  

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNational NuclearhasAdministration77 SandiaGuidance to the RevisedLinks(. ©

396

Code Tables | National Nuclear Security Administration  

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNational NuclearhasAdministration77 SandiaGuidance to the RevisedLinks(. ©Code

397

Collaboration Topics - Meshing | National Nuclear Security Administration  

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNational NuclearhasAdministration77 SandiaGuidance to the RevisedLinks(.Meshing |

398

Collaboration Topics - System Software | National Nuclear Security  

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNational NuclearhasAdministration77 SandiaGuidance to the RevisedLinks(.Meshing

399

Indian National CDM Authority | 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 on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revision hasInformation Earth's Heat JumpInc Place: Eden Prairie, Minnesota Zip: 55344ESMAPIndian National CDM

400

Transuranic waste characterization sampling and analysis methods manual. Revision 1  

SciTech Connect (OSTI)

This Methods Manual provides a unified source of information on the sampling and analytical techniques that enable Department of Energy (DOE) facilities to comply with the requirements established in the current revision of the Transuranic Waste Characterization Quality Assurance Program Plan (QAPP) for the Waste Isolation Pilot Plant (WIPP) Transuranic (TRU) Waste Characterization Program (the Program) and the WIPP Waste Analysis Plan. This Methods Manual includes all of the testing, sampling, and analytical methodologies accepted by DOE for use in implementing the Program requirements specified in the QAPP and the WIPP Waste Analysis Plan. The procedures in this Methods Manual are comprehensive and detailed and are designed to provide the necessary guidance for the preparation of site-specific procedures. With some analytical methods, such as Gas Chromatography/Mass Spectrometry, the Methods Manual procedures may be used directly. With other methods, such as nondestructive characterization, the Methods Manual provides guidance rather than a step-by-step procedure. Sites must meet all of the specified quality control requirements of the applicable procedure. Each DOE site must document the details of the procedures it will use and demonstrate the efficacy of such procedures to the Manager, National TRU Program Waste Characterization, during Waste Characterization and Certification audits.

Suermann, J.F.

1996-04-01T23:59:59.000Z

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


401

Defense Waste Processing Facility wasteform and canister description: Revision 2  

SciTech Connect (OSTI)

This document describes the reference wasteform and canister for the Defense Waste Processing Facility (DWPF). The principal changes include revised feed and glass product compositions, an estimate of glass product characteristics as a function of time after the start of vitrification, and additional data on glass leaching performance. The feed and glass product composition data are identical to that described in the DWPF Basic Data Report, Revision 90/91. The DWPF facility is located at the Savannah River Plant in Aiken, SC, and it is scheduled for construction completion during December 1989. The wasteform is borosilicate glass containing approximately 28 wt % sludge oxides, with the balance consisting of glass-forming chemicals, primarily glass frit. Borosilicate glass was chosen because of its stability toward reaction with potential repository groundwaters, its relatively high ability to incorporate nuclides found in the sludge into the solid matrix, and its reasonably low melting temperature. The glass frit contains approximately 71% SiO/sub 2/, 12% B/sub 2/O/sub 3/, and 10% Na/sub 2/O. Tests to quantify the stability of DWPF waste glass have been performed under a wide variety of conditions, including simulations of potential repository environments. Based on these tests, DWPF waste glass should easily meet repository criteria. The canister is filled with about 3700 lb of glass which occupies 85% of the free canister volume. The filled canister will generate approximately 690 watts when filled with oxides from 5-year-old sludge and precipitate from 15-year-old supernate. The radionuclide activity of the canister is about 233,000 curies, with an estimated radiation level of 5600 rad/hour at the canister surface. 14 figs., 28 tabs.

Baxter, R.G.

1988-12-01T23:59:59.000Z

402

WILDLIFE REFUGE BACA NATIONAL  

E-Print Network [OSTI]

Rio Grande National Forest Rio Grande National Forest San Isabel National Forest Solar Energy Study Great Sand Dunes National Preserve 285 160 160 160 285 Carson National Forest Grand Mesa National Forest Note 2) (As of 6/5/2009) Solar Energy Study Area (As of 6/5/2009) BLM Lands Being Analyzed for Solar

Laughlin, Robert B.

403

Revised 4/15/2002 _____________________________ Environment, Health, & Safety _________ __________________  

E-Print Network [OSTI]

Revised 4/15/2002 _____________________________ Environment, Health, & Safety, medium, and large dewars o Recognize policy concerning transporting dewars in an elevator Written Exam

Eisen, Michael

404

,"New York Dry Natural Gas Reserves Revision Decreases (Billion...  

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

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","New York Dry Natural Gas Reserves Revision Decreases (Billion Cubic Feet)",1,"Annual",2013...

405

,"New York Dry Natural Gas Reserves Revision Increases (Billion...  

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

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","New York Dry Natural Gas Reserves Revision Increases (Billion Cubic Feet)",1,"Annual",2013...

406

Ohio Coalbed Methane Proved Reserves Revision Increases (Billion...  

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

W Withheld to avoid disclosure of individual company data. Release Date: 1242014 Next Release Date: 12312015 Referring Pages: Coalbed Methane Reserves Revision Increases...

407

,"U.S. Coalbed Methane Proved Reserves Revision Increases (Billion...  

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

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","U.S. Coalbed Methane Proved Reserves Revision Increases (Billion Cubic Feet)",1,"Annual",2013...

408

,"U.S. Coalbed Methane Proved Reserves Revision Decreases (Billion...  

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

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","U.S. Coalbed Methane Proved Reserves Revision Decreases (Billion Cubic Feet)",1,"Annual",2013...

409

BONNEVILLE POWER ADMINISTRATION'S REQUEST FOR APPROVAL 1 OF REVISED...  

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

revised Oversupply Management Protocol tariff amendment for filing effective March 31, 2013 through September 30, 2015 and approve the tariff filing as providing...

410

Revised DOE sku calculations | Department of Energy  

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power.pdf11-161-LNG |September 15,2015Department ofRequirementsEnergyJ u lReturnBuildingsofRevised

411

ADR Revised Policy | Department of Energy  

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergy Cooperation |South Valley ResponsibleSubmissionofDepartment of Energy 6:ofPolicyRevised

412

NV/YMP radiological control manual, Revision 2  

SciTech Connect (OSTI)

The Nevada Test Site (NTS) and the adjacent Yucca Mountain Project (YMP) are located in Nye County, Nevada. The NTS has been the primary location for testing nuclear explosives in the continental US since 1951. Current activities include operating low-level radioactive and mixed waste disposal facilities for US defense-generated waste, assembly/disassembly of special experiments, surface cleanup and site characterization of contaminated land areas, and non-nuclear test operations such as controlled spills of hazardous materials at the hazardous Materials (HAZMAT) Spill Center (HSC). Currently, the major potential for occupational radiation exposure is associated with the burial of low-level nuclear waste and the handling of radioactive sources. Planned future remediation of contaminated land areas may also result in radiological exposures. The NV/YMP Radiological Control Manual, Revision 2, represents DOE-accepted guidelines and best practices for implementing Nevada Test Site and Yucca Mountain Project Radiation Protection Programs in accordance with the requirements of Title 10 Code of Federal Regulations Part 835, Occupational Radiation Protection. These programs provide protection for approximately 3,000 employees and visitors annually and include coverage for the on-site activities for both personnel and the environment. The personnel protection effort includes a DOE Laboratory Accreditation Program accredited dosimetry and personnel bioassay programs including in-vivo counting, routine workplace air sampling, personnel monitoring, and programmatic and job-specific As Low as Reasonably Achievable considerations.

Gile, A.L. [comp.] [comp.

1996-11-01T23:59:59.000Z

413

Updating Maryland's Sea-level Rise  

E-Print Network [OSTI]

Updating Maryland's Sea-level Rise Projections Scientific and Technical Working Group Maryland Climate Change Commission June 26, 2013 #12;Sea-level Rise Expert Group Donald F. Boesch* , University-author of the National Assessment Scenarios report Author of paper(s) on recent sea-level rise ~ Author contributing

Ezer,Tal

414

Implementation of a level 1 trigger system using high speed serial (VXS) techniques for the 12GeV high luminosity experimental programs at Thomas Jefferson National Accelerator Facility  

SciTech Connect (OSTI)

We will demonstrate a hardware and firmware solution for a complete fully pipelined multi-crate trigger system that takes advantage of the elegant high speed VXS serial extensions for VME. This trigger system includes three sections starting with the front end crate trigger processor (CTP), a global Sub-System Processor (SSP) and a Trigger Supervisor that manages the timing, synchronization and front end event readout. Within a front end crate, trigger information is gathered from each 16 Channel, 12 bit Flash ADC module at 4 nS intervals via the VXS backplane, to a Crate Trigger Processor (CTP). Each Crate Trigger Processor receives these 500 MB/S VXS links from the 16 FADC-250 modules, aligns skewed data inherent of Aurora protocol, and performs real time crate level trigger algorithms. The algorithm results are encoded using a Reed-Solomon technique and transmission of this Level 1 trigger data is sent to the SSP using a multi-fiber link. The multi-fiber link achieves an aggregate trigger data transfer rate to the global trigger at 8 Gb/s. The SSP receives and decodes Reed-Solomon error correcting transmission from each crate, aligns the data, and performs the global level trigger algorithms. The entire trigger system is synchronous and operates at 250 MHz with the Trigger Supervisor managing not only the front end event readout, but also the distribution of the critical timing clocks, synchronization signals, and the global trigger signals to each front end readout crate. These signals are distributed to the front end crates on a separate fiber link and each crate is synchronized using a unique encoding scheme to guarantee that each front end crate is synchronous with a fixed latency, independent of the distance between each crate. The overall trigger signal latency is <3 uS, and the proposed 12GeV experiments at Jefferson Lab require up to 200KHz Level 1 trigger rate.

C. Cuevas, B. Raydo, H. Dong, A. Gupta, F.J. Barbosa, J. Wilson, W.M. Taylor, E. Jastrzembski, D. Abbott

2009-11-01T23:59:59.000Z

415

Features, Events, and Processes: system Level  

SciTech Connect (OSTI)

The purpose of this analysis report is to evaluate and document the inclusion or exclusion of the system-level features, events, and processes (FEPs) with respect to modeling used to support the total system performance assessment for the license application (TSPA-LA). A screening decision, either Included or Excluded, is given for each FEP along with the technical basis for screening decisions. This information is required by the U.S. Nuclear Regulatory Commission (NRC) at 10 CFR 63.113 (d, e, and f) (DIRS 156605). The system-level FEPs addressed in this report typically are overarching in nature, rather than being focused on a particular process or subsystem. As a result, they are best dealt with at the system level rather than addressed within supporting process-level or subsystem-level analyses and models reports. The system-level FEPs also tend to be directly addressed by regulations, guidance documents, or assumptions listed in the regulations; or are addressed in background information used in development of the regulations. For included FEPs, this analysis summarizes the implementation of the FEP in the TSPA-LA (i.e., how the FEP is included). For excluded FEPs, this analysis provides the technical basis for exclusion from the TSPA-LA (i.e., why the FEP is excluded). The initial version of this report (Revision 00) was developed to support the total system performance assessment for site recommendation (TSPA-SR). This revision addresses the license application (LA) FEP List (DIRS 170760).

D. McGregor

2004-10-15T23:59:59.000Z

416

Low-Level Waste Regulation: Putting Principles Into Practice - 13297 - The Richard S. Hodes, M.D., Honor Lecture Award  

SciTech Connect (OSTI)

In carrying out its mission to ensure the safe use of radioactive materials for beneficial civilian purposes while protecting people and the environment, the U.S. Nuclear Regulatory Commission (NRC) adheres to its Principles of Good Regulation. The Principles-Independence, Openness, Efficiency, Clarity, and Reliability-apply to the agency as a whole in its decision-making and to the individual conduct of NRC employees. This paper describes the application of the Principles in a real-life staff activity, a guidance document used in the NRC's low-level radioactive waste (LLW) program, the Concentration Averaging and Encapsulation Branch Technical Position (CA BTP). The staff's process to revise the document, as well as the final content of the document, were influenced by following the Principles. For example, consistent with the Openness Principle, the staff conducted a number of outreach activities and received many comments on three drafts of the document. Stakeholder comments affected the final staff positions in some cases. The revised CA BTP, once implemented, is expected to improve management and disposal of LLW in the United States. Its positions have an improved nexus to health and safety; are more performance-based than previously, thus providing licensees with options for how they achieve the required outcome of protecting an inadvertent human intruder into a disposal facility; and provide for disposal of more sealed radioactive sources, which are a potential threat to national security. (author)

Kennedy, James E. [Low-Level Waste Branch Division of Waste Management and Environmental Protection, U.S. Nuclear Regulatory Commission, Washington, DC, 20555-0001 (United States)] [Low-Level Waste Branch Division of Waste Management and Environmental Protection, U.S. Nuclear Regulatory Commission, Washington, DC, 20555-0001 (United States)

2013-07-01T23:59:59.000Z

417

Heavy Ion Fusion Science Virtual National Laboratory  

E-Print Network [OSTI]

to today's large NP accelerators like GSI-FAIR, RHIC economical for 1-2 GWe baseload power plants. Heavy chambers. · Competitive economics: projected in several power plant studies and with no high levelSlide 1 Heavy Ion Fusion Science Virtual National Laboratory Briefing for the National Academy

418

Policy Flash 2013-38 Revised Merit Review Guide For Financial...  

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

8 Revised Merit Review Guide For Financial Assistance Policy Flash 2013-38 Revised Merit Review Guide For Financial Assistance Attached is Policy Flash 2013-38 Revised Merit Review...

419

Design/installation and structural integrity assessment of Bethel Valley low-level waste collection and transfer system upgrade for Building 3092 (Central Off-Gas Scrubber Facility) at Oak Ridge National Laboratory  

SciTech Connect (OSTI)

This document describes and assesses planned modifications to be made to the Building 3092 Central Off-Gas Scrubber Facility of the Oak Ridge National Laboratory, Oak Ridge, Tennessee. The modifications are made in responsible to the requirements of 40CFR264 Subpart J, relating to environmental protection requirements for buried tank systems. The modifications include the provision of a new scrubber recirculation tank in a new, below ground, lines concrete vault, replacing and existing recirculation sump that does not provide double containment. A new buried, double contained pipeline is provided to permit discharge of spent scrubber recirculation fluid to the Central Waste Collection Header. The new vault, tank, and discharge line are provided with leak detection and provisions to remove accumulated liquid. New scrubber recirculation pumps, piping, and accessories are also provided. This assessment concludes that the planned modifications comply with applicable requirements of 40CFR264 Subpart J, as set forth in Appendix F to the Federal Facility Agreement, Docket No. 89-04-FF, covering the Oak Ridge Reservation.

NONE

1995-01-01T23:59:59.000Z

420

Design/Installation and Structural Integrity Assessment of the Bethel Valley Low-Level Waste Collection and Transfer System Upgrade for Building 3544 (Process Waste Treatment Plant) at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

This document describes and assesses planned modifications to be made to the Building 3544 Process Waste Treatment Plant of the Oak Ridge National Laboratory, Oak Ridge, Tennessee. The modifications are made in response to the requirements of the Federal Facility Agreement (FFA) relating to environmental protection requirements for tank systems. The modifications include the provision of a new double contained LLW line replacing an existing buried line that does not provide double containment. This new above ground, double contained pipeline is provided to permit discharge of treated process waste fluid to an outside truck loading station. The new double contained discharge line is provided with leak detection and provisions to remove accumulated liquid. An existing LLW transfer pump, concentrated waste tank, piping and accessories are being utilized, with the addition of a secondary containment system comprised of a dike, a chemically resistant internal coating on the diked area surfaces and operator surveillance on a daily basis for the diked area leak detection. This assessment concludes that the planned modifications comply with applicable requirements of Federal Facility Agreement, Docket No. 89-04-FF, covering the Oak Ridge Reservation.

NONE

1996-12-01T23:59:59.000Z

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


421

Revised Date September 18, 2013 Capital Project Planning  

E-Print Network [OSTI]

. Identify Funding Funding Source(s) 2. Cost Estimate Information (from preliminary estimate form): 3_- Project Name Cost Estimate Low Range High Range #12;Revised Date ­ January 25, 2013 Priority RankingRevised Date ­ September 18, 2013 Capital Project Planning Project Approval Form All capital

422

Development of Revised Energy Standards for Texas Buildings: Preliminary Results  

E-Print Network [OSTI]

for Energy Studies (CES) at The University of Texas at Austin is revising and updating the nonresidential building portion of the Energy Conservation Manual. The proposed revision is a Texas-specific adaptation of ASHRAE Standard 90.1P ("Energy Efficient...

Hunn, B. D.; Jones, J. W.; Silver, S. C.

1988-01-01T23:59:59.000Z

423

AIPS Memo 85 DDT Revised and AIPSMark (93) Measurements  

E-Print Network [OSTI]

AIPS Memo 85 DDT Revised and AIPSMark (93) Measurements Eric W. Greisen February 9, 1994 Abstract The AIPS certification and benchmarking package known as DDT has been revised to replace the obsolete self of performance tests made with the 15JAN94 release of AIPS using both the old and new versions of DDT

Groppi, Christopher

424

Revised: March 1, 2005 Page 1 UCSB Environmental Health & Safety  

E-Print Network [OSTI]

safe for transport. #12;Revised: March 1, 2005 Page 3 · Abandoned and unlabeled chemical containersRevised: March 1, 2005 Page 1 UCSB Environmental Health & Safety Emergency Response Guidelines spill-cleanups, odor complaints, pickup of abandoned chemicals and related alarms (see Attachment). EH

Bigelow, Stephen

425

1 INTRODUCTION Japanese standard Law was revised in 1998. The  

E-Print Network [OSTI]

a situation which does not comply with other requirements of the Building Standard Law, concerning fire safety, Ministry of Construction, Japan ABSTRACT: Japanese Building Standard Law was revised in 1998. The highlight1 INTRODUCTION Japanese standard Law was revised in 1998. The highlight related to the structural

Spencer Jr., B.F.

426

Revised 1997 Retail Electricity Price Forecast Principal Author: Ben Arikawa  

E-Print Network [OSTI]

Revised 1997 Retail Electricity Price Forecast March 1998 Principal Author: Ben Arikawa Electricity 1997 FORE08.DOC Page 1 CALIFORNIA ENERGY COMMISSION ELECTRICITY ANALYSIS OFFICE REVISED 1997 RETAIL ELECTRICITY PRICE FORECAST Introduction The Electricity Analysis Office of the California Energy Commission

427

Belief Revision with Unreliable Observations Craig Boutilier \\Lambda  

E-Print Network [OSTI]

Belief Revision with Unreliable Observations Craig Boutilier \\Lambda Dept. Computer Science University of British Columbia Vancouver, British Columbia Canada, V6T 1W5 cebly@cs.ubc.ca Nir Friedman yz@cs.cornell.edu Abstract Research in belief revision has been dominated by work that lies firmly within the classic AGM

Friedman, Nir

428

Belief Revision in Horn Theories$ James P. Delgrandea  

E-Print Network [OSTI]

Belief Revision in Horn Theories$ James P. Delgrandea , Pavlos Peppasb,c a School of Computing Science, Simon Fraser University, Burnaby, B.C., Canada V5A 1S6 b Centre for Quantum Computation Administration, University of Patras, Patras 265 00, Greece Abstract This paper investigates belief revision

Delgrande, James P.

429

Parallel Belief Revision James Delgrande and Yi Jin  

E-Print Network [OSTI]

Parallel Belief Revision James Delgrande and Yi Jin School of Computing Science Simon Fraser University Burnaby, B.C. V5A 1S6 Canada {jim,yij}@cs.sfu.ca Abstract A recalcitrant problem in approaches to iterated belief revi- sion is that, after first revising by a formula and then by a formula

Delgrande, James P.

430

Revised October 2013 JO RAE WRIGHT FELLOWSHIP for  

E-Print Network [OSTI]

Revised October 2013 JO RAE WRIGHT FELLOWSHIP for OUTSTANDING WOMEN in SCIENCE Application for Academic Year 2014-2015 The Jo Rae Wright Fellowship for Outstanding Women in Science was created in memory the deadline published online will not be accepted. #12;Revised October 2013 JO RAE WRIGHT FELLOWSHIP (choose

Ferrari, Silvia

431

DRAFT NISTIR 7628 Revision 1 Guidelines for Smart Grid Cybersecurity  

E-Print Network [OSTI]

DRAFT NISTIR 7628 Revision 1 Guidelines for Smart Grid Cybersecurity: Vol. 2, Privacy and the Smart Grid The Smart Grid Interoperability Panel ­ Smart Grid Cybersecurity Committee #12;DRAFT NISTIR 7628 Revision 1 Guidelines for Smart Grid Cybersecurity: Vol. 2, Privacy and the Smart Grid The Smart Grid

432

Photovoltaic Reliability and Engineering (Revised) (Fact Sheet)  

SciTech Connect (OSTI)

Capabilities fact sheet for the National Center for Photovoltaics: Photovoltaic Reliability and Engineering. One-sided sheet that includes Scope, Core Competencies and Capabilities, and Contact/Web information.

Not Available

2011-06-01T23:59:59.000Z

433

Notice of Intent to Revise DOE O 457.1, Nuclear Counterterrorism  

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

Intent is to revise DOE O 457.1 and include the content of DOE M 457.1-1 as appendices to the revised order.

2013-02-07T23:59:59.000Z

434

E-Print Network 3.0 - assurance program revision Sample Search...  

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

Technologies and Information Sciences 3 Revised Statement of Investment Policies and Guidelines at BonaVista Asset Management Ltd. August 16, 2010 Summary: . Revised Statement of...

435

POLICY FLASH 2014-25 Revision to the Procurement Strategy Panel...  

Energy Savers [EERE]

5 Revision to the Procurement Strategy Panel (PSP) Briefing Process POLICY FLASH 2014-25 Revision to the Procurement Strategy Panel (PSP) Briefing Process For DOE questions...

436

Policy Flash 2013-66 Revised Merit Review Guide for Financial...  

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

66 Revised Merit Review Guide for Financial Assistance, JULY 2013 Policy Flash 2013-66 Revised Merit Review Guide for Financial Assistance, JULY 2013 Questions concerning this...

437

EIS-0288-S1: Revision to EPA Notice of Availability Draft Supplemental...  

Energy Savers [EERE]

288-S1: Revision to EPA Notice of Availability Draft Supplemental Environmental Impact Statement EIS-0288-S1: Revision to EPA Notice of Availability Draft Supplemental...

438

Voluntary Protection Program Review, Pacific Northwest National Laboratory- June 2009  

Broader source: Energy.gov [DOE]

Evaluation to determine whether the Pacific Northwest National Laboratory is continuing to perform at a level deserving DOE-VPP Star recognition.

439

Voluntary Protection Program Onsite Review, Idaho National Laboratory- October 2009  

Broader source: Energy.gov [DOE]

Evaluation to determine whether the Idaho National Laboratory is continuing to perform at a level deserving DOE-VPP Star recognition.

440

Voluntary Protection Program Onsite Review, Bechtel National Incorporated- October 2008  

Broader source: Energy.gov [DOE]

Evaluation to determine whether the Bechtel National Incorporated Waste Treatment Plant is continuing to perform at a level deserving DOE-VPP Star recognition.

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


441

A Review of Criticality Accidents 2000 Revision  

SciTech Connect (OSTI)

Criticality accidents and the characteristics of prompt power excursions are discussed. Sixty accidental power excursions are reviewed. Sufficient detail is provided to enable the reader to understand the physical situation, the chemistry and material flow, and when available the administrative setting leading up to the time of the accident. Information on the power history, energy release, consequences, and causes are also included when available. For those accidents that occurred in process plants, two new sections have been included in this revision. The first is an analysis and summary of the physical and neutronic features of the chain reacting systems. The second is a compilation of observations and lessons learned. Excursions associated with large power reactors are not included in this report.

Thomas P. McLaughlin; Shean P. Monahan; Norman L. Pruvost; Vladimir V. Frolov; Boris G. Ryazanov; Victor I. Sviridov

2000-05-01T23:59:59.000Z

442

Sandia Site Office Assessment of Activity-Levell Work Planning...  

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

of Activity-Level Work Planning and Control at Sandia National Laboratories New Mexico (SNL) Dates of Activity : 02142011 - 02182011 Report Preparer: Patricia Williams...

443

Nevada National Security Site  

Broader source: Energy.gov [DOE]

HISTORYIn 1950, President Truman established what is now known as the Nevada National Security Site (NNSS) to perform nuclear weapons testing activities.  In support of national defense initiatives...

444

National Science Bowl Finals  

SciTech Connect (OSTI)

National Science Bowl finals and awards at the National Building Museum in Washington D.C. Monday 5/3/2010

2010-05-03T23:59:59.000Z

445

National Energy Policy (Complete)  

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

Energy Policy May 2001 Report of the National Energy Policy Development Group Reliable, Affordable, and Environmentally Sound Energy for America's Future Report of the National...

446

National Science Bowl Finals  

ScienceCinema (OSTI)

National Science Bowl finals and awards at the National Building Museum in Washington D.C. Monday 5/3/2010

None

2010-09-01T23:59:59.000Z

447

National Nuclear Security Administration  

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

and Related Structures within TA-3 at Los Alamos National Laboratory, Los Alamos, New Mexico U. S. Department of Energy National Nuclear Security Administration Los Alamos Area...

448

University of Washington Focus the Nation Panel: Climate Change Impacts on Indigenous Populations  

E-Print Network [OSTI]

biodiesel and solar energy), and they have revised their commercial dredging policy so that only vacuum that because of their dependence on local resources and a life-way that is adapted to the cold arctic climateUniversity of Washington Focus the Nation Panel: Climate Change Impacts on Indigenous Populations 1

Rigor, Ignatius G.

449

National Ignition Facility Cryogenic Target Systems Interim Management Plan  

SciTech Connect (OSTI)

Restricted availability of funding has had an adverse impact, unforeseen at the time of the original decision to projectize the National Ignition Facility (NIF) Cryogenic Target Handling Systems (NCTS) Program, on the planning and initiation of these efforts. The purpose of this document is to provide an interim project management plan describing the organizational structure and management processes currently in place for NCTS. Preparation of a Program Execution Plan (PEP) for NCTS has been initiated, and a current draft is provided as Attachment 1 to this document. The National Ignition Facility is a multi-megajoule laser facility being constructed at Lawrence Livermore National Laboratory (LLNL) by the National Nuclear Security Administration (NNSA) in the Department of Energy (DOE). Its primary mission is to support the Stockpile Stewardship Program (SSP) by performing experiments studying weapons physics, including fusion ignition. NIF also supports the missions of weapons effects, inertial fusion energy, and basic science in high-energy-density physics. NIF will be operated by LLNL under contract to the University of California (UC) as a national user facility. NIF is a low-hazard, radiological facility, and its operation will meet all applicable federal, state, and local Environmental Safety & Health (ES&H) requirements. The NCTS Interim Management Plan provides a summary of primary design criteria and functional requirements, current organizational structure, tracking and reporting procedures, and current planning estimates of project scope, cost, and schedule. The NIF Director controls the NIF Cryogenic Target Systems Interim Management Plan. Overall scope content and execution schedules for the High Energy Density Physics Campaign (SSP Campaign 10) are currently undergoing rebaselining and will be brought into alignment with resources expected to be available throughout the NNSA Future Years National Security Plan (FYNSP). The revised schedule for delivering this system will be decided at the national level, based on experiment campaign requirement dates that will be derived through this process. The current milestone date for achieving indirect-drive ignition on the NIF is December 2010. Maintaining this milestone requires that the cryogenic systems be complete and available for fielding experiments early enough that the planned experimental campaigns leading up to ignition can be carried out. The capability of performing non-ignition cryogenic experiments is currently required by March 2006, when the NIF's first cluster of beams is operational. Plans for cryogenic and non-cryogenic experiments on the NIF are contained in NNSA's Campaign 10 Program Plans for Ignition (MTE 10.1) and High Energy Density Sciences (MTE 10.2). As described in this document, the NCTS Program Manager is responsible for managing NIF Cryogenic Target Systems development, engineering, and deployment. Through the NIF Director, the NCTS Program Manager will put in place an appropriate Program Execution Plan (draft attached) at a later time consistent with the maturing and funding these efforts. The PEP will describe management methods for carrying out these activities.

Warner, B

2002-04-25T23:59:59.000Z

450

OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY  

E-Print Network [OSTI]

1/17/2008 OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY In 2002, the National Research distribution and monitoring systems. Over 20 contaminants of concern were evaluated over the course Guidance Levels for Selected Submarine Contaminants. #12;1/17/2008 OAK RIDGE NATIONAL LABORATORY U. S

451

National Poverty Center Working Paper Series October 2005  

E-Print Network [OSTI]

National Poverty Center Working Paper Series #05-24 October 2005 The Level and Composition at the National Poverty Center Working Paper Series index at: http of the author(s) and do not necessarily reflect the view of the National Poverty Center or any sponsoring agency

Shyy, Wei

452

National Renewable Energy Laboratory  

E-Print Network [OSTI]

National Renewable Energy Laboratory Innovation for Our Energy Future ponsorship Format Reversed Color:White rtical Format Reversed-A ertical Format Reversed-B National Renewable Energy Laboratory National Renewable Energy Laboratory Innovation for Our Energy Future National Renewable Energy Laboratory

453

Solar Decathlon: Powered by the Sun (Revised)  

SciTech Connect (OSTI)

The Solar Decathlon is a collegiate competition to design and build the most energy efficient, solar-powered house. It is also an event on the National Mall in Washington D.C. to which the public is invited. This gatefold brochure describes the Solar Decathlon 2005 competition and event, including a schedule of activities.

Not Available

2005-08-01T23:59:59.000Z

454

Design/installation and structural integrity assessment under the Federal Facility Agreement for Bethel Valley Low-Level Waste Collection and Transfer System upgrade for Building 2026 (High Radiation Level Analytical Laboratory) and Building 2099 (Monitoring and Control Station) at Oak Ridge National Laboratory  

SciTech Connect (OSTI)

This document presents a Design/Installation and Structural Integrity Assessment for a replacement tank system for portions of the Bethel Valley Low Level Waste (LLW) System, located at the Oak Ridge Reservation, Oak Ridge, Tennessee. This issue of the assessment covers the design aspects of the replacement tank system, and certifies that the design has sufficient structural integrity and is acceptable for the storing or treating of hazardous and/or radioactive substances. The present issue identifies specific activities that must be completed during the fabrication, installation, and testing of the replacement tank system in order to provide assurance that the final installation complies with governing requirements. Portions of the LLW system are several decades old, or older, and do not comply with current environmental protection regulations. Several subsystems of the LLW system have been designated to receive a state-of-the-art replacement and refurbishment. One such subsystem serves Building 2026, the High Radiation Level Analytical Laboratory. This assessment focuses on the scope of work for the Building 2026 replacement LLW Collection and Transfer System, including the provision of a new Monitoring and Control Station (Building 2099) to receive, store, and treat (adjust pH) low level radioactive waste.

Not Available

1994-10-01T23:59:59.000Z

455

System-Level Virtualization for High Performance Computing Geoffroy Vallee  

E-Print Network [OSTI]

System-Level Virtualization for High Performance Computing Geoffroy Vall´ee Oak Ridge National Laboratory Oak Ridge, TN 37830, USA valleegr@ornl.gov Thomas Naughton Oak Ridge National Laboratory Oak Ridge, TN 37830, USA naughtont@ornl.gov Christian Engelmann Oak Ridge National Laboratory Oak Ridge, TN

Engelmann, Christian

456

Supporting documentation for the 1997 revision to the DOE Insulation Fact Sheet  

SciTech Connect (OSTI)

The Department of Energy (DOE) Insulation Fact Sheet has been revised to reflect developments in energy conservation technology and the insulation market. A nationwide insulation cost survey was made by polling insulation contractors and builders, and the results are reported here. These costs, along with regional weather data, regional fuel costs, and fuel-specific system efficiencies were used to produce recommended insulation levels for new and existing houses. This report contains all of the methodology, algorithms, assumptions, references, and data resources that were used to produce the 1997 DOE Insulation Fact Sheet.

Stovall, T.K.

1997-08-22T23:59:59.000Z

457

Notice of Intent to Revise DOE O 475.2A, Identifying Classified Information  

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

The revision will incorporate changes that were identified during the 1-year review after initial issuance

2014-03-06T23:59:59.000Z

458

Multiple Semi-Revision in Possibilistic Logic Guilin Qi, Weiru Liu, David A. Bell  

E-Print Network [OSTI]

a set of inconsistent belief bases [2­5, 11, 13­15, 19, 23]. Fuhrmann in [11] considered a multiple semi-revisionMultiple Semi-Revision in Possibilistic Logic Guilin Qi, Weiru Liu, David A. Bell School. Semi-revision is a model of belief change that differs from revision in that a new formula

Liu, Weiru

459

Mojave National Preserve Joshua Tree National Park  

E-Print Network [OSTI]

Forest (SBNF) Angeles National Forest (ANF) Cleveland National Forest (CNF) CNF CNF SBNF ANF CACA 049111°0'0"N 34°0'0"N 34°0'0"N 33°0'0"N 33°0'0"N California Desert Conservation Area BLM Solar Energy Project Contingent Corridor Deleted Corridor Land Status BLM National Park Service Forest Service Military USFWS

Laughlin, Robert B.

460

Sandia National Laboratories: National Rotor Testbed Functional...  

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

of the National Rotor Testbed: An Aeroelastically Relevant Research-Scale Wind Turbine Rotor." Approximately 60 researchers from various institutions and countries attended...

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


461

Revised 2/6/11 _______________________________Environment, Health, & Safety_______________________________  

E-Print Network [OSTI]

suitable field safety and operational procedures · Practice safe decontamination · Adopt work practicesRevised 2/6/11 _______________________________Environment, Health, & Safety (through Safety Compliance Management) http://www.scm-safety.com/classroom_training.html · Cal Inc Training

Eisen, Michael

462

Revised 1/17/2013 ________________________ __ Environment, Health, & Safety _____ _ __________  

E-Print Network [OSTI]

Revised 1/17/2013 ________________________ __ Environment, Health, & Safety _____ _ __________ Training Program EHS 278 ~ Ladder Safety Course Syllabus Subject Category: Occupational Safety Course and set up ladders in order to perform work at LBNL. Course Objectives: After successful completion

Eisen, Michael

463

Use a Vent Condenser to Recover Flash Steam Energy (Revised)  

SciTech Connect (OSTI)

This revised ITP tip sheet on vent condenser to recover flash steam energy provides how-to advice for improving industrial steam systems using low-cost, proven practices and technologies.

Not Available

2006-05-01T23:59:59.000Z

464

THIRD EDITION (REVISED PRINTING) SERVICE-ORIENTED COMPUTING  

E-Print Network [OSTI]

....................................................................................................10 1.3 Service-Oriented Architecture and ComputingTHIRD EDITION (REVISED PRINTING) SERVICE-ORIENTED COMPUTING AND WEB SOFTWARE INTEGRATION FROM) ............................................................................................................xv Part I Distributed Service-Oriented Software Development and Web Data Management

Chen, Yinong

465

Revised7/14/10 DEPARTMENT OF GEOLOGY & GEOPHYSICS  

E-Print Network [OSTI]

. If the cause of this petition is to prevent delay in graduation, record on page 2 your project schedule for each semester until your expected date of graduation.) _____________________________________________________________________________________________ _____________________________________________________________________________________________ _____________________________________________________________________________________________ _____________________________________________________________________________________________ _____________________________________________________________________________________________ Current graduation: ______________________________ Revised graduation: ____________________________ Month

Johnson, Cari

466

Working Document: Revisions as of July 10, 2001  

E-Print Network [OSTI]

Working Document: Revisions as of July 10, 2001 Summary of Multiagent Planning Architecture MPA Planning-Cell Managers 15 5.1 Meta Planning-Cell Manager Agents: Search Manager and Critic Manager . . . . . . . . . . . . . . 22 6.2.2 Scheduler Agent

Wilkins, David E.

467

Working Document: Revisions as of October 9, 1998  

E-Print Network [OSTI]

Working Document: Revisions as of October 9, 1998 Multiagent Planning Architecture MPA Version 1 and Agent Library . . . . . . . . . . . . . . . . . . . . . 10 3.2 Managing Agents-Cell Managers 27 5.1 Meta Planning-Cell Manager . . . . . . . . . . . . . . . . . . . . . . . . . . 28 5

Wilkins, David E.

468

Working Document: Revisions as of July 10, 2001  

E-Print Network [OSTI]

Working Document: Revisions as of July 10, 2001 Summary of Multiagent Planning Architecture MPA Planning­Cell Managers 15 5.1 Meta Planning­Cell Manager Agents: Search Manager and Critic Manager . . . . . . . . . . . . . . 22 6.2.2 Scheduler Agent

Wilkins, David E.

469

Working Document: Revisions as of October 9, 1998  

E-Print Network [OSTI]

Working Document: Revisions as of October 9, 1998 Summary of Multiagent Planning Architecture MPA Planning-Cell Managers 16 5.1 Meta Planning-Cell Manager and Scheduling . . . . . . . . . . . . . . . . . . . . . . . . . . . . 24 6.2.1 Planner Agents: Search Manager

Wilkins, David E.

470

Questions and answers based on revised 10 CFR Part 20  

SciTech Connect (OSTI)

NUREG/CR-6204 is a collection of questions and answers that were originally issued in seven sets and which pertain to revised 10 CFR Part 20. The questions came from both outside and within the NRC. The answers were compiled and provided by NRC staff within the offices of Nuclear Reactor Regulation, Nuclear Material Safety and Safeguards, Nuclear Regulatory Research, the Office of State Programs, and the five regional offices. Although all of the questions and answers have been reviewed by attorneys in the NRC Office of the General Counsel, they do not constitute official legal interpretations relevant to revised 10 CFR Part 20. The questions and answers do, however, reflect NRC staff decisions and technical options on aspects of the revised 10 CFR Part 20 regulatory requirements. This NUREG is being made available to encourage communication among the public, industry, and NRC staff concerning the major revisions of the NRC`s standards for protection against radiation.

Borges, T.; Stafford, R.S.; Lu, P.Y. [Oak Ridge National Lab., TN (United States); Carter, D. [Nuclear Regulatory Commission, Washington, DC (United States)

1994-05-01T23:59:59.000Z

471

CEQ Extends Comment Period on Revised Draft Guidance on Consideration...  

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

draft guidance on consideration of greenhouse gas (GHG) emissions and the effects of climate change in NEPA reviews. The comment period now ends on March 25, 2015. The revised...

472

Wyoming Coalbed Methane Proved Reserves Revision Decreases (Billion...  

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

Decreases (Billion Cubic Feet) Wyoming Coalbed Methane Proved Reserves Revision Decreases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8...

473

New Mexico Coalbed Methane Proved Reserves Revision Decreases...  

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

Decreases (Billion Cubic Feet) New Mexico Coalbed Methane Proved Reserves Revision Decreases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7...

474

Montana Coalbed Methane Proved Reserves Revision Decreases (Billion...  

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

Decreases (Billion Cubic Feet) Montana Coalbed Methane Proved Reserves Revision Decreases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8...

475

Utah Coalbed Methane Proved Reserves Revision Increases (Billion...  

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

Increases (Billion Cubic Feet) Utah Coalbed Methane Proved Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8...

476

New Mexico Coalbed Methane Proved Reserves Revision Increases...  

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

Increases (Billion Cubic Feet) New Mexico Coalbed Methane Proved Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7...

477

Kansas Coalbed Methane Proved Reserves Revision Increases (Billion...  

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

Increases (Billion Cubic Feet) Kansas Coalbed Methane Proved Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8...

478

West Virginia Coalbed Methane Proved Reserves Revision Increases...  

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

Increases (Billion Cubic Feet) West Virginia Coalbed Methane Proved Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7...

479

Montana Coalbed Methane Proved Reserves Revision Increases (Billion...  

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

Increases (Billion Cubic Feet) Montana Coalbed Methane Proved Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8...

480

Wyoming Coalbed Methane Proved Reserves Revision Increases (Billion...  

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

Increases (Billion Cubic Feet) Wyoming Coalbed Methane Proved Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8...

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