Sample records for nrc guidance nrc

  1. HFE Process Guidance and Standards for potential application to updating NRC guidance

    SciTech Connect (OSTI)

    Jacques Hugo; J. J. Persensky

    2012-07-01T23:59:59.000Z

    The U.S. Nuclear Regulatory Commission (NRC) reviews and evaluates the human factors engineering (HFE) programs of applicants for nuclear power plant construction permits, operating licenses, standard design certifications, and combined operating licenses. The purpose of these safety reviews is to help ensure that personnel performance and reliability are appropriately supported. Detailed design review procedures and guidance for the evaluations is provided in three key documents: the Standard Review Plan (NUREG-0800), the HFE Program Review Model (NUREG-0711), and the Human-System Interface Design Review Guidelines (NUREG-0700). These documents were last revised in 2007, 2004 and 2002, respectively. The NRC is committed to the periodic update and improvement of these guidance documents to ensure that they remain state-of-the-art design evaluation tools. Thus, the NRC has initiated a project with BNL to update the NRC guidance to remain current with recent research on human performance, advances in HFE methods and tools, and new technology. INL supported Brookhaven National Lab (BNL) to update the detailed HFE review criteria contained in NUREG-0711 and NUREG-0700 based on (1) feedback obtained from end users, (2) the results of NRC research and development efforts supporting the NRC staff’s HFE safety reviews, and (3) other material the project staff identify as applicable to the update effort. INL submitted comments on development plans and sections of NUREGs 0800, 0711, and 0700. The contractor prepared the report attached here as the deliverable for this work.

  2. NRC Recommendations

    Broader source: Energy.gov [DOE]

    Presentation on NRC recommendations to the DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004 to discuss and define role of systems analysis in DOE Hydrogen Program.

  3. IN NRC PUBLICATIONS NRC Reference Material

    E-Print Network [OSTI]

    Decommissioning Process

    1999-01-01T23:59:59.000Z

    Publicly released records include, to name a few, NUREG-series publications; Federal Register notices; applicant, licensee, and vendor documents and correspondence; NRC correspondence and internal memoranda; bulletins and information notices; inspection and investigative reports; licensee event reports; and Commission papers and their attachments. NRC publications in the NUREG series, NRC regulations, and Title 10, Energy, in the Code of Federal Regulations may also be purchased from one of these two sources.

  4. Superfund Policy Statements and Guidance Regarding Disposition of Radioactive Waste in Non-NRC Licensed Disposal Facilities - 13407

    SciTech Connect (OSTI)

    Walker, Stuart [U.S. Environmental Protection Agency (United States)] [U.S. Environmental Protection Agency (United States)

    2013-07-01T23:59:59.000Z

    This talk will discuss EPA congressional testimony and follow-up letters, as well as letters to other stakeholders on EPA's perspectives on the disposition of radioactive waste outside of the NRC licensed disposal facility system. This will also look at Superfund's historical practices, and emerging trends in the NRC and agreement states on waste disposition. (author)

  5. NRC Leadership Expectations and Practices for Sustaining a High...

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

    16, 2012 Presenter: William C. Ostendorff, NRC Commissioner Topics Covered: NRC Mission Safety Culture NRC Oversight NRC Inspection Program Technical Qualification Continuous...

  6. NRC Construction Light Source Flicker: What We

    E-Print Network [OSTI]

    California at Davis, University of

    NRC Construction Light Source Flicker: What We Need to Know, and Why You Should Care NRC Construction Jennifer A. Veitch, Ph.D. (c) 2013, National Research Council Canada #12;NRC Construction Handbook: Reference & Application (9th Ed.), 2000, p. 3-20 #12;NRC Construction Flicker Effects 1

  7. STATUS OF THE NRC'S DECOMMISSIONING PROGRAM

    SciTech Connect (OSTI)

    Orlando, D. A.; Camper, L. W.; Buckley, J.

    2002-02-25T23:59:59.000Z

    On July 21, 1997, the U.S. Nuclear Regulatory Commission published the final rule on Radiological Criteria for License Termination (the License Termination Rule) as Subpart E to 10 CFR Part 20. NRC regulations require that materials licensees submit Decommissioning Plans to support the decommissioning of its facility if it is required by license condition, or if the procedures and activities necessary to carry out the decommissioning have not been approved by NRC and these procedures could increase the potential health and safety impacts to the workers or the public. NRC regulations also require that reactor licensees submit Post-shutdown Decommissioning Activities Reports and License Termination Plans to support the decommissioning of nuclear power facilities. This paper provides an update on the status of the NRC's decommissioning program. It discusses the status of permanently shut-down commercial power reactors, complex decommissioning sites, and sites listed in the Site Decommissioning Management Plan. The paper provides the status of various tools and guidance the NRC is developing to assist licensees during decommissioning, including a Standard Review Plan for evaluating plans and information submitted by licensees to support the decommissioning of nuclear facilities and the D and D Screen software for determining the potential doses from residual radioactivity. Finally, it discusses the status of the staff's current efforts to streamline the decommissioning process.

  8. NRC - regulator of nuclear safety

    SciTech Connect (OSTI)

    NONE

    1997-05-01T23:59:59.000Z

    The U.S. Nuclear Regulatory Commission (NRC) was formed in 1975 to regulate the various commercial and institutional uses of nuclear energy, including nuclear power plants. The agency succeeded the Atomic Energy Commission, which previously had responsibility for both developing and regulating nuclear activities. Federal research and development work for all energy sources, as well as nuclear weapons production, is now conducted by the U.S. Department of Energy. Under its responsibility to protect public health and safety, the NRC has three principal regulatory functions: (1) establish standards and regulations, (2) issue licenses for nuclear facilities and users of nuclear materials, and (3) inspect facilities and users of nuclear materials to ensure compliance with the requirements. These regulatory functions relate to both nuclear power plants and to other uses of nuclear materials - like nuclear medicine programs at hospitals, academic activities at educational institutions, research work, and such industrial applications as gauges and testing equipment. The NRC places a high priority on keeping the public informed of its work. The agency recognizes the interest of citizens in what it does through such activities as maintaining public document rooms across the country and holding public hearings, public meetings in local areas, and discussions with individuals and organizations.

  9. NRC antitrust licensing actions, 1978--1996

    SciTech Connect (OSTI)

    Mayer, S.J.; Simpson, J.J.

    1997-09-01T23:59:59.000Z

    NUREG-0447, Antitrust Review of Nuclear Power Plants, was published in May 1978 and includes a compilation and discussion of U.S. Nuclear Regulatory Commission (NRC) proceedings and activity involving the NRC`s competitive review program through February 1978, NUREG-0447 is an update of an earlier discussion of the NRC`s antitrust review of nuclear power plants, NR-AIG-001, The US Nuclear Regulatory Commission`s Antitrust Review of Nuclear Power Plants: The Conditioning of Licenses, which reviewed the Commission`s antitrust review function from its inception in December 1970 through April 1976. This report summarizes the support provided to NRC staff in updating the compilation of the NRC`s antitrust licensing review activities for commercial nuclear power plants that have occurred since February 1978. 4 refs., 4 tabs.

  10. NRC okays nuclear merger at Entergy Corp

    SciTech Connect (OSTI)

    Not Available

    1990-02-01T23:59:59.000Z

    The Nuclear Regulatory Commission (NRC) has approved the consolidation of Entergy Corp's nuclear operations into the utility's proposed nuclear management company, Entergy Operations Inc. The NRC action is a significant step in a consolidation process that would place operational responsibility for Entergy's nuclear plants in Mississippi, Arkansas, and Louisiana with Entergy Operations. The NRC action would authorize transfer of the operating licenses for Arkansas Nuclear One (ANO) at Russellville, Ark, Waterford-3 at Taft, La, and Grand Gulf-1 at Port Gibson, Miss, to Entergy Operations. A consolidated nuclear organization will allow for a more focused management structure in its nuclear operations and will result in greater operational efficiencies.

  11. 1996 NRC annual report. Volume 13

    SciTech Connect (OSTI)

    NONE

    1997-10-01T23:59:59.000Z

    This 22nd annual report of the US Nuclear Regulatory Commission (NRC) describes accomplishments, activities, and plans made during Fiscal Year 1996 (FH 1996)--October 1, 1995, through September 30, 1996. Significant activities that occurred early in FY 1997 are also described, particularly changes in the Commission and organization of the NRC. The mission of the NRC is to ensure that civilian uses of nuclear materials in the US are carried out with adequate protection of public health and safety, the environment, and national security. These uses include the operation of nuclear power plants and fuel cycle plants and medical, industrial, and research applications. Additionally, the NRC contributes to combating the proliferation of nuclear weapons material worldwide. The NRC licenses and regulates commercial nuclear reactor operations and research reactors and other activities involving the possession and use of nuclear materials and wastes. It also protects nuclear materials used in operation and facilities from theft or sabotage. To accomplish its statutorily mandated regulatory mission, the NRC issues rules and standards, inspects facilities and operations, and issues any required enforcement actions.

  12. NRC comprehensive records disposition schedule. Revision 3

    SciTech Connect (OSTI)

    NONE

    1998-02-01T23:59:59.000Z

    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).

  13. REVIEW OF NRC APPROVED DIGITAL CONTROL SYSTEMS ANALYSIS

    SciTech Connect (OSTI)

    D.W. Markman

    1999-09-17T23:59:59.000Z

    Preliminary design concepts for the proposed Subsurface Repository at Yucca Mountain indicate extensive reliance on modern, computer-based, digital control technologies. The purpose of this analysis is to investigate the degree to which the U. S. Nuclear Regulatory Commission (NRC) has accepted and approved the use of digital control technology for safety-related applications within the nuclear power industry. This analysis reviews cases of existing digitally-based control systems that have been approved by the NRC. These cases can serve as precedence for using similar types of digitally-based control technologies within the Subsurface Repository. While it is anticipated that the Yucca Mountain Project (YMP) will not contain control systems as complex as those required for a nuclear power plant, the review of these existing NRC approved applications will provide the YMP with valuable insight into the NRCs review process and design expectations for safety-related digital control systems. According to the YMP Compliance Program Guidance, portions of various NUREGS, Regulatory Guidelines, and nuclear IEEE standards the nuclear power plant safety related concept would be applied to some of the designs on a case-by-case basis. This analysis will consider key design methods, capabilities, successes, and important limitations or problems of selected control systems that have been approved for use in the Nuclear Power industry. An additional purpose of this analysis is to provide background information in support of further development of design criteria for the YMP. The scope and primary objectives of this analysis are to: (1) Identify and research the extent and precedence of digital control and remotely operated systems approved by the NRC for the nuclear power industry. Help provide a basis for using and relying on digital technologies for nuclear related safety critical applications. (2) Identify the basic control architecture and methods of key digital control systems approved for use in the nuclear power industry by the NRC. (3) Identify and discuss key design issues, features, benefits, and limitations of these NRC approved digital control systems that can be applied as design guidance and correlated to the Monitored Geologic Repository (MGR) design requirements. (4) Identify codes and standards used in the design of these NRC approved digital control systems and discuss their possible applicability to the design of a subsurface nuclear waste repository. (5) Evaluate the NRC approved digital control system's safety, reliability and maintainability features and issues. Apply these to MGR design methodologies and requirements. (6) Provide recommendations for use in developing design criteria in the System Description Documents for the digital control systems of the subsurface nuclear waste repository at Yucca Mountain. (7) Develop recommendations for applying NRC approval methods for digital control systems for the subsurface nuclear waste repository at Yucca Mountain. This analysis will focus on the development of the issues, criteria and methods used and required for identifying the appropriate requirements for digital based control systems. Attention will be placed on development of recommended design criteria for digital controls including interpretation of codes, standards and regulations. Attention will also focus on the use of digital controls and COTS (Commercial Off-the-shelf) technology and equipment in selected NRC approved digital control systems, and as referenced in applicable codes, standards and regulations. The analysis will address design issues related to COTS technology and how they were dealt with in previous NRC approved digital control systems.

  14. Microsoft PowerPoint - 5_Pat Smith_NMMSS_2013_Presentation_NRC...

    National Nuclear Security Administration (NNSA)

    Reconciliation Pat Smith PSI NRC Lead NRC Reconciliation NRC Reconciliation requirements per NUREGBR-0007, Rev. 6 All RIS's must submit an MSR (Material Summary Report)...

  15. Nuclear safety information sharing agreement between NRC and...

    Office of Environmental Management (EM)

    for DOE and NRC to exchange information related to safety issues associated with non-reactor nuclear facilities. The NRC-DOE Inter-Agency nuclear safety information sharing...

  16. DOE Petitions for NRC Review in Yucca Mountain Proceeding | Department...

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

    Petitions for NRC Review in Yucca Mountain Proceeding DOE Petitions for NRC Review in Yucca Mountain Proceeding April 12, 2010 - 10:16am Addthis The United States Department of...

  17. Microsoft PowerPoint - Upcoming NMMSS Training 120811-NRC comments...

    National Nuclear Security Administration (NNSA)

    Date Course Location December 2-4, 2014 NRC - NMMSS I * Germantown, MD February 10-13, 2015 DOE - NMMSS I Germantown, MD March 24-26, 2015 NRC - NMMSS I * Germantown, MD June...

  18. A review of NRC staff uses of probabilistic risk assessment

    SciTech Connect (OSTI)

    Not Available

    1994-03-01T23:59:59.000Z

    The NRC staff uses probabilistic risk assessment (PRA) and risk management as important elements its licensing and regulatory processes. In October 1991, the NRC`s Executive Director for Operations established the PRA Working Group to address concerns identified by the Advisory Committee on Reactor Safeguards with respect to unevenness and inconsistency in the staff`s current uses of PRA. After surveying current staff uses of PRA and identifying needed improvements, the Working Group defined a set of basic principles for staff PRA use and identified three areas for improvements: guidance development, training enhancements, and PRA methods development. For each area of improvement, the Working Group took certain actions and recommended additional work. The Working Group recommended integrating its work with other recent PRA-related activities the staff completed and improving staff interactions with PRA users in the nuclear industry. The Working Group took two key actions by developing general guidance for two uses of PRA within the NRC (that is, screening or prioritizing reactor safety issues and analyzing such issues in detail) and developing guidance on basic terms and methods important to the staff`s uses of PRA.

  19. DOE/NRC 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 to8/08/2012 254O 311.1B3127NRC

  20. Microsoft Word - SmartGrid - NRC Input to DOE Requestrvjcomments...

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

    Notices) Smart Grid Implementation Input - NRC Contact: Kenn A. Miller, Office of Nuclear Reactor Regulation, 301-415-3152 Comments relevant to the following two sections...

  1. NRC Transportation Security (Part 73 SNF Update and Part 37 Category...

    Office of Environmental Management (EM)

    NRC Transportation Security (Part 73 SNF Update and Part 37 Category 1 and 2 Materials) NRC Transportation Security (Part 73 SNF Update and Part 37 Category 1 and 2 Materials) NRC...

  2. Comparative Analysis Between US NRC Requirements and US DOE Orders - 13402

    SciTech Connect (OSTI)

    Chakraborti, Sayan [MRIGlobal, 425 Volker Blvd, Kansas City, MO 64110 (United States)] [MRIGlobal, 425 Volker Blvd, Kansas City, MO 64110 (United States); Stone, Lynn; Hyatt, Jeannette [Savannah River Nuclear Solutions (United States)] [Savannah River Nuclear Solutions (United States)

    2013-07-01T23:59:59.000Z

    Small modular reactor (SMR) is a nuclear reactor design approach that is expected to herald in a new era of clean energy in the U.S. These reactors are less than one-third the size of conventional large nuclear power reactors, and have factory-fabricated components that may be transported by rail or truck to a site selected to house a small nuclear reactor. To facilitate the licensing of these smaller nuclear reactor designs, the Nuclear Regulatory Commission (NRC) is in the process of developing a regulatory infrastructure to support licensing review of these unique reactor designs. As part of these activities, the NRC has been meeting with the Department of Energy (DOE) and with individual SMR designers to discuss potential policy, licensing, and key technical differences in SMR designs. It is anticipated by the NRC that such licensing interaction and guidance early in the design process will contribute towards minimizing complexity while adding stability and predictability in the licensing and subsequent regulation of new reactor designs such as SMRs. In conjunction with the current NRC initiative of developing the SMR licensing process, early communication and collaboration in the identification and resolution of any potential technical and licensing differences between NRC requirements and similar requirements applicable at DOE sites would help to expedite demonstration and implementation of SMR technology in the US. In order to foster such early communication, Savannah River Nuclear Solutions (SRNS) has begun taking the first steps in identifying and evaluating potential licensing gaps that may exist between NRC and DOE requirements in siting SMRs at DOE sites. A comparison between the existing NRC regulations for Early Site Permits and the DOE Orders was undertaken to establish the degree of correlation between NRC requirements and compliance methods in place at DOE sites. The ability to use existing data and information to expedite the development of the Environmental Report is being evaluated at the Savannah River Site as a case study for application across the DOE Complex. This paper will present areas of direct correlation as well as those where the need for site specific data for either DOE operations or NRC compliance warrant additional interaction between the agencies. Areas where further refinement of the SMR technologies may drive collaborative development of revised regulations through such means as industry consensus standards will also be highlighted. Both NRC and DOE have requirements that mandate public involvement in their processes. The importance and value of early engagement with the public as well as collaborating regulatory agencies is of critical importance when deploying new technologies. (authors)

  3. Congress, NRC mull utility access to FBI criminal files

    SciTech Connect (OSTI)

    Ultroska, D.

    1984-08-01T23:59:59.000Z

    Experiences at Alabama Power Company and other nuclear utilities have promped a request for institutionalizing security checks of personnel in order to eliminated convicted criminals and drug users. The Nuclear Regulatory Commission (NRC), which could provide FBI criminal history information by submitting fingerprints, does not do so, and would require new legislation to take on that duty. Believing that current malevolent employees can be managed with existing procedures, NRC allows criminal background checks only on prospective employees in order to avoid a negative social impact on personnel. Legislation to transfer criminal histories to nuclear facilities is now pending, and NRC is leaning toward a request for full disclosure, partly because of terrorist threats and partly to save manpower time and costs in reviewing case histories.

  4. EPRI/NRC-RES fire human reliability analysis guidelines.

    SciTech Connect (OSTI)

    Lewis, Stuart R. (Electric Power Research Institute, Charlotte, NC); Cooper, Susan E. (U.S. Nuclear Regulatory Commission, Rockville, MD); Najafi, Bijan (SAIC, Campbell, CA); Collins, Erin (SAIC, Campbell, CA); Hannaman, Bill (SAIC, Campbell, CA); Kohlhepp, Kaydee (Scientech, Tukwila, WA); Grobbelaar, Jan (Scientech, Tukwila, WA); Hill, Kendra (U.S. Nuclear Regulatory Commission, Rockville, MD); Hendrickson, Stacey M. Langfitt; Forester, John Alan; Julius, Jeff (Scientech, Tukwila, WA)

    2010-03-01T23:59:59.000Z

    During the 1990s, the Electric Power Research Institute (EPRI) developed methods for fire risk analysis to support its utility members in the preparation of responses to Generic Letter 88-20, Supplement 4, 'Individual Plant Examination - External Events' (IPEEE). This effort produced a Fire Risk Assessment methodology for operations at power that was used by the majority of U.S. nuclear power plants (NPPs) in support of the IPEEE program and several NPPs overseas. Although these methods were acceptable for accomplishing the objectives of the IPEEE, EPRI and the U.S. Nuclear Regulatory Commission (NRC) recognized that they required upgrades to support current requirements for risk-informed, performance-based (RI/PB) applications. In 2001, EPRI and the USNRC's Office of Nuclear Regulatory Research (RES) embarked on a cooperative project to improve the state-of-the-art in fire risk assessment to support a new risk-informed environment in fire protection. This project produced a consensus document, NUREG/CR-6850 (EPRI 1011989), entitled 'Fire PRA Methodology for Nuclear Power Facilities' which addressed fire risk for at power operations. NUREG/CR-6850 developed high level guidance on the process for identification and inclusion of human failure events (HFEs) into the fire PRA (FPRA), and a methodology for assigning quantitative screening values to these HFEs. It outlined the initial considerations of performance shaping factors (PSFs) and related fire effects that may need to be addressed in developing best-estimate human error probabilities (HEPs). However, NUREG/CR-6850 did not describe a methodology to develop best-estimate HEPs given the PSFs and the fire-related effects. In 2007, EPRI and RES embarked on another cooperative project to develop explicit guidance for estimating HEPs for human failure events under fire generated conditions, building upon existing human reliability analysis (HRA) methods. This document provides a methodology and guidance for conducting a fire HRA. This process includes identification and definition of post-fire human failure events, qualitative analysis, quantification, recovery, dependency, and uncertainty. This document provides three approaches to quantification: screening, scoping, and detailed HRA. Screening is based on the guidance in NUREG/CR-6850, with some additional guidance for scenarios with long time windows. Scoping is a new approach to quantification developed specifically to support the iterative nature of fire PRA quantification. Scoping is intended to provide less conservative HEPs than screening, but requires fewer resources than a detailed HRA analysis. For detailed HRA quantification, guidance has been developed on how to apply existing methods to assess post-fire fire HEPs.

  5. Report to the NRC on guidance for preparing scenarios for emergency preparedness exercises at nuclear generating stations. Draft report for comment

    SciTech Connect (OSTI)

    Martin, G.F.; Hickey, E.E.; Moeller, M.P.; Schultz, D.H.; Bethke, G.W.

    1986-03-01T23:59:59.000Z

    A scenario guidance handbook was prepared to assist emergency planners in developing scenarios for emergency preparedness exercises at nuclear power plants. The handbook provides guidance for the development of the objectives of an exercise, the descriptions of scenario events and responses, and the instructions to the participants. Information concerning implementation of the scenario, critiques and findings, and generation and format of scenario data are also included. Finally, examples of manual calculational techniques for producing radiological data are included as an appendix.

  6. Enhancement of NRC station blackout requirements for nuclear power plants

    SciTech Connect (OSTI)

    McConnell, M. W. [United States Nuclear Regulatory Commission, Mail Stop: 012-H2, Washington, DC 20555 (United States)

    2012-07-01T23:59:59.000Z

    The U.S. Nuclear Regulatory Commission (NRC) established a Near-Term Task Force (NTTF) in response to Commission direction to conduct a systematic and methodical review of NRC processes and regulations to determine whether the agency should make additional improvements to its regulatory system and to make recommendations to the Commission for its policy direction, in light of the accident at the Fukushima Dai-ichi Nuclear Power Plant. The NTTF's review resulted in a set of recommendations that took a balanced approach to defense-in-depth as applied to low-likelihood, high-consequence events such as prolonged station blackout (SBO) resulting from severe natural phenomena. Part 50, Section 63, of Title 10 of the Code of Federal Regulations (CFR), 'Loss of All Alternating Current Power,' currently requires that each nuclear power plant must be able to cool the reactor core and maintain containment integrity for a specified duration of an SBO. The SBO duration and mitigation strategy for each nuclear power plant is site specific and is based on the robustness of the local transmission system and the transmission system operator's capability to restore offsite power to the nuclear power plant. With regard to SBO, the NTTF recommended that the NRC strengthen SBO mitigation capability at all operating and new reactors for design-basis and beyond-design-basis external events. The NTTF also recommended strengthening emergency preparedness for prolonged SBO and multi-unit events. These recommendations, taken together, are intended to clarify and strengthen US nuclear reactor safety regarding protection against and mitigation of the consequences of natural disasters and emergency preparedness during SBO. The focus of this paper is on the existing SBO requirements and NRC initiatives to strengthen SBO capability at all operating and new reactors to address prolonged SBO stemming from design-basis and beyond-design-basis external events. The NRC initiatives are intended to enhance core and spent fuel pool cooling, reactor coolant system integrity, and containment integrity. (authors)

  7. NRC TLD Direct Radiation Monitoring Network. Progress report, July--September 1993: Volume 13, No. 3

    SciTech Connect (OSTI)

    Struckmeyer, R.

    1993-11-01T23:59:59.000Z

    This report provides the status and results of the NRC Thermoluminescent Dosimeter (TLD) Direct Radiation Monitoring Network. It presents the radiation levels measured in the vicinity of NRC licensed facilities throughout the country for the third quarter of 1993.

  8. Recommendations for NEAMS Engagement with the NRC: Preliminary Report

    SciTech Connect (OSTI)

    Bernholdt, David E [ORNL

    2012-06-01T23:59:59.000Z

    The vision of the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program is to bring a new generation of analytic tools to the nuclear engineering community in order to facilitate students, faculty, industry and laboratory researchers in investigating advanced reactor and fuel cycle designs. Although primarily targeting at advance nuclear technologies, it is anticipated that these new capabilities will also become interesting and useful to the nuclear regulator Consequently, the NEAMS program needs to engage with the Nuclear Regulatory Commission as the software is being developed to ensure that they are familiar with and ready to respond to this novel approach when the need arises. Through discussions between key NEAMS and NRC staff members, we tentatively recommend annual briefings to the Division of Systems Analysis in the NRC's Office of Nuclear Regulatory Research. However the NEAC subcommittee review of the NEAMS program may yield recommendations that would need to be considered before finalizing this plan.

  9. NRC Reviewer Aid for Evaluating the Human Factors Engineering Aspects of Small Modular Reactors

    SciTech Connect (OSTI)

    OHara J. M.; Higgins, J.C.

    2012-01-13T23:59:59.000Z

    Small modular reactors (SMRs) are a promising approach to meeting future energy needs. Although the electrical output of an individual SMR is relatively small compared to that of typical commercial nuclear plants, they can be grouped to produce as much energy as a utility demands. Furthermore, SMRs can be used for other purposes, such as producing hydrogen and generating process heat. The design characteristics of many SMRs differ from those of current conventional plants and may require a distinct concept of operations (ConOps). The U.S. Nuclear Regulatory Commission (NRC) conducted research to examine the human factors engineering (HFE) and the operational aspects of SMRs. The research identified thirty potential human-performance issues that should be considered in the NRC's reviews of SMR designs and in future research activities. The purpose of this report is to support NRC HFE reviewers of SMR applications by identifying some of the questions that can be asked of applicants whose designs have characteristics identified in the issues. The questions for each issue were identified and organized based on the review elements and guidance contained in Chapter 18 of the Standard Review Plan (NUREG-0800), and the Human Factors Engineering Program Review Model (NUREG-0711).

  10. Reassessment of the NRC`s program for protecting allegers against retaliation

    SciTech Connect (OSTI)

    Not Available

    1994-01-01T23:59:59.000Z

    On July 6, 1993, the Nuclear Regulatory Commission`s (NRC`s) Executive Director for Operations established a review team to reassess the NRC`s program for protecting allegers against retaliation. The team evaluated the current system, and solicited comments from various NRC offices, other Federal agencies, licensees, former allegers, and the public. This report is subject to agency review. The report summarizes current processes and gives an overview of current problems. It discusses: (1) ways in which licensees can promote a quality-conscious work environment, in which all employees feel free to raise concerns without fear of retaliation; (2) ways to improve the NRC`s overall handling of allegations; (3) the NRC`s involvement in the Department of Labor process; (4) related NRC enforcement practices; and (5) methods other than investigation and enforcement that may be useful in treating allegations of potential or actual discrimination. Recommendations are given in each area.

  11. Microsoft PowerPoint - 8_Peter Habighorst_NRC_Act of 2012-status...

    National Nuclear Security Administration (NNSA)

    General licenses 8 NRC Internal actions, cont. * Exports to power reactors in Canada, Germany and Japan were identified: - KNK, THTR, AVR, JOYO, FUGEN, Bruce * General licenses...

  12. Microsoft PowerPoint - 2_Peter J. Habighorst_NRC Remarks 2013...

    National Nuclear Security Administration (NNSA)

    General licenses 8 NRC Internal actions, cont. * Exports to power reactors in Canada, Germany and Japan were identified: - KNK, THTR, AVR, JOYO, FUGEN, Bruce * General licenses...

  13. NRC Technical Research Program to Evaluate Extended Storage and Transportation of Spent Nuclear Fuel - 12547

    SciTech Connect (OSTI)

    Einziger, R.E.; Compton, K.; Gordon, M.; Ahn, T.; Gonzales, H. [United States Nuclear Regulatory Commission, Rockville, Maryland 20852 (United States); Pan, Y. [Center for Nuclear Waste Regulatory Analyses, San Antonio, TX 78238 (United States)

    2012-07-01T23:59:59.000Z

    Any new direction proposed for the back-end of spent nuclear fuel (SNF) cycle will require storage of SNF beyond the current licensing periods. The Nuclear Regulatory Commission (NRC) has established a technical research program to determine if any changes in the 10 CFR part 71, and 72 requirements, and associated guidance might be necessary to regulate the safety of anticipated extended storage, and subsequent transport of SNF. This three part program of: 1) analysis of knowledge gaps in the potential degradation of materials, 2) short-term research and modeling, and 3) long-term demonstration of systems, will allow the NRC to make informed regulatory changes, and determine when and if additional monitoring and inspection of the systems is necessary. The NRC has started a research program to obtain data necessary to determine if the current regulatory guidance is sufficient if interim dry storage has to be extended beyond the currently approved licensing periods. The three-phased approach consists of: - the identification and prioritization of potential degradation of the components related to the safe operation of a dry cask storage system, - short-term research to determine if the initial analysis was correct, and - a long-term prototypic demonstration project to confirm the models and results obtained in the short-term research. The gap analysis has identified issues with the SCC of the stainless steel canisters, and SNF behavior. Issues impacting the SNF and canister internal performance such as high and low temperature distributions, and drying have also been identified. Research to evaluate these issues is underway. Evaluations have been conducted to determine the relative values that various types of long-term demonstration projects might provide. These projects or follow-on work is expected to continue over the next five years. (authors)

  14. Roadmap to NRC Approval of Ceramic Matrix Composites in Generation IV Reactors

    SciTech Connect (OSTI)

    M. G. Jenkins; E. Lara-Curzio; W. Windes

    2006-05-01T23:59:59.000Z

    This report provides an initial roadmap to obtain Nuclear Regulatory Commission (NRC) approval for using these material systems in a nuclear application. The possible paths taken to achieving NRC approval are necessarily subject to change as this is an on-going process that shifts as more data and a clearer understanding of the nuclear regulations are gathered.

  15. Development of the NRC`s Human Performance Investigation Process (HPIP). Volume 3, Development documentation

    SciTech Connect (OSTI)

    Paradies, M.; Unger, L. [System Improvements, Inc., Knoxville, TN (United States); Haas, P.; Terranova, M. [Concord Associates, Inc., Knoxville, TN (United States)

    1993-10-01T23:59:59.000Z

    The three volumes of this report detail a standard investigation process for use by US Nuclear Regulatory Commission (NRC) personnel when investigating human performance related events at nuclear power plants. The process, called the Human Performance Investigation Process (HPIP), was developed to meet the special needs of NRC personnel, especially NRC resident and regional inspectors. HPIP is a systematic investigation process combining current procedures and field practices, expert experience, NRC human performance research, and applicable investigation techniques. The process is easy to learn and helps NRC personnel perform better field investigations of the root causes of human performance problems. The human performance data gathered through such investigations provides a better understanding of the human performance issues that cause events at nuclear power plants. This document, Volume III, is a detailed documentation of the development effort and the pilot training program.

  16. Recommendations for NRC policy on shift scheduling and overtime at nuclear power plants

    SciTech Connect (OSTI)

    Lewis, P.M.

    1985-07-01T23:59:59.000Z

    This report contains the Pacific Northwest Laboratory's (PNL's) recommendations to the US Nuclear Regulatory Commission (NRC) for an NRC policy on shift scheduling and hours of work (including overtime) for control room operators and other safety-related personnel in nuclear power plants. First, it is recommended that NRC make three additions to its present policy on overtime: (1) limit personnel to 112 hours of work in a 14-day period, 192 hours in 28 days, and 2260 hours in one year; exceeding these limits would require plant manager approval; (2) add a requirement that licensees obtain approval from NRC if plant personnel are expected to exceed 72 hours of work in a 7-day period, 132 hours in 14 days, 228 hours in 28 days, and 2300 hours in one year; and (3) make the policy a requirement, rather than a nonbinding recommendation. Second, it is recommended that licensees be required to obtain NRC approval to adopt a routine 12-hour/day shift schedule. Third, it is recommended that NRC add several nonbinding recommendations concerning routine 8-hour/day schedules. Finally, because additional data can strengthen the basis for future NRC policy on overtime, five methods are suggested for collecting data on overtime and its effects. 44 refs., 10 tabs.

  17. Status of VICTORIA: NRC peer review and recent code applications

    SciTech Connect (OSTI)

    Bixler, N.E. [Sandia National Labs., Albuquerque, NM (United States); Schaperow, J.H. [Nuclear Regulatory Commission, Washington, DC (United States)

    1997-12-01T23:59:59.000Z

    VICTORIA is a mechanistic computer code designed to analyze fission product behavior within a nuclear reactor coolant system (RCS) during a severe accident. It provides detailed predictions of the release of radioactive and nonradioactive materials from the reactor core and transport and deposition of these materials within the RCS. A summary of the results and recommendations of an independent peer review of VICTORIA by the US Nuclear Regulatory Commission (NRC) is presented, along with recent applications of the code. The latter include analyses of a temperature-induced steam generator tube rupture sequence and post-test analyses of the Phebus FPT-1 test. The next planned Phebus test, FTP-4, will focus on fission product releases from a rubble bed, especially those of the less-volatile elements, and on the speciation of the released elements. Pretest analyses using VICTORIA to estimate the magnitude and timing of releases are presented. The predicted release of uranium is a matter of particular importance because of concern about filter plugging during the test.

  18. A RE-LOOK AT THE US NRC SAFETY GOALS

    SciTech Connect (OSTI)

    mubayi v.

    2013-09-22T23:59:59.000Z

    Since they were adopted in 1986, the US NRC’s Safety Goals have played a valuable role as a de facto risk acceptance criterion against which the predicted performance of a commercial nuclear power reactor can be evaluated and assessed. The current safety goals are cast in terms of risk metrics called quantitative health objectives (QHOs), limiting numerical values of the risks of the early and latent health effects of accidental releases of radioactivity to the offsite population. However, while demonstrating compliance with current safety goals has been an important step in assessing the acceptance of the risk posed by LWRs, new or somewhat different goals may be needed that go beyond the current early fatality and latent cancer fatality QHOs in assessing reactor risk. Natural phenomena such as hurricanes seem to be suitable candidates for establishing a background rate to derive a risk goal as their order of magnitude cost of damages is similar to those estimated in severe accident Level 3 PRAs done for nuclear power plants. This paper obtains a risk goal that could have a wider applicability, compared to the current QHOs, as a technology-neutral goal applicable to future reactors and multi-unit sites.

  19. Status of NRC approval of EPRI electromagnetic interference susceptibility testing guidelines for digital equipment

    SciTech Connect (OSTI)

    James, R.W. [Electric Power Research Institute, Palo Alto, CA (United States); Shank, J.W. [Public Service Electric & Gas Company, Hancock`s Bridge, NJ (United States); Yoder, C. [Baltimore Gas & Electric, Lusby, MD (United States)

    1996-12-31T23:59:59.000Z

    Historically, nuclear power plants installing digital equipment have been required to conduct expensive, site-specific electromagnetic interference (EMI) surveys to demonstrate that EMI will not affect the operation of sensitive electronic equipment. Consequently, EPRI formed a Utility Working Group which developed a set of generic EMI susceptibility testing guidelines, which were published as an EPRI report in September 1994. These guidelines are based upon EMI survey data obtained from several different plants and include criteria for determining their applicability. The Working Group interacted with NRC staff to obtain NRC approval. In April 1996, the NRC issued a Safety Evaluation Report (SER) endorsing the guidelines as a valid means of demonstrating EMI compatibility. The issuance of this SER was conditional on issuing a revision to the EPRI EMI Guidelines. This paper summarizes the guidelines, the NRC SER, and the current status of Revision 1 to the report.

  20. Microsoft PowerPoint - 4_JOHN_BALLARD_MARY_MCCDONNELL_NRC DOE...

    National Nuclear Security Administration (NNSA)

    Len Myers Special Requests (301) 903-2180 Len.Myers@nnsa.doe.gov Patricia Smith NRC Reconciliation (301) 903-6860 PatriciaR.Smith@nnsa.doe.gov Reasons to Call NMMSS -...

  1. Spent Nuclear Fuel Project path forward: nuclear safety equivalency to comparable NRC-licensed facilities

    SciTech Connect (OSTI)

    Garvin, L.J.

    1995-11-01T23:59:59.000Z

    This document includes the Technical requirements which meet the nuclear safety objectives of the NRC regulations for fuel treatment and storage facilities. These include requirements regarding radiation exposure limits, safety analysis, design and construction. This document also includes administrative requirements which meet the objectives of the major elements of the NRC licensing process. These include formally documented design and safety analysis, independent technical review, and oppportunity for public involvement.

  2. NRC Monitoring of Salt Waste Disposal at the Savannah River Site - 13147

    SciTech Connect (OSTI)

    Pinkston, Karen E.; Ridge, A. Christianne; Alexander, George W.; Barr, Cynthia S.; Devaser, Nishka J.; Felsher, Harry D. [U.S. Nuclear Regulatory Commission (United States)] [U.S. Nuclear Regulatory Commission (United States)

    2013-07-01T23:59:59.000Z

    As part of monitoring required under Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA), the NRC staff reviewed an updated DOE performance assessment (PA) for salt waste disposal at the Saltstone Disposal Facility (SDF). The NRC staff concluded that it has reasonable assurance that waste disposal at the SDF meets the 10 CFR 61 performance objectives for protection of individuals against intrusion (chap.61.42), protection of individuals during operations (chap.61.43), and site stability (chap.61.44). However, based on its evaluation of DOE's results and independent sensitivity analyses conducted with DOE's models, the NRC staff concluded that it did not have reasonable assurance that DOE's disposal activities at the SDF meet the performance objective for protection of the general population from releases of radioactivity (chap.61.41) evaluated at a dose limit of 0.25 mSv/yr (25 mrem/yr) total effective dose equivalent (TEDE). NRC staff also concluded that the potential dose to a member of the public is expected to be limited (i.e., is expected to be similar to or less than the public dose limit in chap.20.1301 of 1 mSv/yr [100 mrem/yr] TEDE) and is expected to occur many years after site closure. The NRC staff used risk insights gained from review of the SDF PA, its experience monitoring DOE disposal actions at the SDF over the last 5 years, as well as independent analysis and modeling to identify factors that are important to assessing whether DOE's disposal actions meet the performance objectives. Many of these factors are similar to factors identified in the NRC staff's 2005 review of salt waste disposal at the SDF. Key areas of interest continue to be waste form and disposal unit degradation, the effectiveness of infiltration and erosion controls, and estimation of the radiological inventory. Based on these factors, NRC is revising its plan for monitoring salt waste disposal at the SDF in coordination with South Carolina Department of Health and Environmental Control (SCDHEC). DOE has completed or begun additional work related to salt waste disposal to address these factors. NRC staff continues to evaluate information related to the performance of the SDF and has been working with DOE and SCDHEC to resolve NRC staff's technical concerns. (authors)

  3. NRC safety research in support of regulation - FY 1994. Volume 9

    SciTech Connect (OSTI)

    NONE

    1995-06-01T23:59:59.000Z

    This report, the tenth in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1994. The goal of the Office of Nuclear Regulatory Research (RES) is to ensure the availability of sound technical bases for timely rulemaking and related decisions in support of NRC regulatory/licensing/inspection activities. RES also has responsibilities related to the resolution of generic safety issues and to the review of licensee submittals regarding individual plant examinations. It is the responsibility of RES to conduct the NRC`s rulemaking process, including the issuance of regulatory guides and rules that govern NRC licensed activities.

  4. Comparisons of ANSI standards cited in the NRC standard review plan, NUREG-0800 and related documents

    SciTech Connect (OSTI)

    Ankrum, A.R.; Bohlander, K.L.; Gilbert, E.R.; Pawlowski, R.A.; Spiesman, J.B. [Pacific Northwest Lab., Richland, WA (United States)

    1995-11-01T23:59:59.000Z

    This report provides the results of comparisons of the cited and latest versions of ANSI standards cited in the NRC Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (NUREG 0800) and related documents. The comparisons were performed by Battelle Pacific Northwest Laboratories in support of the NRC`s Standard Review Plan Update and Development Program. Significant changes to the standards, from the cited version to the latest version, are described and discussed in a tabular format for each standard. Recommendations for updating each citation in the Standard Review Plan are presented. Technical considerations and suggested changes are included for related regulatory documents (i.e., Regulatory Guides and the Code of Federal Regulations) citing the standard. The results and recommendations presented in this document have not been subjected to NRC staff review.

  5. Comparisons of ASTM standards cited in the NRC standard review plan, NUREG-0800 and related documents

    SciTech Connect (OSTI)

    Ankrum, A.R.; Bohlander, K.L.; Gilbert, E.R.; Pawlowski, R.A.; Spiesman, J.B.

    1995-10-01T23:59:59.000Z

    This report provides the results of comparisons of the cited and latest versions of ASTM standards cited in the NRC Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (NUREG 0800) and related documents. The comparisons were performed by Battelle Pacific Northwest Laboratories in support of the NRC`s Standard Review Plan Update and Development Program. Significant changes to the standards, from the cited version to the latest version, are described and discussed in a tabular format for each standard. Recommendations for updating each citation in the Standard Review Plan are presented. Technical considerations and suggested changes are included for related regulatory documents (i.e., Regulatory Guides and the Code of Federal Regulations) citing the standard. The results and recommendations presented in this document have not been subjected to NRC staff review.

  6. New security measures are proposed for N-plants: Insider Rule package is issued by NRC

    SciTech Connect (OSTI)

    Not Available

    1984-09-01T23:59:59.000Z

    New rules proposed by the Nuclear Regulatory Commission (NRC) will require background investigations and psychological assessments of new job candidates and continual monitoring of the behavior of all power plant workers with access to sensitive areas. Licensees will have to submit an ''access authorization'' program for approval describing how they will conduct these security activities. The employee checks will go back five years to examine credit, educational, and criminal histories. Implementation of the rules could involve the Edison Electric Institute as an intermediary to funnel criminal checks from the Justice Department and FBI. The NRC is also considering a clarification of areas designated as ''vital'' because current designations may be too strict.

  7. NRC staff site characterization analysis of the Department of Energy`s Site Characterization Plan, Yucca Mountain Site, Nevada

    SciTech Connect (OSTI)

    NONE

    1989-08-01T23:59:59.000Z

    This Site Characterization Analysis (SCA) documents the NRC staff`s concerns resulting from its review of the US Department of Energy`s (DOE`s) Site Characterization Plan (SCP) for the Yucca Mountain site in southern Nevada, which is the candidate site selected for characterization as the nation`s first geologic repository for high-level radioactive waste. DOE`s SCP explains how DOE plans to obtain the information necessary to determine the suitability of the Yucca Mountain site for a repository. NRC`s specific objections related to the SCP, and major comments and recommendations on the various parts of DOE`s program, are presented in SCA Section 2, Director`s Comments and Recommendations. Section 3 contains summaries of the NRC staff`s concerns for each specific program, and Section 4 contains NRC staff point papers which set forth in greater detail particular staff concerns regarding DOE`s program. Appendix A presents NRC staff evaluations of those NRC staff Consultation Draft SCP concerns that NRC considers resolved on the basis of the SCP. This SCA fulfills NRC`s responsibilities with respect to DOE`s SCP as specified by the Nuclear Waste Policy Act (NWPA) and 10 CFR 60.18. 192 refs., 2 tabs.

  8. NRC Earth Science Decadal Survey-Mission Concept Earth Sciences from the Astronomer's Perspective, a Deep

    E-Print Network [OSTI]

    Christian, Eric

    NRC Earth Science Decadal Survey-Mission Concept Earth Sciences from the Astronomer's Perspective Irina Melnikova #12;1 Earth Sciences from the Astronomer's Perspective 1.0 Mission Concept and Purpose Earth observations from satellites located in deep space offer the exciting opportunity to look

  9. Understanding and Interpreting the NRC's "Data-Based Assessment of Research-Doctorate

    E-Print Network [OSTI]

    Navara, Kristen

    member per year [2000-2006] R Avg. citations per publication [2000-2006] R % Faculty with Grant [2005-06 AY] R % Interdisciplinary Faculty [2005-06 AY] % non-Asian Minority Faculty [2005-06 AY] D % Female Faculty [2005-06 AY] D Awards/Faculty Member [2001-2006] R 10 #12;10/21/2010 6 NRC Methodology

  10. NRC (Nuclear Regulatory Commission) perspective of software QA (quality assurance) in the nuclear history

    SciTech Connect (OSTI)

    Weiss, S.H.

    1988-01-01T23:59:59.000Z

    Computer technology has been a part of the nuclear industry since its inception. However, it is only recently that computers have been integrated into reactor operations. During the early history of commercial nuclear power in the United States, the US Nuclear Regulatory Commission (NRC) discouraged the use of digital computers for real-time control and monitoring of nuclear power plant operation. At the time, this position was justified since software engineering was in its infancy, and horror stories on computer crashes were plentiful. Since the advent of microprocessors and inexpensive computer memories, significant advances have been made in fault-tolerant computer architecture that have resulted in highly reliable, durable computer systems. The NRC's requirement for safety parameter display system (SPDS) stemmed form the results of studies and investigations conducted on the Three Mile Island Unit 2 (TMI-2) accident. An NRC contractor has prepared a handbook of software QA techniques applicable to the nuclear industry, published as NUREG/CR-4640 in August 1987. Currently, the NRC is considering development of an inspection program covering software QA. Future efforts may address verification and validation as applied to expert systems and artificial intelligence programs.

  11. Development of the NRC`s Human Performance Investigation Process (HPIP). Volume 2, Investigators`s Manual

    SciTech Connect (OSTI)

    Paradies, M.; Unger, L. [System Improvements, Inc., Knoxville, TN (United States); Haas, P.; Terranova, M. [Concord Associates, Inc., Knoxville, TN (United States)

    1993-10-01T23:59:59.000Z

    The three volumes of this report detail a standard investigation process for use by US Nuclear Regulatory Commission (NRC) personnel when investigating human performance related events at nuclear power plants. The process, called the Human Performance Investigation Process (HPIP), was developed to meet the special needs of NRC personnel, especially NRC resident and regional inspectors. HPIP is a systematic investigation process combining current procedures and field practices, expert experience, NRC human performance research, and applicable investigation techniques. The process is easy to learn and helps NRC personnel perform better field investigations of the root causes of human performance problems. The human performance data gathered through such investigations provides a better understanding of the human performance issues that cause event at nuclear power plants. This document, Volume II, is a field manual for use by investigators when performing event investigations. Volume II includes the HPIP Procedure, the HPIP Modules, and Appendices that provide extensive documentation of each investigation technique.

  12. U.S. DOE Approach to Address U.S. NRC Key Technical Issues for a License Application

    SciTech Connect (OSTI)

    Ziegler, J. D.; Gunter, T. C.; Gamble, R. P.; Bradbury, R. B.

    2003-02-25T23:59:59.000Z

    Interactions between the U.S. Department of Energy (DOE) staff and the U.S. Nuclear Regulatory Commission (NRC) staff prior to submittal of a license application (LA) for NRC review are focused on resolution of issues relevant to licensing a geologic repository at the Yucca Mountain site. These interactions take place in meetings that are open to the public, the State of Nevada, affected units of local government, and other interested parties. Consistent with a 1992 agreement between the DOE and NRC, resolution of an issue at the staff level can be achieved during the pre-licensing period when the NRC staff has no further questions or comments regarding how the DOE is addressing that issue. In no case does such resolution at the NRC staff level preclude an issue being raised during the licensing proceedings by the NRC or another party to the proceedings. Beginning in 1996, interactions between the DOE and NRC began to focus significant attention on the nine topical areas, called Key Technical Issues (KTIs), that the NRC staff considers to be important in evaluating the post-closure performance of a Yucca Mountain repository. DOENRC meetings to discuss each KTI and achieve technical agreement on the information needed to resolve the issues were held between August 2000 and September 2001. As a result of these meetings, 293 agreements were reached regarding information to be developed by the DOE to supplement the basis for NRC review of the initial LA.* As of April 23, 2003, 77 of these agreements are considered by the NRC to be complete based on information provided by the DOE.

  13. Twenty-third DOE/NRC nuclear air cleaning and treatment conference

    SciTech Connect (OSTI)

    Bellamy, R.R.; Hayes, J.J.; First, M.W.

    1995-01-01T23:59:59.000Z

    The Twenty-Third Department of Energy/Nuclear Regulatory Commission (DOE/NRC) nuclear Air-Cleaning and Treatment Conference was held July 25-28, 1994, in Buffalo, New York. The conference was also sponsored by the Harvard Air-Cleaning Laboratory and the Internation Society of Nuclear Air Treatment Technologies, a nonprofit organization founded to promote technology transfer in the nuclear air-cleaning and treatment area. A total of 192 air-cleaning specialists attended the conference. The United States and 11 foreign countries were represented. The specialists are affiliated with all aspects of the nuclear industry, including government agencies, educational institutions, utilities, architect-engineers, equipment suppliers, and consultants. The high level of international interests is evident from the 40% of papers sponsored by foreign interests. More than 20% of the attendees as well as several members of the Program Committee were from outside the United States. Major topics discussed at this conference included nuclear air-cleaning codes and standards, waste disposal, particulate filter developments (including testing and performance under stress and after aging), sampling and monitoring of process and effluent streams, off-gasses from fuel reprocessing, adsorbents and adsorption, accident control and analysis, and revised source terms for power-plant accidents. A highlight of the conference concerned operations a at the DOE facility at West Valley, New York, where construction is under way to solidify radioactive waste. A recurrent theme throughout the sessions was that, in spite of the large number of guidance documents available in the form of regulations, codes, standards, and directives, multiple difficulties arise when all are invoked simultaneously. Gas processing needs, rather than controls for civilian power plants, will provide the principal challenge during the next decade for the air-cleaning specialists of the world. 15 refs.

  14. Technical Basis for Physical Fidelity of NRC Control Room Training Simulators for Advanced Reactors

    SciTech Connect (OSTI)

    Minsk, Brian S.; Branch, Kristi M.; Bates, Edward K.; Mitchell, Mark R.; Gore, Bryan F.; Faris, Drury K.

    2009-10-09T23:59:59.000Z

    The objective of this study is to determine how simulator physical fidelity influences the effectiveness of training the regulatory personnel responsible for examination and oversight of operating personnel and inspection of technical systems at nuclear power reactors. It seeks to contribute to the U.S. Nuclear Regulatory Commission’s (NRC’s) understanding of the physical fidelity requirements of training simulators. The goal of the study is to provide an analytic framework, data, and analyses that inform NRC decisions about the physical fidelity requirements of the simulators it will need to train its staff for assignment at advanced reactors. These staff are expected to come from increasingly diverse educational and experiential backgrounds.

  15. Accident Conditions versus Regulatory Test for NRC-Approved UF6 Packages

    SciTech Connect (OSTI)

    MILLS, G. SCOTT; AMMERMAN, DOUGLAS J.; LOPEZ, CARLOS

    2003-01-01T23:59:59.000Z

    The Nuclear Regulatory Commission (NRC) approves new package designs for shipping fissile quantities of UF{sub 6}. Currently there are three packages approved by the NRC for domestic shipments of fissile quantities of UF{sub 6}: NCI-21PF-1; UX-30; and ESP30X. For approval by the NRC, packages must be subjected to a sequence of physical tests to simulate transportation accident conditions as described in 10 CFR Part 71. The primary objective of this project was to relate the conditions experienced by these packages in the tests described in 10 CFR Part 71 to conditions potentially encountered in actual accidents and to estimate the probabilities of such accidents. Comparison of the effects of actual accident conditions to 10 CFR Part 71 tests was achieved by means of computer modeling of structural effects on the packages due to impacts with actual surfaces, and thermal effects resulting from test and other fire scenarios. In addition, the likelihood of encountering bodies of water or sufficient rainfall to cause complete or partial immersion during transport over representative truck routes was assessed. Modeled effects, and their associated probabilities, were combined with existing event-tree data, plus accident rates and other characteristics gathered from representative routes, to derive generalized probabilities of encountering accident conditions comparable to the 10 CFR Part 71 conditions. This analysis suggests that the regulatory conditions are unlikely to be exceeded in real accidents, i.e. the likelihood of UF{sub 6} being dispersed as a result of accident impact or fire is small. Moreover, given that an accident has occurred, exposure to water by fire-fighting, heavy rain or submersion in a body of water is even less probable by factors ranging from 0.5 to 8E-6.

  16. Managing aging in nuclear power plants: Insights from NRC maintenance team inspection reports

    SciTech Connect (OSTI)

    Fresco, A.; Subudhi, M.; Gunther, W.; Grove, E.; Taylor, J. [Brookhaven National Lab., Upton, NY (United States)

    1993-12-01T23:59:59.000Z

    A plant`s maintenance program is the principal vehicle through which age-related degradation is managed. From 1988 to 1991, the NRC evaluated the maintenance program of every nuclear power plant in the United States. Forty-four out of a total of 67 of the reports issued on these in-depth team inspections were reviewed for insights into the strengths and weaknesses of the programs as related to the need to understand and manage the effects of aging on nuclear plant systems, structures, and components. Relevant information was extracted from these inspection reports and sorted into several categories, including Specific Aging Insights, Preventive Maintenance, Predictive Maintenance and Condition Monitoring, Post Maintenance Testing, Failure Trending, Root Cause Analysis and Usage of Probabilistic Risk Assessment in the Maintenance Process. Specific examples of inspection and monitoring techniques successfully used by utilities to detect degradation due to aging have been identified. The information also was sorted according to systems and components, including: Auxiliary Feedwater, Main Feedwater, High Pressure Injection for both BWRs and PWRs, Service Water, Instrument Air, and Emergency Diesel Generator Air Start Systems, and Emergency Diesel Generators Air Start Systems, emergency diesel generators, electrical components such as switchgear, breakers, relays, and motor control centers, motor operated valves and check valves. This information was compared to insights gained from the Nuclear Plant Aging Research (NPAR) Program. Attributes of plant maintenance programs where the NRC inspectors felt that improvement was needed to properly address the aging issue also are discussed.

  17. Comparisons of ANS, ASME, AWS, and NFPA standards cited in the NRC standard review plan, NUREG-0800, and related documents

    SciTech Connect (OSTI)

    Ankrum, A.R.; Bohlander, K.L.; Gilbert, E.R.; Spiesman, J.B. [Pacific Northwest Lab., Richland, WA (United States)

    1995-11-01T23:59:59.000Z

    This report provides the results of comparisons of the cited and latest versions of ANS, ASME, AWS and NFPA standards cited in the NRC Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (NUREG 0800) and related documents. The comparisons were performed by Battelle Pacific Northwest Laboratories in support of the NRC`s Standard Review Plan Update and Development Program. Significant changes to the standards, from the cited version to the latest version, are described and discussed in a tabular format for each standard. Recommendations for updating each citation in the Standard Review Plan are presented. Technical considerations and suggested changes are included for related regulatory documents (i.e., Regulatory Guides and the Code of Federal Regulations) citing the standard. The results and recommendations presented in this document have not been subjected to NRC staff review.

  18. PHYSICAL FIDELITY CONSIDERATIONS FOR NRC ADVANCED REACTOR CONTROL ROOM TRAINING SIMULATORS USED FOR INSPECTOR/EXAMINER TRAINING

    SciTech Connect (OSTI)

    Branch, Kristi M.; Mitchell, Mark R.; Miller, Mark; Cochrum, Steven

    2010-11-07T23:59:59.000Z

    This paper describes research into the physical fidelity requirements of control room simulators to train U.S. Nuclear Regulatory Commission (NRC) staff for their duties as inspectors and license examiners for next-generation nuclear power plants. The control rooms of these power plants are expected to utilize digital instrumentation and controls to a much greater extent than do current plants. The NRC is assessing training facility needs, particularly for control room simulators, which play a central role in NRC training. Simulator fidelity affects both training effectiveness and cost. Research has shown high simulation fidelity sometimes positively affects transfer to the operational environment but sometimes makes no significant difference or actually impedes learning. The conditions in which these different effects occur are often unclear, especially for regulators (as opposed to operators) about whom research is particularly sparse. This project developed an inventory of the tasks and knowledges, skills, and abilities that NRC regulators need to fulfill job duties and used expert panels to characterize the inventory items by type and level of cognitive/behavioral capability needed, difficulty to perform, importance to safety, frequency of performance, and the importance of simulator training for learning these capabilities. A survey of current NRC staff provides information about the physical fidelity of the simulator on which the student trained to the control room to which the student was assigned and the effect lack of fidelity had on learning and job performance. The study concludes that a high level of physical fidelity is not required for effective training of NRC staff.

  19. Structure/piping sensitivity studies for the US NRC Seismic Safety Margins Research Program. [PWR; BWR

    SciTech Connect (OSTI)

    Shieh, L.C.; O'Connell, W.J.; Johnson, J.J.

    1983-01-01T23:59:59.000Z

    The Seismic Safety Margins Research Program (SSMRP) is a NRC-funded, multi-year program conducted by Lawrence Livermore National Laboratory (LLNL). One of the goals of the program is to develop a complete, fully coupled analysis procedure (including methods and computer codes) for estimating the risk of an earthquake-caused radioactive release from commercial nuclear power plant. The analysis procedure is based upon a state-of-the-art evaluation of the current seismic analysis design process and explicitly includes the uncertainties inherent in such a process. The results will be used to improve seismic licensing requirements for nuclear power plants. In Phase I, a probabilistic computational procedure was developed for the seismic safety assessment. In Phase II, sensitivity studies were performed, codes and models were improved, and analysis of the Zion plant was completed.

  20. Comparison of the NRC and the IAEA regulatory documents in the area of nuclear fuel systems

    SciTech Connect (OSTI)

    El-Adham, K.; Shinaishin, M.A.

    1991-04-01T23:59:59.000Z

    A main objective of this work was to identify the safety requirements in the area of fuel system design and performance from both the International Atomic Energy Agency (IAEA) and U.S. Nuclear Regulatory Commission (NRC) points of view. The study covered requirements during normal plant operation as well as during accident conditions. This study revealed that, although none of the factors to be considered for fuel safety were neglected in the IAEA regulatory documents, these documents are not complete in themselves, particularly because they lack quantitative guidelines and specific industrial standards. Although generality makes the IAEA requirements adaptable to many countries, on the other hand, it makes their applicability constrained by the availability of highly qualified and experienced personnel who can translate the qualitative requirements given in these documents into actual engineering solutions. 20 refs.

  1. CANDU reactors, their regulation in Canada, and the identification of relevant NRC safety issues

    SciTech Connect (OSTI)

    Charak, I.; Kier, P.H. [Argonne National Lab., IL (United States)

    1995-04-01T23:59:59.000Z

    Atomic Energy of Canada, Limited (AECL) and its subsidiary in the US, are considering submitting the CANDU 3 design for standard design certification under 10 CFR Part 52. CANDU reactors are pressurized heavy water power reactors. They have some substantially different safety responses and safety systems than the LWRs that the commercial power reactor licensing regulations of the US Nuclear Regulatory Commission (NRC) have been developed to deal with. In this report, the authors discuss the basic design characteristics of CANDU reactors, specifically of the CANDU 3 where possible, and some safety-related consequences of these characteristics. The authors also discuss the Canadian regulatory provisions, and the CANDU safety systems that have evolved to satisfy the Canadian regulatory requirements as of December 1992. Finally, the authors identify NRC regulations, mainly in 10 CFR Parts 50 and 100, with issues for CANDU 3 reactor designs. In all, eleven such regulatory issues are identified. They are: (1) the ATWS rule ({section}50.62); (2) station blackout ({section}50.63); (3) conformance with Standard Review Plan (SRP); (4) appropriateness of the source term ({section}50.34(f) and {section}100.11); (5) applicability of reactor coolant pressure boundary (RCPB) requirements ({section}50.55a, etc); (6) ECCS acceptance criteria ({section}50.46)(b); (7) combustible gas control ({section}50.44, etc); (8) power coefficient of reactivity (GDC 11); (9) seismic design (Part 100); (10) environmental impacts of the fuel cycle ({section}51.51); and (11) (standards {section}50.55a).

  2. Technical description of the NRC long-term whole-rod and crud performance test

    SciTech Connect (OSTI)

    Einziger, R.E.; Fish, R.L.; Knecht, R.L.

    1982-09-01T23:59:59.000Z

    Westinghouse Hanford Company (WHC) and EG and G-Idaho are jointly conducting a long-term, low-temperature, spent-fuel, whole rod and crud behavior test to provide the Nuclear Regulatory Commission (NRC) with information to assist in the licensing of light water reactor (LWR) spent-fuel, dry storage facilities. Readily available fuel rods from an H.B. Robinson Unit 2 (PWR) fuel assembly and a Peach Bottom-II (BWR) fuel assembly were selected for use in the 50-month test. Both intact and defected rods will be tested in inert and oxidizing atmospheres. A 230/sup 0/C test temperature was selected for the first 10-month run. Both nondestructive and destructive examinations are planned to characterize the fuel rod behavior during the 5-y test. Four interim examinations and a final examination will be conducted. Crud spallation behavior will be investigated by sampling the crud particulate from the test capsules at each of the four interim examinations and at the end of the test. The background to whole rod testing, description of rod breach mechanisms, and a detailed description of the test are presented in this document.

  3. LBB evaluation for a typical Japanese PWR primary loop by using the US NRC approved methods

    SciTech Connect (OSTI)

    Swamy, S.A.; Bhowmick, D.C.; Prager, D.E. [Westinghouse Nuclear Technology Division, Pittsburgh, PA (United States)

    1997-04-01T23:59:59.000Z

    The regulatory requirements for postulated pipe ruptures have changed significantly since the first nuclear plants were designed. The Leak-Before-Break (LBB) methodology is now accepted as a technically justifiable approach for eliminating postulation of double-ended guillotine breaks (DEGB) in high energy piping systems. The previous pipe rupture design requirements for nuclear power plant applications are responsible for all the numerous and massive pipe whip restraints and jet shields installed for each plant. This results in significant plant congestion, increased labor costs and radiation dosage for normal maintenance and inspection. Also the restraints increase the probability of interference between the piping and supporting structures during plant heatup, thereby potentially impacting overall plant reliability. The LBB approach to eliminate postulating ruptures in high energy piping systems is a significant improvement to former regulatory methodologies, and therefore, the LBB approach to design is gaining worldwide acceptance. However, the methods and criteria for LBB evaluation depend upon the policy of individual country and significant effort continues towards accomplishing uniformity on a global basis. In this paper the historical development of the U.S. LBB criteria will be traced and the results of an LBB evaluation for a typical Japanese PWR primary loop applying U.S. NRC approved methods will be presented. In addition, another approach using the Japanese LBB criteria will be shown and compared with the U.S. criteria. The comparison will be highlighted in this paper with detailed discussion.

  4. Summary of Information Presented at an NRC-Sponsored Low-Power Shutdown Public Workshop, April 27, 1999, Rockville, Maryland

    SciTech Connect (OSTI)

    Wheeler, Timothy A.; Whitehead, Donnie W.; Lois, Erasmia

    1999-07-01T23:59:59.000Z

    This report summarizes a public workshop that was held on April 27, 1999, in Rockville, Maryland. The workshop was conducted as part of the US Nuclear Regulatory Commission's (NRC) efforts to further develop its understanding of the risks associated with low power and shutdown operations at US nuclear power plants. A sufficient understanding of such risks is required to support decision-making for risk-informed regulation, in particular Regulatory Guide 1.174, and the development of a consensus standard. During the workshop the NRC staff discussed and requested feedback from the public (including representatives of the nuclear industry, state governments, consultants, private industry, and the media) on the risk associated with low-power and shutdown operations.

  5. Uranium-Loaded Water Treatment Resins: 'Equivalent Feed' at NRC and Agreement State-Licensed Uranium Recovery Facilities - 12094

    SciTech Connect (OSTI)

    Camper, Larry W.; Michalak, Paul; Cohen, Stephen; Carter, Ted [Nuclear Regulatory Commission (United States)

    2012-07-01T23:59:59.000Z

    Community Water Systems (CWSs) are required to remove uranium from drinking water to meet EPA standards. Similarly, mining operations are required to remove uranium from their dewatering discharges to meet permitted surface water discharge limits. Ion exchange (IX) is the primary treatment strategy used by these operations, which loads uranium onto resin beads. Presently, uranium-loaded resin from CWSs and mining operations can be disposed as a waste product or processed by NRC- or Agreement State-licensed uranium recovery facilities if that licensed facility has applied for and received permission to process 'alternate feed'. The disposal of uranium-loaded resin is costly and the cost to amend a uranium recovery license to accept alternate feed can be a strong disincentive to commercial uranium recovery facilities. In response to this issue, the NRC issued a Regulatory Issue Summary (RIS) to clarify the agency's policy that uranium-loaded resin from CWSs and mining operations can be processed by NRC- or Agreement State-licensed uranium recovery facilities without the need for an alternate feed license amendment when these resins are essentially the same, chemically and physically, to resins that licensed uranium recovery facilities currently use (i.e., equivalent feed). NRC staff is clarifying its current alternate feed policy to declare IX resins as equivalent feed. This clarification is necessary to alleviate a regulatory and financial burden on facilities that filter uranium using IX resin, such as CWSs and mine dewatering operations. Disposing of those resins in a licensed facility could be 40 to 50 percent of the total operations and maintenance (O and M) cost for a CWS. Allowing uranium recovery facilities to treat these resins without requiring a license amendment lowers O and M costs and captures a valuable natural resource. (authors)

  6. Proceedings of the 21st DOE/NRC nuclear air cleaning conference; Volume 2, Sessions 9--16

    SciTech Connect (OSTI)

    First, M.W. [ed.] [Harvard Univ., Boston, MA (United States). Harvard Air Cleaning Lab.

    1991-02-01T23:59:59.000Z

    The 21st meeting of the Department of Energy/Nuclear Regulatory Commission (DOE/NRC) Nuclear Air Cleaning Conference was held in San Diego, CA on August 13--16, 1990. The proceedings have been published as a two volume set. Volume 2 contains sessions covering adsorbents, nuclear codes and standards, modelling, filters, safety, containment venting and a review of nuclear air cleaning programs around the world. Also included is the list of attendees and an index of authors and speakers. (MHB)

  7. NRC Consultation and Monitoring at the Savannah River Site: Focusing Reviews of Two Different Disposal Actions - 12181

    SciTech Connect (OSTI)

    Ridge, A. Christianne; Barr, Cynthia S.; Pinkston, Karen E.; Parks, Leah S.; Grossman, Christopher J.; Alexander, George W. [U.S. Nuclear Regulatory Commission (United States)

    2012-07-01T23:59:59.000Z

    Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA) requires the U.S. Department of Energy (DOE) to consult with the U.S. Nuclear Regulatory Commission (NRC) for certain non-high level waste determinations. The NDAA also requires NRC to monitor DOE's disposal actions related to those determinations. In Fiscal Year 2011, the NRC staff reviewed DOE performance assessments for tank closure at the F-Tank Farm (FTF) Facility and salt waste disposal at the Saltstone Disposal Facility (SDF) at the Savannah River Site (SRS) as part of consultation and monitoring, respectively. Differences in inventories, waste forms, and key barriers led to different areas of focus in the NRC reviews of these two activities at the SRS. Because of the key role of chemically reducing grouts in both applications, the evaluation of chemical barriers was significant to both reviews. However, radionuclide solubility in precipitated metal oxides is expected to play a significant role in FTF performance whereas release of several key radionuclides from the SDF is controlled by sorption or precipitation within the cementitious wasteform itself. Similarly, both reviews included an evaluation of physical barriers to flow, but differences in the physical configurations of the waste led to differences in the reviews. For example, NRC's review of the FTF focused on the modeled degradation of carbon steel tank liners while the staff's review of the SDF performance included a detailed evaluation of the physical degradation of the saltstone wasteform and infiltration-limiting closure cap. Because of the long time periods considered (i.e., tens of thousands of years), the NRC reviews of both facilities included detailed evaluation of the engineered chemical and physical barriers. The NRC staff reviews of residual waste disposal in the FTF and salt waste disposal in the SDF focused on physical barriers to flow and chemical barriers to radionuclide release from the waste. Because the waste inventory and concentration at both sites is sufficient to generate unacceptable doses to an off-site member of the public or inadvertent intruder in the absence of engineered barriers, the NRC staff review focused on the engineering features DOE plans to put in place to limit radionuclide release. At the FTF, DOE expects that peak doses are delayed beyond a 10,000 year performance period by a combination of (1) the flow-limiting effect of the steel tank liner and (2) chemical conditions created by the stabilizing grout overlying the waste that limit the solubility of key radionuclides for tens of thousands of years. At the SDF, DOE expects that flow will be significantly limited by water shedding along the closure cap lower drainage layer and that radionuclide release will be further limited by radionuclide precipitation or sorption within the high pH, chemically reducing conditions created within the saltstone waste form. Because the performance of both facilities depends on the performance of engineered barriers for thousands of years, the reviews included a detailed evaluation of the expected long-term behavior of these barriers. As previously discussed, NRC staff reviews of DOE waste determinations during consultation are designed to evaluate the three NDAA criteria, whereas the review of an updated PA during monitoring only addresses whether the NRC staff has reasonable assurance that the planned disposal action will meet the performance objectives of 10 CFR Part 61. The NRC staff review of the Waste Determination for the FTF did not include conclusions about whether the planned disposal of residual waste at the FTF would meet the NDAA criteria because of the substantial uncertainties in the degree of waste removal DOE would achieve and other technical uncertainties. The main product of the NRC staff review of the planned FTF disposal action is the recommendation that DOE should conduct waste release experiments to increase support for key modeling assumptions related to: (1) the evolution of pH and Eh in the grouted tank syst

  8. Greater-than-Class C low-level radioactive waste characterization. Appendix E-5: Impact of the 1993 NRC draft Branch Technical Position on concentration averaging of greater-than-Class C low-level radioactive waste

    SciTech Connect (OSTI)

    Tuite, P.; Tuite, K.; Harris, G. [Waste Management Group, Inc., Peekskill, NY (United States)

    1994-09-01T23:59:59.000Z

    This report evaluates the effects of concentration averaging practices on the disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) generated by the nuclear utility industry and sealed sources. Using estimates of the number of waste components that individually exceed Class C limits, this report calculates the proportion that would be classified as GTCC LLW after applying concentration averaging; this proportion is called the concentration averaging factor. The report uses the guidance outlined in the 1993 Nuclear Regulatory Commission (NRC) draft Branch Technical Position on concentration averaging, as well as waste disposal experience at nuclear utilities, to calculate the concentration averaging factors for nuclear utility wastes. The report uses the 1993 NRC draft Branch Technical Position and the criteria from the Barnwell, South Carolina, LLW disposal site to calculate concentration averaging factors for sealed sources. The report addresses three waste groups: activated metals from light water reactors, process wastes from light-water reactors, and sealed sources. For each waste group, three concentration averaging cases are considered: high, base, and low. The base case, which is the most likely case to occur, assumes using the specific guidance given in the 1993 NRC draft Branch Technical Position on concentration averaging. To project future GTCC LLW generation, each waste category is assigned a concentration averaging factor for the high, base, and low cases.

  9. EPRI/NRC-RES fire PRA guide for nuclear power facilities. Volume 1, summary and overview.

    SciTech Connect (OSTI)

    Not Available

    2004-09-01T23:59:59.000Z

    This report documents state-of-the-art methods, tools, and data for the conduct of a fire Probabilistic Risk Assessment (PRA) for a commercial nuclear power plant (NPP) application. The methods have been developed under the Fire Risk Re-quantification Study. This study was conducted as a joint activity between EPRI and the U. S. NRC Office of Nuclear Regulatory Research (RES) under the terms of an EPRI/RES Memorandum of Understanding [RS.1] and an accompanying Fire Research Addendum [RS.2]. Industry participants supported demonstration analyses and provided peer review of this methodology. The documented methods are intended to support future applications of Fire PRA, including risk-informed regulatory applications. The documented method reflects state-of-the-art fire risk analysis approaches. The primary objective of the Fire Risk Study was to consolidate recent research and development activities into a single state-of-the-art fire PRA analysis methodology. Methodological issues raised in past fire risk analyses, including the Individual Plant Examination of External Events (IPEEE) fire analyses, have been addressed to the extent allowed by the current state-of-the-art and the overall project scope. Methodological debates were resolved through a consensus process between experts representing both EPRI and RES. The consensus process included a provision whereby each major party (EPRI and RES) could maintain differing technical positions if consensus could not be reached. No cases were encountered where this provision was invoked. While the primary objective of the project was to consolidate existing state-of-the-art methods, in many areas, the newly documented methods represent a significant advancement over previously documented methods. In several areas, this project has, in fact, developed new methods and approaches. Such advances typically relate to areas of past methodological debate.

  10. SSI sensitivity studies and model improvements for the US NRC Seismic Safety Margins Research Program. Rev. 1

    SciTech Connect (OSTI)

    Johnson, J.J.; Maslenikov, O.R.; Benda, B.J.

    1984-10-01T23:59:59.000Z

    The Seismic Safety Margins Research Program (SSMRP) is a US NRC-funded program conducted by Lawrence Livermore National Laboratory. Its goal is to develop a complete fully coupled analysis procedure for estimating the risk of an earthquake-induced radioactive release from a commercial nuclear power plant. In Phase II of the SSMRP, the methodology was applied to the Zion nuclear power plant. Three topics in the SSI analysis of Zion were investigated and reported here - flexible foundation modeling, structure-to-structure interaction, and basemat uplift. The results of these investigations were incorporated in the SSMRP seismic risk analysis. 14 references, 51 figures, 13 tables.

  11. US NRC-Sponsored Research on Stress Corrosion Cracking Susceptibility of Dry Storage Canister Materials in Marine Environments - 13344

    SciTech Connect (OSTI)

    Oberson, Greg; Dunn, Darrell [U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Washington DC, 20555 (United States)] [U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Washington DC, 20555 (United States); Mintz, Todd; He, Xihua; Pabalan, Roberto; Miller, Larry [Center for Nuclear Waste Regulatory Analyses, 6220 Culebra Rd, San Antonio TX, 78238 (United States)] [Center for Nuclear Waste Regulatory Analyses, 6220 Culebra Rd, San Antonio TX, 78238 (United States)

    2013-07-01T23:59:59.000Z

    At a number of locations in the U.S., spent nuclear fuel (SNF) is maintained at independent spent fuel storage installations (ISFSIs). These ISFSIs, which include operating and decommissioned reactor sites, Department of Energy facilities in Idaho, and others, are licensed by the U.S. Nuclear Regulatory Commission (NRC) under Title 10 of the Code of Federal Regulations, Part 72. The SNF is stored in dry cask storage systems, which most commonly consist of a welded austenitic stainless steel canister within a larger concrete vault or overpack vented to the external atmosphere to allow airflow for cooling. Some ISFSIs are located in marine environments where there may be high concentrations of airborne chloride salts. If salts were to deposit on the canisters via the external vents, a chloride-rich brine could form by deliquescence. Austenitic stainless steels are susceptible to chloride-induced stress corrosion cracking (SCC), particularly in the presence of residual tensile stresses from welding or other fabrication processes. SCC could allow helium to leak out of a canister if the wall is breached or otherwise compromise its structural integrity. There is currently limited understanding of the conditions that will affect the SCC susceptibility of austenitic stainless steel exposed to marine salts. NRC previously conducted a scoping study of this phenomenon, reported in NUREG/CR-7030 in 2010. Given apparent conservatisms and limitations in this study, NRC has sponsored a follow-on research program to more systematically investigate various factors that may affect SCC including temperature, humidity, salt concentration, and stress level. The activities within this research program include: (1) measurement of relative humidity (RH) for deliquescence of sea salt, (2) SCC testing within the range of natural absolute humidity, (3) SCC testing at elevated temperatures, (4) SCC testing at high humidity conditions, and (5) SCC testing with various applied stresses. Results to date indicate that the deliquescence RH for sea salt is close to that of MgCl{sub 2} pure salt. SCC is observed between 35 and 80 deg. C when the ambient (RH) is close to or higher than this level, even for a low surface salt concentration. (authors)

  12. Nuclear Crisis Communications: The Plan Worked. A Critique of NRC Communications in the Fukushima Daiichi Reactor Crisis - 12073

    SciTech Connect (OSTI)

    Brenner, Eliot; Harrington, Holly; Schmidt, Rebecca [U.S. Nuclear Regulatory Commission, Rockville, MD 20852 (United States)

    2012-07-01T23:59:59.000Z

    'Call the AV-Photo folks and get someone in here to shoot b-roll. We'll never be able to accommodate the network cameras and the only way I can get this to the media is to produce it ourselves'. Eliot Brenner, Director NRC Office of Public Affairs, March 12, 2011. For the past four years we have been speaking to audiences at Waste Management about communications issues. Last year, though we were kept from attending because of the federal budget crisis, our surrogates described to you the lessons the nuclear industry should draw from the BP Gulf oil spill crisis. Those remarks were delivered 11 days before the Fukushima Daiichi tragedy became the nuclear landmark of a generation - an industry changing event with worldwide ramifications, both in science and regulation and in communications. Eliot Brenner cut his teeth on crisis communication in the aviation industry where tragedy unfolds rapidly. He has been a speech-writer to three cabinet secretaries, spokesman for the Federal Aviation Administration and now spokesman for the Nuclear Regulatory Commission since 2004. Holly Harrington manages the NRC crisis response program and has 26 years federal public affairs experience, including eight years at the Federal Emergency Management Agency. Her crisis experience includes the 1989 Loma Prieta earthquake, numerous hurricanes and floods, Sept 11, and, now Fukushima Daiichi. Rebecca Schmidt is a veteran government relations professional whose decades in Washington include service with the House Armed Services Committee, the House Budget Committee and the Secretary of Defense. Collectively, the Offices of Public Affairs and Congressional Affairs conducted the largest outreach for the agency since Three Mile Island. We worked with the basic rule, described to Waste Management last year just 11 days before Fukushima - communicate early, often and clearly. The response - while not without its problems and lessons - went as smoothly as a chaotic event like Fukushima could go. That was due in large measure to the fact that the NRC has a well-tested system of responding to nuclear emergencies, and we followed our plan. (authors)

  13. Can. J. Fish. Aquat. Sci. 61: 11131123 (2004) doi: 10.1139/F04-061 2004 NRC Canada Influence of shoreline features on fish distribution

    E-Print Network [OSTI]

    McMaster University

    1113 Can. J. Fish. Aquat. Sci. 61: 1113­1123 (2004) doi: 10.1139/F04-061 © 2004 NRC Canada Influence of shoreline features on fish distribution in the Laurentian Great Lakes A. Wei, P. Chow-Fraser, and D. Albert Abstract: In this paper, we used assembled fish distributions (over 9500 field

  14. From 1998 to 2000, through the Interagency Steering Committee on Radiation Standards (ISCORS), the U.S. Nuclear Regulatory Commission (NRC) and the U.S. Environmental

    E-Print Network [OSTI]

    naturally occurring radioactivity, and (3) support rulemaking decisions by NRC and EPA. The voluntary survey of naturally occurring radioactive material (NORM). Altogether 311 sewage sludge samples and 35 ash samples#12;#12;iii ABSTRACT From 1998 to 2000, through the Interagency Steering Committee on Radiation

  15. NRC safety research in support of regulation. Volume 8, FY 1993

    SciTech Connect (OSTI)

    Not Available

    1994-06-01T23:59:59.000Z

    This report, the ninth in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1993. A special emphasis on accomplishments in nuclear power plant aging research reflects recognition that number of plants are entering the final portion of their original 40-year operating licenses and that, in addition to current aging effects, a focus on safety considerations for license renewal becomes timely. The primary purpose of performing regulatory research is to develop and provide the Commission and its staff with sound technical bases for regulatory decisions on the safe operation of licensed nuclear reactors and facilities, to find unknown or unexpected safety problems, and to develop data and related information for the purpose of revising the Commission`s rules, regulatory guides, or other guidance.

  16. Ground-water flow and transport modeling of the NRC-licensed waste disposal facility, West Valley, New York

    SciTech Connect (OSTI)

    Kool, J.B.; Wu, Y.S. (HydroGeoLogic, Inc., Herndon, VA (United States))

    1991-10-01T23:59:59.000Z

    This report describes a simulation study of groundwater flow and radionuclide transport from disposal at the NRC licensed waste disposal facility in West Valley, New York. A transient, precipitation driven, flow model of the near-surface fractured till layer and underlying unweathered till was developed and calibrated against observed inflow data into a recently constructed interceptor trench for the period March--May 1990. The results suggest that lateral flow through the upper, fractured till layer may be more significant than indicated by previous, steady state flow modeling studies. A conclusive assessment of the actual magnitude of lateral flow through the fractured till could however not be made. A primary factor contributing to this uncertainty is the unknown contribution of vertical infiltration through the interceptor trench cap to the total trench inflow. The second part of the investigation involved simulation of the migration of Sr-90, Cs-137 and Pu-239 from the one of the fuel hull disposal pits. A first-order radionuclide leach rate with rate coefficient of 10{sup {minus}6}/day was assumed to describe radionuclide release into the disposal pit. The simulations indicated that for wastes buried below the fractured till zone, no significant migration would occur. However, under the assumed conditions, significant lateral migration could occur for radionuclides present in the upper, fractured till zone. 23 refs., 68 figs., 12 tabs.

  17. Application of the NUREG/CR-6850 EPRI/NRC Fire PRA Methodology to a DOE Facility

    SciTech Connect (OSTI)

    Tom Elicson; Bentley Harwood; Richard Yorg; Heather Lucek; Jim Bouchard; Ray Jukkola; Duan Phan

    2011-03-01T23:59:59.000Z

    The application NUREG/CR-6850 EPRI/NRC fire PRA methodology to DOE facility presented several challenges. This paper documents the process and discusses several insights gained during development of the fire PRA. A brief review of the tasks performed is provided with particular focus on the following: • Tasks 5 and 14: Fire-induced risk model and fire risk quantification. A key lesson learned was to begin model development and quantification as early as possible in the project using screening values and simplified modeling if necessary. • Tasks 3 and 9: Fire PRA cable selection and detailed circuit failure analysis. In retrospect, it would have been beneficial to perform the model development and quantification in 2 phases with detailed circuit analysis applied during phase 2. This would have allowed for development of a robust model and quantification earlier in the project and would have provided insights into where to focus the detailed circuit analysis efforts. • Tasks 8 and 11: Scoping fire modeling and detailed fire modeling. More focus should be placed on detailed fire modeling and less focus on scoping fire modeling. This was the approach taken for the fire PRA. • Task 14: Fire risk quantification. Typically, multiple safe shutdown (SSD) components fail during a given fire scenario. Therefore dependent failure analysis is critical to obtaining a meaningful fire risk quantification. Dependent failure analysis for the fire PRA presented several challenges which will be discussed in the full paper.

  18. PRA In Design: Increasing Confidence in Pre-operational Assessments of Risks (Results of a Joint NASA/ NRC Workshop)

    SciTech Connect (OSTI)

    Robert Youngblood

    2010-06-01T23:59:59.000Z

    In late 2009, the National Aeronautics and Space Administration (NASA) and the U.S. Nuclear Regulatory Commission (NRC) jointly organized a workshop to discuss technical issues associated with application of risk assessments to early phases of system design. The workshop, which was coordinated by the Idaho National Laboratory, involved invited presentations from a number of PRA experts in the aerospace and nuclear fields and subsequent discussion to address the following questions: (a) What technical issues limit decision-makers’ confidence in PRA results, especially at a preoperational phase of the system life cycle? (b) What is being done to address these issues? (c) What more can be done? The workshop resulted in participant observations and suggestions on several technical issues, including the pursuit of non-traditional approaches to risk assessment and the verification and validation of risk models. The workshop participants also identified several important non-technical issues, including risk communication with decision makers, and the integration of PRA into the overall design process.

  19. NRC Form 741

    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 ofElectronic InputNuclear Approved:the;Nuclear

  20. NRC Job Code V6060: Extended in-situ and real time monitoring. Task 4: Detection and monitoring of leaks at nuclear power plants external to structures

    SciTech Connect (OSTI)

    Sheen, S. H. (Nuclear Engineering Division)

    2012-08-01T23:59:59.000Z

    In support of Task 4 of the NRC study on compliance with 10 CFR part 20.1406, minimization of contamination, Argonne National Laboratory (ANL) conducted a one-year scoping study, in concert with a parallel study performed by NRC/NRR staff, on monitoring for leaks at nuclear power plants (NPPs) external to structures. The objective of this task-4 study is to identify and assess those sensors and monitoring techniques for early detection of abnormal radioactive releases from the engineered facility structures, systems and components (SSCs) to the surrounding underground environment in existing NPPs and planned new reactors. As such, methods of interest include: (1) detection of anomalous water content of soils surrounding SSCs, (2) radionuclides contained in the leaking water, and (3) secondary signals such as temperature. ANL work scope includes mainly to (1) identify, in concert with the nuclear industry, the sensors and techniques that have most promise to detect radionuclides and/or associated chemical releases from SSCs of existing NPPs and (2) review and provide comments on the results of the NRC/NRR staff scoping study to identify candidate technologies. This report constitutes the ANL deliverable of the task-4 study. It covers a survey of sensor technologies and leak detection methods currently applied to leak monitoring at NPPs. The survey also provides a technology evaluation that identifies their strength and deficiency based on their detection speed, sensitivity, range and reliability. Emerging advanced technologies that are potentially capable of locating releases, identifying the radionuclides, and estimating their concentrations and distributions are also included in the report along with suggestions of required further research and development.

  1. Final Environmental Impact Statement for the construction and operation of Claiborne Enrichment Center, Homer, Louisiana (Docket No. 70-3-70). Volume 2, Public comments and NRC response

    SciTech Connect (OSTI)

    Zeitoun, A. [Science Applications International Corp., Germantown, MD (United States)

    1994-08-01T23:59:59.000Z

    The Final Environmental Impact Statement (FEIS) (Volume 1), was prepared by the Nuclear Regulatory Commission (NRC) in accordance with regulation 10 CFR Part 51, which implements the National Environmental Policy Act (NEPA), to assess the potential environmental impacts for licensing the construction and operation of a proposed gaseous centrifuge enrichment facility to be built in Claiborne Parish, Louisiana by Louisiana Energy Services, L.P. (LES). The proposed facility would have a production capacity of about 866 metric tons annually of up to 5 weight percent enriched UF{sub 6}, using a proven centrifuge technology. Included in the assessment are co on, both normal operations and potential accidents (internal and external events), and the eventual decontamination and decommissioning of the site. In order to help assure that releases from the operation of the facility and potential impacts on the public are as low as reasonably achievable, an environmental monitoring program was developed by LES to detect significant changes in the background levels of uranium around the site. Other issues addressed include the purpose and need for the facility, the alternatives to the proposed action, potential disposition of the tails, the site selection process, and environmental justice. The NRC staff concludes that the facility can be constructed and operated with small and acceptable impacts on the public and the environment, and proposes to issue a license to the applicant, Louisiana Energy Services, to authorize construction and operation of the proposed facility. The letters in this Appendix have been divided into three sections. Section One contains letters to which the NRC responded by addressing specific comments. Section Two contains the letters that concerned the communities of Forest Grove and Center Springs. Section Three is composed of letters that required no response. These letters were generally in support of the facility.

  2. Nuclear waste management technical support in the development of nuclear waste form criteria for the NRC. Task 1. Waste package overview

    SciTech Connect (OSTI)

    Dayal, R.; Lee, B.S.; Wilke, R.J.; Swyler, K.J.; Soo, P.; Ahn, T.M.; McIntyre, N.S.; Veakis, E.

    1982-02-01T23:59:59.000Z

    In this report the current state of waste package development for high level waste, transuranic waste, and spent fuel in the US and abroad has been assessed. Specifically, reviewed are recent and on-going research on various waste forms, container materials and backfills and tentatively identified those which are likely to perform most satisfactorily in the repository environment. Radiation effects on the waste package components have been reviewed and the magnitude of these effects has been identified. Areas requiring further research have been identified. The important variables affecting radionuclide release from the waste package have been described and an evaluation of regulatory criteria for high level waste and spent fuel is presented. Finally, for spent fuel, high level, and TRU waste, components which could be used to construct a waste package having potential to meet NRC performance requirements have been described and identified.

  3. Validation of the U.S. NRC coupled code system TRITON/TRACE/PARCS with the special power excursion reactor test III (SPERT III)

    SciTech Connect (OSTI)

    Wang, R. C.; Xu, Y.; Downar, T. [Dept. of Nuclear Engineering and Radiological Sciences, Univ. of Michigan, Ann Arbor, MI 48104 (United States); Hudson, N. [RES Div., U.S. NRC, Rockville, MD (United States)

    2012-07-01T23:59:59.000Z

    The Special Power Excursion Reactor Test III (SPERT III) was a series of reactivity insertion experiments conducted in the 1950's. This paper describes the validation of the U.S. NRC Coupled Code system TRITON/PARCS/TRACE to simulate reactivity insertion accidents (RIA) by using several of the SPERT III tests. The work here used the SPERT III E-core configuration tests in which the RIA was initiated by ejecting a control rod. The resulting super-prompt reactivity excursion and negative reactivity feedback produced the familiar bell shaped power increase and decrease. The energy deposition during such a power peak has important safety consequences and provides validation basis for core coupled multi-physics codes. The transients of five separate tests are used to benchmark the PARCS/TRACE coupled code. The models were thoroughly validated using the original experiment documentation. (authors)

  4. Standards, Guidance and Practices for Improved Data Quality

    SciTech Connect (OSTI)

    Martin B. Sattison

    2010-06-01T23:59:59.000Z

    Since the mid 1980s, the Idaho National Laboratory (INL) has been involved with numerous projects to collect operational reactor data, develop data tools, and trend and analyze that data for the U.S. Nuclear Regulatory Commission (NRC). Because the data are used in subsequent risk analyses, the NRC must have confidence in the quality of the data delivered. The NRC tasked the INL to establish a comprehensive data quality assurance program. A key element of that effort was to establish a set of requirements based on industry and government standards, guidance and good practices. This paper discusses where these were found, the process of extracting the requirements and recommendations from the source materials, and the consolidation of them into a concise set of 22 standards, guidance and practices for technical data quality. While this set was created specifically for the data programs within the NRC’s Office of Research, they have broad application to many high-technology industries.

  5. Guide to NRC reporting and recordkeeping requirements. Compiled from requirements in Title 10 of the U.S. Code of Federal Regulations as codified on December 31, 1993; Revision 1

    SciTech Connect (OSTI)

    Collins, M.; Shelton, B.

    1994-07-01T23:59:59.000Z

    This compilation includes in the first two sections the reporting and recordkeeping requirements applicable to US Nuclear Regulatory Commission (NRC) licensees and applicants and to members of the public. It includes those requirements codified in Title 10 of the code of Federal Regulations, Chapter 1, on December 31, 1993. It also includes, in a separate section, any of those requirements that were superseded or discontinued between January 1992 and December 1993. Finally, the appendix lists mailing and delivery addresses for NRC Headquarters and Regional Offices mentioned in the compilation. The Office of Information Resources Management staff compiled this listing of reporting and recordkeeping requirements to briefly describe each in a single document primarily to help licensees readily identify the requirements. The compilation is not a substitute for the regulations, and is not intended to impose any new requirements or technical positions. It is part of NRC`s continuing efforts to comply with the Paperwork Reduction Act of 1980 and the Office of Management and Budget regulations that mandate effective and efficient Federal information resources management programs.

  6. Analysis of a CRDM Nozzle Break LOCA Without Scram Using the U.S. NRC Coupled Code TRAC-M/PARCS

    SciTech Connect (OSTI)

    Cuadra, A.; Ragusa, J.; Downar, T. [Purdue University, West Lafayette, IN 47907 (United States); Ivanov, K. [The Pennsylvania State University, University Park, PA 16802 (United States)

    2002-07-01T23:59:59.000Z

    Recently, through-wall circumferential cracks in several control rod drive mechanism (CRDM) nozzle penetrations were detected at the Oconee-3 nuclear power plant. The presence of these cracks was seen as a potential precursor to a small break loss of coolant accident. In order to assess the impact of a postulated failure of a CRDM housing, analyses were performed using the U.S. NRC coupled thermal-hydraulics and neutronics code TRAC-M/PARCS. Although deemed highly unlikely, it was assumed that no control rods inserted in order to bound any possible reactivity transient associated with the break. The thermal-hydraulic model used to perform the study is based on an existing model of Oconee, built for PTS analysis, which models the whole plant and some of its control systems. A refined vessel model based on a TMI model was used to increase the resolution of the results and facilitate coupling to PARCS. All relevant ECCS systems were modeled and the control system allowed for, in addition to automatic actions, some assumed operator intervention. In particular, HPI throttling was modeled to maintain the hot leg subcooled at 42 +/- 7 K, and prevent an excessive amount of cold water from being injected into the system. A spatial kinetics analysis of this event was necessary because of the wide range of core conditions which occurred during the transient, from hot full power operation conditions to the cold zero power shutdown state. Analysis of the event with point kinetics and 'best estimate' reactivity coefficients resulted in significant miss-prediction of the core power response. Conversely, the three-dimensional kinetics solution with cross section data generated over the entire range of the event led to a more accurate calculation of the power response and the overall analysis of the system transient response. This paper will describe the analysis of the control rod drive nozzle break event without scram using TRAC-M/PARCS. (authors)

  7. NRC review of Electric Power Research Institute`s advanced light water reactor utility requirements document. Passive plant designs, chapter 1, project number 669

    SciTech Connect (OSTI)

    Not Available

    1994-08-01T23:59:59.000Z

    The Electric Power Research Institute (EPRI) is preparing a compendium of technical requirements, referred to as the {open_quotes}Advanced Light Water Reactor [ALWR] Utility Requirements Document{close_quotes}, that is acceptable to the design of an ALWR power plant. When completed, this document is intended to be a comprehensive statement of utility requirements for the design, construction, and performance of an ALWR power plant for the 1990s and beyond. The Requirements Document consists of three volumes. Volume 1, {open_quotes}ALWR Policy and Summary of Top-Tier Requirements{close_quotes}, is a management-level synopsis of the Requirements Document, including the design objectives and philosophy, the overall physical configuration and features of a future nuclear plant design, and the steps necessary to take the proposed ALWR design criteria beyond the conceptual design state to a completed, functioning power plant. Volume II consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant [approximately 1350 megawatts-electric (MWe)]. Volume III contains utility design requirements for nuclear plants for which passive features will be used in their designs (approximately 600 MWe). In April 1992, the staff of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, issued Volume 1 and Volume 2 (Parts 1 and 2) of its safety evaluation report (SER) to document the results of its review of Volumes 1 and 2 of the Requirements Document. Volume 1, {open_quotes}NRC Review of Electric Power Research Institute`s Advanced Light Water Reactor Utility Requirements Document - Program Summary{close_quotes}, provided a discussion of the overall purpose and scope of the Requirements Document, the background of the staff`s review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review.

  8. NRC review of Electric Power Research Institute`s advanced light water reactor utility requirements document. Passive plant designs, chapters 2-13, project number 669

    SciTech Connect (OSTI)

    Not Available

    1994-08-01T23:59:59.000Z

    The Electric Power Research Institute (EPRI) is preparing a compendium of technical requirements, referred to as the {open_quotes}Advanced Light Water Reactor [ALWR] Utility Requirements Document{close_quotes}, that is acceptable to the design of an ALWR power plant. When completed, this document is intended to be a comprehensive statement of utility requirements for the design, construction, and performance of an ALWR power plant for the 1990s and beyond. The Requirements Document consists of three volumes. Volume I, {open_quotes}ALWR Policy and Summary of Top-Tier Requirements{close_quotes}, is a management-level synopsis of the Requirements Document, including the design objectives and philosophy, the overall physical configuration and features of a future nuclear plant design, and the steps necessary to take the proposed ALWR design criteria beyond the conceptual design state to a completed, functioning power plant. Volume II consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant [approximately 1350 megawatts-electric (MWe)]. Volume III contains utility design requirements for nuclear plants for which passive features will be used in their designs (approximately 600 MWe). In April 1992, the staff of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, issued Volume 1 and Volume 2 (Parts 1 and 2) of its safety evaluation report (SER) to document the results of its review of Volumes 1 and 2 of the Requirements Document. Volume 1, {open_quotes}NRC Review of Electric Power Research Institute`s Advanced Light Water Reactor Utility Requirements Document - Program Summary{close_quotes}, provided a discussion of the overall purpose and scope of the Requirements Document, the background of the staff`s review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review.

  9. Public Comments on the proposed 10 CFR Part 51 rule for renewal of nuclear power plant operating licenses and supporting documents: Review of concerns and NRC staff response. Appendices

    SciTech Connect (OSTI)

    NONE

    1996-05-01T23:59:59.000Z

    This volume contains several appendices. Appendix A contains the list of individuals and organizations providing comments at various stages of the rulemaking process. The names of commenters at the public meetings are listed in the order that they spoke at the meeting; those who submitted written comments are listed by docket number. Appendix B contains the summaries of comments made. Each comment summary is identified by a unique comment number. Appendix C presents the concerns and NRC staff responses. Each concern embodies one or more comments on similar or related issues. The associated comment numbers are referenced for each concern. The concerns are organized by topic areas. A three-letter identifier for the topic, followed by a number, is assigned to each concern.

  10. Regulatory guidance for lightning protection in nuclear power plants

    SciTech Connect (OSTI)

    Kisner, R. A.; Wilgen, J. B.; Ewing, P. D.; Korsah, K. [Oak Ridge National Laboratory, P. O. Box 2008, Oak Ridge, TN 37831-6007 (United States); Antonescu, C. E. [U.S. Nuclear Regulatory Commission, Washington, DC 20555 (United States)

    2006-07-01T23:59:59.000Z

    Oak Ridge National Laboratory (ORNL) was engaged by the U.S. Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research (RES) to develop the technical basis for regulatory guidance to address design and implementation practices for lightning protection systems in nuclear power plants (NPPs). Lightning protection is becoming increasingly important with the advent of digital and low-voltage analog systems in NPPs. These systems have the potential to be more vulnerable than older analog systems to the resulting power surges and electromagnetic interference (EMI) when lightning strikes facilities or power lines. This paper discusses the technical basis for guidance to licensees and applicants covered in Regulatory Guide (RG) 1.204, Guidelines for Lightning Protection of Nuclear Power Plants, issued August 2005. RG 1.204 describes guidance for practices that are acceptable to the NRC staff for protecting nuclear power structures and systems from direct lightning strikes and the resulting secondary effects. (authors)

  11. Regulatory Guidance for Lightning Protection in Nuclear Power Plants

    SciTech Connect (OSTI)

    Kisner, Roger A [ORNL; Wilgen, John B [ORNL; Ewing, Paul D [ORNL; Korsah, Kofi [ORNL; Antonescu, Christina E [ORNL

    2006-01-01T23:59:59.000Z

    Abstract - Oak Ridge National Laboratory (ORNL) was engaged by the U.S. Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research (RES) to develop the technical basis for regulatory guidance to address design and implementation practices for lightning protection systems in nuclear power plants (NPPs). Lightning protection is becoming increasingly important with the advent of digital and low-voltage analog systems in NPPs. These systems have the potential to be more vulnerable than older analog systems to the resulting power surges and electromagnetic interference (EMI) when lightning strikes facilities or power lines. This paper discusses the technical basis for guidance to licensees and applicants covered in Regulatory Guide (RG) 1.204, Guidelines for Lightning Protection of Nuclear Power Plants, issued August 2005. RG 1.204 describes guidance for practices that are acceptable to the NRC staff for protecting nuclear power structures and systems from direct lightning strikes and the resulting secondary effects.

  12. Scenario guidance handbook for emergency-preparedness exercises at nuclear facilities

    SciTech Connect (OSTI)

    Laughlin, G.J.; Martin, G.F.; Desrosiers, A.E.

    1983-01-01T23:59:59.000Z

    As part of the Emergency Preparedness Implementation Appraisal Program conducted by the Nuclear Regulatory Commission (NRC) with the technical assistance of the Pacific Northwest Laboratory (PNL), emergency preparedness exercises are observed on an annual basis at all licensed reactor facilities. One of the significant findings to arise from these observations was that a large number of the commonly observed problems originated in the design of the scenarios used as a basis for each exercise. In an effort to help eliminate some of these problems a scenario guidance handbook has been generated by PNL for the NRC to assist nuclear power plant licensees in developing scenarios for emergency preparedness exercises.

  13. RH Packaging Program Guidance

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2006-11-07T23:59:59.000Z

    The purpose of this program guidance document is to provide the technical requirements for use, operation, inspection, and maintenance of the RH-TRU 72-B Waste Shipping Package and directly related components. This document complies with the requirements as specified in the RH-TRU 72-B Safety Analysis Report for Packaging (SARP), and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9212. If there is a conflict between this document and the SARP and/or C of C, the C of C shall govern. The C of C states: "...each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application." It further states: "...each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP tasks the Waste Isolation Pilot Plant (WIPP) Management and Operating (M&O) Contractor with assuring the packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with 10 Code of Federal Regulations (CFR) §71.8, "Deliberate Misconduct." Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) shall be notified immediately. CBFO will evaluate the issue and notify the NRC if required. In accordance with 10 CFR Part 71, "Packaging and Transportation of Radioactive Material," certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21, "Reporting of Defects and Noncompliance," regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to these regulations are conducted. This document details the instructions to be followed to operate, maintain, and test the RH-TRU 72-B packaging. This Program Guidance standardizes instructions for all users. Users shall follow these instructions or equivalent approved instructions. Following these instructions assures that operations meet the requirements of the SARP.

  14. RH Packaging Program Guidance

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2008-01-12T23:59:59.000Z

    The purpose of this program guidance document is to provide the technical requirements for use, operation, inspection, and maintenance of the RH-TRU 72-B Waste Shipping Package (also known as the "RH-TRU 72-B cask") and directly related components. This document complies with the requirements as specified in the RH-TRU 72-B Safety Analysis Report for Packaging (SARP), and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9212. If there is a conflict between this document and the SARP and/or C of C, the C of C shall govern. The C of C states: "...each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application." It further states: "...each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP tasks the Waste Isolation Pilot Plant (WIPP) Management and Operating (M&O) Contractor with assuring the packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations (CFR) §71.8, "Deliberate Misconduct." Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required.In accordance with 10 CFR Part 71, "Packaging and Transportation of Radioactive Material," certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21, "Reporting of Defects and Noncompliance," regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to these regulations are conducted. This document details the instructions to be followed to operate, maintain, and test the RH-TRU 72-B packaging. This Program Guidance standardizes instructions for all users. Users shall follow these instructions or equivalent approved instructions. Following these instructions assures that operations meet the requirements of the SARP.

  15. Guidance

    Broader source: Energy.gov [DOE]

    This site provides a centralized topical resource for enforceable DOE and federal health, safety and security requirements and related guidance documents. DOE’s guidance documents support understanding, ensure technical and management capabilities and collaborative improvement efforts.

  16. RESEARCH CENTRES GRID National Research Centres (NRC)

    E-Print Network [OSTI]

    F2 Battery House Waite Sports Ground (Fullarton Rd) C6 Waite Oval EATING PLACES Lirra Lirra Café E2 Arboretum (Inset) B6 BBQ Area - Gum Oval C2 BBQ Area - Waterhole D6 Garden of Discovery F1 McLeod House Union (AUU) Office / Shop E2 McLeod House, G External Studies Office D2 Charles Hawker, G Student

  17. Material Balance Report NRC 742u

    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 theOFFICEACMEFUTUREMain Draft SEIS References11.a

  18. Material Balance Report NRC 742u

    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 theOFFICEACMEFUTUREMain Draft SEIS

  19. Material Balance Report NRC 742u

    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 theOFFICEACMEFUTUREMain Draft SEIS *** Company Name

  20. Material Balance Report NRC 742u

    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 theOFFICEACMEFUTUREMain Draft SEIS *** Company

  1. Material Balance Report NRC 742u

    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 theOFFICEACMEFUTUREMain Draft SEIS ***

  2. Physical Inventory Listing NRC 742cu

    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 VEGAS POLICESpecial Analysis of1

  3. Physical Inventory Listing NRC 742cu

    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 VEGAS POLICESpecial Analysis

  4. Physical Inventory Listing NRC 742cu

    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 VEGAS POLICESpecial

  5. Sample Form DOE NRC 740M

    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 Reviewwill help prepare local students forStorm WaterCONCISE

  6. o:\informs\fixforms\nrc741.wpf

    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 EnergyEnergyENERGYWomen Owned SmallOf TheViolationsRio Blanco ResponsibleSuiteFrom: Larry HunteruTHEFORM

  7. NRC Licensing Strategy Development for the NGNP

    SciTech Connect (OSTI)

    Mark R. Holbrook; Trevor Cook

    2008-09-01T23:59:59.000Z

    The Next Generation Nuclear Plant (NGNP) project will provide the basis for commercialization of a new generation of advanced nuclear plants that utilize hightemperature gas-cooled reactor (HTGR) technology. The inherently safe HTGR design characteristics can be utilized to supply high-temperature process heat, co-generated electricity, and/or hydrogen for a number of industrial applications (e.g., petrochemical processes). Completion of the NGNP will result in a facility that demonstrates the safety and economics of the design, the commercial industrial potential of the technology, and the viability of the licensing strategy.

  8. NRC Solomons RFQ | 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 CenterFranconia, Virginia: Energy Resources Jump to:46 -Energieprojekte3Information Exploration/DevelopmentLegalSolomons RFQ Jump to:

  9. ARM - Campaign Instrument - nrc-convair580

    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 DesertgovInstrumentsap-surfgovInstrumentsnfov Comments? We would love to

  10. Regulatory guidance document

    SciTech Connect (OSTI)

    NONE

    1994-05-01T23:59:59.000Z

    The Office of Civilian Radioactive Waste Management (OCRWM) Program Management System Manual requires preparation of the OCRWM Regulatory Guidance Document (RGD) that addresses licensing, environmental compliance, and safety and health compliance. The document provides: regulatory compliance policy; guidance to OCRWM organizational elements to ensure a consistent approach when complying with regulatory requirements; strategies to achieve policy objectives; organizational responsibilities for regulatory compliance; guidance with regard to Program compliance oversight; and guidance on the contents of a project-level Regulatory Compliance Plan. The scope of the RGD includes site suitability evaluation, licensing, environmental compliance, and safety and health compliance, in accordance with the direction provided by Section 4.6.3 of the PMS Manual. Site suitability evaluation and regulatory compliance during site characterization are significant activities, particularly with regard to the YW MSA. OCRWM`s evaluation of whether the Yucca Mountain site is suitable for repository development must precede its submittal of a license application to the Nuclear Regulatory Commission (NRC). Accordingly, site suitability evaluation is discussed in Chapter 4, and the general statements of policy regarding site suitability evaluation are discussed in Section 2.1. Although much of the data and analyses may initially be similar, the licensing process is discussed separately in Chapter 5. Environmental compliance is discussed in Chapter 6. Safety and Health compliance is discussed in Chapter 7.

  11. Implementation of NUREG 1318 guidance within the Yucca Mountain Project

    SciTech Connect (OSTI)

    La Monica, L.B.; Waddell, J.D.; Hardin, E.L. [Science Applications International Corp., Las Vegas, NV (USA)

    1990-10-01T23:59:59.000Z

    This paper discusses the implementation of a quality assurance program that fulfills the requirements of the U.S. Nuclear Regulatory Commission (NRC). Additional guidance for this program was provided in NUREG 1318, Technical Position on Items and Activities in the High-Level Waste Geologic Repository Program Subject to Quality Assurance Requirements for the identification of items and activities important to public radiological safety and waste isolation for placement on a Q-List and Quality Activities List and also for graded application of QA measures. The process and organization for implementing this guidance is discussed.

  12. Implementation of NUREG-1318 guidance within the Yucca Mountain Project

    SciTech Connect (OSTI)

    La Monica, L.B.; Waddell, J.D.; Hardin, E.L.

    1990-04-01T23:59:59.000Z

    The US Department of Energy`s Yucca Mountain Project is implementing a quality assurance program that fulfills the requirements of the US Nuclear Regulatory Commission (NRC). Additional guidance for this program was provided in NUREG 1318, ``Technical Position on Items and Activities in the High-Level Waste Geologic Repository Program Subject to Quality Assurance Requirements`` for identification of items and activities important to public radiological safety and waste isolation. The process and organization for implementing this guidance is discussed. 3 refs., 2 figs.

  13. Codes and standards and other guidance cited in regulatory documents

    SciTech Connect (OSTI)

    Nickolaus, J.R.; Bohlander, K.L.

    1996-08-01T23:59:59.000Z

    As part of the U.S. Nuclear Regulatory Commission (NRC) Standard Review Plan Update and Development Program (SRP-UDP), Pacific Northwest National Laboratory developed a listing of industry consensus codes and standards and other government and industry guidance referred to in regulatory documents. The SRP-UDP has been completed and the SRP-Maintenance Program (SRP-MP) is now maintaining this listing. Besides updating previous information, Revision 3 adds approximately 80 citations. This listing identifies the version of the code or standard cited in the regulatory document, the regulatory document, and the current version of the code or standard. It also provides a summary characterization of the nature of the citation. This listing was developed from electronic searches of the Code of Federal Regulations and the NRC`s Bulletins, Information Notices, Circulars, Enforcement Manual, Generic Letters, Inspection Manual, Policy Statements, Regulatory Guides, Standard Technical Specifications and the Standard Review Plan (NUREG-0800).

  14. EMI/RFI and Power Surge Withstand Guidance for the U.S. Nuclear Regulatory Commission

    SciTech Connect (OSTI)

    Ewing, PD

    2001-09-07T23:59:59.000Z

    This paper discusses the regulatory guidance implemented by U.S. NRC for minimizing malfunctions and upsets in safety-related instrumentation and control (I and C) systems in nuclear power plants caused by electromagnetic interference (EMI), radio-frequency interference (RFI), and power surges. The engineering design, installation, and testing practices deemed acceptable to U.S. NRC are described in Regulatory Guide (RG) 1.180, ''Guidelines for Evaluating Electromagnetic and Radio-Frequency in Safety-Related Instrumentation and Control Systems'' (January 2000) and in a Safety Evaluation Report (SER) endorsing EPRI TR-102323, ''Guidelines for Electromagnetic Interference Testing in Power Plants,'' (April 1996). These engineering practices provide a well-established, systematic approach for ensuring electromagnetic compatibility (EMC) and surge withstand capability (SWC).

  15. RH Packaging Program Guidance

    SciTech Connect (OSTI)

    Washington TRU Solutions, LLC

    2003-08-25T23:59:59.000Z

    The purpose of this program guidance document is to provide technical requirements for use, operation, inspection, and maintenance of the RH-TRU 72-B Waste Shipping Package and directly related components. This document complies with the requirements as specified in the RH-TRU 72-B Safety Analysis Report for Packaging (SARP), and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9212. If there is a conflict between this document and the SARP and/or C of C, the SARP and/or C of C shall govern. The C of C states: ''...each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, ''Operating Procedures,'' of the application.'' It further states: ''...each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, ''Acceptance Tests and Maintenance Program of the Application.'' Chapter 9.0 of the SARP tasks the Waste Isolation Pilot Plant (WIPP) Management and Operating (M&O) contractor with assuring the packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC approved, users need to be familiar with 10 CFR {section} 71.11, ''Deliberate Misconduct.'' Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. CBFO will evaluate the issue and notify the NRC if required. This document details the instructions to be followed to operate, maintain, and test the RH-TRU 72-B packaging. This Program Guidance standardizes instructions for all users. Users shall follow these instructions. Following these instructions assures that operations are safe and meet the requirements of the SARP. This document is available on the Internet at: ttp://www.ws/library/t2omi/t2omi.htm. Users are responsible for ensuring they are using the current revision and change notices. Sites may prepare their own document using the word-for-word steps in th is document, in sequence, including Notes and cautions. Site specific information may be included as necessary. The document, and revisions, must then be submitted to CBFO at sitedocuments@wipp.ws for approval. A copy of the approval letter from CBFO shall be available for audit purposes. Users may develop site-specific procedures addressing preoperational activities, quality assurance (QA), hoisting and rigging, and radiation health physics to be used with the instructions contained in this document. Users may recommend changes to this document by submitting their recommendations (in writing) to the WIPP M&O Contractor RH Packaging Maintenance Engineer for evaluation. If approved, the change(s) will be incorporated into this document for use by ALL users. Before first use and every 12 months after, user sites will be audited to this document to ensure compliance. They will also be audited within one year from the effective date of revisions to this document.

  16. Applying Human-performance Models to Designing and Evaluating Nuclear Power Plants: Review Guidance and Technical Basis

    SciTech Connect (OSTI)

    O'Hara, J.M.

    2009-11-30T23:59:59.000Z

    Human performance models (HPMs) are simulations of human behavior with which we can predict human performance. Designers use them to support their human factors engineering (HFE) programs for a wide range of complex systems, including commercial nuclear power plants. Applicants to U.S. Nuclear Regulatory Commission (NRC) can use HPMs for design certifications, operating licenses, and license amendments. In the context of nuclear-plant safety, it is important to assure that HPMs are verified and validated, and their usage is consistent with their intended purpose. Using HPMs improperly may generate misleading or incorrect information, entailing safety concerns. The objective of this research was to develop guidance to support the NRC staff's reviews of an applicant's use of HPMs in an HFE program. The guidance is divided into three topical areas: (1) HPM Verification, (2) HPM Validation, and (3) User Interface Verification. Following this guidance will help ensure the benefits of HPMs are achieved in a technically sound, defensible manner. During the course of developing this guidance, I identified several issues that could not be addressed; they also are discussed.

  17. DOE Replies Support NRC Commissioners and Authority to Withdraw...

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

    today, DOE explained that the arguments that it lacked authority to withdraw the pending Yucca Mountain license application are uniformly without merit. DOE's reply brief is...

  18. Proposed Outline for DOE-LM / NRC Working Group Meeting

    Office of Legacy Management (LM)

    Agenda Monticello Mill Tailings Site (MMTS) Operable Unit III Biomonitoring Scope and Status Future Scope of Groundwater Treatment June 27, 2011 (8 a.m. - 1 p.m.) U.S....

  19. PRESENTATION TO NRC BURNING PLASMA PANEL DR. STEPHEN O. DEAN

    E-Print Network [OSTI]

    JANUARY 17, 2003 In response to request by panel co-chair John Ahearne as follows: "We have heard from" #12;2 BOTTOM LINES FUSION IS NOT ON THE RADAR SCREEN OF THE U. S. ELECTRIC UTILITIES ! To get DEVELOPMENT WOULD ALSO ATTRACT INTEREST FROM INDUSTRY GENERAL ATOMICS, FOR HISTORICAL REASONS, IS UNIQUE

  20. Kathy Yelick Co-authors NRC Report on Computer Performance -...

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

    the lab's NERSC Division, was a panelist in a March 22 discussion of "The Future of Computer Performance: Game Over or Next Level?" a new report by the National Research Council....

  1. Predictive Bias and Sensitivity in NRC Fuel Performance Codes

    SciTech Connect (OSTI)

    Geelhood, Kenneth J.; Luscher, Walter G.; Senor, David J.; Cunningham, Mitchel E.; Lanning, Donald D.; Adkins, Harold E.

    2009-10-01T23:59:59.000Z

    The latest versions of the fuel performance codes, FRAPCON-3 and FRAPTRAN were examined to determine if the codes are intrinsically conservative. Each individual model and type of code prediction was examined and compared to the data that was used to develop the model. In addition, a brief literature search was performed to determine if more recent data have become available since the original model development for model comparison.

  2. NRC allows TVA to resume construction on unit 1

    SciTech Connect (OSTI)

    NONE

    1992-01-01T23:59:59.000Z

    The article very briefly describes the construction status of the Tennessee Valley Authority (TVA) Watts Bar Nuclear Plant unit 1. The project was halted by TVA for two years due to quality assurance issues. The US Nuclear Regulatory Commission approved resumption of work, noting that corrective actions were adequate. The status of other TVA reactors is also noted.

  3. Recent MELCOR and VICTORIA Fission Product Research at the NRC

    SciTech Connect (OSTI)

    Bixler, N.E.; Cole, R.K.; Gauntt, R.O.; Schaperow, J.H.; Young, M.F.

    1999-01-21T23:59:59.000Z

    The MELCOR and VICTORIA severe accident analysis codes, which were developed at Sandia National Laboratories for the U. S. Nuclear Regulatory Commission, are designed to estimate fission product releases during nuclear reactor accidents in light water reactors. MELCOR is an integrated plant-assessment code that models the key phenomena in adequate detail for risk-assessment purposes. VICTORIA is a more specialized fission- product code that provides detailed modeling of chemical reactions and aerosol processes under the high-temperature conditions encountered in the reactor coolant system during a severe reactor accident. This paper focuses on recent enhancements and assessments of the two codes in the area of fission product chemistry modeling. Recently, a model for iodine chemistry in aqueous pools in the containment building was incorporated into the MELCOR code. The model calculates dissolution of iodine into the pool and releases of organic and inorganic iodine vapors from the pool into the containment atmosphere. The main purpose of this model is to evaluate the effect of long-term revolatilization of dissolved iodine. Inputs to the model include dose rate in the pool, the amount of chloride-containing polymer, such as Hypalon, and the amount of buffering agents in the containment. Model predictions are compared against the Radioiodine Test Facility (RTF) experiments conduced by Atomic Energy of Canada Limited (AECL), specifically International Standard Problem 41. Improvements to VICTORIA's chemical reactions models were implemented as a result of recommendations from a peer review of VICTORIA that was completed last year. Specifically, an option is now included to model aerosols and deposited fission products as three condensed phases in addition to the original option of a single condensed phase. The three-condensed-phase model results in somewhat higher predicted fission product volatilities than does the single-condensed-phase model. Modeling of U02 thermochemistry was also improved, and results in better prediction of vaporization of uranium from fuel, which can react with released fission products to affect their volatility. This model also improves the prediction of fission product release rates from fuel. Finally, recent comparisons of MELCOR and VICTORIA with International Standard Problem 40 (STORM) data are presented. These comparisons focus on predicted therrnophoretic deposition, which is the dominant deposition mechanism. Sensitivity studies were performed with the codes to examine experimental and modeling uncertainties.

  4. Agenda Highlights: 2012 DOE-NRC NMMSS Annual User Training

    National Nuclear Security Administration (NNSA)

    Initiatives U.S.-Australian Cooperation Agreement AwardsRecognitions Update on Blue Ribbon Commission Report (Tentative) Cyber security Issues and Implications GAO report...

  5. Agenda Highlights: 2012 DOE-NRC NMMSS Annual User Training

    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 | NationalTbilisi | National

  6. Nuclear Material Transaction Report NRC 741_1

    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 ofElectronic InputNuclearNature of7379583ForensicsB 1 1

  7. Nuclear Material Transaction Report NRC 741_1

    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 ofElectronic InputNuclearNature of7379583ForensicsB 1

  8. Nuclear Material Transaction Report NRC741_1

    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 ofElectronic InputNuclearNature of7379583ForensicsB 1C

  9. Nuclear Material Transaction Report nrc741_1

    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 ofElectronic InputNuclearNature of7379583ForensicsB 1C

  10. Nuclear Material Transaction Report nrc741_1

    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 ofElectronic InputNuclearNature of7379583ForensicsB 1C

  11. Nuclear Material Transaction Report nrc741_1

    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 ofElectronic InputNuclearNature of7379583ForensicsB 1C

  12. Nuclear Material Transaction Report nrc741_1

    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 ofElectronic InputNuclearNature of7379583ForensicsB 1C

  13. Nuclear Material Transaction Report nrc741_1

    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 ofElectronic InputNuclearNature of7379583ForensicsB 1C

  14. Nuclear Material Transaction Report nrc741_1

    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 ofElectronic InputNuclearNature of7379583ForensicsB 1C

  15. Nuclear Material Transaction Report nrc741_1

    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 ofElectronic InputNuclearNature of7379583ForensicsB

  16. DOE/NRC F 740M | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGYWomentheATLANTA, GA - U.S. DepartmenttoJune 16,April 29,MayBonnevilleTheNNSA

  17. DOE/NRC F 742 | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGYWomentheATLANTA, GA - U.S. DepartmenttoJune 16,April 29,MayBonnevilleTheNNSAfor nuclear

  18. DOE/NRC F 742C | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGYWomentheATLANTA, GA - U.S. DepartmenttoJune 16,April 29,MayBonnevilleTheNNSAfor

  19. NRC Leadership Expectations and Practices for Sustaining a High Performing

    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 EnergyEnergyENERGY TAXBalanced Scorecard Federal2 to:Diesel Engines|ForeignNNSAFluorOrganization |

  20. Nuclear safety information sharing agreement between NRC and DOE's Office

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:Year in3.pdfEnergyDepartment of Energy Advanced1, 2014NuclearCommission,ScienceWasteandof

  1. Microsoft Word - 0906 NMMSS News DOE NRC Approved.doc

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: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 the Yucca MountainSourceUsers6 SPONSORED BY DOE AND

  2. NRC Institute for Fuel Cell Innovation | 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 CenterFranconia, Virginia: Energy Resources Jump to:46 -Energieprojekte3Information Exploration/DevelopmentLegal

  3. ISDAC - NRC Convair-580 Flight Hours Date Flight

    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 MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun withconfinementEtching. | EMSLthe U.S.;2cSupercomputing: The Top Three-

  4. DOE Replies Support NRC Commissioners and Authority to Withdraw Yucca

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-UpHeat Pump Models | Department of EnergyJanuary 4, 2012 Page 1

  5. Use of Barrier Analysis in NRC Staff's Performance Assessment Reviews |

    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 | Department of Energy SofDelaware EnergyPotomac31, 2013 |Heaters

  6. Jennifer Schaefer > NRC Postdoctoral Fellow - National Institute 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 MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFunInfraredJefferson LabJeffersonStandards and Technology > Center Alumni

  7. Review of Technical Studies in the United States in Support of Burnup Credit Regulatory Guidance

    SciTech Connect (OSTI)

    Wagner, John C [ORNL] [ORNL; Parks, Cecil V [ORNL] [ORNL; Mueller, Don [ORNL] [ORNL; Gauld, Ian C [ORNL] [ORNL

    2010-01-01T23:59:59.000Z

    Taking credit for the reduction in reactivity associated with fuel depletion can enable more cost-effective, higher-density storage, transport, disposal, and reprocessing of spent nuclear fuel (SNF) while maintaining sufficient subcritical margin to establish an adequate safety basis. Consequently, there continues to be considerable interest in the United States (U.S.), as well as internationally, in the increased use of burnup credit in SNF operations, particularly related to storage, transport, and disposal of commercial SNF. This interest has motivated numerous technical studies related to the application of burnup credit, both domestically and internationally, as well as the design of SNF storage, transport and disposal systems that rely on burnup credit for maintaining subcriticality. Responding to industry requests and needs, the U.S. Nuclear Regulatory Commission (NRC) initiated a burnup credit research program in 1999, with support from the Oak Ridge National Laboratory (ORNL), to develop regulatory guidance and the supporting technical bases for allowing and expanding the use of burnup credit in pressurized-water reactor SNF storage and transport applications. Although this NRC research program has not been continuous since its inception, considerable progress has been achieved in many key areas in terms of increased understanding of relevant phenomena and issues, availability of relevant information and data, and subsequently updated regulatory guidance for expanded use of burnup credit. This paper reviews technical studies performed by ORNL for the U.S. NRC burnup credit research program. Examples of topics include reactivity effects associated with reactor operating characteristics, fuel assembly characteristics, burnable absorbers, control rods, spatial burnup distributions, cooling time, and assembly misloading; methods and data for validation of isotopic composition predictions; methods and data for validation of criticality calculations; and operational issues and data related to assembly burnup confirmation. The objective of this paper is to summarize the work and significant accomplishments, with references to the technical reports and publications for complete details, and provide a useful resource to others in the burnup credit community.

  8. Guidance for implementing the long-term surveillance program for UMTRA Project Title I Disposal Sites

    SciTech Connect (OSTI)

    NONE

    1996-02-01T23:59:59.000Z

    This guidance document has two purposes: it provides guidance for writing site-specific long-term surveillance plans (LTSP) and it describes site surveillance, monitoring, and long-term care techniques for Title I disposal sites of the Uranium Mill Tailings Radiation Control Act (UMTRCA) (42 USC Section 7901 et seq.). Long-term care includes monitoring, maintenance, and emergency measures needed to protect public health and safety and the environment after remedial action is completed. This document applies to the UMTRCA-designated Title I disposal sites. The requirements for long-term care of the Title I sites and the contents of the LTSPs are provided in U.S. Nuclear Regulatory Commission (NRC) regulations (10 CFR Section 40.27) provided in Attachment 1.

  9. CH Packaging Program Guidance

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2005-02-28T23:59:59.000Z

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT shipping package, and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and U.S. Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event of a conflict between this document and the SARP or C of C, the C of C shall govern. The C of Cs state: "each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application." They further state: "each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP charges the Waste Isolation Pilot Plant (WIPP) management and operating (M&O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations (CFR) §71.8. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required.

  10. CH Packaging Program Guidance

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2003-04-30T23:59:59.000Z

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT shipping package, and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event of a conflict between this document and the SARP or C of C, the C of C shall govern. The C of Cs state: ''each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application.'' They further state: ''each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application.'' Chapter 9.0 of the SARP charges the WIPP management and operating (M&O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with 10 CFR 71.11. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. CBFO will evaluate the issue and notify the NRC if required. This document provides the instructions to be followed to operate, maintain, and test the TRUPACT-II and HalfPACT packaging. The intent of these instructions is to standardize operations. All users will follow these instructions or equivalent instructions that assure operations are safe and meet the requirements of the SARPs.

  11. CH Packaging Program Guidance

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2002-03-04T23:59:59.000Z

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT Shipping Package, and directly related components. This document complies with the minimum requirements as specified in TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event there is a conflict between this document and the SARP or C of C, the SARP and/or C of C shall govern. C of Cs state: ''each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application.'' They further state: ''each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application.'' Chapter 9.0 of the SAR P charges the WIPP Management and Operation (M&O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with 10 CFR 71.11. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. CBFO will evaluate the issue and notify the NRC if required. This document details the instructions to be followed to operate, maintain, and test the TRUPACT-II and HalfPACT packaging. The intent of these instructions is to standardize these operations. All users will follow these instructions or equivalent instructions that assure operations are safe and meet the requirements of the SARPs.

  12. Human-system Interfaces to Automatic Systems: Review Guidance and Technical Basis

    SciTech Connect (OSTI)

    OHara, J.M.; Higgins, J.C.

    2010-01-31T23:59:59.000Z

    Automation has become ubiquitous in modern complex systems and commercial nuclear power plants are no exception. Beyond the control of plant functions and systems, automation is applied to a wide range of additional functions including monitoring and detection, situation assessment, response planning, response implementation, and interface management. Automation has become a 'team player' supporting plant personnel in nearly all aspects of plant operation. In light of the increasing use and importance of automation in new and future plants, guidance is needed to enable the NRC staff to conduct safety reviews of the human factors engineering (HFE) aspects of modern automation. The objective of the research described in this report was to develop guidance for reviewing the operator's interface with automation. We first developed a characterization of the important HFE aspects of automation based on how it is implemented in current systems. The characterization included five dimensions: Level of automation, function of automation, modes of automation, flexibility of allocation, and reliability of automation. Next, we reviewed literature pertaining to the effects of these aspects of automation on human performance and the design of human-system interfaces (HSIs) for automation. Then, we used the technical basis established by the literature to develop design review guidance. The guidance is divided into the following seven topics: Automation displays, interaction and control, automation modes, automation levels, adaptive automation, error tolerance and failure management, and HSI integration. In addition, we identified insights into the automaton design process, operator training, and operations.

  13. Guidance for implementing the UMTRA Project long-term surveillance program

    SciTech Connect (OSTI)

    Not Available

    1992-09-01T23:59:59.000Z

    The US Nuclear Regulatory Commission (NRC) has issued a general license for the custody and long-term care of US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project permanent disposal sites. The purpose of this general license is to ensure that the UMTRA disposal sites will be cared for in such a manner as to protect the public health and safety and the environment upon completion of remedial actions. The general license will be in effect for a disposal site when NRC accepts the disposal site long-term surveillance plan (LTSP) that meets the requirements of 10 CFR 40.27. The site LTSP describes in detail the long-term surveillance program, including any monitoring, maintenance, and emergency measures necessary to fulfill the conditions of the general license. This guidance document provides (1) instructions for preparing the disposal site LTSPs and (2) instructions for carrying out the UMTRA Project long-term surveillance program, including any monitoring that may be required. The information provided in this document also is in accordance with the regulatory requirements set forth in 40 CFR 192. On January 5, 1985, the US Tenth Circuit Court of Appeals remanded the groundwater standards, 40 CFR 192.02. Proposed groundwater standards were issued for comment on September 24, 1987 (52 FR 3600). When the groundwater standards become final, this document will be revised, as appropriate. This document also will be updated in response to any changes to 10 CFR 40, or in response to changes in the manner in which the long-term care of the licensed disposal sites is carried out.

  14. Guidance for implementing the UMTRA Project long-term surveillance program. Final report, Revision 1

    SciTech Connect (OSTI)

    Not Available

    1992-09-01T23:59:59.000Z

    The US Nuclear Regulatory Commission (NRC) has issued a general license for the custody and long-term care of US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project permanent disposal sites. The purpose of this general license is to ensure that the UMTRA disposal sites will be cared for in such a manner as to protect the public health and safety and the environment upon completion of remedial actions. The general license will be in effect for a disposal site when NRC accepts the disposal site long-term surveillance plan (LTSP) that meets the requirements of 10 CFR 40.27. The site LTSP describes in detail the long-term surveillance program, including any monitoring, maintenance, and emergency measures necessary to fulfill the conditions of the general license. This guidance document provides (1) instructions for preparing the disposal site LTSPs and (2) instructions for carrying out the UMTRA Project long-term surveillance program, including any monitoring that may be required. The information provided in this document also is in accordance with the regulatory requirements set forth in 40 CFR 192. On January 5, 1985, the US Tenth Circuit Court of Appeals remanded the groundwater standards, 40 CFR 192.02. Proposed groundwater standards were issued for comment on September 24, 1987 (52 FR 3600). When the groundwater standards become final, this document will be revised, as appropriate. This document also will be updated in response to any changes to 10 CFR 40, or in response to changes in the manner in which the long-term care of the licensed disposal sites is carried out.

  15. Computer surety: computer system inspection guidance. [Contains glossary

    SciTech Connect (OSTI)

    Not Available

    1981-07-01T23:59:59.000Z

    This document discusses computer surety in NRC-licensed nuclear facilities from the perspective of physical protection inspectors. It gives background information and a glossary of computer terms, along with threats and computer vulnerabilities, methods used to harden computer elements, and computer audit controls.

  16. Technical Guidance

    Broader source: Energy.gov [DOE]

    The Office of Technical Guidance, within the Office of Health, Safety and Security develops and issues Government-wide and Department-wide technical guidance to ensure that classified nuclear...

  17. Microsoft PowerPoint - 4_Paul_NRC MC&A Inspection Summary NMMSS...

    National Nuclear Security Administration (NNSA)

    Inspector preferred not doing this during an outage, but doing it when there are Reactor Services available to move the bridge and perform 10-15 bundle spot check verifications -...

  18. Beta particle measurement and dosimetry Requirements at NRC-licensed facilities

    SciTech Connect (OSTI)

    Rathbun, L.A.; Endres, G.W.R.; Fox, R.A.; Roberson, P.L.; Scherpelz, R.I.

    1984-08-01T23:59:59.000Z

    Researchers from Pacific Northwest Laboratroy (PNL) have conducted beta radiation measurements under laboratory and field conditions to assess the degree of the measurement problem and offer suggestions for possible remedies. The primary measurement systems selected for use in this study were the silicon (Si) surface barrier spectrometer system and the multielement beta dosimeter. Three boiling water reactors (BWRs), two pressurized water reactors (PWRs), and one fuel fabrication facility were visited during the course of the study. Although beta fields from cobalt-60 were the most common type found at commercial reactor facilities, higher energy beta fields were found at locations associated with spent fuel handling, liquid radioactive waste, and BWR turbine components. Commercially-available dosimeters and survey instruments were used to measure the same laboratory and licensee facility beta fields characterized with PNL's active and passive spectrometers. A prototype spectrometer was also used in the laboratory measurements. The commercial instruments and dosimeters used in this study typically responded low to the beta fields measured, especially where maximum beta energies were less than approximately 500 keV.

  19. Microsoft PowerPoint - 7_GARY_LANGLIE_NMMSS 2014 NRC HEU Report...

    National Nuclear Security Administration (NNSA)

    speech 91% of HEU exports occurred before 1990 Most HEU exported to France, Germany, and Canada HEU Imports - 100 200 300 400 500 600 700 800 900 1958 1959 1960 1961...

  20. U.S. NRC CONFIRMATORY LEVEL 1 PRA SUCCESS CRITERIA ACTIVITIES

    SciTech Connect (OSTI)

    Donald Helton; Hossein Esmaili; Robert Buell

    2011-03-01T23:59:59.000Z

    The U.S. Nuclear Regulatory Commission’s standardized plant analysis risk (SPAR) models are used to support a number of risk-informed initiatives. The fidelity and realism of these models are ensured through a number of processes including cross-comparison with industry models, review and use by a wide range of technical experts, and confirmatory analysis. This paper will describe a key activity in the latter arena. Specifically, this paper will describe MELCOR analyses performed to augment the technical basis for confirming or modifying specific success criteria of interest. The analyses that will be summarized provide the basis for confirming or changing success criteria in a specific 3-loop pressurized-water reactor and a Mark-I boiling-water reactor. Initiators that have been analyzed include loss-of-coolant accidents, loss of main feedwater, spontaneous steam generator tube rupture, inadvertent opening of a relief valve at power, and station blackout. For each initiator, specific aspects of the accident evolution are investigated via a targeted set of calculations (3 to 22 distinct accident analyses per initiator). Further evaluation is ongoing to extend the analyses’ conclusions to similar plants (where appropriate), with consideration of design and modeling differences on a scenario-by-scenario basis. This paper will also describe future plans.

  1. Joint NRC/ANS meeting on basic thermal-hydraulic mechanisms in LWR analysis

    SciTech Connect (OSTI)

    Hsu, Y Y; Lee, R [comps.

    1983-04-01T23:59:59.000Z

    Separate abstracts were prepared for 18 papers in this conference proceedings. Three papers are also included in the proceedings that were previously abstracted for EDB. (LEW)

  2. Overview of ORNL/NRC programs addressing durability of concrete structures

    SciTech Connect (OSTI)

    Naus, D.J.; Oland, C.B.

    1994-06-01T23:59:59.000Z

    The role of reinforced concrete relative to its applications as either safety-related structures in nuclear power or engineered barriers of low-level radioactive waste disposal facilities is described. Factors that can affect the long-term durability of reinforced concrete are identified. Overviews are presented of the Structural Aging Program, which is addressing the aging management of safety-related concrete structures in nuclear power plants, and the Permeability Test Methods and Data Program, which is identifying pertinent data and information for use in performance assessments of engineered barriers for low-level radioactive waste disposal.

  3. Microsoft PowerPoint - 12_BRIAN_HORN_NRC and DOE recognition...

    National Nuclear Security Administration (NNSA)

    and - Inventory reconciled within 30 days of receipt - 170 RIS's * 65 reactors * 7 Fuel cycle * 98 Licensees primarily possessing < 350 grams of fissile "Outstanding" in...

  4. NRC Concrete Meeting Busby on Roadmaps_120213_rev1.pptx (Read...

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

    LWRS o ngoing ac;vi;es 2013---2015 Mechanisms Understanding Materials Characteriza:on NDEMonitoring Structural Significance Engineering Valida:on Poten;al R &D g ap 2013---18...

  5. Can. J. Fish. Aquat. Sci. 56: 17001706 (1999) 1999 NRC Canada PERSPECTIVE

    E-Print Network [OSTI]

    Pacifique (Oncorhynchus spp.) de la côte nord-ouest de l'Amérique du Nord ont connu des déclins régionaux et straying from their natal streams during spawning migrations. Management efforts aimed at expediting freshwater habitat in streams w

  6. University of North Carolina at Chapel Hill 2006 NRC Assessment of Research Doctorate Programs

    E-Print Network [OSTI]

    Crews, Stephen

    , Architecture and Archaeology American Art and Architecture; Ancient, Medieval, Renaissance and Baroque Art and Architecture; Asian Art and Architecture; Contemporary Art; Modern Art and Architecture; Theory and Criticism, Biochemistry, Environmental Chemistry, Materials Chemistry, Medicinal- Pharmaceutical Chemistry, Inorganic

  7. http://www.nrc.gov/reading-rm/doc-collections/cfr/part052/full...

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

    fission product release (during the entire period of its passage) would not receive a radiation dose in excess of 25 rem TEDE; (x) Information demonstrating that site...

  8. Dismantling of Loop-Type Channel Equipment of MR Reactor in NRC 'Kurchatov Institute' - 13040

    SciTech Connect (OSTI)

    Volkov, Victor; Danilovich, Alexey; Zverkov, Yuri; Ivanov, Oleg; Kolyadin, Vyacheslav; Lemus, Alexey; Pavlenko, Vitaly; Semenov, Sergey; Fadin, Sergey; Shisha, Anatoly; Chesnokov, Alexander [National Research Centre 'Kurchatov Institute', Moscow (Russian Federation)] [National Research Centre 'Kurchatov Institute', Moscow (Russian Federation)

    2013-07-01T23:59:59.000Z

    In 2009 the project of decommissioning of MR and RTF reactors was developed and approved by the Expert Authority of the Russian Federation (Gosexpertiza). The main objective of the decommissioning works identified in this project: - complete dismantling of reactor equipment and systems; - decontamination of reactor premises and site in accordance with the established sanitary and hygienic standards. At the preparatory stage (2008-2010) of the project the following works were executed: loop-type channels' dismantling in the storage pool; experimental fuel assemblies' removal from spent fuel repositories in the central hall; spent fuel assembly removal from the liquid-metal-cooled loop-type channel of the reactor core and its placement into the SNF repository; and reconstruction of engineering support systems to the extent necessary for reactor decommissioning. The project assumes three main phases of dismantling and decontamination: - dismantling of equipment/pipelines of cooling circuits and loop-type channels, and auxiliary reactor equipment (2011-2012); - dismantling of equipment in underground reactor premises and of both MR and RTF in-vessel devices (2013-2014); - decontamination of reactor premises; rehabilitation of the reactor site; final radiation survey of reactor premises, loop-type channels and site; and issuance of the regulatory authorities' de-registration statement (2015). In 2011 the decommissioning license for the two reactors was received and direct MR decommissioning activities started. MR primary pipelines and loop-type facilities situated in the underground reactor hall were dismantled. Works were also launched to dismantle the loop-type channels' equipment in underground reactor premises; reactor buildings were reconstructed to allow removal of dismantled equipment; and the MR/RTF decommissioning sequence was identified. In autumn 2011 - spring 2012 results of dismantling activities performed are: - equipment from underground rooms (No. 66, 66A, 66B, 72, 64, 63) - as well as from water and gas loop corridors - was dismantled, with the total radwaste weight of 53 tons and the total removed activity of 5,0 x 10{sup 10} Bq; - loop-type channel equipment from underground reactor hall premises was dismantled; - 93 loop-type channels were characterized, chopped and removed, with radwaste of 2.6 x 10{sup 13} Bq ({sup 60}Co) and 1.5 x 10{sup 13} Bq ({sup 137}Cs) total activity removed from the reactor pool, fragmented and packaged. Some of this waste was placed into the high-level waste (HLW) repository of the Center. Dismantling works were executed with application of remotely operated mechanisms, which promoted decrease of radiation impact on the personnel. The average individual dose for the personnel was 1.9 mSv/year in 2011, and the collective dose is estimated as 0.0605 man x Sv/year. (authors)

  9. Microsoft PowerPoint - 5_Pat Smith_NMMSS_2013_Presentation_NRC Reconciliation.pptx

    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

  10. DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant |

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGYWomentheATLANTA, GA - U.S. Departmentto DevelopMark Duff (LATA KY), ChristaDepartment

  11. o:\informs\fixforms\nrc740m.wpf | 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 EnergyEnergyENERGYWomen Owned SmallOf TheViolationsRio Blanco ResponsibleSuiteFrom: Larry HunteruTHE

  12. DOE Does Not Oppose Petitions to Intervene in Yucca Mountain NRC Proceeding

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists'Montana. DOCUMENTSof Energy DOE Challenge HomeEnergy TheofEM Deputy Assistant|

  13. Proceedings of the 21st DOE/NRC Nuclear Air Cleaning Conference; Sessions 1--8

    SciTech Connect (OSTI)

    First, M.W. [ed.] [Harvard Univ., Boston, MA (United States). Harvard Air Cleaning Lab.

    1991-02-01T23:59:59.000Z

    Separate abstracts have been prepared for the papers presented at the meeting on nuclear facility air cleaning technology in the following specific areas of interest: air cleaning technologies for the management and disposal of radioactive wastes; Canadian waste management program; radiological health effects models for nuclear power plant accident consequence analysis; filter testing; US standard codes on nuclear air and gas treatment; European community nuclear codes and standards; chemical processing off-gas cleaning; incineration and vitrification; adsorbents; nuclear codes and standards; mathematical modeling techniques; filter technology; safety; containment system venting; and nuclear air cleaning programs around the world. (MB)

  14. Can. J. Fish. Aquat. Sci. 53: 20442051 (1996). 1996 NRC Canada Seasonal variation of lipid composition,

    E-Print Network [OSTI]

    F. Cavaletto, Thomas F. Nalepa, Ronald Dermott, Wayne S. Gardner, Michael A. Quigley, and Gregory A on fresh food inputs at this time (Quigley 1988; Der- mott and Corning 1988). Diporeia lipid levels.S. Gardner, M.A. Quigley, and G.A. Lang. National Oceanic and Atm

  15. Kathy Yelick Co-authors NRC Report on Computer Performance - NERSC Center

    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-SeriesFlickrinformation forTechnologiesDialysis Provider3KarlKathyNews, Mar 22,

  16. Microsoft Word - NMMSS Newsletter October 2014 Final-NRC 10-16 comments.docx

    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 the Yucca0 National NuclearNationalNovember 20,

  17. 4th Annual NRC Small Business Seminar and Matchmaking Event | Department of

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists' ResearchThe Office of FossilMembership |9 TABLE 10 COSTS OFK-33Energy March 24,

  18. http://www.nrc.gov/reading-rm/doc-collections/cfr/part020/full-

    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 Reviewwill help prepareA ReviewManualREMS DataNews,ForA A20--

  19. http://www.nrc.gov/reading-rm/doc-collections/cfr/part061/full-

    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 Reviewwill help prepareA ReviewManualREMS DataNews,ForA

  20. DOE Makes Filing with NRC in Support OF Authority to Withdraw Yucca

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up fromDepartmentTieCelebratePartnersDepartmentforDOE Lighting Program

  1. NRC Transportation Security (Part 73 SNF Update and Part 37 Category 1 and

    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, 2010 Printing and MailServicesEfficiency at National|7-174-MAY2

  2. Minutes from 12 December 2006 DOE/NRC Video Teleconference Call on Section 3116 Implementation Activities

    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 EnergyEnergyENERGY TAXBalanced Scorecard Federal2 to: AMilestone for Regional TestEnergyINDIAN12

  3. Microsoft Word - SmartGrid - NRC Input to DOE Requestrvjcomments.docx

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Careerlumens_placard-green.eps MoreWSRC-STI-2007-00250 Rev. 05 Oak09 U . S . D e p a r t m e n t o

  4. Twenty-first DOE/NRC nuclear air-cleaning conference

    SciTech Connect (OSTI)

    Bellamy, R.R. [Nuclear Regulatory Commission, Washington, DC (United States); Moeller, D.W.; First, M.W. [Harvard Univ., Cambridge, MA (United States)

    1991-01-01T23:59:59.000Z

    The Twenty-First Department of Energy/Nuclear Regulatory Commission Nuclear Air-Cleaning Conference was held August 12-16, 1990, in San Diego, California. A total of 232 air-cleaning specialists attended the conference. The United States and 14 foreign countries were represented, and the specialists were affiliated with government agencies, educational institutions, and the nuclear industry. Several major topics were discussed during the conference, including development and use of industry codes and standards; chemical processing off-gas cleaning; particulate filter developments, including filter testing and filter response to physical stress; development of adsorbents, including laboratory testing and in-place testing; incineration and vitrification; containment venting; reactor operations, including design and modeling; and measurement systems capable of verifying safe operation. The conference continued to provide a forum for direct and efficient interchange of technical and philosophical information among the participants. The high level of foreign participation and interest continues, as evidenced by over one half of the papers being sponsored by foreign interests, and one quarter of the attendees being from outside the United States. Further evidence of international interest was seen in a plenary session devoted to nuclear air-cleaning programs in nine different countries. A common concern throughout many of the sessions was the development of meaningful standards, their implementation for existing air-cleaning system, and the use of these standards by regulatory agencies. 13 refs., 2 tabs.

  5. POLICY GUIDANCE MEMORANDUM #19 Guidance on Transition to Eliminate...

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

    9 Guidance on Transition to Eliminate FCIP (Expired) POLICY GUIDANCE MEMORANDUM 19 Guidance on Transition to Eliminate FCIP (Expired) THIS GUIDANCE HAS EXPIRED Guidance on the...

  6. GUIDANCE FOR THE PROPER CHARACTERIZATION AND CLASSIFICATION OF LOW SPECIFIC ACTIVITY MATERIALS AND SURFACE CONTAMINATED OBJECTS FOR DISPOSAL

    SciTech Connect (OSTI)

    PORTSMOUTH JH; BLACKFORD LT

    2012-02-13T23:59:59.000Z

    Regulatory concerns over the proper characterization of certain waste streams led CH2M HILL Plateau Remediation Company (CHPRC) to develop written guidance for personnel involved in Decontamination & Decommissioning (D&D) activities, facility management and Waste Management Representatives (WMRs) involved in the designation of wastes for disposal on and off the Hanford Site. It is essential that these waste streams regularly encountered in D&D operations are properly designated, characterized and classified prior to shipment to a Treatment, Storage or Disposal Facility (TSDF). Shipments of waste determined by the classification process as Low Specific Activity (LSA) or Surface Contaminated Objects (SCO) must also be compliant with all applicable U.S. Department of Transportation (DOE) regulations as well as Department of Energy (DOE) orders. The compliant shipment of these waste commodities is critical to the Hanford Central Plateau cleanup mission. Due to previous problems and concerns from DOE assessments, CHPRC internal critiques as well as DOT, a management decision was made to develop written guidance and procedures to assist CHPRC shippers and facility personnel in the proper classification of D&D waste materials as either LSA or SCO. The guidance provides a uniform methodology for the collection and documentation required to effectively characterize, classify and identify candidate materials for shipping operations. A primary focus is to ensure that waste materials generated from D&D and facility operations are compliant with the DOT regulations when packaged for shipment. At times this can be difficult as the current DOT regulations relative to the shipment of LSA and SCO materials are often not clear to waste generators. Guidance is often sought from NUREG 1608/RAMREG-003 [3]: a guidance document that was jointly developed by the DOT and the Nuclear Regulatory Commission (NRC) and published in 1998. However, NUREG 1608 [3] is now thirteen years old and requires updating to comply with the newer DOT regulations. Similar challenges present themselves throughout the nuclear industry in both commercial and government operations and therefore, this is not only a Hanford Site problem. Shipping radioactive wastes as either LSA or SCO rather than repacking it is significantly cheaper than other DOT radioactive materials shipping classifications particularly when the cost of packages is included. Additionally, the need to 'repackage' materials for transport can often increase worker exposure, necessitated by 'repackaging' waste materials into DOT 7 A Type A containers.

  7. The Effects of Degraded Digital Instrumentation and Control Systems on Human-system Interfaces and Operator Performance: HFE Review Guidance and Technical Basis

    SciTech Connect (OSTI)

    O'Hara, J.M.; W. Gunther, G. Martinez-Guridi

    2010-02-26T23:59:59.000Z

    New and advanced reactors will use integrated digital instrumentation and control (I&C) systems to support operators in their monitoring and control functions. Even though digital systems are typically highly reliable, their potential for degradation or failure could significantly affect operator performance and, consequently, impact plant safety. The U.S. Nuclear Regulatory Commission (NRC) supported this research project to investigate the effects of degraded I&C systems on human performance and plant operations. The objective was to develop human factors engineering (HFE) review guidance addressing the detection and management of degraded digital I&C conditions by plant operators. We reviewed pertinent standards and guidelines, empirical studies, and plant operating experience. In addition, we conducted an evaluation of the potential effects of selected failure modes of the digital feedwater system on human-system interfaces (HSIs) and operator performance. The results indicated that I&C degradations are prevalent in plants employing digital systems and the overall effects on plant behavior can be significant, such as causing a reactor trip or causing equipment to operate unexpectedly. I&C degradations can impact the HSIs used by operators to monitor and control the plant. For example, sensor degradations can make displays difficult to interpret and can sometimes mislead operators by making it appear that a process disturbance has occurred. We used the information obtained as the technical basis upon which to develop HFE review guidance. The guidance addresses the treatment of degraded I&C conditions as part of the design process and the HSI features and functions that support operators to monitor I&C performance and manage I&C degradations when they occur. In addition, we identified topics for future research.

  8. Recommendations for probabilistic seismic hazard analysis: Guidance on uncertainty and use of experts

    SciTech Connect (OSTI)

    Budnitz, R.J.; Apostolakis, G.; Boore, D.M. [and others

    1997-04-01T23:59:59.000Z

    Probabilistic Seismic Hazard Analysis (PSHA) is a methodology that estimates the likelihood that various levels of earthquake-caused ground motion will be exceeded at a given location in a given future time period. Due to large uncertainties in all the geosciences data and in their modeling, multiple model interpretations are often possible. This leads to disagreement among experts, which in the past has led to disagreement on the selection of ground motion for design at a given site. In order to review the present state-of-the-art and improve on the overall stability of the PSHA process, the U.S. Nuclear Regulatory Commission (NRC), the U.S. Department of Energy (DOE), and the Electric Power Research Institute (EPRI) co-sponsored a project to provide methodological guidance on how to perform a PSHA. The project has been carried out by a seven-member Senior Seismic Hazard Analysis Committee (SSHAC) supported by a large number other experts. The SSHAC reviewed past studies, including the Lawrence Livermore National Laboratory and the EPRI landmark PSHA studies of the 1980`s and examined ways to improve on the present state-of-the-art. The Committee`s most important conclusion is that differences in PSHA results are due to procedural rather than technical differences. Thus, in addition to providing a detailed documentation on state-of-the-art elements of a PSHA, this report provides a series of procedural recommendations. The role of experts is analyzed in detail. Two entities are formally defined-the Technical Integrator (TI) and the Technical Facilitator Integrator (TFI)--to account for the various levels of complexity in the technical issues and different levels of efforts needed in a given study.

  9. Multi-physics coupled code reactor analysis with the U.S. NRC code system TRACE/PARCS

    SciTech Connect (OSTI)

    Xu, Y.; Downar, T.; Ward, A. [Purdue Univ. (United States); Kozlowski, T. [KTH, Nuclear Power Safety (Sweden); Ivanov, K. [Penn State Univ. (United States)

    2006-07-01T23:59:59.000Z

    This paper will focus on the PARCS code and some of the recent applications of the coupled TRACE/PARCS codes to OECD LWR benchmarks and to the Advanced CANDU Reactor, the ACR-700. (authors)

  10. NRC Research Program on Plant Aging: Listing and summaries of reports issued through September 1993. Revision 4

    SciTech Connect (OSTI)

    Vora, J.P.

    1993-12-01T23:59:59.000Z

    The US Nuclear Regulatory Commission is conducting the Nuclear Plant Aging Research (NPAR) Program. This is a comprehensive hardware-oriented engineering research program focused on understanding the aging mechanisms of components and systems in nuclear power plants. The NPAR program also focuses on methods for simulating and monitoring the aging-related degradation of these components and systems. In addition, it provides recommendations for effective maintenance to manage aging and for implementation of the research results in the regulatory process. This document contains a listing and index of reports generated in the NPAR Program that were issued through September 1993 and summaries of those reports. Each summary describes the elements of the research covered in the report and outlines the significant results. For the convenience of the user, the reports are indexed by personal author, corporate author, and subject.

  11. Models for source term, flow, transport and dose assessment in NRC`s Iterative Performance Assessment, Phase 2

    SciTech Connect (OSTI)

    McCartin, T.; Codell, R.; Neel, R.; Ford, W.; Wescott, R.; Bradbury, J. [Nuclear Regulatory Commission, Washington, DC (United States); Sagar, B.; Walton, J. [Center for Nuclear Waste Regulatory Analyses, San Antonio, TX (United States)

    1994-12-31T23:59:59.000Z

    The core consequence modules for the recently completed Phase 2 Iterative Performance Assessment (IPA) of the Yucca Mountain repository for high-level nuclear waste depend on models for releases from the engineered barrier system (source term), flow of liquid and gas, transport of radionuclides in the geosphere and assessment of dose to target populations. The source term model includes temperature and moisture phenomena in the near-field environment, general, pitting and crevice corrosion, contact of the waste form by water, dissolution and oxidation of the waste form, and transport of dissolved and gaseous radionuclides from the waste package by advection and diffusion. The liquid flow and transport models describe water flow through fractures and matrix in both the unsaturated and saturated zones. Models for flow of gas and transport of {sup 14}CO{sub 2} released from the engineered barrier system to the atmosphere take into account repository heat and the geothermal gradient. The dose assessment model calculates doses to a regional population and a farm family for an assumed reference biosphere in the vicinity of the repository. The Phase 2 IPA led to a number of suggestions for model improvement: (1) improve the ability of the models to include spatial and temporal variability in the parameters; (2) improve the coupling among processes, especially the effects of changing environments in the waste packages; (3) develop more mechanistic models, but abstracted for use in total system performance assessment; and (4) use more site specific parameters, especially for the dose assessments.

  12. Radiological Control of Water in Reactor Pond of MR Reactor in NRC 'Kurchatov Institute', During Dismantling Work - 13462

    SciTech Connect (OSTI)

    Stepanov, Alexey; Simirsky, Yury; Semin, Ilya; Volkovich, Anatoly; Ivanov, Oleg [National Research Center 'Kurchatov Institute', Moscow (Russian Federation)] [National Research Center 'Kurchatov Institute', Moscow (Russian Federation)

    2013-07-01T23:59:59.000Z

    The analysis of the activity and radionuclide composition of water from the MR reactor pond for ?,?,?-ray radionuclides was made. To solve this problem we use a wide range of laboratory equipment: gamma spectrometric complex, beta spectrometric complex, vacuum alpha spectrometer, and spectrometric complex with liquid scintillator. The water from MR reactor pond contains: Cs-137 (2,6*10{sup 2} Bq/g), Co-60(1,8 Bq/g), Sr-90 (1,0*10{sup 2} Bq/g), H-3 (7,0*10{sup 3} Bq/g), and components of nuclear fuel (U-232,U-234,U-235,U-236,U-238). Therefore the cleaning water from radioactivity waste occurs to be quite a complicated radiochemical task. (authors)

  13. 14824 Federal Register / Vol. 74, No. 61 / Wednesday, April 1, 2009 / Notices accordance with the NRC E-filing rule,

    E-Print Network [OSTI]

    Collins, Gary S.

    and Licensing Board Panel. [FR Doc. E9­7284 Filed 3­31­09; 8:45 am] BILLING CODE 7590­01­P NUCLEAR REGULATORY; (Enforcement Action) This proceeding concerns a request for a hearing submitted on March 13, 2009 by the law.S. Nuclear Regulatory Commission, Washington, DC 20555­0001. Paul B. Abramson, U.S. Nuclear Regulatory

  14. Can. J. Earth Sci. 42: 111114 (2005) doi: 10.1139/E05-012 2005 NRC Canada INTRODUCTION

    E-Print Network [OSTI]

    Archibald, S. Bruce

    and northeastern Washington, USA1 S. Bruce Archibald and David R. Greenwood Abstract: Climate change is a matter. This special issue presents a series of papers that resulted from a symposium held in 2003 on the Okanagan

  15. Can. J. Fish. Aquat. Sci. 57: 18341842 (2000) 2000 NRC Canada Modeling relationships between landscape-level

    E-Print Network [OSTI]

    for steelhead parr were negatively related to percent unconsolidated lithology. Our models predicted to be in low count categories in subwatersheds with >30% unconsolidated lithology. These results provide

  16. Directory of Certificates of Compliance for radioactive materials packages: Report of NRC approved packages. Volume 1, Revision 18

    SciTech Connect (OSTI)

    NONE

    1995-10-01T23:59:59.000Z

    The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volumes 1 and 2. An alphabetical listing by user name is included in the back of Volume 3 of approved QA programs. The reports include a listing of all users of each package design and approved QA programs prior to the publication date.

  17. Directory of certificiates of compliance for radioactive materials packages: Report of NRC approved packages. Revision 19, Volume 1

    SciTech Connect (OSTI)

    NONE

    1996-10-01T23:59:59.000Z

    This directory provides information on packagings approved by the U.S. Nuclear Regulatory Commission.

  18. Microsoft Word - 1aDOE-ID-12-047 Westinghouse EC B3-6 NRC.doc

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

    and safety procedures. They are currently only intending to have fresh fuel material, depleted for this first project, and will ship the material to TAMU. TAMU will receive...

  19. Microsoft PowerPoint - 2_Peter J. Habighorst_NRC Remarks 2013 NMMSS Users Meeting.pptx

    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 theOFFICEACMEFUTUREMain DraftRobinJeffrey

  20. Microsoft PowerPoint - 2_Peter J. Habighorst_NRC Remarks 2013 NMMSS Users Meeting.pptx

    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 theOFFICEACMEFUTUREMain DraftRobinJeffreySTATE OF

  1. Microsoft PowerPoint - 4_Paul_NRC MC&A Inspection Summary NMMSS 2013.ppt [Compatibility Mode]

    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 theOFFICEACMEFUTUREMainFUNDAMENTALSInspection

  2. Microsoft PowerPoint - 12_BRIAN_HORN_NRC and DOE recognition May 13 2014.ppt [Compatibility Mode]

    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 NuclearhasAdministration77NuclearSecurityAdministratorInteractiveRecent3

  3. Microsoft PowerPoint - 7_GARY_LANGLIE_NMMSS 2014 NRC HEU Report Presentation 21April2014.pptx

    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 the Yucca MountainSource TrackingRegulatory

  4. Microsoft PowerPoint - 9_NRC Roundtable Cover_Wensday_NMMSS_2014_Powerpoint_TEMPLATE.ppt [Compatibility Mode]

    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 the Yucca MountainSourceUsers Trainingand Industry

  5. Social Media and the NRC: What We're Doing, Why We're Doing It, and

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists' Research |RegulationRenewable Energy (EERE)Smart ManufacturingDepartmentValleyWhat

  6. Microsoft Word - 1aDOE-ID-12-047 Westinghouse EC B3-6 NRC.doc

    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 JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recovery challenge fundProject QuarterlyDepartmentConducting1, 2014

  7. THE NRC HAS ISSUED Ati ACTION PLAN FOR CLEANUP OF 46 SfTES that;;ece

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$0.C. 20545 OCT 28SacandagaSiteCT-. \5-1 . '

  8. Child Guidance Techniques.

    E-Print Network [OSTI]

    Fraiser, Roberta C.

    1982-01-01T23:59:59.000Z

    TDOC Z TA24S.7 8873 NO.1314 Child Guidance Techniques The Texas MM University System ~ Texas Agricultural Extension Service DMia! C. Pfannstiel . Director College Station B-1314 ... 2 Contents Helpful Guidance T echniques...

  9. wind_guidance

    Broader source: Energy.gov [DOE]

    Guidance to Accompany Non-Availability Waiver of the Recovery Act Buy American Provisions for 5kW and 50kW Wind Turbines

  10. LCC Guidance Rates

    Broader source: Energy.gov [DOE]

    Notepad text file provides the LCC guidance rates in a numbered format for the various regions throughout the U.S.

  11. Water Efficiency Goal Guidance

    Broader source: Energy.gov [DOE]

    The Council on Environmental Quality (CEQ) issued water efficiency goal guidance in Federal Agency Implementation of Water Efficiency and Management Provisions of Executive Order 13514. This...

  12. Introducing BEST PRACTICE GUIDANCE

    E-Print Network [OSTI]

    placement 6. Application of sewage sludges and composts 7. Fertiliser application in land regeneration 8Introducing BEST PRACTICE GUIDANCE FOR LAND REGENERATION Best Practice Guidance for Land of brownfield land for woodland and urban greening after uses. The Notes are devised for practitioners and all

  13. Office of Technical Guidance

    Broader source: Energy.gov [DOE]

    The Office of Technical Guidance develops, promulgates, and interprets national level policies, procedures, and guidance to identify (1) information that must be classified or controlled under statute or Executive order to protect the national security, to ensure the effective operation of the Government, or to protect the privacy interests of individuals and (2) classified or controlled information that may be declassified or decontrolled.

  14. Selected Guidance & Requirements

    Broader source: Energy.gov [DOE]

    This page contains the most requested NEPA guidance and requirement documents and those most often recommended by the Office of NEPA Policy and Compliance. Documents are listed by agency, in...

  15. Directory

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

    NRC Training Presentations Subfolders in "NRC Training Presentations" Go Up 1 Level Go Up 1 Level Up This folder contains no subfolders. Documents in "NRC Training Presentations"...

  16. Quality assurance guidance for TRUPACT-II (Transuranic Package Transporter-II) payload control

    SciTech Connect (OSTI)

    Not Available

    1989-10-01T23:59:59.000Z

    The Transuranic Package Transporter-II (TRUPACT-II) Safety Analysis Report for Packaging (SARP) approved by the Nuclear Regulatory Commission (NRC), discusses authorized methods for payload control in Appendix 1.3.7 and the Quality Assurance (QA) requirements in Section 9.3. Subsection 9.3.2.1 covers maintenance and use of the TRUPACT-II and the specific QA requirements are given in DOE/WIPP 89-012. Subsection 9.3.2.2 covers payload compliance, for which this document was written. 6 refs.

  17. Policy Guidance Memorandum | Department of Energy

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

    Policy Guidance Memorandum Policy Guidance Memorandum Documents Available for Download POLICY GUIDANCE MEMORANDUM 13 Reemployment Priority List Selections This memorandum provides...

  18. Policy Guidance Memorandum | Department of Energy

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

    Policy Guidance Memorandum Policy Guidance Memorandum Documents Available for Download POLICY GUIDANCE MEMORANDUM 38 EXCEPTION TO POLICY REGARDING QUALITY STEP INCREASES This has...

  19. Records and Information Management Transition Guidance (November...

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

    Records and Information Management Transition Guidance (November 2013) Records and Information Management Transition Guidance (November 2013) This guidance document establishes a...

  20. Engineering Library Guidance

    E-Print Network [OSTI]

    Kaji, Hajime

    Science & Engineering Library Library Guidance April 2014 1 #12;Contents 1 Overview of Waseda University Library 2 Science & Engineering Library and the Student Reading Room 3 WINE: Waseda's Library Catalog3 WINE: Waseda's Library Catalog 4 Library Services 5 Notes 2 #12;How many libraries

  1. Tables of cross references among SECY 82-111, NUREG 0700, NUREG 0835, NUREG 0801

    SciTech Connect (OSTI)

    Savage, J.W.

    1982-03-10T23:59:59.000Z

    This memorandum cross references topical statements extracted from four NRC documents that are useful for guidance in reviewing the Human Factors Engineering designs of main control rooms and control centers outside the main control rooms.

  2. Policy and Guidance | Department of Energy

    Energy Savers [EERE]

    Policy and Guidance Policy and Guidance Policy and Guidance Orders and Guides Directive Type Directive Number PolicyGuidance Title and Link Date Published Order DOE O 413.3B...

  3. Energy Sector Cybersecurity Framework Implementation Guidance

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

    DRAFT FOR PUBLIC COMMENT SEPTEMBER, 2014 ENERGY SECTOR CYBERSECURITY FRAMEWORK IMPLEMENTATION GUIDANCE Energy Sector Cybersecurity Framework Implementation Guidance Table of...

  4. Analysis of the OECD/NRC BWR Turbine Trip Transient Benchmark with the Coupled Thermal-Hydraulics and Neutronics Code TRAC-M/PARCS

    SciTech Connect (OSTI)

    Lee, Deokjung [Purdue University (United States); Downar, Thomas J. [Purdue University (United States); Ulses, Anthony [U.S. Nuclear Regulatory Commission (United States); Akdeniz, Bedirhan [Pennsylvania State University (United States); Ivanov, Kostadin N. [Pennsylvania State University (United States)

    2004-10-15T23:59:59.000Z

    An analysis of the Peach Bottom Unit 2 Turbine Trip 2 (TT2) experiment has been performed using the U.S. Nuclear Regulatory Commission coupled thermal-hydraulics and neutronics code TRAC-M/PARCS. The objective of the analysis was to assess the performance of TRAC-M/PARCS on a BWR transient with significance in two-phase flow and spatial variations of the neutron flux. TRAC-M/PARCS results are found to be in good agreement with measured plant data for both steady-state and transient phases of the benchmark. Additional analyses of four fictitious extreme scenarios are performed to provide a basis for code-to-code comparisons and comprehensive testing of the thermal-hydraulics/neutronics coupling. The obtained results of sensitivity studies on the effect of direct moderator heating on transient simulation indicate the importance of this modeling aspect.

  5. PWR FLECHT SEASET 21-rod bundle flow blockage task data and analysis report. NRC/EPRI/Westinghouse Report No. 11. Appendices K-P

    SciTech Connect (OSTI)

    Loftus, M.J.; Hochreiter, L.E.; Lee, N.; McGuire, M.F.; Wenzel, A.H.; Valkovic, M.M.

    1982-09-01T23:59:59.000Z

    This report presents data and limited analysis from the 21-Rod Bundle Flow Blockage Task of the Full-Length Emergency Cooling Heat Transfer Separate Effects and Systems Effects Test Program (FLECHT SEASET). The tests consisted of forced and gravity reflooding tests utilizing electrical heater rods with a cosine axial power profile to simulate PWR nuclear core fuel rod arrays. Steam cooling and hydraulic characteristics tests were also conducted. These tests were utilized to determine effects of various flow blockage configurations (shapes and distributions) on reflooding behavior, to aid in development/assessment of computational models in predicting reflooding behavior of flow blockage configurations, and to screen flow blockage configurations for future 163-rod flow blockage bundle tests.

  6. PWR FLECHT SEASET 163-Rod Bundle Flow Blockage Task data report. NRC/EPRI/Westinghouse report No. 13, August-October 1982

    SciTech Connect (OSTI)

    Loftus, M J; Hochreiter, L E; McGuire, M F; Valkovic, M M

    1983-10-01T23:59:59.000Z

    This report presents data from the 163-Rod Bundle Blow Blockage Task of the Full-Length Emergency Cooling Heat Transfer Systems Effects and Separate Effects Test Program (FLECHT SEASET). The task consisted of forced and gravity reflooding tests utilizing electrical heater rods with a cosine axial power profile to simulate PWR nuclear core fuel rod arrays. These tests were designed to determine effects of flow blockage and flow bypass on reflooding behavior and to aid in the assessment of computational models in predicting the reflooding behavior of flow blockage in rod bundle arrays.

  7. Recommendations to the NRC for review criteria for alternative methods of low-level radioactive waste disposal: Task 2b: Earth-mounded concrete bunkers

    SciTech Connect (OSTI)

    Denson, R.H.; Bennett, R.D.; Wamsley, R.M.; Bean, D.L.; Ainsworth, D.L.

    1988-01-01T23:59:59.000Z

    The US Army Engineers Waterways Experiment Station (WES) and US Army Engineer Division, Huntsville (HNDED) have developed general design criteria and specific design review criteria for the earth-mounded concrete bunker (EMCB) alternative method of low-level radioactive waste (LLW) disposal. An EMCB is generally described as a reinforced concrete vault placed below grade, underneath a tumulus, surrounded by filter-blanket and drainage zones. The tumulus is covered over with a low permeability cover layer and top soil with vegetation. Eight major review criteria categories have been developed ranging from the loads imposed on the EMCB structure through material quality and durability considerations. Specific design review criteria have been developed in detail for each of the eight major categories. 63 refs., 13 figs., 2 tabs.

  8. Recommendations to the NRC for review criteria for alternative methods of low-level radioactive waste disposal: Task 2a, Below-ground vaults

    SciTech Connect (OSTI)

    Denson, R.H.; Bennett, R.D.; Wamsley, R.M.; Bean, D.L.; Ainsworth, D.L.

    1987-12-01T23:59:59.000Z

    The US Army Engineer Waterways Experiment Station (WES) and the US Army Engineer Division, Huntsville (HNDED) have developed general design criteria and specific design review criteria for the below-ground vault (BGV) alternative method of low-level radioactive waste (LLW) disposal. A BGV is a reinforced concrete vault (floor, walls, and roof) placed underground below the frost line, and above the water table, surrounded by filter blanket and drainage zones and covered with a low permeability earth layer and top soil with vegetation. Eight major review criteria categories have been developed ranging from the loads imposed on the BGV structure through material quality and durability considerations. Specific design review criteria have been developed in detail for seven of the eight major categories. 59 refs., 14 figs., 2 tabs.

  9. Impact of reduced dose limits on NRC licensed activities. Major issues in the implementation of ICRP/NCRP dose limit recommendations: Final report

    SciTech Connect (OSTI)

    Meinhold, C.B. [Brookhaven National Lab., Upton, NY (United States)

    1995-05-01T23:59:59.000Z

    This report summarizes information required to estimate, at least qualitatively, the potential impacts of reducing occupational dose limits below those given in 10 CFR 20 (Revised). For this study, a questionnaire was developed and widely distributed to the radiation protection community. The resulting data together with data from existing surveys and sources were used to estimate the impact of three dose-limit options; 10 mSv yr{sup {minus}1} (1 rem yr{sup {minus}1}), 20 mSv yr{sup {minus}1} (2 rem yr{sup {minus}1}), and a combination of an annual limit of 50 mSv yr{sup {minus}1} (5 rem yr{sup {minus}1}) coupled with a cumulative limit, in rem, equal to age in years. Due to the somewhat small number of responses and the lack of data in some specific areas, a working committee of radiation protection experts from a variety of licensees was employed to ensure the exposure data were representative. The following overall conclusions were reached: (1) although 10 mSv yr{sup {minus}1} is a reasonable limit for many licensees, such a limit could be extraordinarily difficult to achieve and potentially destructive to the continued operation of some licensees, such as nuclear power, fuel fabrication, and medicine; (2) twenty mSv yr{sup {minus}1} as a limit is possible for some of these groups, but for others it would prove difficult. (3) fifty mSv yr{sup {minus}1} and age in 10s of mSv appear reasonable for all licensees, both in terms of the lifetime risk of cancer and severe genetic effects to the most highly exposed workers, and the practicality of operation.

  10. Can. J. Earth Sci. 40: 13751391 (2003) doi: 10.1139/E03-048 2003 NRC Canada Paleoenvironmental analysis of the late

    E-Print Network [OSTI]

    Narbonne, Guy

    as up- and downslope currents of tidal and (or) wind-forced origin, influenced the sea floor for sustaining the organisms in this deep-water setting. The current-produced inclination of the frondose

  11. Proceedings of the Third NRC/ASME Symposium on Valve and Pump Testing. Session 1A--Session 2C: Volume 1

    SciTech Connect (OSTI)

    Not Available

    1994-07-01T23:59:59.000Z

    The 1994 Symposium on Valve and Pump Testing, jointly sponsored by the Board of Nuclear Codes and Standards of the American Society of Mechanical Engineers and by the Nuclear Regulatory Commission, provides a forum for the discussion of current programs and methods for inservice testing and motor-operated valve testing at nuclear power plants. The symposium also provides an opportunity to discuss the need to improve that testing in order to help ensure the reliable performance of pumps and valves. The participation of industry representatives, regulators, and consultants results in the discussion of a broad spectrum of ideas and perspectives regarding the improvement of inservice testing of pumps and valves at nuclear power plants. This document, Volume 1, covers sessions 1A through session 2C. The individual papers have been cataloged separately.

  12. Microsoft PowerPoint - 8_Peter Habighorst_NRC_Act of 2012-status final 5-12 presentation.ppt [Compatibility Mode]

    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 ofElectronic Input Options Gary L.Martyn ForeignUse of

  13. Proceedings of the Third NRC/ASME Symposium on Valve and Pump Testing. Volume 2, Session 3A--Session 4B

    SciTech Connect (OSTI)

    Not Available

    1994-07-01T23:59:59.000Z

    The 1994 Symposium on Valve and Pump Testing, jointly sponsored by the Board of Nuclear Codes and Standards of the American Society of Mechanical Engineers and by the Nuclear Regulatory Commission, provides a forum for the discussion of current programs and methods for inservice testing and motor-operated valve testing at nuclear power plants. The symposium also provides an opportunity to discuss the need to improve that testing in order to help ensure the reliable performance of pumps and valves. The participation of industry representatives, regulators, and consultants results in the discussion of a broad spectrum of ideas and perspectives regarding the improvement of inservice testing of pumps and valves at nuclear power plants. Individual papers have been cataloged separately.

  14. Microsoft PowerPoint - 4_JOHN_BALLARD_MARY_MCCDONNELL_NRC DOE REporting requirements_presentations_4-29-14.ppt [Compatibility M

    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 the Yucca Mountain LicenseWelcomeNuclear

  15. O&M Metering Guidance

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

    URL links, and references - Improved document "readability" - Added information regarding water 4 | FEDERAL ENERGY MANAGEMENT PROGRAM femp.energy.gov O&M and Metering Guidance...

  16. Design guidance for play spaces

    E-Print Network [OSTI]

    Design guidance for play spaces March 2006 Lindsey Houston, Roger Worthington, Paddy Harrop #12 Design Process 3 Play Spaces 4 Design Principles 6 Elements of Play 6 Existing Play Structures 8 Contacts, Jason Maclean, Andrew Norris, Bridgette Hall and Tania Crocket in #12;Design guidance for play spaces. 3

  17. RADIOLOGICAL & ENVIRONMENTAL MANAGEMENT GUIDANCE DOCUMENT

    E-Print Network [OSTI]

    Holland, Jeffrey

    RADIOLOGICAL & ENVIRONMENTAL MANAGEMENT GUIDANCE DOCUMENT: Minors in Research Laboratories or Animal Facilities Page 1 of 4 PURPOSE: The purpose of this document is to provide guidance for Purdue sponsored programs which are designed for youth under the age of 15 and which have documented

  18. Enforcement Guidance Supplement 03-01 Supplemental Guidance Concerning...

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

    for Issuing Consent Orders Pursuant to 10 CFR 820.23 In October 2000, the Office of Price-Anderson Enforcement (OE) issued Enforcement Guidance Supplement (EGS) 00-04, "Factual...

  19. Army Policy Guidance for UESCs

    Broader source: Energy.gov [DOE]

    Presentation—given at the Spring 2009 Federal Utility Partnership Working Group (FUPWG) meeting—provides an overview of the U.S. Army's utility energy service contract (UESC) program and its UESC draft policy guidance.

  20. DEPARTMENTAL EMERGENCY PLAN Guidance Document

    E-Print Network [OSTI]

    Johnston, Daniel

    DEPARTMENTAL EMERGENCY PLAN Guidance Document #12;1 TABLE OF CONTENTS TABLE OF CONTENTS .................................................................................................12 EMERGENCY MANAGEMENT TEAM ........................................................12 ............................................................................................25 ADDITIONAL INFORMATIONAL DOCUMENTS.........................................25 #12;2 THIS PAGE

  1. Information architecture. Volume 3: Guidance

    SciTech Connect (OSTI)

    NONE

    1997-04-01T23:59:59.000Z

    The purpose of this document, as presented in Volume 1, The Foundations, is to assist the Department of Energy (DOE) in developing and promulgating information architecture guidance. This guidance is aimed at increasing the development of information architecture as a Departmentwide management best practice. This document describes departmental information architecture principles and minimum design characteristics for systems and infrastructures within the DOE Information Architecture Conceptual Model, and establishes a Departmentwide standards-based architecture program. The publication of this document fulfills the commitment to address guiding principles, promote standard architectural practices, and provide technical guidance. This document guides the transition from the baseline or defacto Departmental architecture through approved information management program plans and budgets to the future vision architecture. This document also represents another major step toward establishing a well-organized, logical foundation for the DOE information architecture.

  2. Renewable Energy Requirement Guidance for EPAct 2005 and Executive...

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

    Renewable Energy Requirement Guidance for EPAct 2005 and Executive Order 13423 Renewable Energy Requirement Guidance for EPAct 2005 and Executive Order 13423 Guidance specifies...

  3. Building America Climate-Specific Guidance | Department of Energy

    Energy Savers [EERE]

    Building America Building America Climate-Specific Guidance Building America Climate-Specific Guidance Building America Climate-Specific Guidance 2014 Housing Innovation...

  4. LM Records and Information Management Transition Guidance (January...

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

    Records and Information Management Transition Guidance (January 2015) LM Records and Information Management Transition Guidance (January 2015) This guidance document establishes a...

  5. Radiation Protection Guidance Hospital Staff

    E-Print Network [OSTI]

    Kay, Mark A.

    Page 1 Radiation Protection Guidance For Hospital Staff Prepared for Stanford The privilege to use ionizing radiation at Stanford University, Stanford Hospital and Clinics, Lucile Packard with radioactive materials or radiation devices are responsible for knowing and adhering to applicable requirements

  6. Work Experience Guidance for Managers

    E-Print Network [OSTI]

    Work Experience Guidance for Managers When approached with a request for work experience, managers. Any queries regarding CRB checks should be directed to your designated HR Manager. When a work any work, paid or unpaid: Before 7am or after 7pm For more than two hours on a school day or Sunday

  7. Guidance on site selection for

    E-Print Network [OSTI]

    harvestingbrash materialfollowingtimber harvestingto supply biomass for heat and power generation. A numberGuidance on site selection for brash removal Forest Research, May 2009 The Research Agency SELECTION FOR BRASH REMOVAL | Forest Research | May 09 #12;Brash Removal Background Interest is growingin

  8. Hybrid vehicle-centric route guidance

    E-Print Network [OSTI]

    Farver, Jennifer M. (Jennifer Margaret), 1976-

    2005-01-01T23:59:59.000Z

    This thesis proposes a hybrid route guidance system in which predictive guidance is generated in a centralized layer and revised in a reactive, decentralized layer that resides on-board the vehicle. This hybrid approach ...

  9. Guidance on measuring and reporting Greenhouse Gas

    E-Print Network [OSTI]

    Guidance on measuring and reporting Greenhouse Gas (GHG) emissions from freight transport This guidance provides clear instructions on calculating the greenhouse gas (GHG) emissions from freight and report your greenhouse gas emissions', by providing more specific information and examples relating

  10. OFFSHORE WIND FARMS Guidance note for Environmental

    E-Print Network [OSTI]

    OFFSHORE WIND FARMS Guidance note for Environmental Impact Assessment In respect of FEPA and CPA requirements Version 2 - June 2004 #12;Offshore Wind Farms: Guidance Note for Environmental Impact Assessment 2004 #12;Offshore Wind Farms: Guidance Note for Environmental Impact Assessment in Respect of FEPA

  11. California Energy Commission GUIDANCE ON WASTE

    E-Print Network [OSTI]

    California Energy Commission GUIDANCE GUIDANCE ON WASTE MANAGEMENT PLANS FOR ENERGY EFFICIENCY) obtain waste management plans for each proposed project receiving funding under the Energy Efficiency of waste. The Energy Commission is providing the following guidance to assist recipients of EECBG Program

  12. Evidence-Based Background Material Underlying Guidance for Federal...

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

    Material Underlying Guidance for Federal Agencies in Implementing Strategic Sustainability Performance Plans Evidence-Based Background Material Underlying Guidance for...

  13. MINOR for Natural Resources Conservation Conserving Earth's biological diversity and safeguarding the benefits or "ecosystem services"

    E-Print Network [OSTI]

    Massachusetts at Amherst, University of

    -fall even yrs) NRC 534 Forest Measurements (4cr-fall odd yrs) 2 NRC 540 Forest Resources Management (4cr Resources Policy & Administration (3cr-sprg) NRC 576 Water Resources Management (3cr-fall even yrs) NRC 590 Resources and Sustainability (3cr-sprg) NRC 597EL Environmental Law (3cr

  14. Review of soil contamination guidance

    SciTech Connect (OSTI)

    Mueller, M.A.; Kennedy, W.E. Jr.; Soldat, J.K.

    1981-08-01T23:59:59.000Z

    A review of existing and proposed radioactive soil contamination standards and guidance was conducted for United Nuclear Corporation (UNC), Office of Surplus Facilities Management. Information was obtained from both government agencies and other sources during a literature survey. The more applicable standards were reviewed, evaluated, and summarized. Information pertaining to soil contamination for both facility operation and facility decommissioning was obtained from a variety of sources. These sources included: the Code of Federal Regulations, regulatory guides, the Federal Register, topical reports written by various government agencies, topical reports written by national laboratories, and publications from the American National Standards Institute (ANSI). It was difficult to directly compare the standards and guidance obtained from these sources since each was intended for a specific situation and different units or bases were used. However, most of the information reviewed was consistent with the philosophy of maintaining exposures at levels as low as reasonably achievable (ALARA).

  15. Non-Power Reactor Operator Licensing Examiner Standards. Revision 1

    SciTech Connect (OSTI)

    NONE

    1995-06-01T23:59:59.000Z

    The Non-Power Reactor Operator Licensing Examiner Standards provide policy and guidance to NRC examiners and establish the procedures and practices for examining and licensing of applicants for NRC operator licenses pursuant to Part 55 of Title 10 of the Code of Federal Regulations (10 CFR 55). They are intended to assist NRC examiners and facility licensees to understand the examination process better and to provide for equitable and consistent administration of examinations to all applicants by NRC examiners. These standards are not a substitute for the operator licensing regulations and are subject to revision or other internal operator examination licensing policy changes. As appropriate, these standards will be revised periodically to accommodate comments and reflect new information or experience.

  16. EECBG Guidance | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:Year in Review: TopEnergy DOEDealingVehicle1 Closing AmericanAdministrative ExpensesGuidance

  17. Guidance for Radiation Accident Management

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun with Big Sky LearningGetGraphene'sEMSLonly) | EMSL Guidance for

  18. Guidance on Incorporating EPA's Pollution Prevention Strategy...

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

    The guidance discusses the Environmental Protection Agency's definition of pollution prevention; how to incorporate pollution prevention into the EPA environmental review process...

  19. EPA - Guidance for Incorporating Environmental Justice Concerns...

    Open Energy Info (EERE)

    Environmental Justice Concerns in EPA's NEPA Compliance Analyses Jump to: navigation, search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance - GuideHandbook:...

  20. Additional Guidance Regarding Application of Current Procedures...

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

    Additional Guidance Regarding Application of Current Procedures for Testing Energy Consumption of Clothes Washers with Warm Rinse Cycles, Issued: June 30, 2010. Draft of DOE...

  1. Participatory Carbon Monitoring: Operational Guidance for National...

    Open Energy Info (EERE)

    Participatory Carbon Monitoring: Operational Guidance for National REDD+ Carbon Accounting Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Participatory Carbon...

  2. Enforcement Guidance Supplement (EGS) 00-04

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

    Enforcement Guidance Supplement EGS: 00-04 Appendix E- Operational Procedures for Enforcement Department of Energy Washington, DC 20585 October 23, 2000 MEMORANDUM FOR: DOE PAAA...

  3. Energy Intensity Baselining and Tracking Guidance

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

    Learn more at betterbuildings.energy.gov Energy Intensity Baselining and Tracking Guidance i Preface The U.S. Department of Energy's (DOE) Better Buildings, Better Plants Program...

  4. Council on Environmental Quality - Guidance for Environmental...

    Open Energy Info (EERE)

    for Environmental Assessments of Forest Health Projects Jump to: navigation, search OpenEI Reference LibraryAdd to library Memorandum: Council on Environmental Quality - Guidance...

  5. POLICY GUIDANCE MEMORANDUM #31 - Procedures for Regularizing...

    Energy Savers [EERE]

    1 - Procedures for Regularizing Illegal Appointments POLICY GUIDANCE MEMORANDUM 31 - Procedures for Regularizing Illegal Appointments As part of the Department's ongoing effort to...

  6. Energy Sector Cybersecurity Framework Implementation Guidance

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

    JANUARY 2015 ENERGY SECTOR CYBERSECURITY FRAMEWORK IMPLEMENTATION GUIDANCE U.S. DEPARTMENT OF ENERGY OFFICE OF ELECTRICITY DELIVERY AND ENERGY RELIABILITY Energy Sector...

  7. Energy Intensity Baselining and Tracking Guidance

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

    Learn more at betterbuildings.energy.gov Energy Intensity Baselining and Tracking Guidance i Preface The U.S. Department of Energy's (DOE's) Better Buildings, Better Plants Program...

  8. Energy Sector Cybersecurity Framework Implementation Guidance...

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

    Cybersecurity Framework Implementation Guidance - Notice of Public Comment: Federal Register Notice, Volume 79, No. 177, September 12, 2014 Energy Sector Cybersecurity Framework...

  9. International Conference on Machine Control & Guidance 2008 1 Automatic Guidance of Track Laying Machines with

    E-Print Network [OSTI]

    1st International Conference on Machine Control & Guidance 2008 1 Automatic Guidance of Track Laying Machines with Respect to Coordinate Systems Th. ENGEL*, JJ. STUBY, Ch. GLAUSER, P. GĂ?LDENAPFEL machine guidance, this text focuses on presenting and solving three challenges without which coordinate

  10. Guidance for performing preliminary assessments under CERCLA

    SciTech Connect (OSTI)

    NONE

    1991-09-01T23:59:59.000Z

    EPA headquarters and a national site assessment workgroup produced this guidance for Regional, State, and contractor staff who manage or perform preliminary assessments (PAs). EPA has focused this guidance on the types of sites and site conditions most commonly encountered. The PA approach described in this guidance is generally applicable to a wide variety of sites. However, because of the variability among sites, the amount of information available, and the level of investigative effort required, it is not possible to provide guidance that is equally applicable to all sites. PA investigators should recognize this and be aware that variation from this guidance may be necessary for some sites, particularly for PAs performed at Federal facilities, PAs conducted under EPA`s Environmental Priorities Initiative (EPI), and PAs at sites that have previously been extensively investigated by EPA or others. The purpose of this guidance is to provide instructions for conducting a PA and reporting results. This guidance discusses the information required to evaluate a site and how to obtain it, how to score a site, and reporting requirements. This document also provides guidelines and instruction on PA evaluation, scoring, and the use of standard PA scoresheets. The overall goal of this guidance is to assist PA investigators in conducting high-quality assessments that result in correct site screening or further action recommendations on a nationally consistent basis.

  11. Steam Load Reduction Guidance Emergency Management Program

    E-Print Network [OSTI]

    Pawlowski, Wojtek

    Steam Load Reduction Guidance Emergency Management Program v October 2014 Steam_Load_Reduction_Guidance_DSRDSR 1.0 PurposeandScope Utilities provides steam to the campus community for space heating, hot water in the steam distribution system or the Central Energy Plant, the preservation of building infrastructure

  12. Technical Standards, ALOHA-Code Guidance - June 22, 2004 | Department...

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

    Guidance - June 22, 2004 June 22, 2004 DOE-EH-4.2.1.4-ALOHA-Code Guidance, ALOHA Computer Code Application Guidance for Documented Safety Analysis This document provides...

  13. albright generating station: Topics by E-print Network

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

    Statement for License Renewal of Nuclear Plants (GEIS), NUREG-1437 (NRC, 1996), (NRC, 1999); (2) the Environmental Report submitted by DEK; (3) consultation with Federal, State,...

  14. Directory

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

    Document Name Sort items in descending order Object Created Object Last Modified NRC Concrete Meeting Busby NRC Concrete Meeting Busby LightWaterReactorSus...

  15. Microsoft PowerPoint - 9_SUZANNE_ANI_NMMSS_2014 MCA-SAni.pptx

    National Nuclear Security Administration (NNSA)

    at the NRC Suzanne M. Ani Office of Nuclear Material Safety & Safeguards Division of Fuel Cycle Safety & Safeguards Material Control & Accounting Branch At the NRC... Office...

  16. Nuclear Safety Information Agreement Between the U.S. Nuclear...

    Office of Environmental Management (EM)

    Operations (NRC)), Jim O'Brien, Director, Office of Nuclear Safety (EHSS DOE), Robert Johnson (Chief, Fuel Manufacturing Branch (NRC)) Front Row: Matt Moury, Associate Under...

  17. The Decline and Death of Nuclear Power

    E-Print Network [OSTI]

    Melville, Jonathan

    2013-01-01T23:59:59.000Z

    2012). NRC: Nuclear Security and Safeguards.nrc.gov.in nuclear reactor maintenance and security. However, when aof nuclear power plants, as well as physical security to

  18. Energy Department Seeks Additional Feedback on Draft Guidance...

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

    Seeks Additional Feedback on Draft Guidance for the Hydroelectric Production Incentive Program Energy Department Seeks Additional Feedback on Draft Guidance for the Hydroelectric...

  19. Final Guidance for EPAct 2005 Section 242 Hydroelectric Incentive...

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

    Final Guidance for EPAct 2005 Section 242 Hydroelectric Incentive Program Final Guidance for EPAct 2005 Section 242 Hydroelectric Incentive Program This document contains the Final...

  20. Energy Department Seeks Feedback on Draft Guidance for the Hydroelectr...

    Office of Environmental Management (EM)

    Feedback on Draft Guidance for the Hydroelectric Production Incentive Program Energy Department Seeks Feedback on Draft Guidance for the Hydroelectric Production Incentive Program...

  1. BLM Manual 8270 - General Procedural Guidance for Paleontological...

    Open Energy Info (EERE)

    - General Procedural Guidance for Paleontological Resource Management Jump to: navigation, search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance - Guide...

  2. Guidance for Energy Efficiency and Conservation Block Grant Grantees...

    Energy Savers [EERE]

    Financing Programs Guidance for Energy Efficiency and Conservation Block Grant Grantees on Financing Programs Provides general guidance to the U.S. Department of Energy's Energy...

  3. GUIDANCE FOR ENERGY EFFICIENCY AND CONSERVATION BLOCK GRANT RECIPIENTS...

    Energy Savers [EERE]

    GUIDANCE FOR ENERGY EFFICIENCY AND CONSERVATION BLOCK GRANT RECIPIENTS ON CLOSEOUT PROCEDURES FOR NON-STATE ENERGY OFFICE RECIPIENTS. GUIDANCE FOR ENERGY EFFICIENCY AND...

  4. Enforcement Guidance Supplement 00-02: Price-Anderson Amendment...

    Office of Environmental Management (EM)

    Enforcement Guidance Supplement 00-02: Price-Anderson Amendment Act (PAAA) Program Reviews Enforcement Guidance Supplement 00-02: Price-Anderson Amendment Act (PAAA) Program...

  5. Enforcement Guidance Supplement 01-01: Nuclear Weapon Program...

    Office of Environmental Management (EM)

    This enforcement guidance focuses on the applicability of 10 CFR Part 830 to nuclear weapon programs and several related enforcement issues. Enforcement Guidance Supplement 01-01:...

  6. DRAFT NEPA Guidance on Consideration of the Effects of Climate...

    Office of Environmental Management (EM)

    DRAFT NEPA Guidance on Consideration of the Effects of Climate Change and Greenhouse Gas Emissions DRAFT NEPA Guidance on Consideration of the Effects of Climate Change and...

  7. 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...

  8. 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...

  9. Technical Standards, CFAST-Code Guidance- July 23, 2004

    Broader source: Energy.gov [DOE]

    DOE-EH-4.2.1.4-CFAST-Code Guidance, CFAST Computer Code Application Guidance for Documented Safety Analysis

  10. POLICY GUIDANCE MEMORANDUM #35 Procedures for Compliance with...

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

    POLICY GUIDANCE MEMORANDUM 35 Procedures for Compliance with Nepotism and Misuse of Position POLICY GUIDANCE MEMORANDUM 35 Procedures for Compliance with Nepotism and Misuse of...

  11. POLICY GUIDANCE MEMORANDUM #09A Direct Hire Authority for Acquisition...

    Office of Environmental Management (EM)

    9A Direct Hire Authority for Acquisition Positions (Expired) POLICY GUIDANCE MEMORANDUM 09A Direct Hire Authority for Acquisition Positions (Expired) THIS GUIDANCE HAS EXPIRED...

  12. POLICY GUIDANCE MEMORANDUM #33 - Requirements for DOE Delegated...

    Energy Savers [EERE]

    3 - Requirements for DOE Delegated Examining Procedures POLICY GUIDANCE MEMORANDUM 33 - Requirements for DOE Delegated Examining Procedures The purpose of this guidance is to...

  13. POLICY GUIDANCE MEMORANDUM #38 EXCEPTION TO POLICY REGARDING...

    Energy Savers [EERE]

    POLICY GUIDANCE MEMORANDUM 38 EXCEPTION TO POLICY REGARDING QUALITY STEP INCREASES POLICY GUIDANCE MEMORANDUM 38 EXCEPTION TO POLICY REGARDING QUALITY STEP INCREASES This has...

  14. POLICY GUIDANCE MEMORANDUM #34B Direct Hire Authority for Contract...

    Energy Savers [EERE]

    4B Direct Hire Authority for Contract Specialist positions POLICY GUIDANCE MEMORANDUM 34B Direct Hire Authority for Contract Specialist positions Policy Guidance Memorandum 34B...

  15. POLICY GUIDANCE MEMORANDUM #02 Using Schedule A Hiring Authority...

    Energy Savers [EERE]

    2 Using Schedule A Hiring Authority for ARRA Positions (Expired) POLICY GUIDANCE MEMORANDUM 02 Using Schedule A Hiring Authority for ARRA Positions (Expired) THIS GUIDANCE HAS...

  16. POLICY GUIDANCE MEMORANDUM #23 Permanent and Nonpermanent Positions...

    Energy Savers [EERE]

    3 Permanent and Nonpermanent Positions, Appointments, & CHRIS Codes POLICY GUIDANCE MEMORANDUM 23 Permanent and Nonpermanent Positions, Appointments, & CHRIS Codes DOE Guidance -...

  17. Guidance on New Construction under an Energy Savings Performance...

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

    New Construction under an Energy Savings Performance Contract Guidance on New Construction under an Energy Savings Performance Contract Document covers the guidance of new...

  18. Energy Department Issues Tribal Renewable Energy Purchase Guidance...

    Office of Environmental Management (EM)

    Tribal Renewable Energy Purchase Guidance and Project Development Resources Energy Department Issues Tribal Renewable Energy Purchase Guidance and Project Development Resources...

  19. State Energy Program Fiscal Year 2006 Formula Grant Guidance

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

    STATE ENERGY PROGRAM NOTICE 06-1 EFFECTIVE DATE: January 6, 2006 SUBJECT: PROGRAM YEAR 2006 STATE ENERGY PROGRAM FORMULA GRANT GUIDANCE PURPOSE To establish grant guidance and...

  20. Guidance for FY2014 Facilities Information Management System...

    Office of Environmental Management (EM)

    Guidance for FY2014 Facilities Information Management System Data Validations Guidance for FY2014 Facilities Information Management System Data Validations FY 2014 FIMS Data...

  1. Treasury, Energy Announce Guidance for Tax Treatment of Smart...

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

    Treasury, Energy Announce Guidance for Tax Treatment of Smart Grid Investment Grants Treasury, Energy Announce Guidance for Tax Treatment of Smart Grid Investment Grants March 10,...

  2. Guidance Regarding Actions That May Proceed During the NEPA Process...

    Energy Savers [EERE]

    Regarding Actions That May Proceed During the NEPA Process: Interim Actions Guidance Regarding Actions That May Proceed During the NEPA Process: Interim Actions DOE guidance to...

  3. Vibrotactile Guidance for Wayfinding of Blind Walkers

    E-Print Network [OSTI]

    Manduchi, Roberto; Flores, German; Kurniawan, Sri; Morales, Lourdes; Martinson, Eric; Sisbot, Akin

    2015-01-01T23:59:59.000Z

    travel aid for the blind. Systems, Man, and Cybernetics,Guidance for Wayfinding of Blind Walkers G. Flores, S.the form of a belt for guiding blind walkers. This interface

  4. Guidance for Local Wind Energy Ordinances

    Broader source: Energy.gov [DOE]

    Note: The documents described in this summary were designed to provide guidance to local governments that wish to develop their own siting rules for wind turbines. While they were developed under...

  5. Moving Your Laboratory Safely Guidance Document

    E-Print Network [OSTI]

    Baker, Chris I.

    Moving Your Laboratory Safely Guidance Document Revised March 2010, Page 1 #12;Table of Contents­radiological 301-496-3457 Ergonomic evaluations 301-496-7990 Hazardous, solid and mixed waste management 301

  6. Guidance Manual for K-12 SchoolsGuidance Manual for K-12 Schools prepared for

    E-Print Network [OSTI]

    Jia, Songtao

    Compliance and Best Management Practices prepared by: October 2006 Facilities O peration and Ma intenanceAreas .............................................................................................1-5 1.3 Best Management PracticesGuidance Manual for K-12 SchoolsGuidance Manual for K-12 Schools prepared for: Environmental

  7. International Conference on Machine Control & Guidance 2008 1 Guidance for Partial Face Excavation Machines

    E-Print Network [OSTI]

    1st International Conference on Machine Control & Guidance 2008 1 Guidance for Partial Face Excavation Machines Nod CLARKE-HACKSTON, Jochen BELZ VMT GmbH Allan HENNEKER Surex Pty Ltd Abstract information to the machine operator, VMT GmbH has developed a system to support precise excavation

  8. PWR FLECHT SEASET 21-rod-bundle flow-blockage task: data and analysis report. NRC/EPRI/Westinghouse report No. 11, main report and appendices A-J

    SciTech Connect (OSTI)

    Loftus, M.J.; Hochreiter, L.E.; Lee, N.; McGuire, M.F.; Wenzel, A.H.; Valkovic, M.M.

    1982-09-01T23:59:59.000Z

    This report presents data and limited analysis from the 21-Rod Bundle Flow Blockage Task of the Full-Length Emergency Cooling Heat Transfer Separate Effects and Systems Effects Test Program (FLECHT SEASET). The tests consisted of forced and gravity reflooding tests utilizing electrical heater rods with a cosine axial power profile to simulate PWR nuclear core fuel rod arrays. Steam cooling and hydraulic characteristics tests were also conducted. These tests were utilized to determine effects of various flow blockage configurations (shapes and distributions) on reflooding behavior, to aid in development/assessment of computational models in predicting reflooding behavior of flow blockage configurations, and to screen flow blockage configurations for future 163-rod flow blockage bundle tests.

  9. Safety of magnetic fusion facilities: Guidance

    SciTech Connect (OSTI)

    NONE

    1996-05-01T23:59:59.000Z

    This document provides guidance for the implementation of the requirements identified in DOE-STD-6002-96, Safety of Magnetic Fusion Facilities: Requirements. This guidance is intended for the managers, designers, operators, and other personnel with safety responsibilities for facilities designated as magnetic fusion facilities. While the requirements in DOE-STD-6002-96 are generally applicable to a wide range of fusion facilities, this Standard, DOE-STD-6003-96, is concerned mainly with the implementation of those requirements in large facilities such as the International Thermonuclear Experimental Reactor (ITER). Using a risk-based prioritization, the concepts presented here may also be applied to other magnetic fusion facilities. This Standard is oriented toward regulation in the Department of Energy (DOE) environment as opposed to regulation by other regulatory agencies. As the need for guidance involving other types of fusion facilities or other regulatory environments emerges, additional guidance volumes should be prepared. The concepts, processes, and recommendations set forth here are for guidance only. They will contribute to safety at magnetic fusion facilities.

  10. Crescent Junction Disposal Site Diversion Channel Design, North Side Disposal Cell Sources of Data:

    E-Print Network [OSTI]

    unknown authors

    Checked b"t me-Kao a MName A e4719 lProblem Statement: " Design erosion protection for the north slope of the disposal cell to prevent detrimental erosion from surface water flows from upland area, consistent with the requirements of 40 CFR Part 192 and NRC guidance in NUREG 1623.

  11. Guidelines for preparing and reviewing applications for the licensing of non-power reactors: Standard review plan and acceptance criteria. NUREG - 1537, Part 2

    SciTech Connect (OSTI)

    NONE

    1996-02-01T23:59:59.000Z

    NUREG - 1537, Part 2 gives guidance on the conduct of licensing action reviews to NRC staff who review non-power reactor licensing applications. These licensing actions include construction permits and initial operating licenses, license renewals, amendments, conversions from highly enriched uranium to low-enriched uranium, decommissioning, and license termination.

  12. Draft Site-Wide Environmental Impact Statement Nevada Appendix...

    National Nuclear Security Administration (NNSA)

    2006 1.37 MB NRC 1977 13.67 MB NRC 1987 17.62 MB NRC 2000 19.91 MB NRC 2009 450.45 KB NSTec 2010 46.49 KB Neahauser et al. 2000 1.18 MB Phillips et al 1994 1.51 MB Rao et al 1982...

  13. NATURAL RESOURCES CONSERVATION Fisheries Ecology & Conservation

    E-Print Network [OSTI]

    Schweik, Charles M.

    NATURAL RESOURCES CONSERVATION Fisheries Ecology & Conservation Fall Semester Spring Semester the Landscape 3 NRC 397AE Aquatic Ecology (odd yrs) 4d NRC 390E Evolution & Conserv. 3e Physical Science Year NRC 597F Conserv. Genetics (even yrs) 4g NRC 597AE Cons. Aq. Sys. (odd yrs) 4g Communication

  14. NATURAL RESOURCES CONSERVATION Forest Ecology & Conservation

    E-Print Network [OSTI]

    Schweik, Charles M.

    NATURAL RESOURCES CONSERVATION Forest Ecology & Conservation Fall Semester Spring Semester First Conservation 3 BCT 150 The Built Envir. 4 NRC 211 Animal Sampling & Ident. 1 NRC 212 Forest Tree & Shrub ID 1; NRC 515 Forest Fire Mgt; NRC 597C Case Studies in Conservation; courses in Sociology, Anthropology

  15. Numerous studies have shown that airborne particulate matter (PM) is associated with

    E-Print Network [OSTI]

    Dominici, Francesca

    such as ozone (O3) [Health Effects Institute 2002; National Research Council (NRC) 2004]. Studies have

  16. Green Impact Universities and Colleges: EXCELLENCE guidance

    E-Print Network [OSTI]

    Harman, Neal.A.

    Green Impact Universities and Colleges: EXCELLENCE guidance 1.0 Introduction Green Impact progressing through institutionally bespoke workbooks to green their departments and campuses, the need, rather than reaching a pre-set endpoint, so we are developing Green Impact to ensure our participants

  17. Gainful Employment Programs Guidance January 2012

    E-Print Network [OSTI]

    Pantaleone, Jim

    with the following information on our GE programs: · Name and Classification of Instructional Program (CIP) code1 Gainful Employment Programs Guidance January 2012 Eric R. Pedersen, Associate Vice Chancellor Background On October 29, 2010, and June 13, 2011, the Department of Education (ED) published final

  18. Mercury Spill Information and Response Guidance

    E-Print Network [OSTI]

    Holland, Jeffrey

    Mercury Spill Information and Response Guidance Background Information Mercury can be found, plumbing traps and vacuum pumps. When mercury is spilled, it forms beads or droplets that can accumulate mercury vapors can be very dangerous, depending on the amount inhaled and the length of exposure

  19. POLICY GUIDANCE MEMORANDUM #27 Certification Program on Prohibited...

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

    Certification Program on Prohibited Personnel Practices and Whistleblower Protections POLICY GUIDANCE MEMORANDUM 27 Certification Program on Prohibited Personnel Practices and...

  20. Use of a Machine Control & Guidance System Determination of Performance

    E-Print Network [OSTI]

    1 Use of a Machine Control & Guidance System Determination of Performance Protection against. Dr. P. Rausch Why Machine Guidance? 1 Introduction Machine Guidance allows higher performance. Higher someone checking down below: 09.07.2008 3 ,,Machine control by shout and gesture". Planned Excavator Job

  1. Guidance on peat soils 1 | Peat | Helen Cariss

    E-Print Network [OSTI]

    Guidance on peat soils 1 | Peat | Helen Cariss Forestry and deep peat Purpose This policy guidance on forestry and deep peat acts as the country level guidance for FCW. It applies to regulatory functions: conserving and enhancing biodiversity climate change mitigation maintaining the peat and soil resource

  2. GC GUIDANCE ON ELECTRIC VEHICLE RECHARGING STATIONS

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-UpHeatMulti-Dimensional Subject: Guidance for natural gas as a feedstock for

  3. GUIDANCE ON CONDUCTING ADVERSE DIVERSITY ANALYSIS

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-UpHeatMulti-Dimensional Subject: Guidance for natural gas asWindEECBG PROGRAM

  4. GC GUIDANCE ON MEETINGS WITH UNION OFFICIALS

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-UpHeatMulti-Dimensional Subject: Guidance for natural gas as a feedstock forMEETINGS WITH

  5. Guidance & Opinions | 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) " ,"ClickPipelinesProvedDecember 2005DepartmentDecemberGlossary ofGroundwater Cleanup ProgressesGuidance

  6. General Privacy Act Guidance | 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 | Department of Energy FreeportEnergyPrivacy Act Guidance General

  7. Site Transition Plan Guidance | Department of Energy

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector GeneralDepartment of Energyof the Americas |DOE FormerEnergy DataPlan Guidance Site Transition

  8. QA in Design Guidance | 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 Systems Engineering Research and DevelopmentDepartmentin Design Guidance QA in Design

  9. Policy and Guidance | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 - September 2006Photovoltaic TheoryPlant 242-ZPolaronRetaliation |Guidance Policy

  10. Policy, Guidance & Reports | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 - September 2006Photovoltaic TheoryPlant 242-ZPolaronRetaliation |GuidanceReports

  11. All NEPA Guidance | Department of Energy

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion |Energyon ArmedWaste andAccess to OUO Access to OUOAlaska Feature ArticlesAlice OrrellGuidance

  12. Enforcement Guidance Supplement 00-03

    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 EnergyEnergyENERGY TAX POLICIES AND INTER-JURISDICTIONAL CHALLENGES March 22,Department of2,Guidance

  13. Human-system interface design review guideline: The development of draft revision 1 to NUREG-0700

    SciTech Connect (OSTI)

    O`Hara, J.; Stubler, W.; Brown, W. [Brookhaven National Lab., Upton, NY (United States)] [and others

    1996-03-01T23:59:59.000Z

    Advanced human-system interface (HSI) technologies are being developed in the commercial nuclear power industry. These HSIs may have significant implications for plant safety in that they will affect the ways in which the operator interacts with and supervises an increasingly complex system. The U.S. Nuclear Regulatory Commission (NRC) reviews the HSI aspects of nuclear plants to ensure that operator performance and reliability are supported. The NRC is developing guidance to support its review of these advanced designs. The guidance consists of an evaluation methodology and an extensive set of human factors guidelines which are used in one aspect of the evaluation. The paper describes the guidance development of the evaluation methodology and the guidelines.

  14. axon guidance factors: Topics by E-print Network

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

    16 The axon guidance receptor gene ROBO1 is a candidate gene for developmental dyslexia CiteSeer Summary: Dyslexia, or specific reading disability, is the most common...

  15. axon guidance events: Topics by E-print Network

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

    14 The axon guidance receptor gene ROBO1 is a candidate gene for developmental dyslexia CiteSeer Summary: Dyslexia, or specific reading disability, is the most common...

  16. axon growth guidance: Topics by E-print Network

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

    18 The axon guidance receptor gene ROBO1 is a candidate gene for developmental dyslexia CiteSeer Summary: Dyslexia, or specific reading disability, is the most common...

  17. axon guidance regulators: Topics by E-print Network

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

    19 The axon guidance receptor gene ROBO1 is a candidate gene for developmental dyslexia CiteSeer Summary: Dyslexia, or specific reading disability, is the most common...

  18. axon guidance defective: Topics by E-print Network

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

    14 The axon guidance receptor gene ROBO1 is a candidate gene for developmental dyslexia CiteSeer Summary: Dyslexia, or specific reading disability, is the most common...

  19. POLICY GUIDANCE MEMORANDUM #30 Job Opportunity Announcement Template...

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

    of Job Opportunity Announcement templates throughout the Deparment to improve Hiring Reform Initiatives. POLICY GUIDANCE MEMORANDUM 30 Job Opportunity Announcement Template...

  20. DOE Audit Guidance for For-Profit Financial Assistance Awards...

    Office of Environmental Management (EM)

    I) April 2012 1 I. GENERAL AUDIT PROGRAM A. PURPOSE AND APPLICABILITY The following General Audit Program provides requirements and guidance for independent audit organizations in...

  1. Guidance for Energy Efficiency and Conservation Block Grant Grantees...

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

    Energy Conservation Bonds and New Clean Renewable Energy Bonds Guidance for Energy Efficiency and Conservation Block Grant Grantees on Qualified Energy Conservation Bonds and...

  2. Guidance for Energy Efficiency and Conservation Block Grant Program...

    Energy Savers [EERE]

    Grant Program Recipients on Formula Grants Guidance for Energy Efficiency and Conservation Block Grant Program Recipients on Formula Grants U.S. Department of Energy (DOE) Office...

  3. Guidance for Energy Efficiency and Conservation Block Grant Recipients...

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

    for Energy Efficiency and Conservation Block Grant Recipients on Program Evaluation Guidelines Guidance for Energy Efficiency and Conservation Block Grant Recipients on Program...

  4. Guidance For Energy Efficiency And Conservation Block Grant Grantees...

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

    For Energy Efficiency And Conservation Block Grant Grantees On Financing Programs Guidance For Energy Efficiency And Conservation Block Grant Grantees On Financing Programs U.S....

  5. Guidance For Energy Efficiency And Conservation Block Grant Grantees...

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

    October 17, 2012 ORIGINALLY ISSUED: December 7, 2009 SUBJECT: GUIDANCE FOR ENERGY EFFICIENCY AND CONSERVATION BLOCK GRANT GRANTEES ON FINANCING PROGRAMS. PURPOSE To provide...

  6. Enforcement Guidance Supplement 00-02: Price-Anderson Amendment...

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

    of program implementation lessons-learned Enforcement Guidance Supplement 00-02: Price-Anderson Amendment Act (PAAA) Program Reviews More Documents & Publications...

  7. Enforcement Guidance Supplement 03-02: Revision to Occurrence...

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

    for Enforcement, published in June 1998, provides the opportunity for the Office of Price-Anderson Enforcement (OE) to periodically issue clarifying guidance regarding the...

  8. Adaptation to Climate Variability and Change: A Guidance Manual...

    Open Energy Info (EERE)

    to Climate Variability and Change: A Guidance Manual for Development Planning Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Adaptation to Climate Variability and...

  9. Greenhouse Gas Guidance and Reporting | Department of Energy

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

    and manage their greenhouse gas (GHG) emissions to meet Federal goals and mitigate climate change. Federal Guidance Read the White House Council on Environmental Quality's...

  10. Office of Personnel Management (OPM) Guidance on Diversity and...

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

    and Inclusion Agency Specific Strategic Plan Guidance.pdf OPM Hispanic Employment Data Report 2011.pdf Model Strategies for Recruitment and Hiring of People with...

  11. Guidance on the Required Period for Grantees to Obligate Funds...

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

    Funds and the Procedures for Reporting of Obligated Funds for the Energy Efficiency Conservation Block Grant (EECBG) Program Guidance on the Required Period for Grantees to...

  12. Microsoft Word - FY 2015 SP Performance Appraisal System Guidance...

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

    Resources Office of the Chief Human Capital Officer U.S. Department of Energy FY 2015 Senior Professional (SP) Performance Appraisal System Opening Guidance 2 Table of...

  13. Microsoft Word - FY 2015 SES Performance Appraisal System Guidance...

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

    Resources Office of the Chief Human Capital Officer U.S. Department of Energy FY 2015 Senior Executive Service (SES) Performance Appraisal System Opening Guidance 2 Table of...

  14. Guidance for State Energy Program Recipients on Policy and Procedures...

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

    for State Energy Program Recipients on Policy and Procedures Pursuant to the Closeout of American Recovery and Reinvestment Act Grants Guidance for State Energy Program Recipients...

  15. Technical background document for soil screening guidance. Review draft

    SciTech Connect (OSTI)

    Not Available

    1994-12-01T23:59:59.000Z

    The document provides the technical background behind the development of the November 1994 Soil Screening Guidance for Superfund. These documents define the Soil Screening framework, a suite of methodologies for developing Soil Screening Levels (SSLs) for 107 chemicals commonly found at Superfund sites. The document is an updated version of the background document developed in support of the September 30, 1993, draft SSL guidance (PB93-963508). The document and the Guidance is available for public comment and is currently undergoing extensive peer review. Because the guidance is still under review, it and this document should not be used until they are finalized following this rigorous technical review and public comment.

  16. POLICY GUIDANCE MEMORANDUM #18 Advertisement of Federal Career...

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

    8 Advertisement of Federal Career Intern Program Employment Opps (Expired) POLICY GUIDANCE MEMORANDUM 18 Advertisement of Federal Career Intern Program Employment Opps (Expired)...

  17. POLICY GUIDANCE MEMORANDUM #32A Schedule A Appointments of Persons...

    Energy Savers [EERE]

    A Appointments of Persons with Disabilities and Appointments for Disabled Veterans POLICY GUIDANCE MEMORANDUM 32A Schedule A Appointments of Persons with Disabilities and...

  18. POLICY GUIDANCE MEMORANDUM #29 Employment Offers Letters Performance...

    Energy Savers [EERE]

    9 Employment Offers Letters Performance Management POLICY GUIDANCE MEMORANDUM 29 Employment Offers Letters Performance Management This memorandum is to ensure compliance with DOE...

  19. Policy Guidance Memorandum #37 Procedures for Excepted Service...

    Energy Savers [EERE]

    7 Procedures for Excepted Service Exceptionally Well Qualified (EWQ) Appointments Policy Guidance Memorandum 37 Procedures for Excepted Service Exceptionally Well Qualified (EWQ)...

  20. POLICY GUIDANCE MEMORANDUM #28 Requirements for Non-Competitive...

    Energy Savers [EERE]

    for Non-Competitive Reassignments into Supervisory andor Managerial Positions POLICY GUIDANCE MEMORANDUM 28 Requirements for Non-Competitive Reassignments into...

  1. Energy Department Releases Guidance for Implementation of Cybersecurit...

    Energy Savers [EERE]

    the framework's prioritized approach. In developing this guidance, we collaborated with private sector stakeholders through the Electricity Subsector Coordinating Council and the...

  2. Microsoft Word - Final ALOHA Guidance Report Version May 24 2004...

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

    has provided guidance and general recommendations in this area through the Accident Phenomenology and Consequence (APAC) Methodology Evaluation Program. As part of this program,...

  3. Safety Planning Guidance for Hydrogen and Fuel Cell Projects

    Fuel Cell Technologies Publication and Product Library (EERE)

    This guidance document provides information on safety requirements for hydrogen and fuel cell projects funded by the U.S. Department of Energy Fuel Cell Technologies Program.

  4. Guidance for Deployment of Mobile Technologies for Nuclear Power...

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

    This report is a guidance document prepared for the benefit of commercial nuclear power plants' (NPPs) supporting organizations and personnel who are considering or undertaking...

  5. Grant Guidance to Administer the American Recovery and Reinvestment...

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

    Energy (DOE) Office of Energy Efficiency and Renewable Energy (EERE) Weatherization Assistance Program Notice 09-01B deals with guidance to program granteesstates and U.S....

  6. Guidance for Federal Departments and Agencies on Establishing...

    Energy Savers [EERE]

    on Establishing, Applying, and Revising Categorical Exclusions Under the National Environmental Policy Act Guidance for Federal Departments and Agencies on Establishing,...

  7. Enforcement Guidance Supplement 00-03, Specific Issues on Applicabilit...

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

    and Technical Specifications. Specifically, this guidance reaffirms that quality assurance (QA) controls required by 10 CFR 830 are not in any way limited by language...

  8. POLICY GUIDANCE MEMORANDUM #11A Approval Process for Dual Compensation...

    Office of Environmental Management (EM)

    1A Approval Process for Dual Compensation Waivers for Reemployed Annuitants POLICY GUIDANCE MEMORANDUM 11A Approval Process for Dual Compensation Waivers for Reemployed Annuitants...

  9. Cask system design guidance for robotic handling

    SciTech Connect (OSTI)

    Griesmeyer, J.M.; Drotning, W.D.; Morimoto, A.K.; Bennett, P.C.

    1990-10-01T23:59:59.000Z

    Remote automated cask handling has the potential to reduce both the occupational exposure and the time required to process a nuclear waste transport cask at a handling facility. The ongoing Advanced Handling Technologies Project (AHTP) at Sandia National Laboratories is described. AHTP was initiated to explore the use of advanced robotic systems to perform cask handling operations at handling facilities for radioactive waste, and to provide guidance to cask designers regarding the impact of robotic handling on cask design. The proof-of-concept robotic systems developed in AHTP are intended to extrapolate from currently available commercial systems to the systems that will be available by the time that a repository would be open for operation. The project investigates those cask handling operations that would be performed at a nuclear waste repository facility during cask receiving and handling. The ongoing AHTP indicates that design guidance, rather than design specification, is appropriate, since the requirements for robotic handling do not place severe restrictions on cask design but rather focus on attention to detail and design for limited dexterity. The cask system design features that facilitate robotic handling operations are discussed, and results obtained from AHTP design and operation experience are summarized. The application of these design considerations is illustrated by discussion of the robot systems and their operation on cask feature mock-ups used in the AHTP project. 11 refs., 11 figs.

  10. Trends in HFE Methods and Tools and Their Applicability to Safety Reviews

    SciTech Connect (OSTI)

    O'Hara, J.M.; Plott, C.; Milanski, J.; Ronan, A.; Scheff, S.; Laux, L.; and Bzostek, J.

    2009-09-30T23:59:59.000Z

    The U.S. Nuclear Regulatory Commission's (NRC) conducts human factors engineering (HFE) safety reviews of applicant submittals for new plants and for changes to existing plants. The reviews include the evaluation of the methods and tools (M&T) used by applicants as part of their HFE program. The technology used to perform HFE activities has been rapidly evolving, resulting in a whole new generation of HFE M&Ts. The objectives of this research were to identify the current trends in HFE methods and tools, determine their applicability to NRC safety reviews, and identify topics for which the NRC may need additional guidance to support the NRC's safety reviews. We conducted a survey that identified over 100 new HFE M&Ts. The M&Ts were assessed to identify general trends. Seven trends were identified: Computer Applications for Performing Traditional Analyses, Computer-Aided Design, Integration of HFE Methods and Tools, Rapid Development Engineering, Analysis of Cognitive Tasks, Use of Virtual Environments and Visualizations, and Application of Human Performance Models. We assessed each trend to determine its applicability to the NRC's review by considering (1) whether the nuclear industry is making use of M&Ts for each trend, and (2) whether M&Ts reflecting the trend can be reviewed using the current design review guidance. We concluded that M&T trends that are applicable to the commercial nuclear industry and are expected to impact safety reviews may be considered for review guidance development. Three trends fell into this category: Analysis of Cognitive Tasks, Use of Virtual Environments and Visualizations, and Application of Human Performance Models. The other trends do not need to be addressed at this time.

  11. Climate Change Guidance: A Pragmatic Approach to Client

    E-Print Network [OSTI]

    Nebraska-Lincoln, University of

    10/21/11 Climate Change Guidance: A Pragmatic Approach to Client Needs Climate, Water and Ecosystems- Shaping the Great Plains October 13, 2011 #12;10/21/11 Climate Change Guidance: A Pragmatic Approach to Client NeedsClimate Science ­ 2011 ·Yes, the climate is changing. ·Climate science is changing

  12. Waypoint Guidance for Small UAVs in Wind John Osborne

    E-Print Network [OSTI]

    Washington at Seattle, University of

    Waypoint Guidance for Small UAVs in Wind John Osborne and Rolf Rysdyk University of Washington, Seattle, WA, 98115,USA I. abstract Wind is often ignored or only implicitly addressed in design of guidance algorithms. For small UAVs exposed to strong winds, wind has a very significant nonlinear effect

  13. Forestry Commission Wales Guidance on rental levels for Hydro Power

    E-Print Network [OSTI]

    initiated a process to facilitate the development of small- scale hydro-electricity schemes on land ownedForestry Commission Wales Guidance on rental levels for Hydro Power Guidance on rental levels for hydro power projects Tel: 02920 475961 Email: hydrowales@forestry.gsi.gov.uk Version 1.0 Mike Pitcher 17

  14. Environmental Guidance Program Reference Book: American Indian Religious Freedom Act

    SciTech Connect (OSTI)

    Not Available

    1987-11-01T23:59:59.000Z

    This Reference Book contains a copy of the American Indian Religious Freedom Act and guidance for DOE compliance with the statute. The document is provided to DOE and contractor staff for informational purposes only and should not be interpreted as legal guidance. Updates that include important new requirements will be provided periodically.

  15. IT Policy, Procedures and Guidance University College, Oxford

    E-Print Network [OSTI]

    Henderson, Gideon

    IT Policy, Procedures and Guidance University College, Oxford Patrick Baird IT and Web Fellow Andy Hamilton IT Manager Helene Augar College Registrar #12;Summary This policy and guidance document. Transgressions (Junior Members) 14 14. Flexible Hours and Working at Home (Staff) 15 15. Revisions to this Policy

  16. Guidance for the Quality Assurance of Fire Protection Systems

    Broader source: Energy.gov [DOE]

    This quality assurance document is intended to provide guidance for the DOE fire protection community in the continuing effort to ensure the reliability of fire protection systems. This guidance document applies the concepts of DOE Order 5700.6C, Quality Assurance, to the management of fire protection systems.

  17. An Adaptive Vehicle Guidance System instigated from Ant Colony Behavior

    E-Print Network [OSTI]

    Casillas Barranquero, Jorge

    safety [4], a minimization of the energy consumption, and others. A Vehicle Guidance System (VGS) assistsAn Adaptive Vehicle Guidance System instigated from Ant Colony Behavior Habib M. Kammoun, Ilhem of the high dynamicity of traffic flow and the polynomial increase in the number of vehicles on road networks

  18. A guide to CERCLA site assessment. Environmental Guidance

    SciTech Connect (OSTI)

    Not Available

    1994-02-01T23:59:59.000Z

    This Pocket Guide is a condensed version of information provided in three EPA documents: Guidance for Performing Preliminary Assessments Under CERCLA, Guidance for Performing Site Inspections Under CERCLA, and Hazard Ranking System Guidance Manual. Additionally the guide provides a DOE perspective on site assessment issues and information on the Federal Agency Hazardous Waste Compliance Docket as well as data sources for DOE site assessments. The guide is intended to present this information in a simple, portable, and direct manner that will allow the user to effectively focus on those aspects of the site assessment process of interest. The guide is not intended as a substitute for the three EPA guidance documents mentioned previously. DOE investigators should be thoroughly familiar with the EPA guidance before conducting site assessments. Use this pocketguide as an overview of procedures and requirements and as a field guide.

  19. Technical guidance for siting criteria development

    SciTech Connect (OSTI)

    Aldrich, D.C.; Sprung, J.L.; Alpert, D.J.; Diegert, K.; Ostmeyer, R.M.; Ritchie, L.T.; Strip, D.R.; Johnson, J.D.; Hansen, K.; Robinson, J.

    1982-12-01T23:59:59.000Z

    Technical guidance to support the formulation and comparison of possible siting criteria for nuclear power plants has been developed in four areas: (1) consequences of hypothetical severe nuclear-power-plant accidents, (2) characteristics of population distributions about current reactor sites, (3) site availability within the continental United States, and (4) socioeconomic impacts of reactor siting. The impact on consequences of source-term magnitude, meteorology, population distribution, and emergency response have been analyzed. Population distributions about current sites were analyzed to identify statistical characteristics, time trends, and regional differences. A site-availability data bank was constructed for the continential United States. The data bank contains information about population densities, seismicity, topography, water availability, and land-use restrictions. Finally, the socioeconomic impacts of rural-industrialization projects, energy boomtowns, and nuclear power plants were examined to determine their nature, magnitude, and dependence on site demography and remoteness.

  20. D & D screening risk evaluation guidance

    SciTech Connect (OSTI)

    Robers, S.K.; Golden, K.M.; Wollert, D.A.

    1995-09-01T23:59:59.000Z

    The Screening Risk Evaluation (SRE) guidance document is a set of guidelines provided for the uniform implementation of SREs performed on decontamination and decommissioning (D&D) facilities. Although this method has been developed for D&D facilities, it can be used for transition (EM-60) facilities as well. The SRE guidance produces screening risk scores reflecting levels of risk through the use of risk ranking indices. Five types of possible risk are calculated from the SRE: current releases, worker exposures, future releases, physical hazards, and criticality. The Current Release Index (CRI) calculates the current risk to human health and the environment, exterior to the building, from ongoing or probable releases within a one-year time period. The Worker Exposure Index (WEI) calculates the current risk to workers, occupants and visitors inside contaminated D&D facilities due to contaminant exposure. The Future Release Index (FRI) calculates the hypothetical risk of future releases of contaminants, after one year, to human health and the environment. The Physical Hazards Index (PHI) calculates the risks to human health due to factors other than that of contaminants. Criticality is approached as a modifying factor to the entire SRE, due to the fact that criticality issues are strictly regulated under DOE. Screening risk results will be tabulated in matrix form, and Total Risk will be calculated (weighted equation) to produce a score on which to base early action recommendations. Other recommendations from the screening risk scores will be made based either on individual index scores or from reweighted Total Risk calculations. All recommendations based on the SRE will be made based on a combination of screening risk scores, decision drivers, and other considerations, as determined on a project-by-project basis.

  1. EECBG Program Notice 10-020B, Guidance for Energy Efficiency...

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

    B, Guidance for Energy Efficiency and Conservation Block Grant Recipients on Closeout Procedures EECBG Program Notice 10-020B, Guidance for Energy Efficiency and Conservation Block...

  2. EECBG Program Notice 09-002B - Guidance for Energy Efficiency...

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

    B - Guidance for Energy Efficiency and Conservation Block Grant Grantees on financing programs EECBG Program Notice 09-002B - Guidance for Energy Efficiency and Conservation Block...

  3. E-Print Network 3.0 - advanced video guidance Sample Search Results

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

    video guidance Search Powered by Explorit Topic List Advanced Search Sample search results for: advanced video guidance Page: << < 1 2 3 4 5 > >> 1 Content Analysis and...

  4. DOE's General Counsel Releases Guidance on Ex Parte Communications During Informal Rulemaking Proceedings

    Broader source: Energy.gov [DOE]

    Washington, DC - The Department of Energy today announced guidance on ex parte communications during informal rulemaking proceedings.  The guidance is intended to encourage the public to provide...

  5. Updating Human Factors Engineering Guidelines for Conducting Safety Reviews of Nuclear Power Plants

    SciTech Connect (OSTI)

    O, J.M.; Higgins, J.; Stephen Fleger - NRC

    2011-09-19T23:59:59.000Z

    The U.S. Nuclear Regulatory Commission (NRC) reviews the human factors engineering (HFE) programs of applicants for nuclear power plant construction permits, operating licenses, standard design certifications, and combined operating licenses. The purpose of these safety reviews is to help ensure that personnel performance and reliability are appropriately supported. Detailed design review procedures and guidance for the evaluations is provided in three key documents: the Standard Review Plan (NUREG-0800), the HFE Program Review Model (NUREG-0711), and the Human-System Interface Design Review Guidelines (NUREG-0700). These documents were last revised in 2007, 2004 and 2002, respectively. The NRC is committed to the periodic update and improvement of the guidance to ensure that it remains a state-of-the-art design evaluation tool. To this end, the NRC is updating its guidance to stay current with recent research on human performance, advances in HFE methods and tools, and new technology being employed in plant and control room design. This paper describes the role of HFE guidelines in the safety review process and the content of the key HFE guidelines used. Then we will present the methodology used to develop HFE guidance and update these documents, and describe the current status of the update program.

  6. Guidance on Dependence Assessment in SPAR-H

    SciTech Connect (OSTI)

    April M. Whaley

    2012-06-01T23:59:59.000Z

    As part of the effort to develop the SPAR-H user guidance, particular attention was paid to the assessment of dependence in order to address user questions about proper application of dependence. This paper presents a discussion of dependence from a psychological perspective and provides guidance on applying this information during the qualitative analysis of dependence to ensure more realistic and appropriate dependence assessments with the SPAR-H method. While this guidance was developed with SPAR-H in mind, it may be informative to other human reliability analysis methods that also use a THERP-based dependence approach, particularly if applied at the human failure event level.

  7. National Environmenal Policy Act Contracting Reform Guidance: Phase 1

    SciTech Connect (OSTI)

    NONE

    1995-08-01T23:59:59.000Z

    The NEPA Contracting Quality Improvement Team identified several contracting improvements to reduce the cost and time for the NEPA process. The team`s February 1995 report recommended a series of steps to achieve the improvements, including issuance of contracting guidance. The guidance will be issued in three phases. This Phase I guidance implements the team`s short-term recommendations. It provides model statements of work and a sample schedule of contractor deliverables, establishes a pilot program for evaluating performance of NEPA support contractors, and describes information resources available on the DOE NEPA Web.

  8. Design of highwall mining equipment electronic guidance package

    SciTech Connect (OSTI)

    Brenden, B.B.; Morgen, G.P.; Shorpik, J.R.; Farrar, R.

    1981-11-01T23:59:59.000Z

    This report provides design specifics and guidance software for a guidance system intended for use in guiding an auger type highwall mining head through thin coal seams to depths of up to 600 ft. A small desk top computer is used at the operator's station to send and receive signals in serialized bit streams to a downhole microprocessor. The guidance system accepts signals from a variety of sensors and uses these signals to plot and control the course of the auger head automatically using computer algorithms designed to keep the auger head in the coal seam and maintain a specified stump thickness.

  9. Guidance manual for conducting technology demonstration activities

    SciTech Connect (OSTI)

    Jolley, R.L.; Morris, M.I.; Singh, S.P.N.

    1991-12-01T23:59:59.000Z

    This demonstration guidance manual has been prepared to assist Martin Marietta Energy Systems, Inc. (Energy Systems), staff in conducting demonstrations. It is prepared in checklist style to facilitate its use and assumes that Energy Systems personnel have project management responsibility. In addition to a detailed step-by-step listing of procedural considerations, a general checklist, logic flow diagram, and several examples of necessary plans are included to assist the user in developing an understanding of the many complex activities required to manage technology demonstrations. Demonstrations are pilot-scale applications of often innovative technologies to determine the commercial viability of the technologies to perform their designed function. Demonstrations are generally conducted on well-defined problems for which existing technologies or processes are less than satisfactory in terms of effectiveness, cost, and/or regulatory compliance. Critically important issues in demonstration management include, but are not limited to, such factors as communications with line and matrix management and with the US Department of Energy (DOE) and Energy Systems staff responsible for management oversight, budgetary and schedule requirements, regulatory compliance, and safety.

  10. Transmission line environmental assessment guidance document

    SciTech Connect (OSTI)

    Jackson, J.; Pentecost, E.; Muzzarelli, J.

    1994-01-01T23:59:59.000Z

    Since 1939, U.S. utility companies have been required to obtain a Presidential Permit to construct electric transmission lines that cross a U.S. border and connect with a foreign utility. The purpose of this document is to provide Presidential Permit applicants with two types of guidance: (1) on the type of environmental and project descriptive information needed to assess the potential impacts of the proposed and alternative actions and (2) on compliance with applicable federal and state regulations. The main three chapters present information on the purpose and content of this document (Chapter 1); legislative, regulatory, and consultation requirements for transmission line interconnect projects (Chapter 2); and identification of basic transmission system design parameters and environmental data requirements for analysis of potential impacts of the proposed action (Chapter 3). Chapter 3 also includes information on possible techniques or measures to mitigate impacts. Appendix A presents an overview of NEPA requirements and DOE`s implementing procedures. Appendix B summarizes information on legislation that may be applicable to transmission line projects proposed in Presidential Permit applications.

  11. axon guidance receptors: Topics by E-print Network

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

    Index 1 The axon guidance receptor gene ROBO1 is a candidate gene for developmental dyslexia CiteSeer Summary: Dyslexia, or specific reading disability, is the most common...

  12. axon guidance molecule: Topics by E-print Network

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

    J. 15 The axon guidance receptor gene ROBO1 is a candidate gene for developmental dyslexia CiteSeer Summary: Dyslexia, or specific reading disability, is the most common...

  13. axon guidance gene: Topics by E-print Network

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

    Index 1 The axon guidance receptor gene ROBO1 is a candidate gene for developmental dyslexia CiteSeer Summary: Dyslexia, or specific reading disability, is the most common...

  14. axon guidance molecules: Topics by E-print Network

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

    J. 15 The axon guidance receptor gene ROBO1 is a candidate gene for developmental dyslexia CiteSeer Summary: Dyslexia, or specific reading disability, is the most common...

  15. Enforcement Guidance Supplement 00-01, Enforcement Position Relative...

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

    as a Contamination Area. DOE relevant guidance is contained in Implementation Guide DOE G 441.1-9, Radioactive Contamination Control Guide (699) and Article 238.3 of the DOE...

  16. Enforcement Guidance Supplement 00-01: Enforcement Position Relative...

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

    as a Contamination Area. DOE relevant guidance is contained in Implementation Guide DOE G 441.1-9, Radioactive Contamination Control Guide (699) and Article 238.3 of the DOE...

  17. Toxic Chemical Release Inventory reporting ``Qs & As``. Environmental Guidance

    SciTech Connect (OSTI)

    Not Available

    1994-03-01T23:59:59.000Z

    This document offers guidance on toxic chemical release inventory reporting, pursuant to Section 313 of the Emergency Planning and Community Right-to-Know Act (EPCRA) at DOE sites.

  18. Qualified Energy Conservation Bond (QECB) Update: New Guidance...

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

    the U.S. Department of Treasury and the Internal Revenue Service Qualified Energy Conservation Bond (QECB) Update: New Guidance from the U.S. Department of Treasury and the...

  19. DOE, Treasury Provide Guidance on Direct Payments for Renewable...

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

    - 2:33pm Addthis DOE and the U.S. Department of Treasury issued guidance on July 9 on the process for renewable energy project owners to receive direct federal payments in lieu of...

  20. 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...

  1. Guidance Based Collision Avoidance of Coordinated Nonholonomic Autonomous Vehicles

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Guidance Based Collision Avoidance of Coordinated Nonholonomic Autonomous Vehicles Xianbo Xiang following control, obstacle avoidance and collision free for coordinated multiple nonholonomic autonomous autonomous ve- hicles dealing with tasks could offer additional advantages, in terms of flexibility

  2. Using the NEPA Requirements and Guidance - Search Index

    Office of Environmental Management (EM)

    file, right click on it, select "Extract all", extract it to any location on your computer or USB drive. 2. Locate and Open the extracted folder "NEPA Requirements and Guidance...

  3. Mini-Guidance Articles from Lessons Learned Quarterly Reports...

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

    by the DOE Office of NEPA Policy and Compliance in consultation with the Office of General Counsel, the DOE NEPA Community, and others. The mini-guidance articles were...

  4. FEMP (Federal Energy Management Program) presents alternative financing guidance memoranda

    SciTech Connect (OSTI)

    NONE

    1998-06-01T23:59:59.000Z

    Utility financing of energy efficient measures becomes easier to accomplish with the two new alternative financing guidance memoranda, released April 17, 1998, that address the use of utility incentives for Federal facilities. The memoranda have been approved by the Alternative Financing Guidance Committee on the Interagency Energy Management Task Force. The memoranda include: (1) Policy Statement No. 001: Authority to Sole Source Utility Service Contracts as Referenced in Section 152 of the Energy Policy Act (EPACT) of 1992; and (2) Policy Statement No. 002: Congressional Notification for Utility Projects Under the Authority of Section 152 of the Energy Policy Act (EPACT) of 1992. The purpose for developing the financing memoranda was to address specific issues within current Federal procurement regulations that require clarification or guidance. This new guidance will allow for increased use of utility incentives as a means of financing energy efficient and life cycle cost-effective projects in Federal facilities.

  5. Management of radioactive material safety programs at medical facilities. Final report

    SciTech Connect (OSTI)

    Camper, L.W.; Schlueter, J.; Woods, S. [and others

    1997-05-01T23:59:59.000Z

    A Task Force, comprising eight US Nuclear Regulatory Commission and two Agreement State program staff members, developed the guidance contained in this report. This report describes a systematic approach for effectively managing radiation safety programs at medical facilities. This is accomplished by defining and emphasizing the roles of an institution`s executive management, radiation safety committee, and radiation safety officer. Various aspects of program management are discussed and guidance is offered on selecting the radiation safety officer, determining adequate resources for the program, using such contractual services as consultants and service companies, conducting audits, and establishing the roles of authorized users and supervised individuals; NRC`s reporting and notification requirements are discussed, and a general description is given of how NRC`s licensing, inspection and enforcement programs work.

  6. Report on Lessons Learned from the NP 2010 Early Site Permit Program FINAL REPORT

    SciTech Connect (OSTI)

    none,

    2008-03-26T23:59:59.000Z

    This report provides a summary of lessons learned from the demonstration of the licensing process for three Early Site Permit (ESP) applications supported as part of the Department of Energy’s (DOE) Nuclear Power 2010 (NP 2010) program. The ESP process was established by the Nuclear Regulatory Commission (NRC) to enable completion of the site evaluation component of nuclear power plant licensing under 10 CFR Part 52 before a utility makes a decision to build a plant. Early Site Permits are valid for 10 to 20 years and can be renewed for an additional 10 to 20 years. NRC review of an ESP application addresses site safety issues, environmental protection issues, and plans for coping with emergencies. Successful completion of the ESP process will establish that a site is suitable for possible future construction and operation of a nuclear power plant. Most importantly, an ESP resolves significant site-related safety and environmental issues early in the decision process and helps achieve acceptance by the public. DOE competitively selected Dominion Nuclear Energy North Anna, LLC (Dominion); System Energy Resources, Inc. (an Entergy subsidiary); and Exelon Generation Company, LLC (Exelon) in 2002 to demonstrate the ESP process and provided cost-shared support through the NP 2010 program. Dominion pursued an ESP for the North Anna site in Virginia; System Energy Resources, Inc. pursued an ESP for the Grand Gulf site in Mississippi; and Exelon pursued an ESP for the Clinton site in Illinois. After successfully demonstrating the process, the NRC issued an ESP for Clinton on March 17, 2007; Grand Gulf on April 5, 2007; and North Anna on November 27, 2007. As with all successful projects, there are lessons to be learned from the NP 2010 early site permitting demonstration that can help improve future implementation guidance documents and regulatory review standards. In general, these lessons pertain to the effectiveness of the regulatory process, experience related to guidance for developing and reviewing ESP applications, issues involving ESP plant parameters, and suggestions for future ESP applicants. The development, submittal, and issuance of these first ESPs under DOE’s NP 2010 program started the momentum to exercise NRC’s new 10 CFR Part 52 licensing process. Several key questions that define critical issues regarding the effectiveness of regulations pertaining to ESPs have been identified and summarized in this report. However, the final resolution of whether the ESP component of the Part 52 process significantly contributes to the predictability in nuclear power plant licensing requires more experience and time, such as the completion of the ongoing combined Construction and Operating License (COL) process for the North Anna and Grand Gulf sites. The three ESP project participants prepared and submitted to DOE lessons learned reports from their experience in developing, submitting, and receiving an ESP. This document summarizes these reports, which are appended hereto. The Nuclear Energy Institute (http://www.nei.org/) and NRC (http://www.nrc.gov/) have also prepared reports regarding their perspectives on lessons learned during the ESP process. Their documents can be accessed on their respective web sites. Following is a summary of the lessons learned from the NP 2010 ESP projects. Effectiveness of the ESP Process: In general, the ESP process is expected (subject to demonstration of the ESP finality provisions in the North Anna and Grand Gulf ESPs) to provide high value for applicants as a site banking and risk mitigation strategy. However, several aspects of the initial process, such as NRC hearings and determining an acceptable approach to the NRC’s Emergency Planning requirements, proved challenging for the applicants. Project Execution: Initial regulatory and industry guidance for planning and executing an ESP application program proved to be insufficient to address NRC’s document review expectations. However, continuous communication between NRC and the applicants helped establish an acceptable framework

  7. U.S. Department Of Energy Commends Industry Consortia for Making...

    Office of Environmental Management (EM)

    (NRC). This application marks the second to the NRC in nearly 30 years to build a new nuclear reactor. Specifically, TVA's application seeks approval to build and operate two...

  8. Mineral balance in juvenile horses in race training

    E-Print Network [OSTI]

    Stephens, Tonya Leigh

    2002-01-01T23:59:59.000Z

    % and 36% over current NRC (1989) recommendations respectively. Phosphorus absorption and retention were not maximized at the highest intakes fed (66 mg/kg/d) which is 32% over current NRC (1989) recommendations. Phosphorus absorption was reduced at d 64...

  9. Slide 1

    National Nuclear Security Administration (NNSA)

    I Germantown, MD November 3-5, 2015 NRC - NMMSS I * Germantown, MD * The NRC-NMMSS 1 training now includes a model on reconciliation Training Point of Contact: John Ballard,...

  10. Microsoft PowerPoint - Upcoming NMMSS Training 2014 and 2015...

    National Nuclear Security Administration (NNSA)

    I Germantown, MD December 2-4, 2014 NRC - NMMSS I* Germantown, MD *The NRC-NMMSS I training now includes a model on reconciliation Training Point of Contact: John Ballard,...

  11. \\\\spock\\INEEL_DCTL\\INEEL-EROB\\documents\

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

    industry. The NRC NEP A Regulations (10 CFR Part 51) require that the NRC prepare an Environmental Impact Statement (EIS) for a permit to construct a nuclear power reactor....

  12. NUREG/CR-6299 BMI-2184

    Office of Scientific and Technical Information (OSTI)

    manner in the NRC regulatory process are maln- tained at the NRC Library, Two White Flint North, 11545 Rockviile Pike, Rockville. MD 20852-2738, for use by the publlc....

  13. DIMACS Center Rutgers University

    E-Print Network [OSTI]

    Hopkins University Andrew Patrick, NRC Canada Norman Sadeh, Carnegie Mellon University Working Group University Mark Ackerman, University of Michigan Fabian Monrose, Johns Hopkins University Andrew Patrick, NRC Canada Norman Sadeh, Carnegie Mellon University Workshop: Cryptography: Theory Meets Practice Dates

  14. MARSAME Appendix B B. SOURCES OF BACKGROUND RADIOACTIVITY

    E-Print Network [OSTI]

    : · The Nuclear Regulatory Commission (NRC) provides information concerning background radioactivity in Background as a Residual Radioactivity Criterion for Decommissioning NUREG-1501 (NRC 1994). · The United Nations Scientific

  15. UnitedStates EnvironmentalProtection

    E-Print Network [OSTI]

    ),theDOEOfficeofEnvironmentalRes- toration and WasteManagement(EM),and the NuclearRegulatoryCommission(NRC)Officeof Nuclear radioactivematerialsandsitesin theNRC'sSite Decommissioning Management Program (SDMP). Contents of Report Thereport includesan

  16. APPENDIX A Acronyms, Abbreviations, Symbols, and Notation

    E-Print Network [OSTI]

    Superfund National Priorities List NRC U.S. Nuclear Regulatory Commission NWWA National Water Well complexation model SDMP NRC's Site Decommissioning Management Plan TDS Total dissolved solids TLM Triple

  17. Long-term surveillance plan for the Gunnison, Colorado, disposal site

    SciTech Connect (OSTI)

    NONE

    1996-02-01T23:59:59.000Z

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

  18. Long-term surveillance plan for the Maybell, Colorado Disposal Site

    SciTech Connect (OSTI)

    NONE

    1997-12-01T23:59:59.000Z

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Maybell disposal site in Moffat County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites are cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Maybell disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination that remedial action is complete for the Maybell site and the NRC formally accepts this LTSP. This document describes the long-term surveillance program the DOE will implement to ensure the Maybell disposal site performs as designed. The program is based on site inspections to identify threats to disposal cell integrity. The LTSP is based on the UMTRA Project long-term surveillance program guidance document and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

  19. Long-term surveillance plan for the Gunnison, Colorado, disposal site

    SciTech Connect (OSTI)

    NONE

    1996-05-01T23:59:59.000Z

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

  20. Long-term surveillance plan for the Cheney disposal site near Grand Junction, Colorado

    SciTech Connect (OSTI)

    NONE

    1997-04-01T23:59:59.000Z

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Cheney disposal site. The site is in Mesa County near Grand Junction, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites are cared for in a manner that protects public health and safety and the environment. Before each disposal site may be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Cheney disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination that remedial action is complete and the NRC formally accepts this plan. This document describes the long-term surveillance program the DOE will implement to ensure that the Cheney disposal site performs as designed. The program is based on site inspections to identify potential threats to disposal cell integrity. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

  1. Long-term surveillance plan for the Gunnison, Colorado disposal site

    SciTech Connect (OSTI)

    NONE

    1996-04-01T23:59:59.000Z

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

  2. Long-term surveillance plan for the Maybell, Colorado Disposal Site

    SciTech Connect (OSTI)

    NONE

    1997-09-01T23:59:59.000Z

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Maybell disposal site in Moffat County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites are cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Maybell disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination that remedial action is complete for the Maybell site and the NRC formally accepts this LTSP. This document describes the long-term surveillance program the DOE will implement to ensure the Maybell disposal site performs as designed. The program is based on site inspections to identify threats to disposal cell integrity. The LTSP is based on the UMTRA Project long-term surveillance program guidance document and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

  3. Long-term surveillance plan for the Gunnison, Colorado, disposal site

    SciTech Connect (OSTI)

    NONE

    1997-04-01T23:59:59.000Z

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

  4. Summary of comments received on staff draft proposed rule on radiological criteria for decommissioning

    SciTech Connect (OSTI)

    Caplin, J.; Page, G.; Smith, D.; Wiblin, C. [Advanced Systems Technology, Inc., Rockville, MD (United States)

    1994-08-01T23:59:59.000Z

    The Nuclear Regulatory Commission (NRC) is conducting an enhanced participatory rulemaking to establish radiological criteria for the decommissioning of NRC licensed facilities. The NRC obtained comments on the scope, issues, and approaches through a series of workshops (57 FR 58727), Generic Environmental Impact Statement (GEIS) scoping meetings (58 FR 33570), a dedicated electronic bulletin board system (58 FR 37760), and written submissions. A summary of workshop and scope-meeting comments was published as NUREG/CR-6156. On February 2, 1994, the Commission published in the Federal Register (59 FR 4868) a notice that the NRC staff had prepared a ``staff draft`` proposed rule on radiological criteria for decommissioning. Copies of the staff draft were distributed to the Agreement States, participants in the earlier meetings, and other interested parties for comment. This report summarizes the comments identified from the 96 docketed letters received on the staff draft. No analysis or response is included in this report. The comments reflect a broad spectrum of viewpoints. Two subjects on which the commenters were in general agreement were (1) that the enhanced participatory rulemaking should proceed, and (2) that the forthcoming GEIS and guidance documents are needed for better understanding of the draft rule.

  5. COL Application Content Guide for HTGRs: Revision to RG 1.206, Part 1 - Status Report

    SciTech Connect (OSTI)

    Wayne Moe

    2012-08-01T23:59:59.000Z

    A combined license (COL) application is required by the Nuclear Regulatory Commission (NRC) for all proposed nuclear plants. The information requirements for a COL application are set forth in 10 CFR 52.79, “Contents of Applications; Technical Information in Final Safety Analysis Report.” An applicant for a modular high temperature gas-cooled reactor (HTGR) must develop and submit for NRC review and approval a COL application which conforms to these requirements. The technical information necessary to allow NRC staff to evaluate a COL application and resolve all safety issues related to a proposed nuclear plant is detailed and comprehensive. To this, Regulatory Guide (RG) 1.206, “Combined License Applications for Nuclear Power Plants” (LWR Edition), was developed to assist light water reactor (LWR) applicants in incorporating and effectively formatting required information for COL application review (Ref. 1). However, the guidance prescribed in RG 1.206 presumes a LWR design proposal consistent with the systems and functions associated with large LWR power plants currently operating under NRC license.

  6. DEVELOPMENT OF HFE SECTIONS OF DG-1145.

    SciTech Connect (OSTI)

    HIGGINS,J.C.; OHARA, J.M.; BONGARRA, J.

    2007-03-26T23:59:59.000Z

    For the licensing of the current fleet of commercial nuclear power plants (NPPs), the Nuclear Regulatory Commission (NRC) used two key documents, NUREG-0800 and Regulatory Guide (RG) 1.70. RG 1.70 provided guidance to applicants on the contents needed in their Safety Analysis Reports (SARs) submitted as part of their application to construct or operate an NPP. NUREG-0800, the NRC Standard Review Plan (SRP), provides guidance to the NRR staff reviewers on performing their safety reviews of these applications. As part of the preparation for a new wave of improved NPP designs the NRC is in the process of updating the SRP and is also developing a new RG designated as draft RG or DG-1145, ''Combined License Applications for Nuclear Power Plants (LWR Edition).'' This will eventually become RG 1.206 and will take the place of RG 1.70. This will provide guidance for combined license (COL) applicants, as well as for other 10CFR Part 52 variations that are permitted.

  7. Human Factors Engineering Program Review Model (NUREG-0711)Revision 3: Update Methodology and Key Revisions

    SciTech Connect (OSTI)

    OHara J. M.; Higgins, J.; Fleger, S.

    2012-07-22T23:59:59.000Z

    The U.S. Nuclear Regulatory Commission (NRC) reviews the human factors engineering (HFE) programs of applicants for nuclear power plant construction permits, operating licenses, standard design certifications, and combined operating licenses. The purpose of these safety reviews is to help ensure that personnel performance and reliability are appropriately supported. Detailed design review procedures and guidance for the evaluations is provided in three key documents: the Standard Review Plan (NUREG-0800), the HFE Program Review Model (NUREG-0711), and the Human-System Interface Design Review Guidelines (NUREG-0700). These documents were last revised in 2007, 2004 and 2002, respectively. The NRC is committed to the periodic update and improvement of the guidance to ensure that it remains a state-of-the-art design evaluation tool. To this end, the NRC is updating its guidance to stay current with recent research on human performance, advances in HFE methods and tools, and new technology being employed in plant and control room design. NUREG-0711 is the first document to be addressed. We present the methodology used to update NUREG-0711 and summarize the main changes made. Finally, we discuss the current status of the update program and the future plans.

  8. REVIEWING PERFORMANCE ASSESSMENTS SUPPORTING

    E-Print Network [OSTI]

    Robert J. Lewis

    2010-01-01T23:59:59.000Z

    Purpose: To summarize current NRC policy and guidance, which should assist in making informed decisions regarding land disposal of unique low-level radioactive waste streams, including disposal of significant quantities of depleted uranium until a new regulation is implemented. Background: In September 2009, NRC staff conducted two public workshops soliciting early public input on major issues associated with a potential rulemaking for land disposal of unique waste streams including, but not limited to, significant quantities of depleted uranium. During these workshops, a number of stakeholders expressed interest or concern with the review of performance assessments supporting land disposal of unique waste streams prior to completion of the rulemaking process. Discussion: The enclosure contains a summary of existing guidance for reviewing performance assessments with a focus on issues associated with the safe disposal of unique waste streams. NRC staff is providing this guidance to the Agreement States for their information, and for distribution to their licensees, as appropriate. If you have any questions regarding this correspondence, please contact me at 301-415-3340 or the individuals named below.

  9. graduate school college of engineering

    E-Print Network [OSTI]

    and professionally." Emily McCarthy, PhD, 2010 NRC Postdoctoral Research Associate, Remote Sensing Division, Naval

  10. Implications of Export/Import Reporting Requirements in the

    E-Print Network [OSTI]

    natural/depleted uranium and thorium currently require no notification to the USG. It appears the NRC may

  11. Safety of magnetic fusion facilities: Volume 2, Guidance

    SciTech Connect (OSTI)

    NONE

    1995-07-01T23:59:59.000Z

    This document provides guidance for the implementation of the requirements identified in Vol. 1 of this Standard. This guidance is intended for the managers, designers, operators, and other personnel with safety responsibilities for facilities designated as magnetic fusion facilities. While Vol. 1 is generally applicable in that requirements there apply to a wide range of fusion facilities, this volume is concerned mainly with large facilities such as the International Thermonuclear Experimental Reactor (ITER). Using a risk-based prioritization, the concepts presented here may also be applied to other magnetic fusion facilities. This volume is oriented toward regulation in the Department of Energy (DOE) environment.

  12. Regulatory and technical reports: (Abstract index journal). Compilation for first quarter 1997, January--March

    SciTech Connect (OSTI)

    Sheehan, M.A.

    1997-06-01T23:59:59.000Z

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors. This compilation is published quarterly and cummulated annually. Reports consist of staff-originated reports, NRC-sponsored conference reports, NRC contractor-prepared reports, and international agreement reports.

  13. ENVIRSCI Upper Level & Praxis Courses updated 2/27/13 1

    E-Print Network [OSTI]

    Massachusetts at Amherst, University of

    Orinithology BIOLOGY 548 Mammology CE-ENGIN 370 Introduction to Environmental & Water Resources ENVIRDES Environmental Biotechnology NRC 534 Forest Measurements NRC 564 Wildlife Habitat Management NRC 565 Dynamics ENVIRSCI 465 Principles of Environmental Site Assessment ENVIRSCI 575 Environmental Soil Chemistry GEO

  14. NATURAL RESOURCES CONSERVATION Forest Ecology & Conservation

    E-Print Network [OSTI]

    Schweik, Charles M.

    NATURAL RESOURCES CONSERVATION Forest Ecology & Conservation Fall Semester Spring Semester First Conservation 3 BCT 150 The Built Envir. 4 NRC 211 Animal Sampling & Ident. 1 NRC 212 Forest Tree & Shrub ID 1 forestry; NRC 575 Case Studies in Conservation; courses in Sociology, Anthropology, Public Policy, GIS

  15. DETERMINATION OF GUIDANCE VALUES FOR CLOSED LANDFILL GAS EMISSIONS

    E-Print Network [OSTI]

    Boyer, Edmond

    DETERMINATION OF GUIDANCE VALUES FOR CLOSED LANDFILL GAS EMISSIONS O. BOUR*, S. BERGER**, C Gambetta, 74 000 Annecy SUMMARY: In order to promote active landfill gas collection and treatment or natural attenuation, it is necessary to identify trigger values concerning landfill gas emissions

  16. Climate policy and competitiveness: Policy guidance and quantitative evidence

    E-Print Network [OSTI]

    Climate policy and competitiveness: Policy guidance and quantitative evidence Jared C. Carbone NicholasRivers July 2014 Abstract When considering adoption of a domestic climate change policy survey the literature on the quantitative impacts of unilateral climate change policy derived from

  17. Updated: September 2009 Data Protection Guidance: Collecting Personal Data

    E-Print Network [OSTI]

    Mumby, Peter J.

    Updated: September 2009 Data Protection Guidance: Collecting Personal Data When collecting Personal clear to anyone providing personal data: · That the University is a data controller it is important to comply with the 8 principles of data protection, for example the personal data should

  18. Autonomous vehicle guidance using analog VLSI neuromorphic sensors

    E-Print Network [OSTI]

    Autonomous vehicle guidance using analog VLSI neuromorphic sensors Giacomo Indiveri and Paul the principles of biological sensory systems into analog VLSI technology the field of neuromorphic engineering the robot with a fast, parallel and low-cost solution for real-time sensory information pre-processing. We

  19. Project Research and Development (PRD) scheme Guidance for Academic Applicants

    E-Print Network [OSTI]

    1 Project Research and Development (PRD) scheme ­ Guidance for Academic Applicants Contents science and technology leadership in future Science and Technology Facility Council projects and gives and development projects which enable STFC to deliver the science programme objectives in the areas of particle

  20. Project Research and Development (PRD) scheme Guidance for Applicants

    E-Print Network [OSTI]

    1 Project Research and Development (PRD) scheme ­ Guidance for Applicants Contents Contents science and technology leadership in future Science and Technology Facility Council projects and gives and development projects which enable STFC to deliver the science programme objectives in the areas of particle

  1. Last Updated: August 2008 Data Protection Guidance: Student Finance

    E-Print Network [OSTI]

    Mumby, Peter J.

    Last Updated: August 2008 Data Protection Guidance: Student Finance Student finance information The University will not release any information to third parties without consent. From time to time the Finance Protection Authority Form, these are available from Finance Services and only relate to information

  2. Guidance on Confidentiality in Student Health and Welfare

    E-Print Network [OSTI]

    Henderson, Gideon

    Guidance on Confidentiality in Student Health and Welfare Executive Summary The law has long manner. This would include information about a student's physical or mental health or financial Health and Welfare, and summarized below, confidential information should be shared with others only

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

    SciTech Connect (OSTI)

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

    2013-02-08T23:59:59.000Z

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

  4. LOOSE TIPPING BPG NOTE 4 Best Practice Guidance

    E-Print Network [OSTI]

    . For further details, see BPG Note 6: Application of sewage sludges and composts. I Improved vegetationLOOSE TIPPING BPG NOTE 4 Best Practice Guidance for Land Regeneration Introduction Reinstatement-scraper method (see for example: Bending et al., 1999; Land Research Associates, 1997, 2000; Moffat and Bending

  5. COMPLETE CULTIVATION BPG NOTE 13 Best Practice Guidance

    E-Print Network [OSTI]

    of sewage sludges and composts. Danielle Sinnett Figure 1 An excavator removing soil. #12;BPG NOTE 13 PAGE 2COMPLETE CULTIVATION BPG NOTE 13 Best Practice Guidance for Land Regeneration Introduction land within the UK, where traditional soil placement techniques using dozers followed by industrial

  6. University Guidance for the REPORTING OF ACCIDENTS, DISEASES AND

    E-Print Network [OSTI]

    and Safety Executive (HSE), Local Authorities and Environmental Health Departments which will provide of this guidance is to advise Heads of Department, Managers and Supervisors of the system by which the University. These may be required by external agencies such as HSE and the University Insurers. 3. REPORTING AN ACCIDENT

  7. REGULATORY GUIDANCE No. 06 -02 Date: July 6, 2006

    E-Print Network [OSTI]

    US Army Corps of Engineers

    ), this guidance applies to the transportation of dredged material for the purpose of dumping it into ocean waters it is determined that testing is needed, however, the physical, chemical, and biological (bioassay) tests relied.S. in accordance with guidelines promulgated by the administrator, the Environmental Protection Agency (EPA) under

  8. Eye movement modelling and gaze guidance Michael Dorr1

    E-Print Network [OSTI]

    Eye movement modelling and gaze guidance Michael Dorr1 , Eleonora Vig1 , Karl R. Gegenfurtner2. This modification of the saliency distribution of the scene leads to a change in eye movement statistics. Our systems. 1 INTRODUCTION The eye movements made by observers on a visual scene are tightly linked

  9. MODEL ANALYSES AND GUIDANCE (MAG) APPLICATION MAG User's Manual

    E-Print Network [OSTI]

    the National Weather Service's (NWS) Numerical Weather Prediction computer models. The website offers Guidance: Provides a path to view products created from the National Weather Service's (NWS) numerical Weather Service's Tropical Cyclone models. These products are only available when tropical cyclones

  10. TREE SEEDING BPG NOTE 10 Best Practice Guidance

    E-Print Network [OSTI]

    achieved by tree planting, using tree stock grown from seed or cuttings in the nursery. However for reclaimed brownfield land, taking account of modern guidance on site preparation and recent research on tree is comparatively inexpensive, and woodland so created can be cheaper than using the equivalent nursery stock. I

  11. THE INDUSTRIAL EXCELLENCE AWARD AS A TRAINING GUIDANCE TOOL

    E-Print Network [OSTI]

    Aristomenis, Antoniadis

    arising out of the industrial revolution, which has seen the emergence of explicit ways of producing goodsTHE INDUSTRIAL EXCELLENCE AWARD AS A TRAINING GUIDANCE TOOL NICHOLAS BILALIS, Professor Department. Introduction This paper presents an approach for meeting the current educational needs of industry

  12. SPAR-H Step-by-Step Guidance

    SciTech Connect (OSTI)

    April M. Whaley; Dana L. Kelly; Ronald L. Boring; William J. Galyean

    2012-06-01T23:59:59.000Z

    Step-by-step guidance was developed recently at Idaho National Laboratory for the US Nuclear Regulatory Commission on the use of the Standardized Plant Analysis Risk-Human Reliability Analysis (SPAR-H) method for quantifying Human Failure Events (HFEs). This work was done to address SPAR-H user needs, specifically requests for additional guidance on the proper application of various aspects of the methodology. This paper overviews the steps of the SPAR-H analysis process and highlights some of the most important insights gained during the development of the step-by-step directions. This supplemental guidance for analysts is applicable when plant-specific information is available, and goes beyond the general guidance provided in existing SPAR-H documentation. The steps highlighted in this paper are: Step-1, Categorizing the HFE as Diagnosis and/or Action; Step-2, Rate the Performance Shaping Factors; Step-3, Calculate PSF-Modified HEP; Step-4, Accounting for Dependence, and; Step-5, Minimum Value Cutoff.

  13. Guidance Document Safe Handling of Sulfides and Hydrogen Sulfide

    E-Print Network [OSTI]

    Guidance Document Safe Handling of Sulfides and Hydrogen Sulfide [This is a brief summary. Read concern would be hydrogen sulfide, whether handling in the pure gaseous form or by generation from various threshold level, the oxidative enzymes would be overwhelmed. Uses: Sulfides and hydrogen sulfide are used

  14. MaGKeyS : a haptic guidance keyboard system for facilitating sensorimotor training and rehabilitation

    E-Print Network [OSTI]

    Lewiston, Craig Edwin

    2009-01-01T23:59:59.000Z

    The Magnetic Guidance Keyboard System (MaGKeyS) embodies a new haptic guidance technology designed to facilitate sensorimotor training and rehabilitation. MaGKeyS works by employing active magnetic force to guide finger ...

  15. Draft Guidance for Section 242 of the Energy Policy Act of 2005...

    Energy Savers [EERE]

    Draft Guidance for Section 242 of the Energy Policy Act of 2005 - Hydroelectric Production Incentive Program - July 2014 Draft Guidance for Section 242 of the Energy Policy Act of...

  16. O:\\A76\\FAIR\\Fair Act 2008\\Guidance\\PDF\\COLLECTION TOOL TRAINING...

    Energy Savers [EERE]

    COLLECTION TOOL TRAINING.pdf.prn.pdf&0; O:A76FAIRFair Act 2008GuidancePDFCOLLECTION TOOL TRAINING.pdf.prn.pdf&0; O:A76FAIRFair Act 2008GuidancePDFCOLLECTION TOOL...

  17. E-Print Network 3.0 - added guidance documents Sample Search...

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

    Notices 1 The 1992 WIPP Land Withdrawal Act, Pub. L. Summary: document, known as the WIPP Subpart A Guidance, is available to the public. In developing the guidance, EPA... .C....

  18. Spreading The Word: Capital Market Consequences of Business Press Coverage of Management Earnings Guidance

    E-Print Network [OSTI]

    Twedt, Brady J

    2013-06-21T23:59:59.000Z

    This study investigates the role of the business press in disseminating management earnings guidance news to capital market participants. Using a unique sample of over 55,000 articles that relate specifically to management guidance, I find that 48...

  19. O:\\A76\\FAIR\\Fair Act 2008\\Guidance\\PDF\\GUIDE TO INVENTORY SUBMISSION...

    Office of Environmental Management (EM)

    O:A76FAIRFair Act 2008GuidancePDFGUIDE TO INVENTORY SUBMISSION ATTCH 2.pdf.prn.pdf&0; O:A76FAIRFair Act 2008GuidancePDFGUIDE TO INVENTORY SUBMISSION ATTCH...

  20. Copyright & Disclaimer Information Copyright 1994, 1995, 1996,1997 Career Guidance Foundation

    E-Print Network [OSTI]

    Bertini, Robert L.

    #12;Copyright & Disclaimer Information Copyright© 1994, 1995, 1996,1997 Career Guidance Foundation CollegeSource digital catalogs are derivitave works owned and copyrighted by Career Guidance Foundation. Catalog content is owned and copyrighted by the appropriate school. While the Career Guidance Foundation

  1. Long-term surveillance plan for the Burro Canyon disposal cell Slick Rock, Colorado

    SciTech Connect (OSTI)

    NONE

    1997-03-01T23:59:59.000Z

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Burro Canyon disposal cell in San Miguel County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites are cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Burro Canyon disposal cell. The general license becomes effective when the NRC concurs with the DOE`s determination that remedial action is complete at the Burro Canyon disposal cell and the NRC formally accepts this LTSP. Attachment 1 contains the concurrence letters from NRC. This LTSP describes the long-term surveillance program the DOE has implemented to ensure that the Burro Canyon disposal cell performs as designed. The program is based on site inspections to identify threats to disposal cell integrity. Ground water monitoring will not be required at the Burro Canyon disposal cell because the ground water protection strategy is supplemental standards based on low yield from the uppermost aquifer. The LTSP is based on the UMTRA Project`s long-term surveillance program guidance and meets the requirements of 10 CFR 40.27(b) and 40 CFR 192.03.

  2. Review of Quantitative Software Reliability Methods

    SciTech Connect (OSTI)

    Chu, T.L.; Yue, M.; Martinez-Guridi, M.; Lehner, J.

    2010-09-17T23:59:59.000Z

    The current U.S. Nuclear Regulatory Commission (NRC) licensing process for digital systems rests on deterministic engineering criteria. In its 1995 probabilistic risk assessment (PRA) policy statement, the Commission encouraged the use of PRA technology in all regulatory matters to the extent supported by the state-of-the-art in PRA methods and data. Although many activities have been completed in the area of risk-informed regulation, the risk-informed analysis process for digital systems has not yet been satisfactorily developed. Since digital instrumentation and control (I&C) systems are expected to play an increasingly important role in nuclear power plant (NPP) safety, the NRC established a digital system research plan that defines a coherent set of research programs to support its regulatory needs. One of the research programs included in the NRC's digital system research plan addresses risk assessment methods and data for digital systems. Digital I&C systems have some unique characteristics, such as using software, and may have different failure causes and/or modes than analog I&C systems; hence, their incorporation into NPP PRAs entails special challenges. The objective of the NRC's digital system risk research is to identify and develop methods, analytical tools, and regulatory guidance for (1) including models of digital systems into NPP PRAs, and (2) using information on the risks of digital systems to support the NRC's risk-informed licensing and oversight activities. For several years, Brookhaven National Laboratory (BNL) has worked on NRC projects to investigate methods and tools for the probabilistic modeling of digital systems, as documented mainly in NUREG/CR-6962 and NUREG/CR-6997. However, the scope of this research principally focused on hardware failures, with limited reviews of software failure experience and software reliability methods. NRC also sponsored research at the Ohio State University investigating the modeling of digital systems using dynamic PRA methods. These efforts, documented in NUREG/CR-6901, NUREG/CR-6942, and NUREG/CR-6985, included a functional representation of the system's software but did not explicitly address failure modes caused by software defects or by inadequate design requirements. An important identified research need is to establish a commonly accepted basis for incorporating the behavior of software into digital I&C system reliability models for use in PRAs. To address this need, BNL is exploring the inclusion of software failures into the reliability models of digital I&C systems, such that their contribution to the risk of the associated NPP can be assessed.

  3. Environmental Management Long-Term Stewardship Transition Guidance

    SciTech Connect (OSTI)

    Kristofferson, Keith

    2001-11-01T23:59:59.000Z

    Long-term stewardship consists of those actions necessary to maintain and demonstrate continued protection of human health and the environment after the completion of facility cleanup. Long-term stewardship is administered and overseen by the U.S. Department of Energy Environmental Management Office of Science and Technology. This report describes the background of long-term stewardship and gives general guidance about considerations when ownership and/or responsibility of a site should be transferred to a long-term stewardship program. This guidance document will assist the U.S. Department of Energy in: (a) ensuring that the long-term stewardship program leads transition planning with respect to facility and site areas, and (b) describing the classes and types of criteria and data required to initiate transition for areas and sites where the facility mission has ended and cleanup is complete.

  4. Regulatory and technical reports (abstract index journal): Annual compilation for 1994. Volume 19, Number 4

    SciTech Connect (OSTI)

    NONE

    1995-03-01T23:59:59.000Z

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC`s intention to publish this compilation quarterly and to cumulate it annually. The main citations and abstracts in this compilation are listed in NUREG number order. These precede the following indexes: secondary report number index, personal author index, subject index, NRC originating organization index (staff reports), NRC originating organization index (international agreements), NRC contract sponsor index (contractor reports), contractor index, international organization index, and licensed facility index. A detailed explanation of the entries precedes each index.

  5. Title list of documents made publicly available: February 1--28, 1995. Volume 17, Number 2

    SciTech Connect (OSTI)

    NONE

    1995-04-01T23:59:59.000Z

    This monthly publication contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. NRC documents that are publicly available may be examined without charge at the NRC Public Document Room (PDR).

  6. Planning guidance for the Chemical Stockpile Emergency Preparedness Program

    SciTech Connect (OSTI)

    Shumpert, B.L.; Watson, A.P.; Sorensen, J.H. [and others] and others

    1995-02-01T23:59:59.000Z

    This planning guide was developed under the direction of the U.S. Army and the Federal Emergency Management Agency (FEMA) which jointly coordinate and direct the development of the Chemical Stockpile Emergency Preparedness Program (CSEPP). It was produced to assist state, local, and Army installation planners in formulating and coordinating plans for chemical events that may occur at the chemical agent stockpile storage locations in the continental United States. This document provides broad planning guidance for use by both on-post and off-post agencies and organizations in the development of a coordinated plan for responding to chemical events. It contains checklists to assist in assuring that all important aspects are included in the plans and procedures developed at each Chemical Stockpile Disposal Program (CSDP) location. The checklists are supplemented by planning guidelines in the appendices which provide more detailed guidance regarding some issues. The planning guidance contained in this document will help ensure that adequate coordination between on-post and off-post planners occurs during the planning process. This planning guide broadly describes an adequate emergency planning base that assures that critical planning decisions will be made consistently at every chemical agent stockpile location. This planning guide includes material drawn from other documents developed by the FEMA, the Army, and other federal agencies with emergency preparedness program responsibilities. Some of this material has been developed specifically to meet the unique requirements of the CSEPP. In addition to this guidance, other location-specific documents, technical studies, and support studies should be used as needed to assist in the planning at each of the chemical agent stockpile locations to address the specific hazards and conditions at each location.

  7. Building Energy Use Benchmarking Guidance | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:Year in Review: Top Five EEREDepartmentFebruaryResistanceBuilding Energy Use Benchmarking Guidance

  8. Regulatory analysis technical evaluation handbook. Final report

    SciTech Connect (OSTI)

    NONE

    1997-01-01T23:59:59.000Z

    The purpose of this Handbook is to provide guidance to the regulatory analyst to promote preparation of quality regulatory analysis documents and to implement the policies of the Regulatory Analysis Guidelines of the US Nuclear Regulatory Commission (NUREG/BR-0058 Rev. 2). This Handbook expands upon policy concepts included in the NRC Guidelines and translates the six steps in preparing regulatory analyses into implementable methodologies for the analyst. It provides standardized methods of preparation and presentation of regulatory analyses, with the inclusion of input that will satisfy all backfit requirements and requirements of NRC`s Committee to Review Generic Requirements. Information on the objectives of the safety goal evaluation process and potential data sources for preparing a safety goal evaluation is also included. Consistent application of the methods provided here will result in more directly comparable analyses, thus aiding decision-makers in evaluating and comparing various regulatory actions. The handbook is being issued in loose-leaf format to facilitate revisions. NRC intends to periodically revise the handbook as new and improved guidance, data, and methods become available.

  9. Auxiliary feedwater system risk-based inspection guide for the Byron and Braidwood nuclear power plants

    SciTech Connect (OSTI)

    Moffitt, N.E.; Gore, B.F.: Vo, T.V. (Pacific Northwest Lab., Richland, WA (USA))

    1991-07-01T23:59:59.000Z

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Byron and Braidwood were selected for the fourth study in this program. The produce of this effort is a prioritized listing of AFW failures which have occurred at the plants and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Byron/Braidwood plants. 23 refs., 1 fig., 1 tab.

  10. Auxiliary feedwater system risk-based inspection guide for the H. B. Robinson nuclear power plant

    SciTech Connect (OSTI)

    Moffitt, N.E.; Lloyd, R.C.; Gore, B.F.; Vo, T.V. [Pacific Northwest Lab., Richland, WA (United States); Garner, L.W. [Nuclear Regulatory Commission, Washington, DC (United States)

    1993-08-01T23:59:59.000Z

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. H. B. Robinson was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the H. B. Robinson plant.

  11. Auxiliary feedwater system risk-based inspection guide for the McGuire nuclear power plant

    SciTech Connect (OSTI)

    Bumgardner, J.D.; Lloyd, R.C.; Moffitt, N.E.; Gore, B.F.; Vo, T.V. [Pacific Northwest Lab., Richland, WA (United States)

    1994-05-01T23:59:59.000Z

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. McGuire was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the McGuire plant.

  12. Auxiliary feedwater system risk-based inspection guide for the J. M. Farley Nuclear Power Plant

    SciTech Connect (OSTI)

    Vo, T.V.; Pugh, R.; Gore, B.F.; Harrison, D.G. (Pacific Northwest Lab., Richland, WA (USA))

    1990-10-01T23:59:59.000Z

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment(PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. J. M. Farley was selected as the second plant for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important at the J. M. Farley plant. 23 refs., 1 fig., 1 tab.

  13. Auxiliary feedwater system risk-based inspection guide for the Ginna Nuclear Power Plant

    SciTech Connect (OSTI)

    Pugh, R.; Gore, B.F.; Vo, T.V.; Moffitt, N.E. (Pacific Northwest Lab., Richland, WA (United States))

    1991-09-01T23:59:59.000Z

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Ginna was selected as the eighth plant for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Ginna plant. 23 refs., 1 fig., 1 tab.

  14. Auxiliary feedwater system risk-based inspection guide for the South Texas Project nuclear power plant

    SciTech Connect (OSTI)

    Bumgardner, J.D.; Nickolaus, J.R.; Moffitt, N.E.; Gore, B.F.; Vo, T.V. [Pacific Northwest Lab., Richland, WA (United States)

    1993-12-01T23:59:59.000Z

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. South Texas Project was selected as a plant for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by the NRC inspectors in preparation of inspection plans addressing AFW risk important components at the South Texas Project plant.

  15. LLW Notes, Volume 12, Number 8

    SciTech Connect (OSTI)

    Norris, C.; Brown, H. [eds.; Gedden, R.; Lovinger, T.; Scheele, L.; Shaker, M.A.

    1997-12-31T23:59:59.000Z

    Contents include articles entitled: Chem-Nuclear documents new plan for Barnwell; Nebraska releases technical analysis of LLRW facility; Southeast Compact suspends funding for NC facility development; NC governor and Southeast Compact differ on proposed MOU; Midwest Compact to return export fees; State legislators` group revises radioactive waste policy; Internal documents discuss administration`s policy on Ward Valley; BLM issues EA for Ward Valley testing; California DHS, NRC criticize DOI`s testing protocols; Army removes training mines from Ward Valley site; The 1997 gubernatorial elections and a look ahead to 1998; Court throws out case challenging Pennsylvania`s siting law; DOE files notice of appeal in WCS suit; Central Compact moves to dismiss ``Veto`` authority suit; Congress exempts NAS from FACA; Judge sets schedule for Ward Valley case; Court won`t order DOE to accept spent fuel by deadline; NRC chairman expresses concern re CERCLA reauthorization; Senators question EPA`s guidance on remediation; EPA issues guidance, criticizes NRC decommissioning rule; Members of Congress clarify FUSRAP transfer; HLW legislation passes House by wide margin; Takings legislation passes House; Energy and water bill signed into law; and Senate confirms 5 of 6 DOE appointees.

  16. Knowledge Management Initiatives Used to Maintain Regulatory Expertise in Transportation and Storage of Radioactive Materials - 12177

    SciTech Connect (OSTI)

    Lindsay, Haile; Garcia-Santos, Norma; Saverot, Pierre; Day, Neil; Gambone Rodriguez, Kimberly; Cruz, Luis; Sotomayor-Rivera, Alexis; Vechioli, Lucieann; Vera, John; Pstrak, David [United States Nuclear Regulatory Commission, Mail Stop EBB-03D-02M, 6003 Executive Boulevard, Rockville, MD 20852 (United States)

    2012-07-01T23:59:59.000Z

    The U.S. Nuclear Regulatory Commission (NRC) was established in 1974 with the mission to license and regulate the civilian use of nuclear materials for commercial, industrial, academic, and medical uses in order to protect public health and safety, and the environment, and promote the common defense and security. Currently, approximately half (?49%) of the workforce at the NRC has been with the Agency for less than six years. As part of the Agency's mission, the NRC has partial responsibility for the oversight of the transportation and storage of radioactive materials. The NRC has experienced a significant level of expertise leaving the Agency due to staff attrition. Factors that contribute to this attrition include retirement of the experienced nuclear workforce and mobility of staff within or outside the Agency. Several knowledge management (KM) initiatives have been implemented within the Agency, with one of them including the formation of a Division of Spent Fuel Storage and Transportation (SFST) KM team. The team, which was formed in the fall of 2008, facilitates capturing, transferring, and documenting regulatory knowledge for staff to effectively perform their safety oversight of transportation and storage of radioactive materials, regulated under Title 10 of the Code of Federal Regulations (10 CFR) Part 71 and Part 72. In terms of KM, the SFST goal is to share critical information among the staff to reduce the impact from staff's mobility and attrition. KM strategies in place to achieve this goal are: (1) development of communities of practice (CoP) (SFST Qualification Journal and the Packaging and Storing Radioactive Material) in the on-line NRC Knowledge Center (NKC); (2) implementation of a SFST seminar program where the seminars are recorded and placed in the Agency's repository, Agency-wide Documents Access and Management System (ADAMS); (3) meeting of technical discipline group programs to share knowledge within specialty areas; (4) development of written guidance to capture 'administrative and technical' knowledge (e.g., office instructions (OIs), generic communications (e.g., bulletins, generic letters, regulatory issue summary), standard review plans (SRPs), interim staff guidance (ISGs)); (5) use of mentoring strategies for experienced staff to train new staff members; (6) use of Microsoft SharePoint portals in capturing, transferring, and documenting knowledge for staff across the Division from Division management and administrative assistants to the project managers, inspectors, and technical reviewers; and (7) development and implementation of a Division KM Plan. A discussion and description of the successes and challenges of implementing these KM strategies at the NRC/SFST will be provided. (authors)

  17. ORCR Form 4.00.3 NIH RCR Guidance Page 1 of 3 Guidance for Developing a Responsible Conduct of Research Instruction Plan for National

    E-Print Network [OSTI]

    ORCR Form 4.00.3 NIH RCR Guidance Page 1 of 3 Guidance for Developing a Responsible Conduct Institutes of Health (NIH) requires that all trainees, fellows, participants and scholars receiving support through any NIH training, career development award (individual or institutional), research education grant

  18. NGNP Project Regulatory Gap Analysis for Modular HTGRs

    SciTech Connect (OSTI)

    Wayne Moe

    2011-09-01T23:59:59.000Z

    The Next Generation Nuclear Plant (NGNP) Project Regulatory Gap Analysis (RGA) for High Temperature Gas-Cooled Reactors (HTGR) was conducted to evaluate existing regulatory requirements and guidance against the design characteristics specific to a generic modular HTGR. This final report presents results and identifies regulatory gaps concerning current Nuclear Regulatory Commission (NRC) licensing requirements that apply to the modular HTGR design concept. This report contains appendices that highlight important HTGR licensing issues that were found during the RGA study. The information contained in this report will be used to further efforts in reconciling HTGR-related gaps in the NRC licensing structure, which has to date largely focused on light water reactor technology.

  19. Nuclear Regulatory Commission Information Digest, 1991 edition

    SciTech Connect (OSTI)

    Olive, K L

    1991-03-01T23:59:59.000Z

    The Nuclear Regulatory Commission Information Digest provides a summary of information about the US Nuclear Regulatory Commission (NRC), NRC's regulatory responsibilities, and the areas NRC licenses. This digest is a compilation of NRC-related data and is designed to provide a quick reference to major facts about the agency and the industry it regulates. In general, the data cover 1975 through 1990, with exceptions noted. For operating US commercial nuclear power reactors, information on generating capacity and average capacity factor is obtained from Monthly Operating Reports submitted to the NRC directly by the licensee. This information is reviewed for consistency only. No independent validation and/or verification is performed by the NRC. For detailed and complete information about tables and figures, refer to the source publications. This digest is published annually for the general use of the NRC staff and is available to the public. 30 figs., 12 tabs.

  20. Long-Term Stewardship Baseline Report and Transition Guidance

    SciTech Connect (OSTI)

    Kristofferson, Keith

    2001-11-01T23:59:59.000Z

    Long-term stewardship consists of those actions necessary to maintain and demonstrate continued protection of human health and the environment after facility cleanup is complete. As the Department of Energy’s (DOE) lead laboratory for environmental management programs, the Idaho National Engineering and Environmental Laboratory (INEEL) administers DOE’s long-term stewardship science and technology efforts. The INEEL provides DOE with technical, and scientific expertise needed to oversee its long-term environmental management obligations complexwide. Long-term stewardship is administered and overseen by the Environmental Management Office of Science and Technology. The INEEL Long-Term Stewardship Program is currently developing the management structures and plans to complete INEEL-specific, long-term stewardship obligations. This guidance document (1) assists in ensuring that the program leads transition planning for the INEEL with respect to facility and site areas and (2) describes the classes and types of criteria and data required to initiate transition for areas and sites where the facility mission has ended and cleanup is complete. Additionally, this document summarizes current information on INEEL facilities, structures, and release sites likely to enter long-term stewardship at the completion of DOE’s cleanup mission. This document is not intended to function as a discrete checklist or local procedure to determine readiness to transition. It is an overarching document meant as guidance in implementing specific transition procedures. Several documents formed the foundation upon which this guidance was developed. Principal among these documents was the Long-Term Stewardship Draft Technical Baseline; A Report to Congress on Long-Term Stewardship, Volumes I and II; Infrastructure Long-Range Plan; Comprehensive Facility Land Use Plan; INEEL End-State Plan; and INEEL Institutional Plan.

  1. Studying Wind Energy/Bird Interactions: A Guidance Document

    SciTech Connect (OSTI)

    Anderson, R. [California Energy Commission (US); Morrison, M. [California State Univ., Sacramento, CA (US); Sinclair, K. [Dept. of Energy/National Renewable Energy Lab. (US); Strickland, D. [WEST, Inc. (US)

    1999-12-01T23:59:59.000Z

    This guidance document is a product of the Avian Subcommittee of the National Wind Coordinating Committee (NWCC). The NWCC was formed to better understand and promote responsible, credible, and comparable avian/wind energy interaction studies. Bird mortality is a concern and wind power is a potential clean and green source of electricity, making study of wind energy/bird interactions essential. This document provides an overview for regulators and stakeholders concerned with wind energy/bird interactions, as well as a more technical discussion of the basic concepts and tools for studying such interactions.

  2. ICDF Complex Waste Profile and Verification Sample Guidance

    SciTech Connect (OSTI)

    W. M. Heileson

    2006-10-01T23:59:59.000Z

    This guidance document will assist waste generators who characterize waste streams destined for disposal at the Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility (ICDF) Complex. The purpose of this document is to develop a conservative but appropriate way to (1) characterize waste for entry into the ICDF; (2) ensure compliance with the waste acceptance criteria; and (3) facilitate disposal at the ICDF landfill or evaporation pond. In addition, this document will establish the waste verification process used by ICDF personnel to ensure that untreated waste meets applicable ICDF acceptance limits

  3. Technical background document for draft soil screening level guidance

    SciTech Connect (OSTI)

    Not Available

    1994-03-01T23:59:59.000Z

    The document provides technical details of the derivation of the September 30, 1993, draft Soil Screening Levels (SSLs) Guidance for Superfund (PB93-963508). The document is presented in two sections. Section I defines SSL and provides background information on the development of SSLs and their application and implementation at Superfund sites, including sampling schemes for measuring SSL attainment. It also provides draft SSLs developed for 30 chemicals. Section II provides the technical basis for the development of SSLs addressing direct ingestion of soil, inhalation of volatiles and fugitive dust, and the soil-to-ground-water exposure pathway, including the assumptions and theories used the their development.

  4. GC GUIDANCE ON BARTER TRANSACTIONS INVOLVING DOE-OWNED URANIUM

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-UpHeatMulti-Dimensional Subject: Guidance for natural gas as a feedstock for conversionGC

  5. General Counsel's Office Issues Guidance on Inherently Governmental

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-UpHeatMulti-Dimensional Subject: Guidance for natural gasDepartmentPlasma |GeishaGen

  6. Energy.gov Article Guidance | 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) " ,"ClickPipelinesProvedDecember 2005DepartmentDecember 2011District |DepartmentEnergy.gov Article Guidance

  7. Environment Policy, Guidance & Reports | 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) " ,"ClickPipelinesProvedDecember 2005DepartmentDecember 2011DistrictLLC | DepartmentPolicy, Guidance &

  8. Guidance on Reading the Scorecard | 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) " ,"ClickPipelinesProvedDecember 2005DepartmentDecemberGlossary ofGroundwater CleanupDepartment ofGuidance

  9. Privacy Impact Assessment Template and Guidance | Department of Energy

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

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

  10. BLM Geothermal Guidance Documents Website | 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 NoPublic Utilities Address: 160 EastMaine: EnergyAustin Energy Place:Guidance Documents Website Jump to: navigation,

  11. BLM Manual 8270 - General Procedural Guidance for Paleontological Resource

    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 NoPublic Utilities Address: 160 EastMaine: EnergyAustin Energy Place:Guidance Documents Website:

  12. Environmental Justice: Guidance Under NEPA | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists'Montana.Program -DepartmentNovember 1, 2010December 1, 1996Guidance from the Council

  13. State Energy Program Notice 14-2, Implementation Model Guidance |

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists' Research |RegulationRenewable EnergySouthwest4, 2010TheDepartmentGuidance for

  14. EPA Climate Leaders Mobile Source Guidance | 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 Home Page on Office of InspectorConcentrating Solar Power Basics (The followingDirectLow Carbon TransitionENERGY STAR JumpGuidance

  15. Enforcement Guidance Supplement 02-01:Enforcement Position Relative to 10 CFR 835 Bioassay Accreditation

    Broader source: Energy.gov [DOE]

    Section 1.3 of the Operational Procedures for Enforcement, published in June 1998, provides the opportunity for the Office of Price-Anderson Enforcement (OE) to periodically issue clarifying guidance regarding the processes used in its enforcement activities. OE typically issues such guidance in the form of Enforcement Guidance Supplements (EGSs), which provide information or recommendations only and impose no requirements or actions on Department of Energy (DOE) contractors.

  16. Enforcement Guidance Supplement 02-01: Enforcement Position Relative to 10 CFR 835 Bioassay Accreditation

    Broader source: Energy.gov [DOE]

    Section 1.3 of the Operational Procedures for Enforcement, published in June 1998, provides the opportunity for the Office of Price-Anderson Enforcement (OE) to periodically issue clarifying guidance regarding the processes used in its enforcement activities. OE typically issues such guidance in the form of Enforcement Guidance Supplements (EGSs), which provide information or recommendations only and impose no requirements or actions on Department of Energy (DOE) contractors.

  17. Webinar: Guidance for Filling Out a Detailed H2A Production Case Study

    Broader source: Energy.gov [DOE]

    Video recording and text version of the webinar titled, Guidance for Filling Out a Detailed H2A Production Case Study, originally presented on July 9, 2013.

  18. E-Print Network 3.0 - act environmental guidance Sample Search...

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

    Search Powered by Explorit Topic List Advanced Search Sample search results for: act environmental guidance Page: << < 1 2 3 4 5 > >> 1 Impact Assessment and Project Appraisal...

  19. Guidance on the Elements Necessary to Qualify as an Energy Conservation Measure Under an ESPC

    Broader source: Energy.gov [DOE]

    Document provides guidance on the statuatory definition of "energy conservation measure" (ECM) for the purpose of a Federal energy savings performance contract (ESPC).

  20. UAV guidance control laws for autonomous coordinated tracking of a moving ground target.

    E-Print Network [OSTI]

    Wise, Richard, 1975-

    2007-01-01T23:59:59.000Z

    ??This research develops the Unmanned Aerial Vehicles (UAV) control guidance laws for two UAVs to track a moving ground target in a constant wind while… (more)