Bøger af U S Nuclear Regulatory Commission
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253,95 kr. The staff of the U.S. Nuclear Regulatory Commission (NRC) has prepared this Supplement to the Draft Environmental Impact Statement (EIS) for an Early Site Permit (ESP) at the North Anna ESP Site (SDEIS) because Dominion Nuclear North Anna, LLC (Dominion or applicant) amended its ESP application, as described in Revision 6 to its application for an ESP. In Revision 6 (which was submitted to the NRC on April 13, 2006), Dominion described a new approach for cooling its proposed Unit 3. Under the revised approach, Unit 3 would use a closed-cycle cooling system, rather than the originally proposed once-through cooling system. The newly-proposed system would not use the 1376-ha (3400-ac) waste heat treatment facility for cooling. Dominion also proposed to increase the power level of both proposed Units 3 and 4 from 4300 megawatts-thermal (MW(t)) to 4500 MW(t).
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- 253,95 kr.
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- Final Report: Volume 2
263,95 kr. This environmental impact statement (EIS) has been prepared in response to an application submitted to the U.S. Nuclear Regulatory Commission (NRC) by Exelon Generation Company, LLC (Exelon) for an early site permit (ESP). The proposed action requested in Exelon's application is for the NRC to (1) approve a site within the existing Clinton Power Station (CPS) boundaries as suitable for the construction and operation of a new nuclear power generating facility and (2) issue an ESP for the proposed site identified as the Exelon ESP site located adjacent to the CPS. In its application, Exelon proposes a plan for redressing the environmental effects of certain site-preparation and construction activities, i.e., those activities allowed by Title 10 of the Code of Federal Regulations (CFR) 50.10(e)(1), performed by an ESP holder under 10 CFR 52.25. In accordance with the plan, the site would be redressed if the NRC issues the requested ESP (containing the site redress plan), the ESP holder performs these site-preparation and construction activities, the ESP is not referenced in an application for a construction permit or combined operating license, and no alternative use is found for the site. This EIS includes the NRC staff's analysis that considers and weighs the environmental impacts of constructing and operating a new nuclear unit at the Exelon ESP site or at alternative sites, and mitigation measures available for reducing or avoiding adverse impacts. It also includes the staff's recommendation to the Commission regarding the proposed action.
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- 263,95 kr.
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- Final Report
288,95 kr. This environmental impact statement (EIS) has been prepared in response to an application submitted to the U.S. Nuclear Regulatory Commission (NRC) by Exelon Generation Company, LLC (Exelon) for an early site permit (ESP). The proposed action requested in Exelon's application is for the NRC to (1) approve a site within the existing Clinton Power Station (CPS) boundaries as suitable for the construction and operation of a new nuclear power generating facility and (2) issue an ESP for the proposed site identified as the Exelon ESP site located adjacent to the CPS. In its application, Exelon proposes a plan for redressing the environmental effects of certain site-preparation and construction activities, i.e., those activities allowed by Title 10 of the Code of Federal Regulations (CFR) 50.10(e)(1), performed by an ESP holder under 10 CFR 52.25. In accordance with the plan, the site would be redressed if the NRC issues the requested ESP (containing the site redress plan), the ESP holder performs these site-preparation and construction activities, the ESP is not referenced in an application for a construction permit or combined operating license, and no alternative use is found for the site. This EIS includes the NRC staff's analysis that considers and weighs the environmental impacts of constructing and operating a new nuclear unit at the Exelon ESP site or at alternative sites, and mitigation measures available for reducing or avoiding adverse impacts. It also includes the staff's recommendation to the Commission regarding the proposed action.
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- 288,95 kr.
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288,95 kr. The United States of America ratified the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (Joint Convention) in April 2003. The Joint Convention establishes an international peer review process among Contracting Parties and provides incentives for nations to take appropriate steps to bring their nuclear activities into compliance with general safety standards and practices. The U.S. participated in Review Meetings of the Contracting Parties to the Joint Convention in November 2003, May, 2006, and May 2009, in Vienna, Austria. This Fourth Report, an update of the U.S. National Report prepared under the Joint Convention in September 2011, documents spent fuel and radioactive waste management safety in the U.S. under the terms of the Joint Convention. It was prepared by the U. S. Government for review by the Contracting Parties.
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- 288,95 kr.
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- Main Report
218,95 kr. The NRC is establishing a risk-informed revision of the design-basis pipe break size requirements in 10 CFR 50.46, Appendix K to Part 50, and GDC 35 which requires estimates of LOCA frequencies as a function of break size.
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- 218,95 kr.
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208,95 kr. The NRC contracted with LLNL to compile the supplement to NUREG-1609 to incorporate additional information specific to tritium-producing burnable absorber rods.
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- 208,95 kr.
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208,95 kr. The U.S. Nuclear Regulatory Commission Performance and Accountability Report is an account of the agency's effectiveness and efficiency in achieving its mission.
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- 208,95 kr.
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218,95 kr. Cracking in pressurized water reactor (PWR) bottom mounted instrumentation (BMI) fabricated from Alloy 600 base material was first identified at the South Texas Project, (STP) Unit 1 plant in the United States (US). Based on the failure analysis of the BMI, the licensee concluded that the cracking was due to primary water stress corrosion cracking (PWSCC). PWSCC has been identified as the primary degradation mechanism affecting PWR high nickel alloy nozzles and welds (e.g., Alloy 600 tubing, piping, or forging material, and Alloy 82/182 weld material) in the reactor coolant system. To address these concerns, the Nuclear Regulatory Commission (NRC) issued NRC Bulletin 2003-02, "Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity," on August 21, 2003, to all holders of operating licenses for PWRs. The purpose of the bulletin was to request information from the industry related to the structural integrity of the reactor pressure vessel BMI nozzles at PWR facilities. This report summarizes the NRC staff's review of licensee responses to the Bulletin, licensee's BMI inspection results, industry activities related to BMI inspections, and the staff's conclusions regarding the need for additional regulatory action in this area. A brief summary regarding the inspection results of the BMI penetrations and the associated aging monitoring programs for the foreign reactors is included in this report.
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- 218,95 kr.
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- Effects of Fire Protection System Actuation on Safety-Related Equipment
208,95 kr. Actuation of Fire Protection Systems (FPS) in Nuclear Power Plants have resulted in adverse interactions with equipment important to safety. Precursor operational experience has shown that 37% of all FPS actuations damaged some equipment, and 20% of all FPS actuations have resulted in a plant transient and reactor trip. On an average, 0.17 FPS actuations per reactor year have been experienced in nuclear power plants in this country. This report presents the regulatory analysis for GI-57, "Effects of Fire Protection System Actuation on Safety-Related Equipment". The risk reduction estimates, cost/benefit analyses, and other insights gained during this effort have shown that implementation of the recommendations contained in this report can significantly reduce risk, and that these improvements can be warranted in accordance with the backfit rule, 10 CFR 50.109(a)(3). However, plant specific analyses are required in order to identify such improvements. Generic analyses can not serve to identify improvements that could be warranted for individual, specific plants. Plant specific analyses of the type needed for this purpose are underway as part of the Individual Plant Examination of External Events (IPEEE) program.
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- 208,95 kr.
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218,95 kr. NUREG-1801, "Generic Aging Lessons Learned (GALL) Report," is referenced as a technical basis document in NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants" (SRP-LR). The GALL Report identifies aging management programs (AMP), which were determined to be acceptable programs to manage the aging effects of systems, structures and components (SSC) in the scope of license renewal, as required by 10 CFR Part 54, "Requirements for Renewal of Operating Licenses for Nuclear Power Plants."
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- 218,95 kr.
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- Appendices A through L
253,95 kr. The purpose of this NUREG is to establish the feasibility of developing a risk-informed and performance-based regulatory structure for the licensing of future nuclear power plants (NPPs). As such, this NUREG documents a "Framework" that provides an approach, scope and criteria that could be used to develop a set of requirements that would serve as an alternative to 10 CFR 50 for licensing future NPPs; however, this Framework is not the entire process. It is an initial phase in is to demonstrate the feasibility of such a concept, recognizing that for full implementation there will be outstanding programmatic, policy, and technical issues to be resolved. As such, this feasibility study does not represent a staff position, but rather a significant piece of research. The second phase, which involves implementation, is comprised of several, iterative steps: resolution of issues, development of draft requirements and regulations, pilots and tests, and rulemaking.
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- 253,95 kr.
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- Main Report
218,95 kr. The purpose of this NUREG is to establish the feasibility of developing a risk-informed and performance-based regulatory structure for the licensing of future nuclear power plants (NPPs). As such, this NUREG documents a "Framework" that provides an approach, scope and criteria that could be used to develop a set of requirements that would serve as an alternative to 10 CFR 50 for licensing future NPPs; however, this Framework is not the entire process. It is an initial phase in is to demonstrate the feasibility of such a concept, recognizing that for full implementation there will be outstanding programmatic, policy, and technical issues to be resolved. As such, this feasibility study does not represent a staff position, but rather a significant piece of research. The second phase, which involves implementation, is comprised of several, iterative steps: resolution of issues, development of draft requirements and regulations, pilots and tests, and rulemaking.
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- 218,95 kr.
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218,95 kr. The NRC Performance and Accountability Report presents the agency's program performance and financial management information during Fiscal Year 2006.
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- 218,95 kr.
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208,95 kr. This report summarizing the lessons learned from the nine pilot site visits that were performed to review early implementation of the maintenance rule using the draft NRC Maintenance Inspection Procedure.
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- 208,95 kr.
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208,95 kr. Based on a Policy Statement on Severe Accidents, the licensee of each nuclear power plant is requested to perform an individual plant examination. The plant examination systematically looks for vulnerabilities to severe accidents and cost-effective safety improvements that reduce or eliminate the important vulnerabilities. This document presents guidance for performing and reporting the results of the individual plant examination of external events (IPEEE). The guidance for reporting the results of the individual plant examination of internal events (IPE) is presented in NUREG-1335.
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- 208,95 kr.
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218,95 kr. Computational fluid dynamics (CFD) is used to predict steam generator inlet plenum mixing during a particular phase of a severe accident in a pressurized-water reactor. Boundary conditions are obtained from SCDAP/RELAP5 predictions of a TMLB' station blackout. Full- scale CFD predictions are completed for the scaled-up geometry of a 1/7th scale test facility to isolate the scaleup effect. These predictions are repeated with a Westinghouse model 44 steam generator design. The effect of tube leakage on the mixing is also considered. Finally, predictions are completed for a steam generator from a Combustion Engineering (CE) nuclear power plant. Scaleup predictions indicate that data at 1/7th scale are indicative of the full-scale behavior for similar geometries. Predictions for a model 44 steam generator design indicate slightly less mixing and increased plume oscillations and indicate that the geometry is an important parameter. Tube leakage does not show a significant impact on the mixing for leakage rates below 1.4 kg/s at these severe accident conditions. A CE steam generator design results in significantly less inlet plenum mixing. The highest tube entrance temperatures approach the hot leg temperatures in this case. Heat transfer rates to the secondary side are determined to be a dominant governing parameter.
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- 218,95 kr.
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- Final Report
218,95 kr. This report provides criteria and associated technical bases for evaluating the feasibility and reliability of postfire operator manual actions implemented in nuclear power plants. The U.S. Nuclear Regulatory Commission (NRC) developed this report as a reference guide for agency staff who evaluate the acceptability of manual actions, submitted by licensees as exemption requests from the requirements of Paragraph III.G.2 of Appendix R, "Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979," to Title10, Part 50, "Domestic Licensing of Production and Utilization Facilities," of the Code of Federal Regulations (10 CFR Part 50), as a means of achieving and maintaining hot shutdown conditions during and after fire events. The staff may use this information in the review of future postfire operator manual actions to determine if the feasibility and reliability of the operator manual action were adequately evaluated.
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- 218,95 kr.
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- Fiscal Year 2006
208,95 kr. The Performance and Accountability Report provides performance results and audited financial statements that enable Congress, the President, and the public to assess the performance of the agency in achieving its mission and stewardship of its resources. The report contains a concise overview, management's discussion and analysis, as well as performance and financial sections. Additional details of performance results and program evaluations can be found in the appendices.
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- 208,95 kr.
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208,95 kr. Dominion Nuclear North Anna, LLC submitted its application for an early site permit (ESP) for the North Anna site on September 25, 2003. Then, on April 13, 2006, Dominion submitted Revision 6 of the application to propose a change tothe cooling system for postulated Unit 3, and an increase in the power level for both postulated Units 3 and 4.
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- 208,95 kr.
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- Submittal Guidance
208,95 kr. Based on a Policy Statement on Severe Accidents Regarding Future Designs and Existing Plants, the performance of a plant examination is requested from the licensee of each nuclear power plant. The plant examination looks for vulnerabilities to severe accidents and cost-effective safety improvements that reduce or eliminate the important vulnerabilities. This document delineates the guidance for reporting the results of that plant examination.
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- 208,95 kr.
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208,95 kr. The U.S. Nuclear Regulatory Commission (NRC) Performance and Accountability Report presents the agency's program performance and financial manage- ment information for fiscal year (FY) 2010. The annual report provides the public with an opportunity to as- sess how effectively the NRC uses its funds to achieve results. When preparing this report, the NRC staff fol- lowed the requirements of the Chief Financial Officers Act, as amended by the Reports Consolidation Act of 1990, Government Management Reform Act of 1994, and Government Performance Results Act of 1993. This Performance and Accountability Report covers activities from October 1, 2009, to September 30, 2010.
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- 208,95 kr.
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218,95 kr. The safety evaluation report documents the technical review of the Nine Mile Point Nuclear Station Unit 1 and 2, license renewal application by the staff of the U.S. Nuclear Regulatory Commission.
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- 218,95 kr.
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228,95 kr. This document provides guidance for the review and approval of applications for packages used to transport radioactive material (other than spent fuel) under Title 10, Code of Federal Regulations, Chapter I, Part 71.
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- 228,95 kr.
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208,95 kr. With the increase in the number of power reactors submitting applications for renewed licenses, the U.S. Nuclear Regulatory Commission (NRC) staff realized that members of the public near different power reactor sites had similar questions related to the license renewal process and the risks associated with renewing the licenses. This report, through a question-and-answer format, provides staff responses to frequently asked questions on the license renewal process for commercial, nuclear power reactors. The questions were taken from a variety of sources over the past several years, including written inquiries to the NRC and questions asked at public meetings and during informal discussions with the NRC staff. In responding to the questions, the NRC staff attempted to provide the answers in a clear and non-technical form.
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- 208,95 kr.
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218,95 kr. This report documents an assessment of Generic Issue 43, "Contamination of Instrument Air Lines," and Generic Letter 88-14, "Instrument Air Supply System Problems Affecting Safety-Related Equipment." This assessment is part of an ongoing initiative through which the U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Regulatory Research, is reviewing selected agency regulations and decisions to determine whether they are achieving the desired results. For this assessment, the staff compared expectations with outcomes. Whenever outcomes fell short of expectations, the staff attempted to identify ways to enhance the effectiveness, efficiency, and realism of the NRC's regulatory process.
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- 218,95 kr.
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218,95 kr. This compilation contains 30 reports issued by the Advisory Committee on Nuclear Waste (ACNW) during the sixteenth and seventeenth years of its operation. The reports were submitted to the Chairman and the Executive Director for Operations of the U. S. Nuclear Regulatory Commission (NRC). Reports prepared by the Committee have been made available to the public through the NRC Public Document Room, the U. S. Library of Congress, and the Internet at http: //www.nrc.gov/reading-rm/doc-collections/
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- 218,95 kr.
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- Final Report
218,95 kr. The Standard Review Plan (SRP) for Transportation Packages for Spent Nuclear Fuel provides guidance for the review and approval of applications for packages used to transport spent nuclear fuel under 10 CFR Part 71.
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- 218,95 kr.
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- Final Report
208,95 kr. This environmental impact statement (EIS) was prepared in response to an application submitted to the U.S. Nuclear Regulatory Commission (NRC) by the National Institute of Standards and Technology (NIST) to renew the operating license for the National Bureau of Standards Reactor (NBSR) for a period of an additional 20 years. This is the second operating license renewal application for the NBSR. The first license renewal was granted May 16, 1984, and included a power uprate from 10 megawatts of thermal power (MWt) to 20 MWt. This EIS includes the NRC staff's analysis that considers and weighs the environmental impacts of the proposed action, as well as mitigation measures available for reducing or avoiding adverse impacts. It also includes the staff's recommendation regarding the proposed action.
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- 208,95 kr.
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208,95 kr. The research and test reactor operator licensing (RTROL) examiner standards establish the procedures and practices for administering initial and requalification written examinations and operating tests to license applicants and operators pursuant to Title 10, Part 55, "Operators Licenses," of the Code of Federal Regulations (10 CFR Part 55).
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- 208,95 kr.
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208,95 kr. This safety evaluation report documents the technical review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, license renewal application by the U.S. Nuclear Regulatory Commission staff.
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- 208,95 kr.