核電標(biāo)準(zhǔn)、規(guī)范與法規(guī)清單.docx

ASTM B353-2002核設(shè)施(除核燃料包殼外)鍛制鋯與鋯合金無縫焊接管標(biāo)準(zhǔn)規(guī)范Standard Specification for Wrought Zirconium and Zirconium Alloy Seamless and Welded Tubes for Nuclear Service (Except Nuclear Fuel Cladding)ASTM B811-2002核反應(yīng)堆燃料包殼鍛制鋯合金無縫管標(biāo)準(zhǔn)規(guī)范Standard Specification for Wrought Zirconium Alloy Seamless Tubes for Nuclear Reactor Fuel CladdingANSI/ASTM C781-2002高溫氣冷核反應(yīng)堆石墨與硼酸化石墨元部件試驗(yàn)標(biāo)準(zhǔn)實(shí)施規(guī)程Standard Practice for Testing Graphite and Boronated Graphite Components for High-Temperature Gas-Cooled Nuclear ReactorsASTM C986-1989制定核燃料循環(huán)培訓(xùn)計(jì)劃Developing Training Programs in the Nuclear Fuel CycleASTM C1010-1983核燃料再加工設(shè)備的驗(yàn)收、檢測與操作前試驗(yàn)Acceptance, Checkout and Pre-Operational Testing of a Nuclear Fuels Reprocessing FacilityASTM C1011-1983核燃料生產(chǎn)用無電極電導(dǎo)儀器選擇或規(guī)范Selection or Specification of Electrodeless Conductivity Instruments for the Nuclear Fuel CycleASTM C1062-2000核燃料溶解裝置設(shè)計(jì)、制造與安裝標(biāo)準(zhǔn)指南Standard Guide for Design, Fabrication, and Installation of Nuclear Fuel Dissolution FacilitiesASTM C1128-1995核燃料循環(huán)材料分析參考材料制備標(biāo)準(zhǔn)指南Standard Guide for Preparation of Working Reference Materials for Use in the Analysis of Nuclear Fuel Cycle MaterialsASTM C1156-2003分析核燃料循環(huán)材料測定方法的精度建立標(biāo)準(zhǔn)指南Standard Guide for Establishing Calibration for a Measurement Method Used to Analyze Nuclear Fuel Cycle MaterialsASTM C1297-2003核燃料循環(huán)材料分析實(shí)驗(yàn)室分析法鑒定標(biāo)準(zhǔn)指南Standard Guide for Qualification of Laboratory Analysts for the Analysis of Nuclear Fuel Cycle MaterialsASTM C1431-1999鋁基廢核燃料腐蝕試驗(yàn)的維護(hù)容器清理標(biāo)準(zhǔn)指南Standard Guide for Corrosion Testing of Aluminum-Based Spent Nuclear Fuel in Support of Repository DisposalASTM C1454-2000對(duì)鈾金屬廢核燃料自燃分析進(jìn)行自燃/易燃性試驗(yàn)標(biāo)準(zhǔn)指南Standard Guide for Pyrophoricity/Combustibility Testing in Support of Pyrophoricity Analyses of Metallic Uranium Spent Nuclear FuelASTM D3911-2003設(shè)計(jì)基本事故(DBA)的模擬條件下評(píng)價(jià)輕水核電廠用涂層的標(biāo)準(zhǔn)試驗(yàn)方法Standard Test Method for Evaluating Coatings Used in Light-Water Nuclear Power Plants at Simulated Design Basis Accident (DBA) ConditionsASTM D3912-1995輕水核電廠涂層耐化學(xué)性標(biāo)準(zhǔn)試驗(yàn)方法Standard Test Method for Chemical Resistance of Coatings Used in Light-Water Nuclear Power PlantsASTM D4082-1995測定射線對(duì)輕水核電廠涂層所產(chǎn)生影響的標(biāo)準(zhǔn)試驗(yàn)方法Standard Test Method for Effects of Gamma Radiation on Coatings for Use in Light-Water Nuclear Power PlantsASTM D5139-1990核電廠涂層定量檢查樣本制備標(biāo)準(zhǔn)規(guī)范Standard Specification for Sample Preparation for Qualification Testing of Coatings to be Used in Nuclear Power PlantsASTM D5163a-2005核電廠運(yùn)行用I級(jí)涂層性能監(jiān)測程序制定標(biāo)準(zhǔn)指南Standard Guide for Establishing Procedures to Monitor the Performance of Service Level I Coatings in an Operating Nuclear Power PlantASTM D5962-1996核反應(yīng)堆 I級(jí)區(qū)域內(nèi)不合格涂層（油漆）維護(hù)標(biāo)準(zhǔn)指南Standard Guide for Maintaining Unqualified Coatings (Paints) Within Level I Areas of a Nuclear Power FacilityASTM D7167-2005確定核電廠安全相關(guān)覆層設(shè)備III級(jí)里襯系統(tǒng)運(yùn)行性能監(jiān)測程序標(biāo)準(zhǔn)指南Standard Guide for Establishing Procedures to Monitor the Performance of Safety-Related Coating Service Level III Lining Systems in an Operating Nuclear Power PlantASTM E185-2002輕水冷卻核反應(yīng)堆容器的監(jiān)督程序設(shè)計(jì)的標(biāo)準(zhǔn)操作規(guī)程Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor VesselsASTM E509-2003輕水冷卻核反應(yīng)堆容器運(yùn)轉(zhuǎn)冷卻過程標(biāo)準(zhǔn)指南Standard Guide for In-Service Annealing of Light-Water Cooled Nuclear Reactor VesselsASTM E692-2000高分辨率射線光譜分析法照射核燃料中銫137的標(biāo)準(zhǔn)試驗(yàn)方法Standard Test Method for Determining the Content of Cesium-137 in Irradiated Nuclear Fuels by High-Resolution Gamma-Ray Spectral AnalysisASTM E1035-2002核反應(yīng)堆容器支承結(jié)構(gòu)中子輻照量測定標(biāo)準(zhǔn)實(shí)施規(guī)程Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support StructuresASTM E2215-2002輕水核電反應(yīng)堆監(jiān)視艙評(píng)估標(biāo)準(zhǔn)實(shí)施規(guī)程Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor VesselsHD 475 S1-1986核電儀器圓板尺寸標(biāo)準(zhǔn)Dimensions of Planchets used in Nuclear Electronic InstrumentsHD 370 S2-1987NIM標(biāo)準(zhǔn)(電子核儀器用)模塊插座裝置與標(biāo)準(zhǔn)19英寸架式安裝裝置Modular Plug-in Unit and Standard 19-inch Rack Mounting Unit Based on NIM Standard (for Electronic Nuclear Instruments)HD 462 S1-1987正常操作與事故條件下輕水核反應(yīng)堆液流處理監(jiān)控設(shè)備Process Stream Radiation Monitoring Equipment in Light Water Nuclear Reactors for Normal Operating and Incident ConditionsANSI/IEEE 7-4.3.2-2003核電廠安全系統(tǒng)數(shù)字計(jì)算機(jī)標(biāo)準(zhǔn)Criteria for Digital Computers in Safety Systems of Nuclear Power Generating StationsANSI/IEEE 308-2001核電廠1E級(jí)電力系統(tǒng)標(biāo)準(zhǔn)Power Systems for Nuclear Power Generating Stations, Criteria for Class 1EANSI/IEEE 317-1983核電廠安全殼結(jié)構(gòu)電氣貫穿組件Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating StationsANSI/IEEE 323-2003核電廠1E級(jí)設(shè)備質(zhì)量鑒定Qualifying Class 1E Equipment for Nuclear Power Generating StationsANSI/IEEE 334-1999核電廠1E級(jí)電動(dòng)機(jī)連續(xù)負(fù)載質(zhì)量鑒定Qualifying Continuous Duty Class 1E Motors for Nuclear Power Generating StationsANSI/IEEE 344-2004核電廠1E級(jí)設(shè)備防震鑒定推薦實(shí)施規(guī)范Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating StationsANSI/IEEE 338-1987核電廠安全系統(tǒng)周期監(jiān)督檢測準(zhǔn)則Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety SystemsANSI/IEEE 352-1994核電廠安全系統(tǒng)可靠性分析主要原則指南Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety SystemsANSI/IEEE 379-2000核電廠安全系統(tǒng)中單一故障標(biāo)準(zhǔn)應(yīng)用Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety SystemsANSI/IEEE 382-1996核電廠用帶安全相關(guān)功能的電力操作閥組件的執(zhí)行機(jī)構(gòu)的合格鑒定Actuators for Power-Operated Valve Assemblies with Safety-Related Functions for Nuclear Power-Plants, Qualification ofANSI/IEEE 383-2003核電廠1E級(jí)電纜質(zhì)量鑒定與現(xiàn)場拼接標(biāo)準(zhǔn)Standard for Qualifying Class 1E Electric Cables and Field Splices for Nuclear Power Generating StationsANSI/IEEE 387-1995核電廠備用柴油發(fā)電機(jī)電源標(biāo)準(zhǔn)準(zhǔn)則Standard Criteria for Diesel-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating StationsANSI/IEEE 420-2001核電廠用1E級(jí)控制臺(tái)、控制板及操縱板的設(shè)計(jì)和合格鑒定標(biāo)準(zhǔn)Standard for the Design and Qualification of Class 1E Control Boards, Panels and Racks Used in Nuclear Power Generating StationsANSI/IEEE 497-2002核電廠用事故監(jiān)測儀標(biāo)準(zhǔn)判據(jù)Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating StationsANSI/IEEE 572-2004核電廠1E級(jí)連接組件的質(zhì)量鑒定標(biāo)準(zhǔn)Standard for Qualification of Class 1E Connection Assemblies for Nuclear Power Generating StationsANSI/IEEE 577-2004核電廠安全系統(tǒng)的設(shè)計(jì)及運(yùn)行中的可靠性分析要求Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations, Requirements forANSI/IEEE 628-2001核電廠1E級(jí)電路電纜管道系統(tǒng)的設(shè)計(jì)、安裝和合格鑒定的標(biāo)準(zhǔn)Raceway Systems for Class 1E Circuits for Nuclear Power Generating Stations, Criteria for the Design, Installation, and Qualification ofANSI/IEEE 638-1992核電廠用IE級(jí)變壓器的合格鑒定Standard for Qualification of Class 1E Transformers for Nuclear Power Generating StationsANSI/IEEE 649-1992核電廠用合格的1E級(jí)電動(dòng)機(jī)控制臺(tái)Qualifying Class 1E Motor Control Centers for Nuclear Power Generating StationsANSI/IEEE 650-1991核電廠用1E級(jí)靜態(tài)電池充電器與轉(zhuǎn)換器的鑒定Qualifications of Class 1E Static Battery Chargers and Inverters for Nuclear Power Generating StationsANSI/IEEE 690-2004核電廠1E級(jí)電路用電纜系統(tǒng)的設(shè)計(jì)和安裝Design and Installation of Cable Systems for Class 1E Circuits in Nuclear Power Generating StationsANSI/IEEE 741-2002核電廠1E 類電力系統(tǒng)和設(shè)備防護(hù)的標(biāo)準(zhǔn)判據(jù)Standard Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating StationsANSI/IEEE 765-2002核電廠優(yōu)先選用電源Preferred Power Supply for Nuclear Power Generating StationsANSI/IEEE 845-1999核電廠、控制室和其他周邊區(qū)域人-機(jī)系統(tǒng)性能評(píng)價(jià)指南Guide to Evaluation of Man-Machine Performance in Nuclear Power Generating Stations, Control Rooms, and Other PeripheriesANSI/IEEE 933-1999核電廠可靠性工作計(jì)劃定義指南Guide for the Definition of Reliability Program Plans for Nuclear Power Generating StationsANSI/IEEE 1023-2004核電廠與其他核設(shè)施的系統(tǒng)、設(shè)備和裝置的人體工程力學(xué)應(yīng)用推薦實(shí)施規(guī)程Recommended Practice for the Application of Human Factors Engineering to Systems, Equipment, and Facilities of Nuclear Power Generating Stations and Other Nuclear FacilitiesANSI/IEEE 1082-1997核電廠人類行為可靠性分析指南Guide for Incorporating Human Action Reliability Analysis for Nuclear Power Generating StationsANSI/IEEE 1205-2000核電廠1E級(jí)設(shè)備老化影響的判定、監(jiān)測與減輕處理Assessing, Monitoring, and Mitigating Aging Effects on Class 1E Equipment Used in Nuclear Power Generating StationsANSI/IEEE 1289-2004核電廠計(jì)算機(jī)監(jiān)測與控制顯示設(shè)備的人體工程力學(xué)設(shè)計(jì)應(yīng)用指南Guide for the Application of Human Factors Engineering in the Design of Computer-Based Monitoring and Control Displays for Nuclear Power Generating StationsANSI/IEEE 1290-1996核電廠電動(dòng)控制閥門電機(jī)應(yīng)用、保護(hù)、控制與試驗(yàn)指南Guide for MOV (Motor-Operated Valve) Motor Application, Protection, Control, and Testing in Nuclear Power Generating StationsANSI/IEEE C37.82-1987核電廠1E級(jí)裝置用開關(guān)裝置組件鑒定Switchgear Assemblies for Class 1E Applications in Nuclear Power Generating Stations, Qualification ofANSI/IEEE C37.105-1987核電廠1E防護(hù)繼電器與附件鑒定標(biāo)準(zhǔn)Qualifying Class 1E Protective Relays and Auxiliaries for Nuclear Power Generating StationsASME BPVC Section 3 Division 3ASME鍋爐與壓力容器規(guī)程第3章：核設(shè)施元部件制造規(guī)則 第3部分：消耗核燃料和高等級(jí)放射性廢物用外殼系統(tǒng)和運(yùn)輸包裝ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components; Division 3; Containment Systems and Transport Packaging for Spent Nuclear Fuel and High Level RadASME BPVC Section 11-2001ASME鍋爐與壓力容器規(guī)程第11章：核電廠部件在役監(jiān)察規(guī)則ASME Boiler & Pressure Vessel Code - Section 11: Rules for Inservice Inspection of Nuclear Power Plant ComponentsANSI/ASME OM-1990核電廠運(yùn)行與維護(hù)Operation and Maintenance of Nuclear Power PlantsASME OM CODE-1998核電廠運(yùn)行與維護(hù)規(guī)程Code for Operation and Maintenance of Nuclear Power PlantsANSI/ASME OM Code-2004核電廠運(yùn)行與維護(hù)規(guī)程Code for Operation and Maintenance of Nuclear Power PlantsASME OM Interpretations 1990-1說明：核電廠運(yùn)行與維護(hù)規(guī)程Interpretations: Code for Operation and Maintenance of Nuclear Power PlantsASME OM Interpretations 1990-8說明：核電廠運(yùn)行與維護(hù)規(guī)程Interpretations: Code for Operation and Maintenance of Nuclear Power PlantsASME OM Interpretations 1990-12說明：核電廠運(yùn)行與維護(hù)規(guī)程Interpretations: Code for Operation and Maintenance of Nuclear Power PlantsANSI/ASME OM-S/G-2003核電廠運(yùn)行、維護(hù)標(biāo)準(zhǔn)與指南Standards and Guides for Operation and Maintenance of Nuclear Power PlantsANSI/ASME OM-S/Ga-2004核電廠運(yùn)行、維護(hù)標(biāo)準(zhǔn)與指南Standards and Guides for Operation and Maintenance of Nuclear Power PlantsASME OMa-S/G Addenda-2001核電廠運(yùn)行、維護(hù)標(biāo)準(zhǔn)與指南：附錄Standards and Guides for Operation and Maintenance of Nuclear Power Plants; AddendaANSI/ASME OMa Code-2005核電廠運(yùn)行與維護(hù)規(guī)程Code for Operation and Maintenance of Nuclear Power PlantsASME OMa CODE Addenda-1999核電廠運(yùn)行與維護(hù)規(guī)程：附錄Code for Operation and Maintenance of Nuclear Power Plants; AddendaANSI/ASME OMb-S/G-2005核電廠運(yùn)行、維護(hù)標(biāo)準(zhǔn)與指南Standards and Guides for Operation and Maintenance of Nuclear Power PlantsASME OMb-S/G Addenda-2002 核電廠運(yùn)行和維護(hù)Operation and Maintenance of Nuclear Power PlantsASME OMb CODE Addenda-2000核電廠的運(yùn)行和維護(hù)規(guī)程：附錄Code for Operation and Maintenance of Nuclear Power Plants; AddendaASME PTC 32.2 Report-1978輕水反應(yīng)堆核燃料性能測試方法Methods of Measuring the Performance of Nuclear Reactor Fuel in Light Water ReactorsANSI/ASME QME-1-2002核電廠放射性機(jī)械設(shè)備鑒定Qualification of Active Mechanical Equipment for Nuclear Power PlantsASME QME-1a Addenda-1998核電廠放射性機(jī)械設(shè)備鑒定：附錄Qualification of Active Mechanical Equipment for Nuclear Power Plants; AddendaASME N45.2.1-1980核電廠流體系統(tǒng)和相關(guān)元件的凈化處理Cleaning of Fluid Systems and Associated Components for Nuclear Power PlantsASME N45.2.2-1978核電廠零部件包裝、運(yùn)輸、接收、儲(chǔ)存與處理Packaging, Shipping, Receiving, Storage, and Handling of Items for Nuclear Power PlantsASME N45.2.3-1973核電廠建設(shè)階段現(xiàn)場清理工作Housekeeping during the Construction Phase of Nuclear Power PlantsASME N45.2.3a Addenda-1978核電廠建設(shè)階段現(xiàn)場清理工作：附錄Housekeeping during the Construction Phase of Nuclear Power Plants; AddendaASME N45.2.5-1978核電廠建設(shè)階段安裝、檢驗(yàn)并檢測結(jié)構(gòu)混凝土、結(jié)構(gòu)鋼、土質(zhì)與地基附加質(zhì)保規(guī)定Supplementary Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations during the Construction Phase of Nuclear Power PlantsASME N45.2.6-1978核電廠監(jiān)察、驗(yàn)收與檢測人員資質(zhì)鑒定Qualifications of Inspection, Examination, and Testing Personnel for Nuclear Power PlantsASME N45.2.8-1975核電廠建設(shè)階段機(jī)械設(shè)備與系統(tǒng)的安裝、檢驗(yàn)與檢測附加質(zhì)保規(guī)定Supplementary Quality Assurance Requirements for Installation, Inspection and Testing of Mechanical Equipment and Systems for the Construction Phase of Nuclear Power PlantsASME N45.2.8a Addenda-1981核電廠建設(shè)階段機(jī)械設(shè)備與系統(tǒng)的安裝、檢驗(yàn)與檢測附加質(zhì)保規(guī)定：附錄Supplementary Quality Assurance Requirements for Installation, Inspection and Testing of Mechanical Equipment and Systems for the Construction Phase of Nuclear Power Plants; AddendaASME N45.2.9-1979核電廠質(zhì)保記錄的收集、存放與維護(hù)規(guī)定Requirements for Collection, Storage, and Maintenance of Quality Assurance Records for Nuclear Power PlantsASME N45.2.11-1974核電廠設(shè)計(jì)質(zhì)保規(guī)定Quality Assurance Requirements for the Design of Nuclear Power PlantsASME N45.2.12-1977核電廠質(zhì)保程序評(píng)審規(guī)定Requirements for Auditing of Quality Assurance Programs for Nuclear Power PlantsASME N45.2.13-1976核電廠零部件、勞務(wù)采購管理質(zhì)保規(guī)定Quality assurance requirements for control of procurement of items and services for nuclear Power PlantsASME N45.2.15-1981核電廠部件升降、安裝與運(yùn)輸Hoisting, Rigging, and Transporting of Items for Nuclear Power PlantsASME N45.2.20-1979核電廠地表下監(jiān)察工作附加質(zhì)保規(guī)定Supplementary Quality Assurance Requirements for Subsurface Investigations for Nuclear Power PlantsASME N45.2.23-1978核電廠質(zhì)保計(jì)劃監(jiān)察人員資質(zhì)鑒定Qualification of Quality Assurance Program Audit Personnel for Nuclear Power PlantsANSI/ASME N509-2002核電廠空氣凈化設(shè)備與部件Nuclear Power Plant Air Cleaning Units and ComponentsASME RA-S-2002核電廠設(shè)施風(fēng)險(xiǎn)概率評(píng)估Probalistic Risk Assessment for Nuclear Power Plant ApplicationsANSI/ANS 2.10-2003核電廠抗震儀器記錄數(shù)據(jù)的處理與初始評(píng)價(jià)標(biāo)準(zhǔn)Criteria for the Handling and Initial Evaluation of Records from Nuclear Power Plant Seismic InstrumentationANSI/ANS 2.23-2002核電廠