【正文】 如：AISI、ANSI、API、ASME、IEC、ISO等。1989.104.EPRI Report TR100082, “Standardization of the Cumulative Absolute Velocity,” December核電站監(jiān)造應(yīng)遵循的法規(guī)、導(dǎo)則和標(biāo)準(zhǔn)國(guó)內(nèi)( 1 ) 核安全法規(guī)HAF 0011986中華人民共和國(guó)民用核設(shè)施安全監(jiān)督管理?xiàng)l例HAF 001/01/01 中華人民共和國(guó)民用核設(shè)施安全監(jiān)督管理例實(shí)施細(xì)則之一附件一 核電廠操縱人員執(zhí)照頒發(fā)和管理程序HAF 001/021995中華人民共和國(guó)民用核設(shè)施安全監(jiān)督管理?xiàng)l例實(shí)施細(xì)則之二 核設(shè)施的安全監(jiān)督HAF001/02/011995中華人民共和國(guó)民用核設(shè)施安全監(jiān)督管理?xiàng)l例實(shí)施細(xì)則之二附件一 核電廠營(yíng)運(yùn)單位報(bào)告制度HAF 0021993核電廠核事故應(yīng)急管理?xiàng)l例HAF 002/011998核電廠核事故應(yīng)急管理?xiàng)l例實(shí)施細(xì)則之一 核電廠營(yíng)運(yùn)單位的應(yīng)急準(zhǔn)備和應(yīng)急響應(yīng)HAF 4011997放射性廢物安全監(jiān)督管理規(guī)定HAF 5011987中華人民共和國(guó)核材料管制條例HAF 501/011990中華人民共和國(guó)核材料管制條例實(shí)施細(xì)則HAF 6011992民用核承壓設(shè)備安全監(jiān)督管理規(guī)定HAF 601/011993民用核承壓設(shè)備安全監(jiān)督管理規(guī)定實(shí)施細(xì)則HAF 6021995民用核承壓設(shè)備無(wú)損檢驗(yàn)人員培訓(xùn)、考核和取證管理辦法HAF 6031995民用核承壓設(shè)備焊工及焊接操作工培訓(xùn)、考核和取證管理辦法( 2 ) 核電廠核安全法規(guī)HAF 1011991核電廠廠址選擇安全規(guī)定HAF 1022004核動(dòng)力廠設(shè)計(jì)安全規(guī)定HAF 1032004核動(dòng)力廠運(yùn)行安全規(guī)定HAF 103/011994核電廠運(yùn)行安全規(guī)定附件一 核電廠換料、修改和事故停堆管理HAF 0031991核電廠質(zhì)量保證安全規(guī)定（3）核電廠核安全導(dǎo)則HAD 101/011994核電廠廠址選擇中的地震問題HAD 101/021987核電廠廠址選擇的大氣彌散問題HAD 101/031987核電廠廠址選擇及評(píng)價(jià)的人口分布問題HAD 101/041989核電廠廠址選擇的外部人為事件HAD 101/051991核電廠廠址選擇中的放射性物質(zhì)水力彌散問題HAD 101/061991核電廠廠址選擇與水文地質(zhì)的關(guān)系HAD 101/071989核電廠廠址查勘HAD 101/081989濱河核電廠廠址設(shè)計(jì)基準(zhǔn)洪水的確定HAD 101/091990濱海核電廠廠址設(shè)計(jì)基準(zhǔn)洪水的確定HAD 101/101991核電廠廠址選擇的極端氣象事件HAD 101/111991核電廠設(shè)計(jì)基準(zhǔn)熱帶氣旋HAD 101/121990核電廠的地基安全問題HAD 102/011989核電廠設(shè)計(jì)總的安全原則HAD 102/021996核電廠的抗震設(shè)計(jì)與鑒定HAD 102/031986用于沸水堆、壓水堆和壓力管式反應(yīng)堆的安全功能和部件分級(jí)HAD 102/041986核電廠內(nèi)部飛射物及其二次效應(yīng)的防護(hù)HAD 102/051989與核電廠設(shè)計(jì)有關(guān)的外部人為事件HAD 102/061990核電廠反應(yīng)堆安全殼系統(tǒng)的設(shè)計(jì)HAD 102/071989核電廠堆芯的安全設(shè)計(jì)HAD 102/081989核電廠反應(yīng)堆冷卻劑系統(tǒng)及其有關(guān)系統(tǒng)HAD 102/091987核電廠最終熱阱及其直接有關(guān)的輸熱系統(tǒng)HAD 102/101988核電廠保護(hù)系統(tǒng)及有關(guān)設(shè)施HAD 102/111996核電廠防火HAD 102/121990核電廠輻射防護(hù)設(shè)計(jì)HAD 102/131996核電廠應(yīng)急動(dòng)力系統(tǒng)HAD 102/141988核電廠安全有關(guān)儀表和控制系統(tǒng)HAD 102/151990核電廠燃料裝卸和貯存系統(tǒng)HAD 103/011987核動(dòng)力廠運(yùn)行限值和條件及運(yùn)行規(guī)程HAD 103/021987核電廠調(diào)試程序HAD 103/031989核電廠堆芯和燃料管理HAD 103/041990核電廠運(yùn)行期間的輻射防護(hù)HAD 103/051996核電廠人員的配備、招聘、培訓(xùn)和授權(quán)HAD 103/061990核電廠安全運(yùn)行管理HAD 103/071988核電廠在役檢查HAD 103/081993核電廠維修HAD 103/091993核電廠安全重要物項(xiàng)的監(jiān)督HAD 401/011990核電廠放射性排出流和廢物管理HAD 401/021997核電廠放射性廢物管理系統(tǒng)的設(shè)計(jì)HAD 003/011988核電廠質(zhì)量保證大綱的制定HAD 003/021989核電廠質(zhì)量保證組織HAD 003/031986核電廠物項(xiàng)和服務(wù)采購(gòu)中的質(zhì)量保證HAD 003/041986核電廠質(zhì)量保證記錄制度HAD 003/051988核電廠質(zhì)量保證監(jiān)查HAD 003/061986核電廠設(shè)計(jì)中的質(zhì)量保證HAD 003/071987核電廠建造期間的質(zhì)量保證HAD 003/081986核電廠物項(xiàng)制造中的質(zhì)量保證HAD 003/091988核電廠調(diào)試和運(yùn)行期間的質(zhì)量保證HAD 003/101989核燃料組件采購(gòu)、設(shè)計(jì)和制造中的質(zhì)量保證HAD 002/011989核動(dòng)力營(yíng)運(yùn)單位的應(yīng)急準(zhǔn)備HAD 002/021990地方政府對(duì)核電廠的應(yīng)急準(zhǔn)備HAD 002/031991核事故輻射應(yīng)急時(shí)對(duì)公眾防護(hù)的干預(yù)原則和水平HAD 002/041991核事故輻射應(yīng)急時(shí)對(duì)公眾防護(hù)的導(dǎo)出干預(yù)水平 0042核電廠安全分析報(bào)告的標(biāo)準(zhǔn)格式和內(nèi)容 第十八章 人因工程和控制室（4） 中華人民共和國(guó)環(huán)境保護(hù)相關(guān)法律法規(guī)法律法規(guī)Regulations of Environmental Protection for Basic Construction of Nuclear Power Plant (Sep. 1984) GB624986核電廠環(huán)境輻射防護(hù)規(guī)定Regulations for the Nationwide Environment Monitoring Management (July 1983) GB1121789核設(shè)施流出物監(jiān)測(cè)的一般規(guī)定GB1237990環(huán)境核輻射監(jiān)測(cè)規(guī)定 Regulations on the Administration of Construction Project Environmental Protection (Nov. 1998) 管理導(dǎo)則和標(biāo)準(zhǔn)GB1121689核設(shè)施流出物和環(huán)境放射性監(jiān)測(cè)質(zhì)量保證計(jì)劃的一般要求GB1180604放射性物質(zhì)安全運(yùn)輸規(guī)定GB1271191低、中水平放射性固體廢物包裝安全標(biāo)準(zhǔn)GB913395放射性廢物的分類GB30971997海水水質(zhì)標(biāo)準(zhǔn)GB38382002地表水環(huán)境質(zhì)量標(biāo)準(zhǔn)GB574985生活飲用水衛(wèi)生標(biāo)準(zhǔn) GB30951996環(huán)境空氣質(zhì)量標(biāo)準(zhǔn) GB/T702386放射性廢物固化體長(zhǎng)期浸出試驗(yàn)GB913488輕水堆核電廠放射性固體廢物處理系統(tǒng)技術(shù)規(guī)定 GB913588輕水堆核電廠放射性廢液處理系統(tǒng)技術(shù)規(guī)定 GB913688輕水堆核電廠放射性廢氣處理系統(tǒng)技術(shù)規(guī)定 GB1458793輕水堆核電廠放射性廢水排放系統(tǒng)技術(shù)規(guī)定GB14569. 193低、中水平放射性廢物固化體性能要求水泥固化體GB89781996污水綜合排放標(biāo)準(zhǔn)GB188712002電離輻射防護(hù)與輻射源安全基本標(biāo)準(zhǔn) 應(yīng)遵循的國(guó)外法規(guī)、標(biāo)準(zhǔn)和規(guī)范核島主要采用美國(guó)核管會(huì)（NRC）、國(guó)家核安全管理委員會(huì)（NNSA）以及國(guó)際原子能委員會(huì)頒布的法規(guī)和導(dǎo)則，主要有RG、10 CFR、ANS、ANSI、ASME、ASTM、NUREG、IAEA、ISA以及IEE、IEEE等通用標(biāo)準(zhǔn)。1991.105.EPRI Report TR102323, Revision 1, “Guidelines for Electromagnetic Interference Testing in Power Plants.”106.EPRI Utility Requirement Document, “Advanced Light Water Reactor Utility Requirements Document,” Revision 8.107.FEMA 356, “Prestandard and Commentary for the Seismic Rehabilitation of Buildings,” Federal Emergency Management Agency, November 2000.108.ICEA Standard Publication P54440, “Ampacities of Cables in OpenTop Cable Trays,” 1986.109.IEEE Standard , “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations,” 1993.110.IEEE Standard 141, “IEEE Remended Practice for Electric Power Distribution for Industrial Plants,” (IEEE Red Book), 1993.111.IEEE Standard 242, “IEEE Remended Practice for Protection and Coordination of Industrial and Commercial Power Systems” (IEEE Buff Book), 1986.112.IEEE Standard 279, “IEEE Standard Criteria for Protection Systems for Nuclear Power Generating Stations,” 1971.113.IEEE Standard 308, “IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations,” 1991.114.IEEE Standard 317, “IEEE Standard for Electric Penetrations Assemblies in Containment Structures for Nuclear Power Generating Stations,” 1983.115.IEEE Standard 323, “IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations,” 1974.116.IEEE Standard 336, “IEEE Standard Installation, Inspection, and Testing Requirements for Power, Instrumentation, and Control Equipment for Nuclear Facilities,” 1985.117.IEEE Standard 338, “IEEE Standard Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Stations Safety Systems,” 1987.118.IEEE Standard 344, “IEEE Remended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations,” 1987.119.IEEE Standard 379, “IEEE Standard Application of the SingleFailure Criterion to Nuclear Power Generating Station Safety Systems,” 2000.120.IEEE Standard 382, “IEEE Standard for Qualification of Actuators for PowerO