根据核行业经验和福岛核事故经验反馈,美国核管会在2014年将用于审查美国核电厂安全分析报告的《标准审查大纲》新增了19.3章"非能动先进轻水堆非安全级系统的监管要求".其中"增强的设计标准"从纵深防御的角度全面提高了非能动先进轻水堆事故72h后和地震后所使用的重要非安全级系统的可靠性和可用性要求.非能动先进轻水堆AP1000设计与标准审查大纲的一致性评估是核安全监管当局的审查重点,也是核电厂设计的重要工作之一.首先介绍了非安全级系统监管要求的演变历程和实施步骤,其次评估了AP1000设计与《标准审查大纲》19.3章要求的一致性,并进一步从可用性、抗震能力、飓风、内部灾害以及水淹防护等多个因素重点分析AP1000设计能否满足"增强的设计标准"要求.最后针对AP1000无法满足《标准审查大纲》19.3章的情况给出具体解决方案的建议.%Section 19.3 "the Regulatory Treatment of Non-safety Systems for Passive Advanced Light Water Reactors" was added to Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants by United States Nuclear Regulatory Commission in 2014,according to the nuclear industry experience and Fukushima Nuclear Accident feedback. The Augmented Design Standards,which enhance the requirement of availability and reliability of the significant non-safety systems applied in the post 72-hour period following an accident and seismic events,are highlighted in this section. To review the compliance of nuclear power plants design with Standard Review Plan is a part of essential work of the Nuclear Safety Administration,as well as the nuclear power plant designers. The evolution process of the Regulatory Treatment of Non-safety Systems is described,and the compliance of AP1000 design with Standard Review Plan 19.3 is evaluated. Furthermore,Augmented Design Standards are analyzed and specified from many factors,such as the availability,seismic design standards,standards for protection against natural phenomena,standards for protection against internal hazards and etc. The suggestion of resolving the incompliance of these augmented design standards are provided in the end.
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