Study on Aging Management Review of Electric and I&C Equipment in Evaluation of Nuclear Power Plant Operation License Extension
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摘要: 通过研读《<核电厂运行许可证>有效期限延续的技术政策（试行）》，并参考国外核电厂延寿活动中的经验，结合国内核电厂的运行许可证延续（OLE）评估活动的实际情况，介绍了核电厂OLE中的电仪设备老化管理筛选、老化效应识别评估和管理活动审查的实施流程及方法；分别以实例形式给出了“物项组”、“假想故障”以及“区域空间法”等的应用策略。策略的应用优化了筛选流程，提高了老化管理审查（AMR）活动的效率，对核电厂OLE有一定借鉴意义。
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关键词:
- 运行许可证延续（OLE） /
- 老化管理审查（AMR） /
- 电厂整体评估（IPA） /
- 老化管理大纲（AMP）
Abstract: By studying the Technical Policy for Extension of Validity Period of Nuclear Power Plant Operation License (Trial) , referring to the experience of foreign nuclear power plants in life extension activities, and combining with the actual situation of domestic nuclear power plant operation license extension (OLE) evaluation activities, this paper introduces the implementation processes and methods of aging management screening, aging effect identification and evaluation, and management activity review of electric and I&C equipment in OLE of nuclear power plants; The application strategies of “item group”, “hypothetical fault” and “regional space method” are given in the form of examples. The application of the strategy optimizes the screening process and improves the efficiency of aging management review (AMR) activities, which can be used as a reference for nuclear power plant OLE. -
表 1 AMR范围筛选原则
Table 1. AMR Scope Screening Principle
序号 AMR筛选原则 原则 1 《核电厂最终安全分析报告》中所描述的执行控制反应性、排出堆芯热量以及包容放射性物质和控制运行排放，限制事故释放几项基本安全功能的SSCs 原则 2 其故障可能影响上述SSCs执行功能的核电厂其他SSCs 原则 3 《核电厂最终安全分析报告》中所描述的防火设计、火灾探测和灭火系统 原则 4 《核电厂最终安全分析报告》中所描述的超设计基准事故的预防或缓解施；《核电厂最终安全分析报告》中包含的超设计基准事故有：未能紧急停堆的预期瞬态（ATWS） 和全厂断电（SBO） 原则 5 未纳入《核电厂最终安全分析报告》，但经国家核安全局批准或国家核安全局所要求的改进项中涉及上述范围的SSCs 
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[1] U. S. NRC. Status of license renewal applications and industry activities[R]. Washington, DC: U. S. NRC, 2019. [2] 叶奇蓁. 后福岛时期我国核电的发展[J]. 中国电机工程学报,2012, 32(11): 1-8. [3] 国家核安全局. <核电厂运行许可证>有效期限延续的技术政策（试行）, 国核安发[2015]280号[EB/OL]. 北京: 中华人民共和国环境保护部. [2015-12-31].https://www.mee.gov.cn/gkml/sthjbgw/haq/201601/t20160105_321062.htm. [4] NRC. Standard review plan for review of license renewal applications for nuclear power plants: NUREG-1800, revision 2[R]. Washington, DC: Office of Nuclear Reactor Regulation, 2010. [5] NRC. Generic aging Lessons Learned (GALL) report- final report: NUREG-1801, revision 2[R]. Washington, DC: Office of Nuclear Reactor Regulation, 2010. [6] Nuclear Energy Institute. Industry guideline for implementing the requirements of 10 CFR Part 54 – the license renewal rule: NEI 95-10, revision 6[R]. Washington, DC: Nuclear Energy Institute, 2005. [7] EPRI. Plant support engineering: license renewal electrical handbook: EPRI 1003057, revision 1[R]. Palo Alto: Electric Power Research Institute, 2007. -
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