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INTEGRATED LEAK RATE TESTING OF CONTAINMENTS - A REGULATORY PERSPECTIVE

机译:容器的综合泄漏率测试-法规的观点

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Appendix J of 10 CFR 50, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors," sets the testing requirements for preoperational and periodic verification of the teak-tight integrity of the primary reactor containment, including systems and components which penetrate containment of light water-cooled power reactors, and establishes the acceptance criteria for such tests. The purposes of the tests are to assure that leakage though the primary reactor containment and systems and components penetrating primary containment would not exceed allowable leakage rate values as specified in the plants' technical specifications. The current Appendix J requirements provide two options for performing the tests. Option A (fully deterministic) requires that after the preoperational leakage rate tests, a set of three integrated leak rate tests (ILRT - termed as Type A tests) shall be performed, at approximately equal intervals during each 10-year service period. Option B does not provide a quantitative requirement for scheduling the periodic Type A tests. However, NEI 94-01, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J," and NRC Regulatory Guide (RG) The containment is a vital engineering safety feature of a nuclear power plant. It encloses the entire reactor and reactor coolant system and serves as a final barrier against the release of radioactive fission products to the environment under various accident conditions. Containment design is based on pressure and temperature loadings associated with a loss-of-coolant -accident resulting from a double-ended rupture of the largest pipe in the reactor coolant system. Recently, it has been reported that in certain 1.163, "Performance-Based Containment Leak Test Program," provide guidelines for determining the frequencies of preoperational and periodic leak rate tests using a performance based approach. The Option B requirements and NEI 94-01 guidance are based on NUREG-1493, "Performance Based Containment Leak-Test Program." Based on the information provided by the operating data and their risk significance, the study calculated the change in risk (in person-rem) to public for the 15 alternatives considered in the study. However, recognizing the non-sensitivity of risk to change in Type A leak rate testing frequencies, as depicted in NUREG-1493, a number of licensees are proposing changes to their Type A test frequencies using NRC risk-informed guidance in RG 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis." The paper discusses certain key deterministic aspects of the risk-informed decision for the plant-specific changes in the ILRT frequencies.
机译:10 CFR 50的附录J“水冷动力堆的主要反应堆安全壳泄漏测试”设定了对主要反应堆安全壳的柚木密封完整性进行操作前和定期验证的测试要求,包括渗透到安全壳内的系统和组件。轻型水冷动力堆,并建立了此类测试的验收标准。测试的目的是确保通过主反应堆安全壳以及穿透主安全壳的系统和组件的泄漏不会超过工厂技术规格中指定的允许泄漏率值。当前的附录J要求提供了执行测试的两个选项。选项A(完全确定性)要求在进行术前泄漏率测试之后,在每个10年的服务期内,应以大约相等的间隔执行一组三个综合泄漏率测试(ILRT-称为A型测试)。选项B没有为计划定期的Type A测试提供定量要求。但是,NEI 94-01,“实施基于性能的10 CFR Part 50附录J的选件的行业指南”和NRC监管指南(RG)围堵是核电厂的重要工程安全功能。它包围了整个反应堆和反应堆冷却剂系统,并作为在各种事故情况下防止放射性裂变产物释放到环境中的最终屏障。安全壳设计基于与因反应堆冷却剂系统中最大管道的双重破裂导致的冷却液流失事故相关的压力和温度负荷。最近,据报道,在某些1.163“基于性能的泄漏测试程序”中,提供了使用基于性能的方法确定操作前和定期泄漏率测试的频率的准则。选项B的要求和NEI 94-01指南均基于NUREG-1493“基于性能的密闭性泄漏测试程序”。根据运营数据提供的信息及其风险重要性,该研究计算了研究中考虑的15种替代方案对公众的风险(面对面)变化。但是,如NUREG-1493中所述,认识到A型泄漏率测试频率变化的风险不敏感,许多被许可人正在使用RG 1.174中NRC风险告知指南来更改其A型测试频率。一种在基于许可的工厂特定变更的风险知情决策中使用概率风险评估的方法。”本文讨论了针对ILRT频率的工厂特定变化的风险决定决策的某些关键确定性方面。

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