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INTEGRATED LEAK RATE TESTING OF CONTAINMENTS - A REGULATORY PERSPECTIVE

机译:遏制综合泄漏率测试 - 监管视角

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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附录J. CFR 50,“主反应堆安全壳泄漏试验的水冷动力堆,”套用于主反应堆安全壳的柚木密封整体性的术前及定期确认,包括系统和组件的测试要求穿透的容纳光水冷功率电抗器,并建立用于这种测试的验收标准。测试的目的是,以确保泄漏虽然如在植物的技术规范中规定的主反应器容器和系统和组件穿透主安全不会超过允许泄漏率值。目前的附录J.要求提供进行试验两种选择。选项A(完全确定性)要求术前泄漏速率测试之后,一组三个集成泄漏率测试(ILRT - 称为A型测试)应在每个10年服务期间执行,以大致相等的间隔。选项B不用于调度周期性A型测试提供了量化要求。然而,NEI 94-01,“10 CFR的基于性能的行业导则实现选择部分50,附录J”和NRC法规指南(RG)的壳是核电站的重要工程安全功能。它包含整个反应堆及反应堆冷却剂系统,并作为对放射性裂变产物的各种事故条件下释放到环境中的最后一道屏障。壳设计是基于与从反应堆冷却剂系统中最大的管的双端破裂导致的失冷却剂-accident相关联的压力和温度的负荷。最近,据报道,在某些1.163,“基于性能的围堵渗漏试验计划”,为确定的使用性能为基础的方法术前和定期的泄漏率测试的频率的指导方针。该选项B的要求和NEI 94-01指导是基于NUREG-1493,“基于性能的壳泄漏测试程序。”根据由操作数据和风险意义所提供的信息,该研究计算风险对公众在研究中考虑了15个替代品的变化(在人-REM)。然而,认识风险的在A型泄漏率变化测试频率,如在NUREG-1493中所描绘的非敏感性,多个被许可人提议在RG 1.174使用NRC风险知情指导他们的A型的测试频率的变化,“在植物特异性变化的许可条件风险的明智决策使用概率风险评估的探讨“。本文讨论了在ILRT频率植物特定变化的风险,明智的某些关键方面的确定性。

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