AP1000堆型核电厂安全性能指标研究
Study on the Safety Performance Indicator for AP1000 Nuclear Power Plant
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摘要: 核电厂安全性能指标(SPI)是国家核安全局核电厂运行期间总体安全状况的表征。安全系统不可用度指标(SSUI)是SPI体系中的一类指标,用于评价重要的事故缓解系统在需要其投入时的可用性。AP1000核电厂因其系统设计的特殊性,无法简单沿用国内现有运行核电厂的结论。本文采用风险指引型决策理念,识别了AP1000核电厂中执行SSUI中指定功能要求的系统,利用概率安全分析(PSA)模型计算这些系统的风险重要度并进行分析,并综合多种因素选择SSUI监测对象。随后,针对1E级直流和不间断电源系统(IDS),确定系统不可用度范围与安全级别的对应关系。Abstract: The Safety Performance Indicator(SPI) for nuclear power plants has been established by National Nuclear Safety Administration of China(NNSA), which is used for evaluating plant safety conditions and implementing corresponding regulatory measures. The Safety System Unavailability Indicator(SSUI) is a part of SPI, which is utilized to evaluate the availability of important accident mitigating systems when demanded. Specific systems and SSUI evaluation criteria are not completely applicable for AP1000 due to its unique design features. In this paper,risk-informed decision making methodology is adopted. Firstly, the systems in AP1000 whose functions are determined in the SSUI are identified, and sorted by system importance that is quantified in the probabilistic safety analysis(PSA). Systems that shall be included in the SSUI are selected based on the result of sorting. Then the risk increase on the unavailability of the class1 E DC and uninterrupted power supply system(IDS) is quantified and correlation between the safety level and unavailability are determined based on the relation between the risk increase and the safety level.