首页> 外文会议>International conference on nuclear engineering;ICONE17 >LESSONS LEARNED AND INSIGHTS FROM IMPLEMENTATION OF EPRI GUIDELINES ON INTERNAL FLOODING AT FORT CALHOUN STATION
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LESSONS LEARNED AND INSIGHTS FROM IMPLEMENTATION OF EPRI GUIDELINES ON INTERNAL FLOODING AT FORT CALHOUN STATION

机译:在Calhoun站内部实施EPRI指南方面汲取的经验教训和启示

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An Internal Flooding Probabilistic Risk Assessment (IF-PRA) study is required to meet the requirements of the Internal Flooding portions of the ASME Internal Events PRA standard [1, 2, 3] and RG 1.200 Rl [4] for risk-informed applications at Nuclear Power Plants (NPPs). An internal flooding study was performed recently for a Nuclear Power Plant (NPP), Fort Calhoun Station (FCS), with a nuclear steam supply system designed by Combustion Engineering. The study was performed using guidance that is currently being developed for industry use by EPRI [5]. The intent of the EPRI draft guidance is to describe how to perform the various tasks to meet the requirements and expectations of the ASME PRA Standard in order to comply with RG 1.200. Performing this analysis provided an opportunity to gain numerous insights on how to best perform the analysis from a technical standpoint. This paper provides lessons learned and insights gained in the implementation of the EPRI draft guidance on internal flooding for PRA.Insights and lessons learned on the assignment of initiating event frequencies, treatment of dynamic flood volumes and time-based operator response timings, and developing associated peer review materials are provided. Discussions dealing with various sources of pipe failure frequencies highlight key differences between commonly used data. Characterizations of spray scenarios were evaluated to determine their impact on plant risk caused by internal flooding events. Maintenance-induced flooding scenarios that are often neglected were evaluated to gain insights on their impact on plant risk.Insights on performing a timely completion of the analysis are provided. Optimization techniques for plant walkdowns to capture relevant information and identify high priority flood areas are discussed. The impact of the flooding scenarios on PRA-related equipment was integrated into the internal events PRA model to quantify the associated risk. The rules used to perform the integration process and the lessons learned from the integration are also discussed.
机译:需要进行内部洪水概率风险评估(IF-PRA)研究,以符合ASME内部事件PRA标准[1、2、3]和RG 1.200 Rl [4]的内部洪水部分的要求。核电厂(NPPs)。最近,对卡尔洪堡站(FCS)的核电站(NPP)进行了内部洪水研究,该核电站配备了由燃烧工程公司设计的核蒸汽供应系统。这项研究是根据EPRI当前为行业使用而制定的指南进行的[5]。 EPRI指南草案的目的是描述如何执行各种任务以满足ASME PRA标准的要求和期望,以符合RG 1.200。进行此分析提供了一个机会,可以从技术角度获得关于如何最好地执行分析的大量见解。本文提供了实施PRA内部洪水的EPRI指南草案时的经验教训和见解。 提供了有关启动事件频率分配,动态洪水流量处理和基于时间的操作员响应时间安排以及开发相关的同行评审材料的见解和经验教训。有关管道故障频率的各种来源的讨论突出了常用数据之间的关键差异。评估了喷雾情景的特征,以确定其对内部洪水事件造成的植物风险的影响。对经常被忽略的维护引发的洪水情景进行了评估,以了解其对工厂风险的影响。 提供了有关及时完成分析的见解。讨论了用于工厂停堆以获取相关信息并识别高优先级洪水区域的优化技术。洪水情境对PRA相关设备的影响已整合到内部事件PRA模型中,以量化相关风险。还讨论了用于执行集成过程的规则以及从集成中学到的经验教训。

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