基于SPAR-H方法对某核电厂因人员误碰蒸汽发生器主给水隔离阀关限位开关导致反应堆自动停堆事件进行的人因失误定量化分析  

Quantitative Analysis of Automatic Reactor Shutdown in NPP Caused by Personnel Accidentally Touching the Limit Switch of Main Feed Water Isolation Valve of Steam Generator Based on SPAR-H Method

作　　者：许友龙 李林峰 马国强 郑丽馨 侯秦脉 XU Youlong;LI Linfeng;MA Guoqiang;ZHENG Lixin;HOU Qinmai(Nuclear and Radiation Safety Center,MEP,Beijing 100082,China;Suzhou Nuclear Power Research Institute,Suzhou,215004,China)

机构地区：[1]生态环境部核与辐射安全中心,北京100082 [2]苏州热工研究院有限公司,苏州215004

出　　处：《核电子学与探测技术》2024年第6期1139-1146,共8页Nuclear Electronics & Detection Technology

摘　　要：2023年1月11日,某核电厂5号机组处于功率运行RP模式。运行部学员对主给水隔离阀的阀门结构包括限位开关位置进行观察学习,在使用手电观察限位开关的过程中误碰到关限位开关。误碰导致主给水隔离阀门自动关闭。随即由于1号蒸汽发生器(SG)水位低叠加上汽水失配信号触发反应堆自动停堆。本文将使用SPAR-H方法,对本事件涉及的人员绩效形成因子PSF开发定量化分析,进一步假设与比对各针对性的纠正行动得到落实后的人员可靠性分析结果,并采用不同的人员可靠性分析方法对事件进行分析与对比,从而为营运单位制定更加有针对性的纠正行动提出改进建议。On January 11,2023,Unit 5 of a nuclear power plant was in reactor power operation mode.The trainees of the operation department observed and learned the valve structure of the main water supply isolation valve,including the position of the limit switch,and accidentally touched the limit switch in the process of observing the limit switch with a flashlight.The mistake caused the main water supply isolation valve to automatically close.Due to the low water level of the No.1 steam generator,the superimposed mismatch signal triggered the automatic shutdown.This paper will use the SPAR-H method to develop a quantitative analysis of the personnel performance formation factor PSF involved in this incident,and assume and compare the personnel reliability analysis results after the implementation of various targeted corrective actions.Different personnel reliability analysis methods are used to analyze and compare the incidents,so as to make more targeted corrective actions for the operation unit and put forward improvement suggestions.

关 键 词：SPAR-H PSF人员绩效形成因子 误碰 人员可靠性分析 人因失误率 

分 类 号：TL48[核科学技术—核技术及应用]