核电厂事故后人因可靠性分析与操纵员绩效改善

Post-accident Human Reliability Analysis and Improvement of Operators' Performance in a NPP

核电厂人因可靠性分析(HRA)是核电厂概率安全评价(PSA)的重要组成部分,能够较好地评价和量化核电厂主控室(MCR)操纵员的行为。通过对国内某核电厂压水堆(PWR)进行HRA分析,对事故后操纵员行为进行分类和归组并对其进行量化分析,对核电厂事件进行基本人误概率和重要度排序。基于HRA分析,从管理的角度,提出对相对应的应急规程(EOP)进行改进,对于重要度较高的操纵员行为,核电厂应加强培训,改善操纵员绩效。

Human Reliability Analysis （HRA） is an important part of Probabilistic Safety Assessment （PSA） in a nuclear power plant （NPP）. It can evaluate and quantify the behaviors of the operators in a main control room （MCR） to a certain degree. The paper classifies and groups the post - accident operator＇ s behaviors and analyzes them in a quantity way on the basis of a HRA analysis of a pressurized water reactor （PWR） in a certain domestic NPP. The basic human errors and criticality of NPP events are arranged in sequence. On the basis of HRA, the paper puts forward the corresponding improvement of emergency operating procedures （EOPs） from the point of management. For the operators＇ behaviors of high criticality, the NPP should enforce training and improve the performance of operators.