Fire Human Reliability Analysis for C-2 Nuclear Power Plant

Abstract

As one of the essential tasks of fire Probabilistic Safety Assessment (PSA), fire Human Reliability Analysis (HRA) has important impact on analysis results and quality of a fire PSA. The scope of a fire HRA mainly includes pre-initiator HRA and post-initiator HRA. In this paper, the screening methodology for the post-initiator HRA of CHASHMA Nuclear Power Plant Unit 2 (C-2) is first introduced briefly with the screening criteria, and the performance shaping factors (PSFs) that should be considered in the fire HRA are studied. Next the post-initiator human failure events (HFEs) for C-2 nuclear power plant are identified and the preliminary quantitative analysis is presented with the screening method. Finally, the detailed quantification of HFEs with the Standardized Plant Analysis Risk Human Reliability Analysis (SPAR-H) method is described briefly and the analysis results are all obtained. The dependency analysis and uncertainty analysis in C-2 fire HRA are also briefly discussed in this paper.