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Evaluation of Human Reliability Analysis Results in Probabilistic Safety Assessment for Korea Standard Nuclear Power Plants  

강대일 (한국원자력연구소 종합안전평가부)
정원대 (한국원자력연구소 종합안전평가부)
양준언 (한국원자력연구소 종합안전평가부)
Publication Information
Journal of the Korean Society of Safety / v.18, no.2, 2003 , pp. 98-103 More about this Journal
Abstract
Based on ASME probabilistic risk assessment (PRA) and NEI PRA peer review guidance, we evaluate a human reliability analysis (HRA) in probabilistic safety assessment (PSA) for Korea standard nuclear power plants, Ulchin Unit 3&4, to improve it performed at under design. The HRA for Ulchin Unit 3&4 is assessed as higher than Grade I based on ASME PRA standard and as higher than Grade 2 based on NEI PRA peer review guidance. The major items to be improved identified through the evaluation process are the documentation, the systematic human reliability analysis, the participitation of operators in the works and review of HRA. We suggest the guidance on the identification and qualitative screening analysis for pre-accident human errors and solve some items to be improved using the suggested guidance.
Keywords
nuclear power plant; probabilistic safety assessment; human reliability analysis;
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  • Reference
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