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

표준 원자력발전소 확률론적 안전성 평가의 인간 신뢰도 분석 평가

  • 강대일 (한국원자력연구소 종합안전평가부) ;
  • 정원대 (한국원자력연구소 종합안전평가부) ;
  • 양준언 (한국원자력연구소 종합안전평가부)
  • Published : 2003.06.01


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.


nuclear power plant;probabilistic safety assessment;human reliability analysis


  1. A.D.Swain, 'Accident Sequence Evaluation Program Human Reliability Analysis Procedure,' NUREG/ CR-4772, S.N.L, Feb. 1987
  2. A.D.Swain and H.E.Guttman, 'Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications,' NUREG/CR-1278, S.N.L, Aug. 1983
  3. E.M. Dougherty and J.R. Fragola, "Human Reliability Analysis: A System Engineering Approach with Nuclear Power Plant Applications," SAlC, John Wiley & Sons, 1988
  4. NEI, 'PRA Peer Review Process Guidance,' NEI-00-02, Aug., 2002
  5. ASME, 'Standard for PRA for NPP Applications,' Rev. 15, 2002
  6. KEPCO, 'Final Probabilistic Safety Assessment Report for Ulchin Units 3 & 4' KEPCO, 1997