Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Development of a human reliability analysis (HRA) guide for qualitative analysis with emphasis on narratives and models for tasks in extreme conditions

  • Kirimoto, Yukihiro (Nuclear Risk Research Center (NRRC), Central Research Institute of Electric Power Industry (CRIEPI)) ;
  • Hirotsu, Yuko (Nuclear Risk Research Center (NRRC), Central Research Institute of Electric Power Industry (CRIEPI)) ;
  • Nonose, Kohei (Nuclear Risk Research Center (NRRC), Central Research Institute of Electric Power Industry (CRIEPI)) ;
  • Sasou, Kunihide (Nuclear Risk Research Center (NRRC), Central Research Institute of Electric Power Industry (CRIEPI))
  • Received : 2020.03.29
  • Accepted : 2020.10.05
  • Published : 2021.02.25
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Abstract

Probabilistic risk assessment (PRA) has improved its elemental technologies used for assessing external events since the Fukushima Daiichi Nuclear Power Station Accident in 2011. HRA needs to be improved for analyzing tasks performed under extreme conditions (e.g., different actors responding to external events or performing operations using portable mitigation equipment). To make these improvements, it is essential to understand plant-specific and scenario-specific conditions that affect human performance. The Nuclear Risk Research Center (NRRC) of the Central Research Institute of Electric Power Industry (CRIEPI) has developed an HRA guide that compiles qualitative analysis methods for collecting plant-specific and scenario-specific conditions that affect human performance into "narratives," reflecting the latest research trends, and models for analysis of tasks under extreme conditions.

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Acknowledgement

The authors would like to express their appreciation to Dr. Dennis Bley for his valuable comments on narrative construction, qualitative analysis of human reliability, the most recent state of technological development including narratives in the United States, as well as his broad knowledge of recent research on HRA. We would like to express our gratitude to the members of the NRRC Risk Assessment Sub-Working Groups with whom discussions were help and who provided advice on how to proceed and cooperate for development of the HRA guide. We would also like to thank the Technical Advisory Committee (TAC), which offered very helpful suggestions during discussions on the HRA research roadmap at NRRC, and Dr. George Apostolakis (Head of NRRC) and several internal experts, who provided very useful advice during discussions on the composition and content of the HRA guide.

References

  1. Alan D. Swain, et al., US Nuclear Regulatory Committee (NRC), Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications, NUREG/CR-1278, Final Report, US NRC, August 1983.
  2. Kirimoto Yukihiro, et al., The Human Reliability Analysis (HRA) Guide with Emphasis on Narratives (2018) - Development of Qualitative Analysis Methods and Analysis Models for Tasks on Extreme Conditions, CRIEPI Research Report O18011, CRIEPI, 2019 (in Japanese).
  3. Jing Xing, et al.. An Integrated Human Event Analysis System (IDHEAS) for Nuclear Power Plant Internal Events At-Power Application vol. 1, US NRC, March 2017. NUREG-2199.
  4. John Forester, et al., The International HRA Empirical Study : Lessons Learned from Comparing HRA Methods Predictions to HAMMLAB Simulator Data, NUREG-2127, US NRC, August 2014.
  5. Jeff Julius, et al., EPRI/NRC-RES "Fire Human Reliability Analysis Guidelines", NUREG-1921 (EPRI 1023001), Final Report, US NRC, July 2012. Final Report.
  6. Alan Kolaczkowski, et al., Good Practices for Implementing Human Reliability Analysis (HRA), NUREG-1792, US NRC, April 2005. Final report.
  7. Advisory Committee on Reactor Safeguards (ACRS), John W. Stetkar, Human Reliability Analysis Models, ML14134A328, US NRC, May 14, 2014.

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