Assessment of HRA method predictions against operating crew performance: Part III: Conclusions and achievements
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Paul Scherrer Inst. (PSI), Villigen (Switzerland)
- Institute for Energy Technology, Halden (Norway). OECD Halden Reactor Project
- US Nuclear Regulatory Commission (NRC), Rockville, MD (United States)
This is the last in a series of three papers documenting two large-scale human reliability analysis (HRA) empirical studies – the International HRA Empirical Study and the US HRA Empirical Study. The goal of the two studies was to develop an empirically-based understanding of the performance, strengths, and weaknesses of HRA methods by comparing HRA method predictions against actual operator performance in simulated accident scenarios on nuclear power plant (NPP) simulators. This paper first addresses areas where there is convergence between the two studies and where differences lie. Then it summarizes the combined insights and conclusions, including key findings on HRA in general through lessons learned about the HRA methods assessed in the studies and specific recommendations for improving guidance, practice and methods. Then it discusses the relevance and usefulness of simulator data for HRA in general. Finally, it presents the key achievements and overall conclusions of the two studies taken together.
- Research Organization:
- Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)
- Sponsoring Organization:
- NRC; USDOE
- Grant/Contract Number:
- AC04-94AL85000
- OSTI ID:
- 1326360
- Report Number(s):
- SAND--2016-5618J; 642203
- Journal Information:
- Reliability Engineering and System Safety, Journal Name: Reliability Engineering and System Safety; ISSN 0951-8320
- Publisher:
- ElsevierCopyright Statement
- Country of Publication:
- United States
- Language:
- English
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