International HRA Empirical Study – Phase 2 Report (NUREG/IA-0216, Volume 2)

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Publication Information

Manuscript Completed: May 2011
Date Published: August 2011

Prepared by:
Andreas Bye1, Erasmia Lois2, Vinh N. Dang3,
Gareth Parry2*, John Forester4, Salvatore Massaiu1,
Ronald Boring4**, Per Øivind Braarud1, Helena Broberg1,
Jeff Julius5, Ilkka Männistö6, Pamela Nelson7

1OECD Halden Reactor Project, Norway
2U.S. Nuclear Regulatory Commission, USA
3Paul Scherrer Institute, Switzerland
4Sandia National Laboratories, USA
5Scientech, USA
6Technical Research Centre of Finland, Finland
7Universidad Nacional Autónoma de México, Mexico
*Currently with ERIN Engineering and Research Inc, USA
**Currently with Idaho National Laboratory, USA

Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

Prepared by:
U.S. Nuclear Regulatory Commission (United States)
OECD Halden Reactor Project (Norway)

Published by:
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

Availability Notice


Volume 2 of NUREG/IA-0216, including NUREG/IA-0216, Vol. 2, Appendix A, documents the results of Phase 2 of the International Human Reliability Analysis (HRA) Empirical Study. This three-phase study is a multinational, multiteam effort supported by the Organization for Economic Cooperation and Development (OECD) Halden Reactor Project, the Swiss Federal Nuclear Safety Inspectorate, the U.S. Electric Power Research Institute, and the U.S. Nuclear Regulatory Commission (NRC). Phase 2 has also been documented as a Halden publication: HWR-915, March 2010.

The objective of this study is to develop an empirically based understanding of the performance, strengths, and weaknesses of different HRA methods used to model human response to accident sequences in probabilistic risk assessments (PRAs). The empirical basis was developed through experiments performed at the Halden Reactor Project HAMMLAB (HAlden huMan-Machine LABoratory) research simulator, with real crews responding to accident situations similar to those modeled in PRAs. The scope of the study is limited to HRA methods thought appropriate for use in PRAs evaluating internal events during full power operations of current light water reactors. The study consists of performing HRAs for predefined human actions, with different HRA teams using different methods. Nuclear power plant crews perform these human actions at the Halden simulator, Halden experimentalists collect and interpret the data to fit HRA data needs, and an independent group of experts compare the results of each HRA method/team to the Halden crew performance data.

Phase 2 consists of the comparison of HRA predictions for nine steam generator tube rupture human actions. Phase 3, which will be documented in Volume 3, consists of the comparison of four loss-of-feedwater human actions. The overall findings of the Study will be documented in a separate NUREG Report. The results of the Empirical Study will provide a technical basis for improving individual methods, improving existing guidance documents for performing and reviewing HRAs (e.g., NUREG-1792, HRA Good Practices), and developing additional guidance and training materials for implementing individual methods.

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