The U.S. HRA empirical study : assessment of HRA method predictions against operating crew performance on a U.S. nuclear power plant simulator / prepared by John Forester, Huafei Liao, Vinh N. Dang, Andreas Bye, Erasmia Lois, Mary Presley, Julie Marble, Rod Nowell, Helena Broberg, Michael Hildenbrandt, Bruce Hallbert, and Tommy Morgan.

Format:

Book

Government document

Author/Creator:

Forester, John (Sandia Labs)

Liao, Huafei (Sandia Labs), author.

Dang, Vinh N., 1965- author.

Bye, Andreas, author.

Lois, Erasmia, author.

Presley, Mary (Electric Power Research Institute), author.

Marble, Julie (NRC), author.

Nowell, Rod (South Texas Project), author.

Broberg, Helena (Institute for Energy Technology, Norway), author.

Hildenbrandt, Michael (Institute for Energy Technology, Norway), author.

Hallbert, Bruce (Idaho Nat. Lab), author.

Morgan, Tommy (Idaho Nat. Lab), author.

Contributor:

U.S. Nuclear Regulatory Commission. Division of Risk Analysis, sponsoring body.

Language:

English

Subjects (All):

Nuclear power plants--Human factors--United States.

Nuclear power plants.

Human-machine systems--United States.

Human-machine systems.

Nuclear power plants--United States--Reliability.

Nuclear power plants--United States--Computer simulation.

Nuclear power plants--Computer simulation.

Nuclear power plants--Human factors.

Nuclear power plants--Reliability.

United States.

Genre:

Online resources.

Physical Description:

1 online resource (xxiv, 437 pages) : illustrations, some color

Other Title:

United States human reliability analysis empirical study: assessment of human reliability analysis method predictions against operating crew performance on a United States nuclear power plant simulator

Assessment of HRA method predictions against operating crew performance on a U.S. nuclear power plant simulator

Place of Publication:

Washington, DC : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, June 2016.

Summary:

This report documents the U.S. Human Reliability Analysis (HRA) Empirical Study (referred to as the U.S. Study in the report), which is a large systematic data collection effort supported by the U.S. Nuclear Regulatory Commission with participation of organizations from five countries representing industry, regulators, and the research community. The objective of the U.S. Study was to improve the insights developed from the International HRA Empirical Study [1-4] (referred to as the International Study) and address the limitations of that study. Similar to the International Study, the U.S. Study evaluated the performance of different HRA methods by comparing method predictions to actual crew performance in simulated accident scenarios conducted in a U.S. nuclear power plant (NPP) simulator. There was significant agreement in the findings and conclusions between the International and U.S. studies in terms of the strengths and weaknesses of the HRA methods evaluated in both studies and in the overall findings about HRA and the identified needed improvements. In addition to identification of some new HRA- and method-related issues, the design of the U.S. Study allowed insights to be obtained on some issues that were not resolved in the International Study. In particular, because multiple HRA teams applied each method in the U.S. Study, comparing their analyses and predictions allowed separation of analyst effects from method effects and allowed conclusions to be drawn on aspects of methods that are susceptible to different application or usage by different analysts that may lead to differences in results. The findings serve as a strong basis for improving the consistency and robustness of HRA, which in turn facilitates identification of mechanisms for improving operating crew performance in NPPs.

Contents:

Introduction

Study design

Empirical data collection and analysis

Methodology for assessing and comparing HRA predictions against simulator data and the intra-method comparisons

Description of scenarios, HFEs, and empirical simulator results

Overview of empirical and predictive quantitative results

Summary of intra-method comparisons

Discussion of factors contributing to the variabilities of HRA results

Insights and overall conclusions

Appendix A. Information package

Appendix B. Experimental procedure for experimenters

Appendix C. NRC crew performance assessment form

Appendix D. Scenario 1 crew by crew

Appendix E. Scenario 2 crew by crew

Appendix F. Scenario 3 crew by crew

Appendix G. Comparison of results from HRA method predictions to empirical data and overall assessments per method

Appendix H. Intra-method comparisons.

Notes:

Title from title screen (viewed on July 26, 2016).

"NUREG-2156."

"Manuscript completed: September 2015; date published: June 2016."

"Erasmia Lois and Y. James Chang, NRC project managers."

"Performing organization: Sandia National Laboratories"--Bibliographic data sheet

"Sponsoring organization: Division of Risk Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission"--Bibliographic data sheet

Includes bibliographical references (2 page).

Has Supplement:

Print version: Forester, John. U.S. HRA empirical study (OCoLC)953799919

OCLC:

956318088