An Analysis of Operational Experience During Low Power and Shutdown and a Plan for Addressing Human Reliability Assessment Issues (NUREG/CR-6093, BNL-NUREG-52388)

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Publication Information

Manuscript Completed: February 1994
Date Published: June 1994

Prepared by:
M. Barriere, W. Luckas, Brookhaven National Laboratory
D. Whitehead, Sandia National Laboratories
A. Ramey-Smith, Nuclear Regulatory Commission

Contributors
D. Bley¹, M. Donovan², W. Brown³, J. Forester⁴, S. Cooper⁵, P. Haas⁶, J. Wreathall⁷, G. Parry²

Brookhaven National Laboratory
Upton, NY 11973-5000

Sandia National Laboratories
Albuquerque, NM 87185

Prepared for:
Division of Safety Issue Resolution
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
NRC FIN L2415, Under DOE Contract No. DE-AC02--76CH00016
NRC FIN L2539, Under DOE Contract No. DE-AC04-76DP00789

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¹PLG, Inc., Newport Beach, CA 92660
²HALLIBURTON NUS Environmental Corp., Gaithersburg, MD 20878
³Brookhaven National Laboratory, Upton, NY 11973
⁴Science Applications International Corp., Albuquerque, NM 87106
⁵Science Applications International Corp., Reston, VA 22090
⁶Concord Associates, Inc., Knoxville, TN 37932
⁷John Wreathall & Co., Dublin, OH 43017

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Abstract

Recent nuclear power plant events (e.g., Chernobyl, Diablo Canyon, and Vogtle) and U.S. Nuclear Regulatory Commission (NRC) reports (e.g., NUREG-1449) have led to concerns regarding human reliability during low power and shutdown (LP&S) conditions and limitations of human reliability analysis (HRA) methodologies in adequately representing the LP&S environment. As a result of these concerns, the NRC initiated two parallel research projects to assess the influence of LP&S conditions on human reliability through an analysis of operational experience at pressurized water reactors (PWRs) and boiling water reactors (BWRs). These research projects, performed by Brookhaven National Laboratory for PWRs, and Sandia National Laboratories for BWRs, identified unique aspects of human performance during LP&S conditions and provided a program plan for research and development necessary to improve existing HRA methodologies. This report documents the results of the analysis of LP&S operating experience and describes the improved HRA program plan.