A multidisciplinary framework for improving the quantification and modeling of human errors of commission and dependency: Development status of a methodology for conducting an integrated HRA/PRA

Conference · Sat Oct 01 04:00:00 EDT 1994

OSTI ID:54621

Barriere, M T; Luckas, W J ^[1]; Cooper, S E ^[2]; Wreathall, J ^[3]; Bley, D C ^[4]; Ramey-Smith, A; Thompson, C M ^[5]

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1. Brookhaven National Lab., Upton, NY (United States)
2. Science Applications International Corp., Reston, VA (United States)
3. John Wreathall & Co., Dublin, OH (United States)
4. PLG, Inc., Newport Beach, CA (United States)
5. Nuclear Regulatory Commission, Rockville, MD (United States)

As part of an NRC-sponsored program evolving from an assessment of human reliability issues in Low Power and Shutdown (LP&S) operations in nuclear power plants (NPPs), an improved approach to human reliability analysis (HRA) is currently being developed. It is intended to be fully integrated with probabilistic risk assessment (PRA) methodology and enable a better assessment of the human contribution to plant risk, both during LP&S and at-power operations. This summary briefly describes progress made in the Detailed HRA Project (FIN L-2415) beyond that presented in October 1993 at the 21st Water Reactor Safety Information Meeting (WRSM). The project`s completed, ongoing, and future efforts are best described in terms of four phases; namely, the Assessment Phase, the Analysis and Characterization Phase, the Development Phase, and the Implementation Phase.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research
• OSTI ID: 54621
• Report Number(s): NUREG/CP--0139; CONF-9410216--; ON: TI95001469
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
ACCIDENTS
HUMAN FACTORS
HUMAN FACTORS ENGINEERING
NUCLEAR POWER PLANTS
PERFORMANCE
REACTOR OPERATORS
REACTOR SAFETY