Implications of an HRA framework for quantifying human acts of commission and dependency: Development of a methodology for conducting an integrated HRA/PRA

Conference · Fri Dec 31 00:00:00 EST 1993

OSTI ID:10129719

Barriere, M T; Luckas, W J; Brown, W S ^[1]; Cooper, S E ^[2]; Wreathall, J ^[3]; Bley, D C ^[4]

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1. Brookhaven National Lab., Upton, NY (United States)
2. Science Applications International Corp., Reston, VA (United States)
3. Wreathall (John) and Co., Dublin, OH (United States)
4. PLG, Inc., Newport Beach, CA (United States)

To support the development of a refined human reliability analysis (HRA) framework, to address identified HRA user needs and improve HRA modeling, unique aspects of human performance have been identified from an analysis of actual plant-specific events. Through the use of the refined framework, relationships between the following HRA, human factors and probabilistic risk assessment (PRA) elements were described: the PRA model, plant states, plant conditions, PRA basic events, unsafe human actions, error mechanisms, and performance shaping factors (PSFs). The event analyses performed in the context of the refined HRA framework, identified the need for new HRA methods that are capable of: evaluating a range of different error mechanisms (e.g., slips as well as mistakes); addressing errors of commission (EOCs) and dependencies between human actions; and incorporating the influence of plant conditions and multiple PSFs on human actions. This report discusses the results of the assessment of user needs, the refinement of the existing HRA framework, as well as, the current status on EOCs, and human dependencies.

• Research Organization: Brookhaven National Lab., Upton, NY (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 10129719
• Report Number(s): BNL-NUREG-60007; CONF-931079-20; ON: DE94007522
• Resource Relation: Conference: 21. water reactor safety information meeting,Bethesda, MD (United States),25-27 Oct 1993; Other Information: PBD: [1993]
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
NUCLEAR POWER PLANTS
REACTOR OPERATORS
RELIABILITY
HUMAN FACTORS
BWR TYPE REACTORS
PWR TYPE REACTORS
REACTOR SAFETY
RISK ASSESSMENT
REACTOR ACCIDENTS
ERRORS
220900
210100
210200
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED