Development of a methodology for conducting an integrated HRA/PRA --. Task 1, An assessment of human reliability influences during LP&S conditions PWRs

Conference · Tue Jun 01 04:00:00 EDT 1993

OSTI ID:10161364

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

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1. Brookhaven National Lab., Upton, NY (United States)
2. Wreathall (John) and Co., Dublin, OH (United States)
3. Science Applications International Corp., McLean, VA (United States)

During Low Power and Shutdown (LP&S) conditions in a nuclear power plant (i.e., when the reactor is subcritical or at less than 10--15% power), human interactions with the plant`s systems will be more frequent and more direct. Control is typically not mediated by automation, and there are fewer protective systems available. Therefore, an assessment of LP&S related risk should include a greater emphasis on human reliability than such an assessment made for power operation conditions. In order to properly account for the increase in human interaction and thus be able to perform a probabilistic risk assessment (PRA) applicable to operations during LP&S, it is important that a comprehensive human reliability assessment (HRA) methodology be developed and integrated into the LP&S PRA. The tasks comprising the comprehensive HRA methodology development are as follows: (1) identification of the human reliability related influences and associated human actions during LP&S, (2) identification of potentially important LP&S related human actions and appropriate HRA framework and quantification methods, and (3) incorporation and coordination of methodology development with other integrated PRA/HRA efforts. This paper describes the first task, i.e., the assessment of human reliability influences and any associated human actions during LP&S conditions for a pressurized water reactor (PWR).

• Research Organization: Brookhaven National Lab., Upton, NY (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 10161364
• Report Number(s): BNL-NUREG--48671; CONF-930702--26; ON: DE93014058
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400
220900
CONTROL SYSTEMS
ERRORS
HUMAN FACTORS
MAN-MACHINE SYSTEMS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PWR TYPE REACTORS
REACTOR CONTROL SYSTEMS
REACTOR OPERATORS
REACTOR SAFETY
REACTOR SHUTDOWN
RELIABILITY
RISK ASSESSMENT