Development of a methodology for conducting an integrated HRA/PRA --

Conference · Fri Jan 01 04:00:00 EST 1993

OSTI ID:7368693

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

---

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: DOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 7368693
• 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 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400 -- Nuclear Reactor Technology-- Control Systems
220900* -- Nuclear Reactor Technology-- Reactor Safety
ANIMALS
CONTROL SYSTEMS
ENRICHED URANIUM REACTORS
ERRORS
HUMAN FACTORS
MAMMALS
MAN
MAN-MACHINE SYSTEMS
PERSONNEL
POWER REACTORS
PRIMATES
PWR TYPE REACTORS
REACTOR CONTROL SYSTEMS
REACTOR OPERATORS
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
RELIABILITY
RISK ASSESSMENT
SAFETY
SHUTDOWN
THERMAL REACTORS
VERTEBRATES
WATER COOLED REACTORS
WATER MODERATED REACTORS