Initial Quantification of Human Errors Associated with Reactor Safety System Components in Licensed Nuclear Power Plants

Technical Report · Thu Jan 01 04:00:00 EST 1981

DOI:https://doi.org/10.2172/5461420· OSTI ID:5461420

Luckas, Jr., W. J. ^[1]; Hall, R. E. ^[1]

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1. Brookhaven National Laboratory (BNL), Upton, NY (United States)

This report provides a methodology for an initial quantification of gross categories of human errors made in conjunction with several reactor safety system components operated, maintained, and tested in licensed nuclear power plants. The resultant human error rates provide the first real systems bases of comparison for the existing derived and/or best judgement equivalent set of such rates or probabilities.

• Research Organization: Brookhaven National Laboratory (BNL), Upton, NY (United States)
• Sponsoring Organization: USDOE; USNRC
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 5461420
• Report Number(s): NUREG/CR--1880; BNL-NUREG--51323; ON: TI85015932
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ENGINEERED SAFETY SYSTEMS
ERRORS
HUMAN FACTORS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
OPERATION
POWER PLANTS
THERMAL POWER PLANTS
human error rate
human errors
probability
quantification
reactor safety system components