Uses of human reliability analysis probabilistic risk assessment results to resolve personnel performance issues that could affect safety
Technical Report
·
OSTI ID:6474224
This report is the first in a series which documents research aimed at improving the usefulness of Probabilistic Risk Assessment (PRA) results in addressing human risk issues. This first report describes the results of an assessment of how well currently available PRA data addresses human risk issues of current concern to NRC. Findings indicate that PRA data could be far more useful in addressing human risk issues with modification of the development process and documentation structure of PRAs. In addition, information from non-PRA sources could be integrated with PRA data to address many other issues. 12 tabs.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6474224
- Report Number(s):
- NUREG/CR-4103; BNL-NUREG-51849; ON: TI86004006
- Country of Publication:
- United States
- Language:
- English
Similar Records
Adequacy of human reliability data for addressing risk reduction issues at commercial nuclear power plants
Integration of human reliability analysis into the probabilistic risk assessment process: Phase 1
Applications of Probabilistic Risk Analysis in Nuclear Criticality Safety Design
Conference
·
Mon Dec 31 23:00:00 EST 1984
·
OSTI ID:6222076
Integration of human reliability analysis into the probabilistic risk assessment process: Phase 1
Conference
·
Mon Oct 01 00:00:00 EDT 1984
·
OSTI ID:6278435
Applications of Probabilistic Risk Analysis in Nuclear Criticality Safety Design
Conference
·
Sun Jun 07 00:00:00 EDT 1992
· Transactions of the American Nuclear Society
·
OSTI ID:6968027
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
HUMAN FACTORS
PERFORMANCE
PERSONNEL
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RELIABILITY
RISK ASSESSMENT
SAFETY
TRAINING
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
HUMAN FACTORS
PERFORMANCE
PERSONNEL
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RELIABILITY
RISK ASSESSMENT
SAFETY
TRAINING
WATER COOLED REACTORS
WATER MODERATED REACTORS