Comparison and application of quantitative human reliability analysis methods for the risk methods integration and evaluation program (RMIEP): Final report
Technical Report
·
OSTI ID:6766694
This report documents a comparison of human reliability analysis (HRA) techniques using data that resulted from the Risk Methods Integration and Evaluation Program (RMIEP) sponsored by the US Nuclear Regulatory Commission. A literature search identified 20 HRA methods for consideration. Twelve methods were evaluated as appropriate for use in probabilistic risk assessment (PRA) for nuclear power plants (NPPs) by using a criteria set developed for that purpose. Data were collected at a commercial NPP with operators responding to walkthroughs of four severe accident scenarios. An HRA systems analysis was also performed for the plant. The data were used in the application and quantitative comparison of selected HRA methods. Qualitative comparisons of the 12 methods are provided via attribute descriptions and ratings of their utility in an HRA selection tool designed to help analysts select appropriate HRA methods based on their goals and available resources. An assessment of the current state of the art of HRA for PRA is presented as well as recommendations for the future use of HRA in PRA.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research; EG and G Idaho, Inc., Idaho Falls (USA); Battelle Columbus Div., OH (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6766694
- Report Number(s):
- NUREG/CR-4835; EGG-2485; BMI-2159; ON: TI89006045
- Country of Publication:
- United States
- Language:
- English
Similar Records
The change in risk due to upgrade to a digital reactor protection system
Modeling and Quantification of Team Performance in Human Reliability Analysis for Probabilistic Risk Assessment
Multidisciplinary framework for human reliability analysis with an application to errors of commission and dependencies
Conference
·
Sat Oct 01 00:00:00 EDT 1994
·
OSTI ID:54600
Modeling and Quantification of Team Performance in Human Reliability Analysis for Probabilistic Risk Assessment
Conference
·
Sun Jun 01 00:00:00 EDT 2014
·
OSTI ID:1149011
Multidisciplinary framework for human reliability analysis with an application to errors of commission and dependencies
Technical Report
·
Tue Aug 01 00:00:00 EDT 1995
·
OSTI ID:106594
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
COMPUTERIZED SIMULATION
DATA ACQUISITION
DATA ANALYSIS
ERRORS
HUMAN FACTORS
LA SALLE COUNTY-1 REACTOR
LA SALLE COUNTY-2 REACTOR
POWER REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RELIABILITY
RISK ASSESSMENT
SAFETY
SIMULATION
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
COMPUTERIZED SIMULATION
DATA ACQUISITION
DATA ANALYSIS
ERRORS
HUMAN FACTORS
LA SALLE COUNTY-1 REACTOR
LA SALLE COUNTY-2 REACTOR
POWER REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RELIABILITY
RISK ASSESSMENT
SAFETY
SIMULATION
WATER COOLED REACTORS
WATER MODERATED REACTORS