Risk sensitivity to human error in the LaSalle PRA (probabilistic risk assessment)
- Brookhaven National Lab., Upton, NY (USA)
A sensitivity evaluation was conducted to assess the impact of human errors on the internal event risk parameters in the LaSalle plant. The results provide the variation in the risk parameters, namely, core melt frequency and accident sequence frequencies, due to hypothetical changes in human error probabilities. Also provided are insights derived from the results, which highlight important areas for concentration of risk limitation efforts associated with human performance. 14 refs., 28 figs., 9 tabs.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Div. of Radiation Protection and Emergency Preparedness; Brookhaven National Lab., Upton, NY (USA)
- Sponsoring Organization:
- NRC
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 7109380
- Report Number(s):
- NUREG/CR-5527; BNL-NUREG--52228; ON: TI90008681
- Country of Publication:
- United States
- Language:
- English
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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
CONTROL EQUIPMENT
DATA BASE MANAGEMENT
DATA PROCESSING
EMERGENCY PLANS
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FEEDWATER
FLOW REGULATORS
FREQUENCY ANALYSIS
HUMAN FACTORS
HYDROGEN COMPOUNDS
LA SALLE COUNTY-1 REACTOR
LA SALLE COUNTY-2 REACTOR
MAINTENANCE
MAN-MACHINE SYSTEMS
MANAGEMENT
MATHEMATICAL MODELS
MITIGATION
OPERATION
OXYGEN COMPOUNDS
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POWER REACTORS
PROBABILITY
PROCESSING
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR MAINTENANCE
REACTOR OPERATION
REACTOR OPERATORS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
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STATISTICAL MODELS
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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
CONTROL EQUIPMENT
DATA BASE MANAGEMENT
DATA PROCESSING
EMERGENCY PLANS
EQUIPMENT
ERRORS
FEEDWATER
FLOW REGULATORS
FREQUENCY ANALYSIS
HUMAN FACTORS
HYDROGEN COMPOUNDS
LA SALLE COUNTY-1 REACTOR
LA SALLE COUNTY-2 REACTOR
MAINTENANCE
MAN-MACHINE SYSTEMS
MANAGEMENT
MATHEMATICAL MODELS
MITIGATION
OPERATION
OXYGEN COMPOUNDS
PERSONNEL
POWER REACTORS
PROBABILITY
PROCESSING
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR MAINTENANCE
REACTOR OPERATION
REACTOR OPERATORS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
SENSITIVITY ANALYSIS
STATISTICAL MODELS
TASK SCHEDULING
TRANSIENTS
VALVES
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS