PRA Applications Program for inspection at Arkansas Nuclear One, Unit 1
Technical Report
·
OSTI ID:5155156
The level one PRA for ANO-1 has been analyzed to identify plant systems and components important to minimizing public risk, as measured by system contributions to plant core melt frequency, and to identify the primary failure modes of these components. This information has been tabulated, and correlated with inspection modules from the NRC Inspection and Enforcement Manual. The report presents a series of tables, organized by system and prioritized by risk importance, which identify components associated with 98% of the inspectable risk due to plant operation. The systems addressed, in descending order of risk importance, are: DC Power, High Pressure Injection, Low Pressure Injection, Service Water, Reactor Protection, Emergency Feedwater, Vital AC Power, Safety Relief Valves, Main Feedwater, and Emergency Feedwater Initiation and Control. This ranking is based on the Fussel-Vesely measure of risk importance, i.e., the fraction of the total core melt frequency which involves failures of the system of interest.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 5155156
- Report Number(s):
- NUREG/CR-5058; PNL-6394; ON: TI88007566
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
210700 -- Nuclear Power Plants-- Regulation & Licensing
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ARKANSAS-1 REACTOR
CONTROL SYSTEMS
COOLING SYSTEMS
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURES
FAULT TREE ANALYSIS
FEEDWATER
HYDROGEN COMPOUNDS
INSPECTION
LOSS OF COOLANT
MAINTENANCE
MELTDOWN
OPERATION
OXYGEN COMPOUNDS
POWER REACTORS
POWER SYSTEMS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR OPERATION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
SURVEILLANCE
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
VALUES
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
210700 -- Nuclear Power Plants-- Regulation & Licensing
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ARKANSAS-1 REACTOR
CONTROL SYSTEMS
COOLING SYSTEMS
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURES
FAULT TREE ANALYSIS
FEEDWATER
HYDROGEN COMPOUNDS
INSPECTION
LOSS OF COOLANT
MAINTENANCE
MELTDOWN
OPERATION
OXYGEN COMPOUNDS
POWER REACTORS
POWER SYSTEMS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR OPERATION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
SURVEILLANCE
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
VALUES
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS