Risk-based selection of SSCs at Peach Bottom
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:5818678
- Philadelphia Electric Company, Wayne (United States)
The purpose of identifying risk significant systems, structures, and components (SSCS) that are within the scope of the maintenance rule is to bring a higher level of attention to a subset of those SSCS. These risk-significant SSCs will have specific performance criteria established for them, and failure to meet this performance criteria will result in establishing goals to ensure the necessary improvement in performance. The Peach Bottom individual plant examination (IPE) results were used to provide insights for the verification of proposed probabilistic risk assessment (PRA) methods set forth in the Industry Maintenance Guidelines for Implementation of the Maintenance Rule. The objective of reviewing the methods for selection of SSCs that are considered risk significant was to ensure the methods used are logical, reproducible, and can be consistently applied.
- OSTI ID:
- 5818678
- Report Number(s):
- CONF-930601--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 68
- 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
BWR TYPE REACTORS
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
MAINTENANCE
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PEACH BOTTOM-1 REACTOR
PEACH BOTTOM-2 REACTOR
PEACH BOTTOM-3 REACTOR
POWER PLANTS
POWER REACTORS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RELIABILITY
RISK ASSESSMENT
SAFETY
THERMAL POWER PLANTS
THERMAL REACTORS
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
BWR TYPE REACTORS
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
MAINTENANCE
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PEACH BOTTOM-1 REACTOR
PEACH BOTTOM-2 REACTOR
PEACH BOTTOM-3 REACTOR
POWER PLANTS
POWER REACTORS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RELIABILITY
RISK ASSESSMENT
SAFETY
THERMAL POWER PLANTS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS