Experience-based classical RCM at Ginna
Conference
·
· Transactions of the American Nuclear Society; (USA)
OSTI ID:5433975
Rochester Gas Electric Company began a comprehensive maintenance improvement program for its Ginna station in early 1985. The program includes all activities and functions related to maintenance and has as its focal point, a plantwide, experience-based, classical reliability-centered maintenance (RCM) program. Although performance of the now nearly 20-year-old plant has been outstanding, aging equipment and rising maintenance burdens pose a serious threat to continued exemplary performance. Ginna's RCM program began with a carefully structured system selection process to focus project resources on those systems most important to continued safe and economical operation. The process began with definition of tangible and intangible system attributes and weighting factors. Each system was then rated separately in a two-step process designed to reduce subjective bias. Twenty systems were selected for study. Additional systems may be added at a later date. The analytical approaches discussed address the identification of failure modes and effects, criticality, and development of RCM tasks to prevent failure for most common system elements. In reality, the depth and focus of the analysis is usually limited to short-term degradation mechanisms or those already experienced, either at Ginna or somewhere else in the industry. To completely address all potential failure mechanisms, additional evaluations are performed specifically for long-term age-related degradation in critical components.
- OSTI ID:
- 5433975
- Report Number(s):
- CONF-881011--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 57
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
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Light-Water Moderated
Nonboiling Water Cooled
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ECONOMICS
ENRICHED URANIUM REACTORS
EPRI
FAILURE MODE ANALYSIS
FAILURES
GINNA-1 REACTOR
INFORMATION SYSTEMS
INSPECTION
MAINTENANCE
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MATERIALS
MODIFICATIONS
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POWER REACTORS
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PWR TYPE REACTORS
REACTOR COMPONENTS
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SYSTEM FAILURE ANALYSIS
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210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
AGING
DESIGN
ECONOMICS
ENRICHED URANIUM REACTORS
EPRI
FAILURE MODE ANALYSIS
FAILURES
GINNA-1 REACTOR
INFORMATION SYSTEMS
INSPECTION
MAINTENANCE
MANAGEMENT
MATERIALS
MODIFICATIONS
PERFORMANCE
POWER REACTORS
PROGRAM MANAGEMENT
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR MAINTENANCE
REACTOR MATERIALS
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RELIABILITY
SERVICE LIFE
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TESTING
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS