Simulation of maintenance effectiveness in repairable systems to control risk due to aging
Conference
·
OSTI ID:6796864
Time- or cyclic-dependent degradation (aging) processes such as wear, corrosion, and fatigue have caused problems at some of the US reactors. This paper presents a methodology to develop optimum maintenance programs that would help control aging-related risks. The study addresses the predictive behavior of systems containing repairable components as represented in current probabilistic risk assessment (PRA) models. The system model chosen for the study is the Draft NUREG-1150 Surry auxiliary feedwater (AFW) system. The simulation results provide an indication of the periodicity at which the aging effects must be corrected to maintain the system failure probability at or below the calculated levels. When maintenance is allowed to periodically correct the effects of aging, the system failure probability is essentially constant over 60 years. Also, results indicate that the system unreliability is not linearly related to the periodicity of aging correction. Therefore, a plant maintenance program would have significant latitude in developing the desired maintenance periodicity limits. In fact, the calculated values for component maintenance periodicity are of such time intervals that aging control can easily be accommodated by a plant maintenance program. 5 refs., 4 figs., 3 tabs.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6796864
- Report Number(s):
- EGG-M-88101; CONF-880824-2; ON: DE89005281
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
AGING
AUXILIARY SYSTEMS
CHEMICAL REACTIONS
CORROSION
ENRICHED URANIUM REACTORS
FAILURES
FATIGUE
FEEDWATER
HYDROGEN COMPOUNDS
MAINTENANCE
MECHANICAL PROPERTIES
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
OXYGEN COMPOUNDS
POWER PLANTS
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RELIABILITY
RISK ASSESSMENT
SAFETY
SURRY-1 REACTOR
SURRY-2 REACTOR
SURRY-3 REACTOR
SURRY-4 REACTOR
THERMAL POWER PLANTS
THERMAL REACTORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
WEAR
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
AGING
AUXILIARY SYSTEMS
CHEMICAL REACTIONS
CORROSION
ENRICHED URANIUM REACTORS
FAILURES
FATIGUE
FEEDWATER
HYDROGEN COMPOUNDS
MAINTENANCE
MECHANICAL PROPERTIES
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
OXYGEN COMPOUNDS
POWER PLANTS
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RELIABILITY
RISK ASSESSMENT
SAFETY
SURRY-1 REACTOR
SURRY-2 REACTOR
SURRY-3 REACTOR
SURRY-4 REACTOR
THERMAL POWER PLANTS
THERMAL REACTORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
WEAR