Nuclear plant aging research on high pressure injection systems
Technical Report
·
OSTI ID:5740478
- EG and G Idaho, Inc., Idaho Falls, ID (USA)
This report represents the results of a review of light water reactor High Pressure Injection System (HPIS) operating experiences reported in the Nuclear Power Experience Data Base, Licensee Event Reports (LER)s, Nuclear Plant Reliability Data System, and plant records. The purpose is to evaluate the potential significance of aging as a contributor to degradation of the High Pressure Injection System. Tables are presented that show the percentage of events for HPIS classified by cause, component, and subcomponents for PWRs. A representative Babcock and Wilcox plant was selected for detailed study. The US Nuclear Regulatory Commission's Nuclear Plant Aging Research guidelines were followed in performing the detailed study that identifies materials susceptible to aging, stressors, environmental factors, and failure modes for the HPIS. In addition to the engineering evaluation, the components that contributed to system unavailability were determined and the aging contribution to HPIS unavailability was evaluated. The unavailability assessment utilized an existing probabilistic risk assessment (PRA), the linear aging model, and generic failure data. 37 refs., 18 figs., 70 tabs.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering; EG and G Idaho, Inc., Idaho Falls, ID (USA)
- Sponsoring Organization:
- NRC
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5740478
- Report Number(s):
- NUREG/CR-4967; EGG--2514; ON: TI89017668
- Country of Publication:
- United States
- Language:
- English
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Light-Water Moderated
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Light-Water Moderated
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AGING
AVAILABILITY
BWR TYPE REACTORS
CONTROL EQUIPMENT
CONTROL SYSTEMS
COOLING SYSTEMS
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
EQUIPMENT
FAILURE MODE ANALYSIS
FLOW REGULATORS
FLUID MECHANICS
HEAT TRANSFER
HIGH PRESSURE COOLANT INJECTION
HYDRAULICS
LOSS OF COOLANT
MAINTENANCE
MECHANICS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
PUMPS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR COOLING SYSTEMS
REACTOR INSTRUMENTATION
REACTOR MAINTENANCE
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
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THERMAL POWER PLANTS
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