The effects of aging in component cooling water systems and the implications for life extension

Conference · Tue Jan 01 00:00:00 EST 1991

OSTI ID:5905857

Lofaro, R; Taylor, J ^[1]; Aggarwal, S ^[2]

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1. Brookhaven National Lab., Upton, NY (USA)
2. Nuclear Regulatory Commission, Washington, DC (USA)

To help assess the effects of aging on safety and reliability, an aging and life extension analysis of component cooling water (CCW) systems in pressurized water reactors (PWRs) has been performed as part of the Nuclear Plant Aging Research (NPAR) program. The NPAR program is sponsored by the NRC Office of Research to provide a technical basis for understanding and managing the effects of aging degradation in nuclear plant applications. The objectives of the two phase CCW system analysis are to characterize the effects of aging, and identify effective methods of detecting and mitigating aging degradation. The effects of aging in CCW systems were characterized by collecting and analyzing failure data from various national databases. The dominant failure causes and mechanisms were identified along with the components most frequently failed. Time-dependent component failure rates were calculated and used to evaluate the effect of aging on system unavailability in later years. Inspection, surveillance, monitoring, and maintenance practices currently in use were compiled from plant and industry sources. These practices were correlated with various aging mechanisms and generic listings were developed for two of the most commonly failed CCW components. 2 refs., 6 figs., 4 tabs.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• Sponsoring Organization: USNRC; Nuclear Regulatory Commission, Washington, DC (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 5905857
• Report Number(s): BNL-NUREG-45736; CONF-910602-9; ON: DE91008109; TRN: 91-010375
• Resource Relation: Conference: American Society of Mechanical Engineers (ASME) pressure vessels and piping conference, San Diego, CA (USA), 23-27 Jun 1991
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
AUXILIARY WATER SYSTEMS
AGING
PWR TYPE REACTORS
REACTOR SAFETY
AVAILABILITY
DATA BASE MANAGEMENT
DESIGN
FAILURES
HEAT EXCHANGERS
INSPECTION
MITIGATION
PRIMARY COOLANT CIRCUITS
PUMPS
REACTOR MAINTENANCE
REACTOR MONITORING SYSTEMS
RELIABILITY
RHR SYSTEMS
SAFETY INJECTION
SEALS
SERVICE LIFE
SURVEILLANCE
TIME DEPENDENCE
AUXILIARY SYSTEMS
COOLING SYSTEMS
ENERGY SYSTEMS
MAINTENANCE
MANAGEMENT
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled