The effects of aging on BWR core isolation cooling systems
- Brookhaven National Lab., Upton, NY (United States)
A study was performed to assess the effects of aging on the Reactor Core Isolation Cooling (RCIC) system in commercial Boiling Water Reactors (BWRs). This study is part of the Nuclear Plant Aging Research (NPAR) program sponsored by the US Nuclear Regulatory Commission. The objectives of this program are to provide an understanding of the aging process and how it affects plant safety so that it can be properly managed. This is one of a number of studies performed under the NPAR program which provide a technical basis for the identification and evaluation of degradation caused by age. The failure data from national databases, as well as plant specific data were reviewed and analyzed to understand the effects of aging on the RCIC system. This analysis identified important components that should receive the highest priority in terms of aging management. The aging characterization provided information on the effects of aging on component failure frequency, failure modes, and failures causes. Current inspection, surveillance, and monitoring practices were also reviewed.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering; Brookhaven National Lab., Upton, NY (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 10192341
- Report Number(s):
- NUREG/CR--6087; BNL-NUREG--52390; ON: TI95002269
- Country of Publication:
- United States
- Language:
- English
Similar Records
Aging assessment of Westinghouse PWR and General Electric BWR containment isolation functions
The effects of aging on Boiling Water Reactor core isolation cooling system
The effects of age on nuclear power plant containment cooling systems
Technical Report
·
Thu Feb 29 23:00:00 EST 1996
·
OSTI ID:211319
The effects of aging on Boiling Water Reactor core isolation cooling system
Conference
·
Wed Jun 01 00:00:00 EDT 1994
·
OSTI ID:10157066
The effects of age on nuclear power plant containment cooling systems
Technical Report
·
Thu Mar 31 23:00:00 EST 1994
·
OSTI ID:10147600
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
AGING
BWR TYPE REACTORS
DATA ANALYSIS
DESIGN
FAILURES
NUCLEAR POWER PLANTS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
RCIC SYSTEMS
REACTOR MAINTENANCE
REACTOR SAFETY
RELIABILITY
SERVICE LIFE
210100
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
AGING
BWR TYPE REACTORS
DATA ANALYSIS
DESIGN
FAILURES
NUCLEAR POWER PLANTS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
RCIC SYSTEMS
REACTOR MAINTENANCE
REACTOR SAFETY
RELIABILITY
SERVICE LIFE