Prioritization of reactor control components susceptible to fire damage as a consequence of aging
- Science and Engineering Associates, Inc., Albuquerque, NM (United States)
- Sandia National Labs., Albuquerque, NM (United States)
The Fire Vulnerability of Aged Electrical Components Test Program is to identify and assess issues of plant aging that could lead to an increase in nuclear power plant risk because of fires. Historical component data and prior analyses are used to prioritize a list of components with respect to aging and fire vulnerability and the consequences of their failure on plant safety systems. The component list emphasizes safety system control components, but excludes cables, large equipment, and devices encompassed in the Equipment Qualification (EQ) program. The test program selected components identified in a utility survey and developed test and fire conditions necessary to maximize the effectiveness of the test program. Fire damage considerations were limited to purely thermal effects.
- Research Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering; Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Science and Engineering Associates, Inc., Albuquerque, NM (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC04-94AL85000
- OSTI ID:
- 10123907
- Report Number(s):
- NUREG/CR-6103; SAND-93-7107; ON: TI94006730; TRN: 94:004554
- Resource Relation:
- Other Information: PBD: Jan 1994
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
POWER REACTORS
AGING
ELECTRICAL EQUIPMENT
FIRE HAZARDS
NUCLEAR POWER PLANTS
210100
210200
220900
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
REACTOR SAFETY