Seismic fragility of nuclear power plant components (Phase II)

Technical Report · Thu Feb 01 00:00:00 EST 1990

DOI:https://doi.org/10.2172/7252519· OSTI ID:7252519

Bandyopadhyay, K K; Hofmayer, C H; Kassir, M K; Pepper, S E ^[1]

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1. Brookhaven National Lab., Upton, NY (USA)

As part of the Component Fragility Program which was initiated in FY 1985, three additional equipment classes have been evaluated. This report contains the fragility results and discussions on these equipment classes which are switchgear, I and C panels and relays. Both low and medium voltage switchgear assemblies have been considered and a separate fragility estimate for each type is provided. Test data on cabinets from the nuclear instrumentation/neutron monitoring system, plant/process protection system, solid state protective system and engineered safeguards test system comprise the BNL data base for I and C panels (NSSS). Fragility levels have been determined for various failure modes of switchgear and I C panels, and the deterministic results are presented in terms of test response spectra. In addition, the test data have been evaluated for estimating the respective probabilistic fragility levels which are expressed in terms of a median value, an uncertainty coefficient, a randomness coefficient and an HCLPF value. Due to a wide variation of relay design and the fragility level, a generic fragility level cannot be established for relays. 7 refs., 13 figs., 12 tabs.

• Research Organization: US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering; Brookhaven National Lab. (BNL), Upton, NY (United States)
• Sponsoring Organization: USNRC
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 7252519
• Report Number(s): NUREG/CR-4659-Vol.3; BNL-NUREG-52007-Vol.3; ON: TI90007785; TRN: 90-008632
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
NUCLEAR POWER PLANTS
REACTOR CONTROL SYSTEMS
REACTOR INSTRUMENTATION
REACTOR COMPONENTS
SEISMIC EFFECTS
DESIGN
RELAYS
SWITCHES
ACCELERATION
DAMPING
DATA BASE MANAGEMENT
ELECTRICAL EQUIPMENT
ENGINEERED SAFETY SYSTEMS
FAILURE MODE ANALYSIS
FRACTURE PROPERTIES
FREQUENCY ANALYSIS
MECHANICAL VIBRATIONS
MODIFICATIONS
PERFORMANCE TESTING
PROBABILISTIC ESTIMATION
REACTOR OPERATION
REACTOR SAFETY
RECOMMENDATIONS
RESPONSE FUNCTIONS
RISK ASSESSMENT
SENSITIVITY ANALYSIS
VARIATIONS
VULNERABILITY
CONTROL SYSTEMS
EQUIPMENT
FUNCTIONS
MANAGEMENT
MECHANICAL PROPERTIES
NUCLEAR FACILITIES
OPERATION
POWER PLANTS
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TESTING
THERMAL POWER PLANTS
220900* - Nuclear Reactor Technology- Reactor Safety
220200 - Nuclear Reactor Technology- Components & Accessories
990200 - Mathematics & Computers