Probabilistic evaluation of main coolant pipe break indirectly induced by earthquakes: Savannah River Project L and P Reactors
- Impell Corp., Mission Viejo, CA (USA)
A probabilistic evaluation of seismically-induced indirect pipe break for the Savannah River Project (SRP) L- and P-Reactor main coolant (process water) piping has been conducted. Seismically-induced indirect pipe break can result primarily from: (1) failure of the anchorage of one or more of the components to which the pipe is anchored; or (2) failure of the pipe due to collapse of the structure. The potential for both types of seismically-induced indirect failures was identified during a seismic walkdown of the main coolant piping. This work involved: (1) identifying components or structures whose failure could result in pipe failure; (2) developing seismic capacities or fragilities of these components; (3) combining component fragilities to develop plant damage state fragilities; and (4) convolving the plant seismic fragilities with a probabilistic seismic hazard estimate for the site in order to obtain estimates of seismic risk in terms of annual probability of seismic-induced indirect pipe break. 6 refs., 5 figs., 2 tabs.
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (USA)
- Sponsoring Organization:
- DOE/DP
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 5569242
- Report Number(s):
- WSRC-RP-89-25; CONF-8910192-11; ON: DE90001374
- Resource Relation:
- Conference: 2. DOE natural phenomena hazards mitigation conference, Knoxville, TN (USA), 3-5 Oct 1989
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
58 GEOSCIENCES
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
L REACTOR
REACTOR COOLING SYSTEMS
SEISMIC EFFECTS
P REACTOR
FORECASTING
FORESTRY
GEOLOGIC FAULTS
GEOMETRY
HEAT EXCHANGERS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MATHEMATICAL MODELS
PIPES
PLANTS
PUMPS
REACTOR COMPONENTS
REACTOR SAFETY
RISK ASSESSMENT
STRESS ANALYSIS
SYSTEM FAILURE ANALYSIS
TANKS
VALVES
ACCIDENTS
CONTAINERS
CONTROL EQUIPMENT
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
EQUIPMENT
FLOW REGULATORS
FLUID MECHANICS
GEOLOGIC FRACTURES
GEOLOGIC STRUCTURES
HEAVY WATER MODERATED REACTORS
MATHEMATICS
MECHANICS
PRODUCTION REACTORS
REACTOR ACCIDENTS
REACTORS
SAFETY
SPECIAL PRODUCTION REACTORS
SYSTEMS ANALYSIS
220900* - Nuclear Reactor Technology- Reactor Safety
580201 - Geophysics- Seismology & Tectonics- (1980-1989)
220700 - Nuclear Reactor Technology- Plutonium & Isotope Production Reactors