Age-dependent risk quantification using standard maintenance records

Conference · Sun Jan 01 04:00:00 EST 1989

DOI:https://doi.org/10.1007/978-1-4899-2370-7_17· OSTI ID:6990548

Roesener, W. S.; Wolford, A. J.; Atwood, C. L.

The risk associated with the operation of many individual nuclear power plants has been calculated using Probabilistic Risk Assessment (PRA) techniques. To date, PRA calculations have used time-averaged unreliabilities and unavailabilities as inputs such that the calculated risks are a time-average and say nothing of the risk trends. The calculation of an age-dependent risk is a fairly simple matter given the age-dependent inputs. The development of valid age-dependents inputs is not such a simple matter. It involves the reduction of large masses of information, which were not recorded for the purposes of PRA, into failure time-histories, and the representation of these time-histories by a model. The results must then be tested to check certain assumptions that are made when the model is applied to the data. The specific methodology developed for the reduction of the information and the application and testing of the model is outlined in a stepwise fashion in this paper. Results of the application of the methodology to the Maintenance Records from the Auxiliary Feedwater (AFW) System of an older Pressurized Water Reactor (PWR) are used throughout the paper to demonstrate the methodology. In addition, a very brief discussion of the AFW system is presented to allow better understanding of the application. 6 refs., 7 figs., 4 tabs.

• Research Organization: EG and G Idaho, Inc., Idaho Falls, ID (USA)
• Sponsoring Organization: NRC
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6990548
• Report Number(s): EGG-M-89191; CONF-8910363--1; ON: DE90007021
• Country of Publication: United States
• Language: English

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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
AGING
AUXILIARY SYSTEMS
BOILERS
COOLING SYSTEMS
DATA BASE MANAGEMENT
DIFFERENTIAL EQUATIONS
ENERGY SYSTEMS
EQUATIONS
FAILURE MODE ANALYSIS
FEEDWATER
HEAT EXCHANGERS
HYDROGEN COMPOUNDS
MACHINERY
MAINTENANCE
MANAGEMENT
MATHEMATICAL MODELS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
OPERATION
OXYGEN COMPOUNDS
PARTIAL DIFFERENTIAL EQUATIONS
POISSON EQUATION
POWER PLANTS
PUMPS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR MAINTENANCE
REACTOR OPERATION
REACTORS
RECOMMENDATIONS
RISK ASSESSMENT
SERVICE LIFE
STATISTICAL MODELS
STEAM GENERATORS
STEAM TURBINES
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL POWER PLANTS
TURBINES
TURBOMACHINERY
VAPOR GENERATORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS