Risk-based configuration control system: Analysis and approaches
- 1. Brookhaven National Lab., Upton, NY (USA)
Description
This paper presents an evaluation of the configuration risks associated with the operation of a nuclear power plant and the approaches to control these risks using risk-based configuration control considerations. In that context, the actual and maximum potential configuration risks at a plant are analyzed and the alternative types criteria for a risk-based configuration control systems are described. The risk-based configuration calculations which are studied here focus on the core-melt frequency impacts from given plant configurations. By calculating the core-melt frequency for given configurations, the configurations which cause large core-melt frequency increases can be identified and controlled. The duration time in which the configuration can exist can then be limited or the core-melt frequency level associated with the configuration can be reduced by various actions. Furthermore, maintenances and tests can be scheduled to avoid the configurations which cause large core-melt frequency increases. Present technical specifications do not control many of these configurations which can cause large core-melt frequency increases but instead focus on many risk-unimportant allowed outage times. Hence, risk-based configuration management can be effectively used to reduce core-melt frequency associated risks at a plant and at the same time can provide flexibility in plant operation. The alternative strategies for controlling the core-melt frequency and other risk contributions include: (1) controlling the increased risk level which is associated with the configuration; (2) controlling the individual configuration risk which is associated with a given duration of a configuration; (3) controlling the time period configuration risk from configurations which occur in a time period
Additional details
Publishing Information
- Imprint Title
- Transactions of the seventeenth water reactor safety information meeting
- Imprint Pagination
- 186 p.
- Journal Page Range
- p. 10.11-10.12.
- Report number
- NUREG/CP--0104
Conference
- Title
- 17. water reactor safety information meeting.
- Dates
- 23-25 Oct 1989.
- Place
- Rockville, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22051913
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONFIGURATION CONTROL; EVALUATION; MAINTENANCE; NUCLEAR POWER PLANTS; REACTOR ACCIDENTS; REACTOR CONTROL SYSTEMS; REACTOR OPERATION; REACTOR SAFETY; RISK ASSESSMENT
- Descriptors DEC
- ACCIDENTS; CONTROL SYSTEMS; NUCLEAR FACILITIES; OPERATION; POWER PLANTS; SAFETY; THERMAL POWER PLANTS
Optional Information
- Secondary number(s)
- CONF-8910222--Summs.