A technique of including the effect of aging of passive components in probabilistic risk assessments
Creators
- 1. Idaho National Engineering Lab., Idaho Falls (United States)
- 2. Nuclear Regulatory Commission, Washington, DC (United States)
Description
The probabilistic risk assessments (PRAS) being developed at most nuclear power plants to calculate the risk of core damage generally focus on the possible failure of active components. The possible failure of passive components is given little consideration. We are developing methods for selecting risk-significant passive components and including them in PRAS. These methods provide effective ways to prioritize passive components for inspection, and where inspection reveals aging damage, mitigation or repair can be employed to reduce the likelihood of component failure. We demonstrated a method by selecting a weld in the auxiliary feedwater (AFW) system, basing our selection on expert judgement of the likelihood of failure and on an estimate of the consequence of component failure to plant safety. We then modified and used the Piping Reliability Analysis Including Seismic Events (PRAISE) computer code to perform a probabilistic structural analysis to calculate the probability that crack growth due to aging would cause the weld to fail. The PRAISE code was modified to include the effects of changing design material properties with age and changing stress cycles. The calculation included the effects of mechanical loads and thermal transients typical of the service loads for this piping design and the effects of thermal cycling caused by a leaking check valve. However, this particular calculation showed little change in low component failure probability and plant risk for 48 years of service. However, sensitivity studies showed that if the probability of component failure is high, the effect on plant risk is significant. The success of this demonstration shows that this method could be applied to nuclear power plants. The demonstration showed the method is too involved (PRAISE takes a long time to perform the calculation and the input information is extensive) for handling a large number of passive components and therefore simpler methods are needed
Additional details
Publishing Information
- Imprint Title
- Proceedings of the Aging Research Information Conference
- Imprint Pagination
- 556 p.
- Journal Page Range
- p. 114-138.
- Report number
- NUREG/CP--0122-Vol.1
Conference
- Title
- Aging research information conference.
- Dates
- 24-27 Mar 1992.
- Place
- Rockville, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24051508
- Subject category
- S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; FAILURES; FATIGUE; NUCLEAR POWER PLANTS; P CODES; REACTOR COMPONENTS; RISK ASSESSMENT; SAFETY ANALYSIS; STRUCTURAL MODELS; WELDED JOINTS
- Descriptors DEC
- COMPUTER CODES; JOINTS; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS
Optional Information
- Contract/Grant/Project number
- Contract AC07-76ID01570
- Secondary number(s)
- CONF-920375--Vol.1.