Analysis of standby and demand stress failures modes
Creators
- 1. Science Applications International Corp., McLean, VA (United States)
Description
This report describes work to develop and demonstrates methods for partitioning standby component failure modes into causes that fail the component while it is in standby, and when it changes state, during testing or from other demands. Failure of the component from standby stresses is modeled using a model that explicitly contains the length of the test interval. Failure of the component from demand stresses such as vibration, wind, etc., is modeled using the probability of failure on demand model. Misuse of these models in PRAS, could lead to PRAs that, give misleading results, or that are more useful for decision purposes. A method was developed and demonstrated to partition standby/demand stresses. The method was used on the work maintenance records from two Nuclear Power Plants (NPPs) to estimate reliability parameters for Motor Operated Valves And Emergency Diesel Generators (EDGs)
Availability note (English)
MF available from INIS under the Report Number; OSTI as TI93003214; NTIS; INIS; GPO.
Files
Additional details
Additional titles
- Subtitle (English)
- Methodology and applications to EDGs and MOVs
Publishing Information
- Imprint Pagination
- 117 p.
- Report number
- NUREG/CR--5823
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24036051
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- COMPUTER CODES; ELECTRIC GENERATORS; FAILURES; GRAND GULF-1 REACTOR; GRAND GULF-2 REACTOR; MAINTENANCE; MONTE CARLO METHOD; PROBABILITY; REACTOR COMPONENTS; RELIABILITY; RISK ASSESSMENT; SURRY-1 REACTOR; SURRY-2 REACTOR; SURRY-3 REACTOR; SURRY-4 REACTOR; TESTING; VALVES
- Descriptors DEC
- BWR TYPE REACTORS; CALCULATION METHODS; CONTROL EQUIPMENT; ELECTRICAL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- SAIC--87-029.