Including test errors in evaluating surveillance test intervals
- 1. Brookhaven National Lab., Upton, NY (United States)
- 2. Univ. Politecnica of Valencia (Spain)
Description
Technical Specifications require surveillance testing to assure that the standby systems important to safety will start and perform their intended functions in the event of plant abnormality. However, as evidenced by operating experience, the surveillance tests may adversely impact safety because of their undesirable side effects, such as initiation of plant transients during testing or wearing-out of safety systems du to testing. This paper first defines the concerns, i.e., the potential adverse effects of surveillance testing, from a risk perspective. Then, the authors present a methodology to evaluate the risk impact of those adverse effects, focusing on two important kinds of adverse impacts of surveillance testing: (1) risk impact of test-caused trips and (2) risk impact of test-caused equipment wear. The quantitative risk methodology is demonstrated with several surveillance tests conducted at boiling water reactors, such as the tests of the main steam isolation valves, the turbine overspeed protection system, and the emergency diesel generators. The authors present the results of the risk-effectiveness evaluation of surveillance test intervals, which compares the adverse risk impact with the beneficial risk impact of testing from potential failure detection, along with insights from sensitivity studies
Additional details
Publishing Information
- Imprint Title
- Proceedings of the US Nuclear Regulatory Commission nineteenth water reactor safety information meeting. Volume 3, Structural engineering; Advanced reactor research; Advanced passive reactors; Human factors research; Human factors issues related to advanced passive LWRs; Thermal hydraulics; Earth sciences
- Imprint Pagination
- 542 p.
- Journal Page Range
- p. 289-300.
- Report number
- NUREG/CP--0119-Vol.3
Conference
- Title
- 19. Nuclear Regulatory Commission (NRC) water reactor safety information meeting.
- Dates
- 28-30 Oct 1991.
- Place
- Bethesda, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24027145
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AVAILABILITY; BWR TYPE REACTORS; ENGINEERED SAFETY SYSTEMS; ERRORS; FAILURES; HUMAN FACTORS; MITIGATION; MONITORING; PWR TYPE REACTORS; RADIATION PROTECTION; REACTOR COMPONENTS; REACTOR SAFETY; RISK ASSESSMENT; SCHEDULES; SENSITIVITY ANALYSIS; SPECIFICATIONS; TRANSIENTS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-911079--Vol.3.