Published April 1992 | Version v1
Report

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).

Optional Information

Secondary number(s)
CONF-911079--Vol.3.