A pilot application of risk-based methods to establish inservice inspection priorities for nuclear components
Creators
- 1. Pacific Northwest Lab., Richland, WA (United States)
Description
As part of the Nondestructive Evaluation Reliability Program, sponsored by the Nuclear Regulatory Commission at the Pacific Northwest Laboratory, a methodology has been developed for establishing inservice inspection priorities for nuclear power plant components. The method uses results of probabilistic risk assessment in combination with the techniques of failure modes and effects analysis to identify and prioritize the most risk-important systems and components for inspection at nuclear power plants. Surry Nuclear Power Station, Unit 1 was selected for demonstrating the methodology. The specific systems selected for analysis were the reactor pressure vessel, the reactor coolant, the low pressure injection including the accumulators, and the auxiliary feedwater. The results included in this paper provide a risk-based ranking of components, which can be used to establish a prioritization of the components and a basis for developing improved inservice inspection plans at nuclear power plants
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0810-6
- Imprint Title
- Fatigue, fracture, and risk 1991
- Imprint Pagination
- 210 p.
- Journal Page Range
- p. 39-46.
Conference
- Title
- 1991 American Society of Mechanical Engineers (ASME) pressure vessels and piping conference.
- Dates
- 23-27 Jun 1991.
- Place
- San Diego, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23054281
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S61: RADIATION PROTECTION AND DOSIMETRY; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AUXILIARY WATER SYSTEMS; COOLANT LOOPS; ENVIRONMENTAL EFFECTS; FAILURE MODE ANALYSIS; IN-SERVICE INSPECTION; PERFORMANCE TESTING; PILOT PLANTS; PRESSURE VESSELS; REACTOR COMPONENTS; RELIABILITY; SAFETY ANALYSIS; US NRC
- Descriptors DEC
- AUXILIARY SYSTEMS; CONTAINERS; FUNCTIONAL MODELS; INSPECTION; NATIONAL ORGANIZATIONS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; TESTING; US ORGANIZATIONS
Optional Information
- Secondary number(s)
- CONF-910602--.