USNRC Regulatory Perspective on Unanticipated Thermal Fatigue in LWR Piping
Creators
- 1. U.S. Nuclear Regulatory Commission, Mail Stop T-10 E10, 20555 Washington D.C., Washington, DC (United States)
- 2. U.S. Nuclear Regulatory Commission, OWFN, M.S. 07 E23, 20555 Washington D.C., Washington, DC (United States)
Description
The regulatory response of the United States Nuclear Regulatory Commission (USNRC) to unanticipated thermal fatigue in light water reactor (LWR) primary piping systems is based on a long history of such events in both US and foreign commercial nuclear plants. This history includes operational conditions leading to surge line stratification, and cracks in feedwater nozzles, high pressure safety injection lines, and residual heat removal lines. US nuclear power plant experience with thermal fatigue has prompted two studies by the USNRC Office for Analysis and Evaluation of Operational Data (AEOD). In addition, the USNRC has provided generic communications to its licensees addressing problems arising from thermal stresses and stratification. Thermal fatigue in general has also been examined by the NRC as a generic safety issue. All these evaluations have alerted the staff to concerns over the broader implications of unanticipated thermal fatigue in piping, including potential problems with plant conditions not being consistent with licensing basis design and inspection commitments. Of particular concern are those problems arising from unanticipated thermal fatigue in un-isolable piping connected to the reactor coolant system. Current USNRC acceptance criteria of licensee actions are based on the USNRC's mission to preserve the public health and safety. (authors)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the specialists meeting on experience with thermal fatigue in LWR piping caused by mixing and stratification
- Imprint Pagination
- 567 p.
- Journal Page Range
- p. 41-72
- Report number
- NEA-CSNI-R--1998-8
Conference
- Title
- Specialists meeting on experience with thermal fatigue in LWR piping caused by mixing and stratification
- Dates
- 8-10 Jun 1998
- Place
- Paris (France)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 43095488
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACKS; LEAKS; NUCLEAR POWER PLANTS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR MAINTENANCE; REACTOR MATERIALS; REACTOR OPERATION; RECOMMENDATIONS; RISK ASSESSMENT; SAFETY ANALYSIS; SAFETY ENGINEERING; SYSTEM FAILURE ANALYSIS; THERMAL FATIGUE; THERMAL HYDRAULICS; THERMAL STRESSES; US NRC; USA; WATER COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; DEVELOPED COUNTRIES; ENERGY SYSTEMS; ENGINEERING; FATIGUE; FLUID MECHANICS; HYDRAULICS; MAINTENANCE; MATERIALS; MECHANICAL PROPERTIES; MECHANICS; NATIONAL ORGANIZATIONS; NORTH AMERICA; NUCLEAR FACILITIES; OPERATION; POWER PLANTS; REACTOR COMPONENTS; REACTORS; STRESSES; SYSTEMS ANALYSIS; THERMAL POWER PLANTS; US ORGANIZATIONS