Aging assessment of Westinghouse PWR and General Electric BWR containment isolation functions [electronic resource].
- Rockville, Md. : U.S. Nuclear Regulatory Commission, 1996.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- 152 pages : digital, PDF file
- Additional Creators:
- U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
United States. Department of Energy. Office of Scientific and Technical Information
- A study was performed to assess the effects of aging on the Containment Isolation (CI) functions of Westinghouse Pressurized Water Reactors and General Electric Boiling Water Reactors. This study is part of the Nuclear Plant Aging Research (NPAR) program, sponsored by the U.S. Nuclear Regulatory Commission. The objectives of this program are to provide an understanding of the aging process and how it affects plant safety so that it can be properly managed. This is one of a number of studies performed under the NPAR program which provide a technical basis for the identification and evaluation of degradation caused by age. Failure data from two national databases, Nuclear Plant Reliability Data System (NPRDS) and Licensee Event Reports (LERs), as well as plant specific data were reviewed and analyzed to understand the effects of aging on the CI functions. This study provided information on the effects of aging on component failure frequency, failure modes, and failure causes. Current inspection, surveillance, and monitoring practices were also reviewed.
- Published through SciTech Connect.
Lee, B.S.; Grove, E.; Travis, R.; DiBiasio, A.
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