Preliminary assessment of valve IST effectiveness [electronic resource].
- Published
- Rockville, Md. : U.S. Nuclear Regulatory Commission, 1994.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- 17 pages : digital, PDF file
- Additional Creators
- Brookhaven National Laboratory, U.S. Nuclear Regulatory Commission, and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- A preliminary review of 1ST effectiveness for Code Class 1, 2, and 3 valves at nuclear power plants was performed. These requirements are specified by ASME Section 11, and the Operations and Maintenance Standards (OM-10). The INPO NPRDS database was used to provide failure reports for these components for 1988 to 1992. This time period coincides with the issuance of Generic Letter 89-04, which resulted in a more consistent application of the requirements by the licensees. For this time period, 8593 valve failures were identified. From the review of the NPRDS database, the primary failure causes and failure modes for motor operated (MOV), air operated (AOV), and check valves (CV) were identified. Solenoid operated valves (SOV) were not reviewed in this study. Plant testing programs were effective in identifying approximately 60% of the CV failures, 46% of the AOV failures, and 44% of the MOV failures.
- Report Numbers
- E 1.99:bnl-nureg--60271
E 1.99: conf-940774--2
conf-940774--2
bnl-nureg--60271 - Subject(s)
- Other Subject(s)
- Note
- Published through SciTech Connect.
06/01/1994.
"bnl-nureg--60271"
" conf-940774--2"
"DE94013030"
3. ASME/NRC symposium on valve and pump testing,Washington, DC (United States),18-21 Jul 1994.
Grove, E.; DiBiasio, A.; Carbonaro, J. - Funding Information
- AC02-76CH00016
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