05000400/FIN-2014007-04
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Finding | |
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Title | Inadequate Categorization of Valves in Potential Release Paths During Accidents |
Description | The team identified a Green non-cited violation of 10 CFR Part 50.55a, Codes and Standards, for the licensees failure to categorize valves that were subject to a specific maximum leakage amount while in the closed position as Category A, as required by their American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code of record. Specifically, the team determined that the licensee failed to correctly categorize six valves that could allow emergency core cooling system (ECCS) leakage into the refueling water storage tank above the water level during ECCS post-accident recirculation operation. During the inspection period, the licensee generated nuclear condition report 699708, and performed an evaluation of the affected valves that verified the valves ability to meet leakage limits based on other monitoring that was in place. The licensees failure to categorize valves that were subject to a specific maximum leakage amount while in the closed position as Category A, as required by their ASME OM Code of record, was a performance deficiency. The performance deficiency was determined to be more than minor because it was associated with the SSC and barrier performance attribute of the Barrier Integrity cornerstone and adversely affected the cornerstone objective of providing reasonable assurance that physical design barriers protect the public from radionuclide releases caused by accidents or events. Specifically, the reliability of the physical design barrier of the leak-tightness of valves in the release paths was not assured since leak testing was not performed due to inaccurate categorization. The team determined the finding to be of very low safety significance (Green) because the finding did not represent an actual open pathway in the physical integrity of reactor containment and did not involve an actual reduction in function of the hydrogen igniters in reactor containment. The team determined that no cross-cutting aspect was applicable because the finding was not indicative of current licensee performance. |
Site: | Harris |
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Report | IR 05000400/2014007 Section 1R21 |
Date counted | Sep 30, 2014 (2014Q3) |
Type: | NCV: Green |
cornerstone | Barrier Integrity |
Identified by: | NRC identified |
Inspection Procedure: | IP 71111.21 |
Inspectors (proximate) | A Ruh C Baron G Ottenberg M Riley R Nease R Patterson S Kobylarz |
Violation of: | 10 CFR 50.55a |
INPO aspect | |
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Finding - Harris - IR 05000400/2014007 | |||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Harris) @ 2014Q3
Self-Identified List (Harris)
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