05000298/FIN-2015003-08
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Finding | |
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Title | Licensee-Identified Violation |
Description | Technical Specification 5.4.1.a requires, in part, that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Appendix A to Regulatory Guide 1.33, Quality Assurance Program Requirements, of February 1978. Section 8.b of Regulatory Guide 1.33 recommends that specific procedures for surveillance tests, inspections, and calibrations should be written (implementing procedures are required for each surveillance test, inspection, or calibration listed in the technical specification) for containment leak-rate and penetration leak-rate tests. The licensee maintains Station Procedure 6.PC.524, Primary Containment Airlock Local Leak Rate Tests, Revision 21 for containment and penetration local leak-rate testing for the primary containment personnel airlock. Contrary to the above, until June 3, 2015, the licensee failed to maintain procedure 6.PC.524 to provide surveillance testing guidance to test the inner personnel airlock equalization valve in the accident direction. This condition resulted in surveillance tests not being performed within their specified frequency and questioned operability of the inner personnel airlock equalization valve. The station implemented the requirements of Surveillance Requirement 3.0.3 and conducted a risk evaluation to determine that integrated leak rate test conducted in Refueling Outage 27 tested the inner personnel airlock equalization valve in the accident condition providing reasonable expectation of operability. The performance deficiency was determined to be more than minor because it was associated with the procedure quality attribute of the Barrier Integrity Cornerstone, and affected the associated cornerstone objective to ensure the containment functionality was maintained. Using Inspection Manual Chapter 0609, Appendix A, The Significance Determination Process (SDP) for Findings At-Power, dated June 19, 2012, inspectors determined that the finding screened as having very low safety significance (Green) because it did not represent an actual: (1) open pathway in the physical integrity of reactor containment (valves, airlocks, etc.) containment isolation system (logic and instrumentation), and heat removal components; and (2) reduction in function of hydrogen igniters in the reactor containment. The license entered this deficiency into the corrective action program Condition Report CR-CNS-2015-00986. |
Site: | Cooper |
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Report | IR 05000298/2015003 Section 4OA7 |
Date counted | Sep 30, 2015 (2015Q3) |
Type: | NCV: Green |
cornerstone | Mitigating Systems |
Identified by: | Licensee-identified |
Inspection Procedure: | |
Inspectors (proximate) | C Henderson D Reinert G Warnick J Braisted J Nance J O'Donnell L Carson M Hayes M Phalen P Elkmann P Hernandez |
Violation of: | Technical Specification - Procedures Technical Specification |
INPO aspect | |
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Finding - Cooper - IR 05000298/2015003 | |||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Cooper) @ 2015Q3
Self-Identified List (Cooper)
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