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A finding of very low safety significance … A finding of very low safety significance (Green) and an associated NCV of 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, was identified by the inspectors following surveillance testing of containment isolation valve LOCA-3A in accordance with plant procedure SP 55 167 4B, Post LOCA Valves Timing Test (IST) from Local Panel-Train B. Specifically, the licensee failed to initiate a condition report in accordance with procedure PI-KW-200, Corrective Action, following a review of the test results by the inservice testing program engineer who subsequently identified a potential condition which called into question the operability of LOCA-3A. The finding was more than minor in accordance with IMC 0612, Power Reactor Inspection Reports, Appendix B, Issue Screening, dated September 20, 2007, because the finding was associated with the structure, system and component (SSC) and barrier performance attribute of the Barrier Integrity Cornerstone and affected the cornerstone objective to provide reasonable assurance that the physical design barriers (fuel cladding, reactor coolant system, and containment) protect the public from radionuclide releases caused by accidents or events. Specifically, the licensee failed to implement the provisions of Corrective Action Procedure, PI-KW-200, which resulted in a failure to ensure operability of containment isolation valve LOCA-3A. The inspectors also determined that the primary cause for this finding was related to the cross-cutting area of human performance, work practices, because personnel have been trained in need for procedural use and adherence but did not follow applicable procedures. (H.4(b) not follow applicable procedures. (H.4(b) +
23:59:59, 31 March 2008 +
23:59:59, 31 March 2008 +
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03:04:23, 30 May 2018 +
23:59:59, 31 March 2008 +
Failure to Follow the Provisions of Corrective Action Procedure PI-KW-200 Following Surveillance Testing of Containment Isolation Valve LOCA-31 +