05000482/FIN-2012003-02: Difference between revisions
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| identified by = NRC | | identified by = NRC | ||
| Inspection procedure = IP 71111.18 | | Inspection procedure = IP 71111.18 | ||
| Inspector = C Long, C Peabody, C Alldredge, N Greene, N Makris, A O | | Inspector = C Long, C Peabody, C Alldredge, N Greene, N Makris, A O'Donnell, L Ricketson, L Carson, N O'Keefe | ||
| CCA = H.7 | | CCA = H.7 | ||
| INPO aspect = WP.3 | | INPO aspect = WP.3 | ||
| description = The inspectors identified a non-cited violation of 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, for a work order that did not accomplish a leak seal repair in accordance with its engineering evaluation. Valve BMV0037 is a safety related ASME Code Class 2 steam generator blow-down valve that had a body-to-bonnet steam leak. Wolf Creek and its vendor produced modification documents to perform a leak-seal repair. The inspectors identified that on December 10, 2011, Wolf Creek installed an injection port in the valve body in close proximity of another injection port. Work orders allowed the location of the injection ports to be determined by the work. The pair was not installed in accordance with change package 9385. After inspector questioning, Wolf Creek performed an evaluation that demonstrated that the valve body retained structural integrity. This issue was entered into the corrective action program under condition report 52992. The failure to ensure that the configuration of a safety-related steam generator blow-down was controlled in accordance with the approved engineering change package during leak seal activities is a performance deficiency. This finding was more than minor because it impacted the procedure quality attribute of the Initiating Events Cornerstone and affected the objective to limit the likelihood of those events that upset plant stability and challenge critical safety functions during shutdown as well as power operations. Using Inspection Manual Chapter 0609, Appendix A, this finding was determined to be of very low safety significance because an evaluation after the modification was able to demonstrate structural integrity. Therefore, the finding does not contribute to both the likelihood of a reactor trip and the likelihood that mitigation equipment will not be available. The inspectors identified the cause of the finding had a human performance crosscutting aspect in the area of resources. Specifically, the licensee did not ensure that the work order instructions were complete, accurate, and reflected up-to-date design documentation sufficiently to control plant configuration in accordance with design | | description = The inspectors identified a non-cited violation of 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, for a work order that did not accomplish a leak seal repair in accordance with its engineering evaluation. Valve BMV0037 is a safety related ASME Code Class 2 steam generator blow-down valve that had a body-to-bonnet steam leak. Wolf Creek and its vendor produced modification documents to perform a leak-seal repair. The inspectors identified that on December 10, 2011, Wolf Creek installed an injection port in the valve body in close proximity of another injection port. Work orders allowed the location of the injection ports to be determined by the work. The pair was not installed in accordance with change package 9385. After inspector questioning, Wolf Creek performed an evaluation that demonstrated that the valve body retained structural integrity. This issue was entered into the corrective action program under condition report 52992. The failure to ensure that the configuration of a safety-related steam generator blow-down was controlled in accordance with the approved engineering change package during leak seal activities is a performance deficiency. This finding was more than minor because it impacted the procedure quality attribute of the Initiating Events Cornerstone and affected the objective to limit the likelihood of those events that upset plant stability and challenge critical safety functions during shutdown as well as power operations. Using Inspection Manual Chapter 0609, Appendix A, this finding was determined to be of very low safety significance because an evaluation after the modification was able to demonstrate structural integrity. Therefore, the finding does not contribute to both the likelihood of a reactor trip and the likelihood that mitigation equipment will not be available. The inspectors identified the cause of the finding had a human performance crosscutting aspect in the area of resources. Specifically, the licensee did not ensure that the work order instructions were complete, accurate, and reflected up-to-date design documentation sufficiently to control plant configuration in accordance with design | ||
}} | }} | ||
Latest revision as of 23:18, 21 February 2018
| Site: | Wolf Creek  |
|---|---|
| Report | IR 05000482/2012003 Section 1R18 |
| Date counted | Jun 30, 2012 (2012Q2) |
| Type: | NCV: Green |
| cornerstone | Initiating Events |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71111.18 |
| Inspectors (proximate) | C Long C Peabody C Alldredge N Greene N Makris A O'Donnell L Ricketson L Carson N O'Keefe |
| CCA | H.7, Documentation |
| INPO aspect | WP.3 |
| ' | |