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AR 02671726 + and AR 02685332 +
The inspectors identified a finding of ver … The inspectors identified a finding of very-low safety significance and associated NCV of 10 CFR 50.55a(g)(4). Specifically, the licensee failed to perform a surface examination to detect cracking on reactor water cleanup small-bore piping prior to performing a weld repair. The license documented the issue in the CAP as AR 02671726 and AR 02685332 and performed an operability review. The licensee has prepared a work order to perform a surface exam of the existing weld and surrounding area. The inspectors determined that the failure to perform the surface examination prior to weld repair of RWCU pipe 1G33C001B as required by 10 CFR 50.55a(g)(4) was a performance deficiency. The inspectors determined that this issue was more-than-minor in accordance with IMC 0612, Appendix B, because it adversely affect the Initiating Events Cornerstone attribute of barrier integrity and because the answer to the question of If left uncorrected, would the performance deficiency have the potential to lead to a more significant safety concern? was yes. Specifically, the lack of a surface exam may result in the entire defect not being removed during the repair and the potential existed for a cracked pipe to remain in service. This could lead to a repeat leak of reactor coolant. The inspectors determined this finding was of very-low safety significance (Green) based on answering no to Question A.1 and A.2 of the Exhibit 1, Initiating Events Screening Questions, in IMC 0609, Attachment A, The Significance Determination Process (SDP) for Findings At-Power. Specifically, the inspectors answered no to the screening question associated with a reactor coolant system leak exceeding the leak rate for a small loss of coolant accident (LOCA) and no to the screening question associated with systems used to mitigate a LOCA. A subsequent visual examination of the weld repair revealed an absence of cracking and the licensee also planned to perform a follow-up surface examination of the repaired area to look for cracking. The inspectors determined that this finding had a cross-cutting aspect in the area of human performance in the aspect of resources, where leaders ensure that personnel, equipment, procedures and other station resources are available and adequate to support nuclear safety. Specifically, the work order that performed the work did not specify a surface examination of the base metal prior to welding. (H.1) of the base metal prior to welding. (H.1)
23:59:59, 30 June 2016 +
23:59:59, 30 June 2016 +
Has query"Has query" is a predefined property that represents meta information (in form of a <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Subobject">subobject</a>) about individual queries and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +, 05000461/FIN-2016002-06 +...
Modification date"Modification date" is a predefined property that corresponds to the date of the last modification of a subject and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
00:55:13, 21 February 2018 +
23:59:59, 30 June 2016 +
Failure to Perform Surface Examination Prior to Weld Repair of a Reactor Water Cleanup System Pipe +