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A self-revealing NCV of 10 CFR 50, Appendi … A self-revealing NCV of 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, was identified because Entergy did not establish a procedure controlling plant equipment appropriate to the circumstances for activities affecting quality. Specifically, the procedure for the control of plant equipment did not require identifying and tagging the switches of deenergized equipment that continued to have control power. As a result, the reactor building ventilation was operated in a manner that dislodged an engineered blowout panel rendering secondary containment inoperable. Entergys corrective action to restore compliance consisted of entering the issue into their corrective action program and implementing a night order to place a caution tag on the control switches of components that are deenergized and continue to have control power available. The inspectors determined that Entergys inadequate procedure for the control of plant equipment such that deenergized loads that continued to have control power were not identified or tagged was a performance deficiency that was reasonably within Entergys ability to foresee and correct and should have been prevented. This finding is more than minor because it is associated with the procedure quality attribute of the Barrier Integrity cornerstone and affected the cornerstone objective to provide reasonable assurance that physical design barriers (containment) protect the public from radionuclide releases caused by accidents or events. Specifically, the lack of identification and/or tagging of the switches for A reactor building ventilation resulted in dislodging a secondary containment blowout panel that rendered secondary containment inoperable. In accordance with IMC 0609.04, Initial Characterization of Findings, and IMC 0609, Appendix G, Shutdown Operations Significance Determination Process, issued February 28, 2005, the inspectors determined that this finding is of very low safety significance (Green) because it did not increase the likelihood of a loss of reactor coolant system inventory, did not degrade the ability to terminate a leak path or add reactor coolant system inventory, and did not degrade the ability to recover decay heat removal if it was lost. Specifically, at the time secondary containment was rendered inoperable, the reactor coolant system was fully flooded, the event did not increase the likelihood of any initiating event, and secondary containment was not required to be operable at the time given no fuel movement, core alterations, or operations with a potential for draining the reactor vessel in progress. The inspectors determined that the finding had a cross-cutting aspect in the Human Performance area, Resources component, because Entergys procedures did not ensure that components in the field were labeled sufficiently and completely, during the bus deenergization, to assure nuclear safety (H.2(c)).zation, to assure nuclear safety (H.2(c)).
23:59:59, 30 June 2013 +
23:59:59, 30 June 2013 +
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03:47:48, 28 September 2017 +
23:59:59, 30 June 2013 +
Inadequate Procedure for Configuration Control Results in a Dislodged Secondary Containment Blowout Panel Due to Reactor Building Ventilation System Pressurization +