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The inspectors reviewed a self-revealing G … The inspectors reviewed a self-revealing Green, non-cited violation of Technical Specification 3.3.4 Remote Shutdown System, for the licensees failure to maintain adequate configuration control of fuses associated with an emergency diesel generator (EDG). The licensees failure to maintain adequate configuration control by not verifying that fuses were properly installed, and adequate post maintenance testing was performed, following maintenance activities was a performance deficiency. Specifically, following the 1R17 refueling outage, from approximately June 13, 2013 until November 22, 2013, EDG 1-3 would not have been able to perform its remote shutdown function due to not being able to be adequately operated at the local EDG control cubicle. The licensee entered this issue into the corrective action program as Notification 50595473, and took prompt actions to restore the fuses to the correct position and verify the positions of the fuses in the other EDG output breaker cubicles. The failure to properly install fuses in the local manual operation circuitry of EDG 1-3 was a performance deficiency. The performance deficiency was more than minor because it was associated with the protection against external events (fire) attribute of the Mitigating Systems Cornerstone, and it adversely affected the cornerstone objective of ensuring the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, it affected the ability to reach and maintain safe shutdown conditions in case of a fire causing a control room abandonment. The inspectors evaluated this finding using Inspection Manual Chapter 0609, Appendix F, Fire Protection Significance Determination Process," dated September 20, 2013. Because it affected the ability to reach and maintain safe shutdown conditions in case of a fire that led to control room evacuation, the Phase 2 methodology of Inspection Manual Chapter 0609, Appendix F, was not appropriate for this finding. Therefore, the senior reactor analyst performed a Phase 3 evaluation to determine the risk significance. The analyst determined that the performance deficiency only increased the risk of the plant as it related to the need to locally control EDG 1-3 following a postulated control room evacuation. The Senior Risk Analyst determined that the change in core damage frequency was less than 1 x 10-6, and the finding was not significant with respect to large, early release frequency. The analyst determined that this finding was of very low risk significance (Green). This finding had a cross-cutting aspect in the area of human performance associated with the work practices component, because the licensee did not ensure supervisory and management oversight of work activities, such that nuclear safety was supported (H.5).h that nuclear safety was supported (H.5).

Discovered date

23:59:59, 30 June 2015 +

Docket

05000275 +

Event date

23:59:59, 30 June 2015 +

Finding integer

4 +

Finding type

Non-cited violation +

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INPO aspect

WP.1 +

Identified by

Self-revealing +

Inspection Manual Chapter

NRC Inspection Manual 0609/Appendix F +

Inspection procedure

IP 71153, Event Followup +

Inspection report

IR 05000275/2015002 +

Inspector

Ryan Alexander +, Michael Kennard +, M Hayes +, Thomas Hipschman +, John Reynoso + and Theresa Buchanan +

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>.

12:58:16, 25 September 2017 +

Person