05000348/FIN-2012004-02
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Finding | |
|---|---|
| Title | Loss of Shutdown Cooling due to an Unplanned Loss of Train A 4160v Safety Related Switchgear |
| Description | A Green self revealing non-cited violation (NCV) of Technical Specifications (TS) 5.4.1.a, Procedures, was identified for the failure to accomplish shutdown of the 1-2A emergency diesel generator (EDG) in accordance with station procedure FNP-1-STP-40.0. The failure resulted in a loss of all shutdown cooling to the Unit 1 reactor. The licensee correctly diagnosed the unplanned loss of shutdown cooling and promptly restarted the 1A residual heat removal (RHR) pump. This violation was entered into the licensees corrective action program as condition report (CR) 434764. Failure to accomplish shutdown of the 1-2A EDG in accordance with station procedure FNP- 1-STP-40.0, is a performance deficiency. The performance deficiency was more-than-minor because it adversely affected the Initiating Events Cornerstone objective of limiting the likelihood of those events that upset plant stability and challenge critical safety functions during shutdown as well as power operations. Specifically, all shutdown cooling to the reactor was lost when 1A RHR pump stopped operating due to loss of electrical power. This finding was assessed using IMC 0609 Attachment 4, Initial Characterization of Findings; Appendix G, Shutdown Operations Significance Determination Process; and Appendix G, Attachment 1, Phase 1 Operational Checklist for Both PWRs and BWRs. The finding was determined to be of very low safety significance (Green) because the inadvertent change in RCS temperature due to loss of RHR was less than 20 percent of the temperature margin time to boil and did not trip any of the criteria of Appendix G, Attachment 1, Checklist 4. The inspectors determined this performance deficiency has a cross-cutting aspect in the area of human performance and resources component because the licensee did not ensure that personnel, equipment, procedures, and other resources were available and adequate to assure nuclear safety. Specifically, step 5.36.4 of FNP-1-STP-40.0, was inadequate and confusing which resulted in a failure to comply with the procedure. |
| Site: | Farley  |
|---|---|
| Report | IR 05000348/2012004 Section 4OA3 |
| Date counted | Sep 30, 2012 (2012Q3) |
| Type: | NCV: Green |
| cornerstone | Initiating Events |
| Identified by: | Self-revealing |
| Inspection Procedure: | IP 71153 |
| Inspectors (proximate) | D Lanyi E Crowe F Ehrhardt G Croon G Laska J Sowa M Miller T Lighty |
| CCA | H.7, Documentation |
| INPO aspect | WP.3 |
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Finding - Farley - IR 05000348/2012004 | ||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Farley) @ 2012Q3
Self-Identified List (Farley)
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