05000416/FIN-2012005-03
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Finding | |
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Title | Failure to Implement Adequate Procedure Instructions to Perform Preventive Maintenance Requiring the Periodic Replacement of the Control Relays in GE Magne Blast Circuit Breakers |
Description | The inspectors reviewed a self-revealing non-cited violation of 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, for the licensees failure to complete preventive maintenance tasks on the high pressure core spray division III diesel generator output breaker in accordance with the corresponding preventive maintenance task template. The licensee entered this issue in their corrective action program as Condition Report CR-GGN-2012-07992. The immediate corrective actions included replacing the failed control relay and restoring operability to the division III diesel generator. The long term corrective actions included revising breaker refurbishment/replacement procedure with directions to replace the control relay and change the procedure frequency to every 10 years versus every 12 years. The inspectors determined that this performance deficiency was more than minor and is therefore a finding because it is associated with the equipment performance attribute of the Mitigating Systems Cornerstone and adversely affected the cornerstone objective of ensuring the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, this failed control relay caused the subject breaker to fail to close during the division III diesel generator monthly surveillance on June 5, 2012. The inspectors used NRC Inspection Manual Chapter 0609, Attachment 4, Initial Characterization of Findings, to determine that the issue affected the Mitigating System Cornerstone. Because the finding pertained only to a degraded condition while the plant was shutdown, the inspectors used Manual Chapter 0609, Appendix G, Shutdown Operations Significance Determination Process, Checklist 8, Cold Shutdown or Refueling Operation Time to Boil > 2 Hours: RCS Level < 23 Above Top of Flange, to determine that the finding was of very low safety significance because it did not increase the likelihood of a loss of reactor coolant system inventory; did not degrade the licensees ability to terminate a leak path or add RCS inventory when needed; did not significantly degrade the licensees ability to recover decay heat removal if lost; and did not affect the safety/relief valves (Green). The inspectors determined that the cause of this finding was a latent issue that is not reflective of current performance, therefore no cross-cutting aspect was identified. |
Site: | Grand Gulf |
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Report | IR 05000416/2012005 Section 1R20 |
Date counted | Dec 31, 2012 (2012Q4) |
Type: | NCV: Green |
cornerstone | Mitigating Systems |
Identified by: | NRC identified |
Inspection Procedure: | IP 71111.2 |
Inspectors (proximate) | B Rice D Proulx G George J Laughlin L Carson N Okonkwo R Kumana R Smith S Achen S Makord Proulxg George J Laughlin L Carson N Okonkwo R Kumana R Smith S Achen S Makor B Rice |
INPO aspect | |
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Finding - Grand Gulf - IR 05000416/2012005 | ||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Grand Gulf) @ 2012Q4
Self-Identified List (Grand Gulf)
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