05000361/FIN-2009005-04
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Finding | |
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| Title | Failure to Correct Problems with Emergency Diesel Generator Train A |
| Description | The inspectors identified a noncited violation of 10 CFR Part 50, Appendix B, Criterion XVI, Corrective Action, for the licensee\'s failure to take adequate corrective actions for conditions adverse to quality associated with Unit 3 emergency diesel generator train A. Specifically, on June 13, 2009, following an emergency diesel generator failure on June 6, 2009, immediate corrective actions were inadequately implemented when improperly configured annunciator power supplies were installed in the emergency diesel generator train A annunciator system. This configuration problem contributed to rapid capacitor degradation as a result of the increased heat from a resistor, which ultimately caused the emergency diesel generator failure to start on December 12, 2009. This finding was entered into the licensees corrective action program as Nuclear Notification NN 200756001. The finding is greater than minor because the failure to correct conditions adverse to quality for the emergency diesel generators is associated with the equipment performance attribute of the Mitigating Systems Cornerstone and affects the associated cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Using the Manual Chapter 0609, Significance Determination Process, Phase 1 Worksheets, the inspectors determined that this finding represented an actual loss of safety function of emergency diesel generator train for greater than the technical specification allowed outage time. This required that a Phase 2 estimation be completed. Because the Phase 2 analysis concluded that the finding was potentially greater than green, a Phase 3 analysis was completed by a regional senior reactor analyst. The San Onofre SPAR model indicated that the delta core damage frequency for emergency diesel generator train A being non-functional was 2.0E-6/yr. For an exposure time of 7 days, this resulted in an incremental core damage frequency of 3.8E-8 for this finding, considering internal events only. The dominant sequence was a station blackout sequence with failure of the diesels, failure to cross-tie power from the other unit, failure to recover either onsite or offsite power, failure of batteries at 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, and a failure to manually control the turbine-driven auxiliary feedwater pump after battery depletion. The senior reactor analyst determined qualitatively that the contribution of external events would not significantly add to this result; therefore, the finding is determined to be of very low safety significance. This finding has a crosscutting aspect in the area of human performance associated with resources because the licensee failed to provide adequate instructions to perform activities affecting quality H.2(c) (Section 1R12) |
| Site: | San Onofre |
|---|---|
| Report | IR 05000361/2009005 Section 1R12 |
| Date counted | Dec 31, 2009 (2009Q4) |
| Type: | NCV: Green |
| cornerstone | Mitigating Systems |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71111.12 |
| Inspectors (proximate) | L Ricketson G Guerra R Lantz P Elkmann J Adams J Reynoso G Warnick C Osterholtz A Fairbanks M Bloodgood R Schmitt |
| CCA | H.7, Documentation |
| INPO aspect | WP.3 |
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Finding - San Onofre - IR 05000361/2009005 | |||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (San Onofre) @ 2009Q4
Self-Identified List (San Onofre)
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