05000346/FIN-2010003-01
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Finding | |
|---|---|
| Title | Failure to Make a Required 8-Hour Event Report Per 10 CFR 50.72(b)(3)(ii)(B) |
| Description | The inspectors identified a Severity Level IV, non-cited violation (NCV) of 10 CFR 50.72(b)(3)(ii)(B), and an associated Green finding, for the licensees failure to recognize that, when in a shutdown condition, an 8-hour event notification to the NRC was required for the power plant being in an unanalyzed condition that significantly degrades plant safety. Specifically, during testing the Steam and Feedwater Rupture Control System (SFRCS) unexpectedly re-energized in a low steam line pressure blocked condition. This condition could cause an inappropriate SFRCS actuation and potentially result in auxiliary feedwater being supplied to a ruptured steam generator. Corrective actions included a change to the SFRCS logic to ensure that a power-on-reset occurs anytime 28 voltage direct current (VDC) power is lost. The inspectors determined that, per IMC 0612, Appendix B, Issue Screening, the failure to report the plant being in an unanalyzed condition that significantly degrades plant safety in accordance with 10 CFR 50.72(b)(3)(ii)(B) was a performance deficiency. Because the performance deficiency involved a violation that could have impacted the regulatory process, it is dispositioned using traditional enforcement. In accordance with Supplement I of the NRC Enforcement Policy, a failure to make a required report to the NRC is a Severity Level IV violation. The inspectors determined the performance deficiency was more than minor because the underlying technical issue affected the Mitigating Systems Cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. This condition did not screen out in Phase 1 of the SDP because there was a potential loss of a safety function for greater than the technical specification allowed outage time. The significance of this condition was evaluated by the Region III Senior Reactor Analyst (SRA) and was determined to be of very low safety significance (Green). The inspectors determined that the primary cause of the performance deficiency affected the cross-cutting component of thorough evaluation of problems in the cross-cutting area of Problem Identification and Resolution. Specifically, the licensee did not properly evaluate a condition adverse to quality for reportability. (P.1(c)) (Section 1R15) |
| Site: | Davis Besse  |
|---|---|
| Report | IR 05000346/2010003 Section 1R15 |
| Date counted | Jun 30, 2010 (2010Q2) |
| Type: | TEV: Severity level IV |
| cornerstone | Mitigating Systems |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71111.15 |
| Inspectors (proximate) | B Palagi J Rutkowski D Passehl A Wilson R Walton R Russell J Cameron E Stamm |
| CCA | P.2, Evaluation |
| INPO aspect | PI.2 |
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Finding - Davis Besse - IR 05000346/2010003 | |||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Davis Besse) @ 2010Q2
Self-Identified List (Davis Besse)
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