05000413/FIN-2012005-02
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Finding | |
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Title | Associated Circuit Issues from 2004 Triennial Fire Protection Audit |
Description | Catawba License Condition 2.C(5), Fire Protection Program, stated, in part, that Duke Energy Carolina, LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report (UFSAR). UFSAR 9.5.1, Fire Protection System, stated, in part, that Catawbas original Fire Protection Program was submitted by letter as the Fire Protection Review which included a response to Branch Technical Position (BTP) APCSB 9.5-1, General Guidelines for Plant Protection. The BTP stated, in part, that redundant safety-related systems that are subject to damage from a single fire hazard should be protected by a combination of fire retardant coatings and fire detection and suppression systems, or a separate system to perform the safety function be provided. NUREG 0954, Safety Evaluation Report related to the operation of Catawba Nuclear Station, Units 1 and 2, dated February 1983, documents the NRCs acceptance of the licensees commitment to Appendix A to Branch Technical Position ASB 9.5-1 for the fire protection program. The Fire Protection Review was documented and maintained in the Plant Design Basis Specification for Fire Protection. Contrary to the above, since initial plant operation, the licensee failed to provide a separate system to adequately perform the safety function of redundant safety-related systems subject to damage from a single fire hazard and not protected by a combination of fire retardant coatings and fire detection and suppression systems. The licensee did not have adequate procedures to operate the SSF in a timely manner to mitigate the effects of a fire-induced spurious opening of the unprotected PORVs and block valves to ensure the safety function they perform would be provided. Because the licensee committed to adopt NFPA 805 and change their fire protection licensing bases to comply with 10 CFR 50.48(c), the NRC is exercising enforcement and reactor oversight process (ROP) discretion for these nonconformances in accordance with the NRC Enforcement Policy, Section 9.1, Enforcement Discretion for Certain Fire Protection Issues (10 CFR 50.48) and Inspection Manual Chapter 0305. Specifically, it was likely these issues would have been identified and addressed during the licensees transition to NFPA 805, they were entered into the licensees corrective action program, immediate corrective action and compensatory measures were taken, they were not likely to have been previously identified by routine licensee efforts, they were not willful, and they were not associated with a finding of high safety significance (Red). Therefore, the criteria of the interim Enforcement Policy and Section 11.05(b) of IMC 0305 have been met. |
Site: | Catawba |
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Report | IR 05000413/2012005 Section 1R05 |
Date counted | Dec 31, 2012 (2012Q4) |
Type: | Violation: Severity level Enforcement Discretion |
cornerstone | Mitigating Systems |
Identified by: | NRC identified |
Inspection Procedure: | IP 71111.05 |
Inspectors (proximate) | A Hutto A Nielson D Jones G Macdonald J Bartley J Laughlin L Lake M Coursey M Meeks R Cureton W Loo |
INPO aspect | |
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Finding - Catawba - IR 05000413/2012005 | ||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Catawba) @ 2012Q4
Self-Identified List (Catawba)
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