05000458/FIN-2014004-02
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Finding | |
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Title | Licensee-Identified Violation |
Description | River Bend Station License Condition 2.C.10, Attachment 4, requires, in part, that the licensee implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Safety Analysis Report, as amended, and as approved in the Station Safety Evaluation Report, dated May 1984, and Supplement 3. Station Safety Evaluation Report, Supplement 3, concluded that the fire protection program was acceptable because it was in conformance with the guidelines of Appendix R,Section III.G. Appendix R,Section III.G, Paragraph 1.a, states, "One train of systems necessary to achieve and maintain hot shutdown conditions from either the control room or emergency control station(s) is free from fire damage." Contrary to the above, on January 9, 2014, the licensee identified that non-safe shutdown cables that shared a common enclosure with safe shutdown cables were not electrically protected and, therefore, did not meet the requirements of Appendix R,Section III.G. Specifically, the licensee identified that the battery ammeter circuits routed from the DC motor control centers to the ammeters located in the Control Room were not fused. These cables were routed in trays and installed in panels with other safe shutdown cables. During a fire event in the Control Room, fire-induced failures could have damaged the ammeter circuit and could have resulted in damaging other safe shutdown cables that are in direct physical contact with these cables in different fire zones. This issue was entered in the licensees corrective action program as Condition Report CR-RBS-2013-04654. A senior reactor analyst performed a detailed risk evaluation and determined that the bounding change to the core damage frequency was approximately 6.5E-8/year. Since this value was less than 1E-7/year, quantification of the large early release frequency was not required. The finding was of very low safety significance (Green). The dominant core damage sequences involved a control room fire initiating event in Panel H13-P808-87B, loss of Division II and Division III emergency AC power sources, and a secondary fire which caused the loss of the Division I emergency AC train. The availability of the reactor core isolation cooling system as well as the station blackout diesel generator helped to minimize the risk. This violation is associated with LER 05000458/2014-001-00. Refer to Section 4OA3.2 of this inspection report for the review and closure of the licensee event report. |
Site: | River Bend |
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Report | IR 05000458/2014004 Section 4OA7 |
Date counted | Sep 30, 2014 (2014Q3) |
Type: | NCV: Green |
cornerstone | Mitigating Systems |
Identified by: | Licensee-identified |
Inspection Procedure: | |
Inspectors (proximate) | P Elkman S Makor A Barrett A Meyen E Schrader G George G Larkin H Freeman J Sowa L Ricketson N Greene |
Violation of: | License Condition - Fire Protection License Condition |
INPO aspect | |
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Finding - River Bend - IR 05000458/2014004 | |||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (River Bend) @ 2014Q3
Self-Identified List (River Bend)
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