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On October 13, 2011, in preparation for coOn October 13, 2011, in preparation for converting from 10 CFR 50, Appendix R, to NFPA 805, a review of the Brunswick Steam Electric Plant (BSEP) Safe Shutdown Analysis identified conditions that may not ensure a protected train of equipment remains available under certain postulated fire scenarios. The analysis determined that a postulated fire in specific fire areas could cause spurious actuation of critical components, potentially resulting in loss of equipment required for safe shutdown. A fire in one of the specified fire areas could potentially adversely affect the following: Suppression Pool level instrument 2-CAC-LT-2602, Residual Heat Removal net positive suction head (i.e., drywell containment overpressure), Reactor Core Isolation Cooling (RCIC), Emergency Bus E-1, and Emergency Bus E-3.</br></br>The safety significance of this event is minimal. Fire watches were established for the affected portions of fire areas RB1-1, RB2-1, TB1, CB-2, CB-13, and CB-23. Additionally, fire detection and suppression equipment in the affected areas were fully functional.</br></br>This was determined to be a historical condition and no root cause could be identified. Corrective actions include establishing an hourly fire watch in the affected fire areas, revision of alternative safe shutdown procedures, and completion of a new safe shutdown analysis.ompletion of a new safe shutdown analysis.  +
December 8, 2011  +
October 13, 2011  +
On October 13, 2011, in preparation for coOn October 13, 2011, in preparation for converting from 10 CFR 50, Appendix R, to NFPA 805, a review of the Brunswick Steam Electric Plant (BSEP) Safe Shutdown Analysis identified conditions that may not ensure a protected train of equipment remains available under certain postulated fire scenarios. The analysis determined that a postulated fire in specific fire areas could cause spurious actuation of critical components, potentially resulting in loss of equipment required for safe shutdown. A fire in one of the specified fire areas could potentially adversely affect the following: Suppression Pool level instrument 2-CAC-LT-2602, Residual Heat Removal net positive suction head (i.e., drywell containment overpressure), Reactor Core Isolation Cooling (RCIC), Emergency Bus E-1, and Emergency Bus E-3.</br></br>The safety significance of this event is minimal. Fire watches were established for the affected portions of fire areas RB1-1, RB2-1, TB1, CB-2, CB-13, and CB-23. Additionally, fire detection and suppression equipment in the affected areas were fully functional.</br></br>This was determined to be a historical condition and no root cause could be identified. Corrective actions include establishing an hourly fire watch in the affected fire areas, revision of alternative safe shutdown procedures, and completion of a new safe shutdown analysis.ompletion of a new safe shutdown analysis.  +
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2,011  +
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05:20:07, 1 December 2017  +
December 8, 2011  +
October 13, 2011  +
Fire Related Unanalyzed Condition that could Impact Equipment Credited in Safe Shutdown Analysis  +
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