ENS 48596
ENS Event | |
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18:06 Dec 14, 2012 | |
Title | Control Building Emergency Ventilation System Inoperable for Two Minutes |
Event Description | At approximately 1306 hours0.0151 days <br />0.363 hours <br />0.00216 weeks <br />4.96933e-4 months <br /> Eastern Standard Time (EST), Brunswick Nuclear Plant lost the operability of both trains of Control Building Emergency Ventilation (CREV) for approximately two minutes. This is reportable per 10CFR50.72(b)(3)(v)(D) as a condition that at the time of discovery could have prevented the fulfillment of the safety function of a system that is needed to mitigate the consequences of an accident.
At the time of the event, Brunswick was implementing a modification to upgrade its control building fire detection. In support of short duration circuitry work on the detectors, CREV train A was placed in service manually in compliance with the Technical Requirements Manual (TRM). This action prevents an auto-start of the opposite CREV train B, and thus Technical Specification (TS) 3.7.3 Condition A was entered to restore CREV train B to service within 7 days. During work to electrically isolate ('jumper') one of the fire detectors associated with CREV train A fire protection, electrical continuity was lost. This caused the detector to fail safe, sending an internal charcoal fire signal to the CREV train A circuitry and shutting it down. With CREV train A shut down due to the signal, TS 3.7.3 Required Action C.1 applied for both CREV trains inoperable, requiring both Units to be in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Actions were taken to immediately re-establish the circuitry, which re-started CREV train A, and TS 3.7.3 Required Action C.1 was exited. This condition did not result in any adverse impact to the health and safety of the public. The safety significance of this event is considered minimal. The CREV function was only inoperable for approximately two minutes. Though considered inoperable, CREV train B remained available and could have been placed in service at any time by alternating the train A and train B control switches. The licensee has notified the NRC Resident Inspector. |
Where | |
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Brunswick North Carolina (NRC Region 2) | |
Reporting | |
10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
LER: | 05000325/LER-2012-007 |
Time - Person (Reporting Time:+-0.38 h-0.0158 days <br />-0.00226 weeks <br />-5.20524e-4 months <br />) | |
Opened: | John Miller 17:43 Dec 14, 2012 |
NRC Officer: | John Knoke |
Last Updated: | Dec 14, 2012 |
48596 - NRC Website
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Unit 1 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |
Unit 2 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (93 %) |
After | Power Operation (93 %) |
Brunswick with 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
WEEKMONTHYEARENS 559972022-07-16T00:20:00016 July 2022 00:20:00
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