ENS 46740
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ENS Event | |
|---|---|
21:40 Apr 7, 2011 | |
| Title | Loss of the Control Room Emergency Ventilation System |
| Event Description | At approximately 1740 hours0.0201 days <br />0.483 hours <br />0.00288 weeks <br />6.6207e-4 months <br /> on April 7, 2011, a loss of the Control Room Emergency Ventilation (CREV) system occurred. At the time of the event, the plant was performing 0MST-DG13R. 'DG-3 Loading Test.' During performance of this test, the 480 VAC Emergency Bus E-7 main feeder breaker tripped unexpectedly. As a result, the CREV emergency makeup damper 2-VA-2J-D-CB closed on this loss of power, resulting in two CREV subsystems required by TS 3.7.3, 'CREV System,' being inoperable. As a result, this condition could have prevented the fulfillment of the safety function for this system. Brunswick has a shared control room, but only Unit 1 was required to enter TS 3.7.3 Required Action C.1. for two CREV subsystems inoperable (i.e., be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />). Unit 2 was operating in Mode 4 for a scheduled refueling outage and did not meet any applicability conditions for TS 3.7.3.
Operability of the CREV subsystems was restored and the related LCO was exited at 1931 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.347455e-4 months <br /> following the restoration of CREV damper 2-VA-2J-D-CB. Investigation of the E-7 bus trip is ongoing. This report is being made in accordance with 10 CFR 50.72(b)(3)(v)(D), as a condition that at the time of discovery could have prevented the fulfillment of the safety function of systems that are needed to mitigate the consequences of an accident. The safety significance of this event is considered minimal. The condition existed for approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 51 minutes. Plant staff took immediate action to return the equipment to service. For the brief time the CREV systems were inoperable, performance of plant personnel and equipment in the Control Room was not adversely affected. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
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 | |
| Time - Person (Reporting Time:+3.37 h0.14 days <br />0.0201 weeks <br />0.00462 months <br />) | |
| Opened: | John Miller 01:02 Apr 8, 2011 |
| NRC Officer: | Dong Park |
| Last Updated: | Apr 8, 2011 |
| 46740 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
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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Mitigate the Consequences of an Accident High Pressure Coolant Injection (Hpci) System Inoperable Due to Seal Leak ENS 437112007-10-11T02:45:00011 October 2007 02:45:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Unit 2 Hpci Pump Seal Failure ENS 431972007-02-28T03:26:00028 February 2007 03:26:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Pressure Coolant Injection (Hpci) Inoperability ENS 429062006-10-13T17:57:00013 October 2006 17:57:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Pressure Coolant Injection (Hpci) System Declared Inoperable Due to Potential Turbine Exhaust Diaphragm Failure ENS 424882006-04-10T20:30:00010 April 2006 20:30:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Control Room Emergency Ventilation System Declared Inoperable Due to Design Deficiency ENS 423052006-02-03T04:36:0003 February 2006 04:36:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - 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