ENS 40297
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ENS Event | |
|---|---|
22:32 Nov 4, 2003 | |
| Title | Brunswick Unit 2 Scram Due to Generator/Turbine Trip |
| Event Description | On November 4, 2003, at approximately 1732 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.59026e-4 months <br />, Unit 2 received a generator/turbine trip due to loss of excitation, which resulted in a Reactor Protection System (RPS) trip. Plant response to the reactor shutdown resulted in High Pressure Coolant Injection and Reactor Core Isolation Cooling [RCIC] system actuations on low reactor coolant level. Additionally, primary containment isolation system actuation signals for valve groups 1, 2, 3 , 6, 8, and 10 were received and the valves closed as required. All four emergency diesel generators automatically started, but did not load because power was never lost to the emergency buses. The loss of power from the generator trip resulted in reactor building ventilation isolation and automatic start of both trains of the Standby Gas Treatment (SBGT) system. SBGT Train A immediately tripped, but was successfully placed in service. All control rods fully inserted into the core. At approximately 1857 hours0.0215 days <br />0.516 hours <br />0.00307 weeks <br />7.065885e-4 months <br />, another RPS trip was received due to low reactor coolant level while cycling Safety Relief Valves; however, all control rods were already inserted.
The safety significance of this event is considered to be minimal. The plant responded as designed to the transient with the exception of the SBGT Train A initial starting issue. An event investigation team has been assembled to determine the cause of the event. Plant response to the event is being evaluated and identified issues will be addressed prior to plant restart. The licensee reported that the station electrical grid is normal and the emergency diesel generators have been shutdown and returned to standby status. The current plant conditions are 550 psi, 496 degrees F with RCIC operating to maintain reactor water level. The main condenser is available and being used to dump steam from the reactor. Two safety relief valves opened during the transient and reclosed as expected. The reactor water level decreased to minimum of approximately 90 inches during the transient. The cause of main steam isolation valve (MSIV) closure is under investigation. The licensee also reported that this event caused a Group 6 Isolation, reactor building ventilation isolation, and standby gas treatment actuation signal on Brunswick Unit 1. These Unit 1 systems have been returned to a normal configuration. The licensee has notified the NRC Resident Inspector. |
| Where | |
|---|---|
Brunswick  North Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| LER: | 05000324/LER-2003-004 |
| Time - Person (Reporting Time:+-1.2 h-0.05 days <br />-0.00714 weeks <br />-0.00164 months <br />) | |
| Opened: | Daniel Hardin 21:20 Nov 4, 2003 |
| NRC Officer: | Gerry Waig |
| Last Updated: | Nov 4, 2003 |
| 40297 - NRC Website
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Brunswick with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge | |
WEEKMONTHYEARENS 569772024-02-19T04:25:00019 February 2024 04:25:00
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ECCS Discharge Reactor Scram Due to Trip from Neutron Monitoring System ENS 429862006-11-11T17:43:00011 November 2006 17:43:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Scram Due to Conductivity Excursion ENS 429552006-11-01T23:37:0001 November 2006 23:37:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Unit 2 Declared an Unusual Event Due to Loss of Offsite Power to the 4Kv Emergency Buses ENS 418372005-07-13T13:17:00013 July 2005 13:17:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Turbine Trip/Reactor Trip ENS 415822005-04-09T05:50:0009 April 2005 05:50:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Scrammed from 61% Power Due to Low Reactor Water Level ENS 409542004-08-14T16:59:00014 August 2004 16:59:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Rps Actuation Due to Loss of Offsite Power ENS 402972003-11-04T22:32:0004 November 2003 22:32:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Brunswick Unit 2 Scram Due to Generator/Turbine Trip 2024-02-19T04:25:00 | |
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