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: | 05000271/LER-2003-004 Hearing - Entergy Exhibit 13 LER 2003-004-00 Brunswick Unit 2 Loss of Generator Excitation Results in Reactor Protection System and Other Specified System Actuations |
| 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 576362025-03-28T18:09:00028 March 2025 18:09:00
[Table view]10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Actuation of Containment Isolation Valves ENS 569772024-02-19T04:25:00019 February 2024 04:25:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Start of Emergency Diesel Generator ENS 564782023-04-20T05:48:00020 April 2023 05:48:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to a Turbine Trip ENS 556272021-12-06T16:25:0006 December 2021 16:25:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Safety System Actuation ENS 545972020-03-22T16:55:00022 March 2020 16:55:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram ENS 540162019-04-22T03:07:00022 April 2019 03:07:00 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 Automatic Reactor Trip and Specified System Actuation ENS 539662019-03-30T21:47:00030 March 2019 21:47:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram and Specified System Actuation ENS 539622019-03-28T20:54:00028 March 2019 20:54:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Actuation of the Primary Containment Isolation System and the Reactor Protecton System ENS 539552019-03-25T08:02:00025 March 2019 08:02:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Start of Four Emergency Diesel Generators ENS 539112019-03-05T10:35:0005 March 2019 10:35:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Actuation of the Primary Containment Isolation System ENS 533192018-04-07T12:36:0007 April 2018 12:36:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip and Pcis Actuation During Stator Cooling System Testing ENS 529742017-09-17T13:38:00017 September 2017 13:38:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator and Primary Containment Isolation System Actuations ENS 526832017-04-17T04:04:00017 April 2017 04:04:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Actuation of Emergency Diesel Generators ENS 517152016-02-07T18:26:0007 February 2016 18:26:00 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 Manual Scram and Alert Declaration Due to Electrical Fault Resulting in Fire/Explosion ENS 478172012-04-09T09:29:0009 April 2012 09:29:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Emergency Diesel Generator Actuation ENS 476972012-02-24T05:37:00024 February 2012 05:37:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Reactor Protection System Actuation During Neutron Instrument Testing ENS 476902012-02-23T04:19:00023 February 2012 04:19:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Due to High Delta-P Across Circulating Water Pump Traveling Screens ENS 474442011-11-16T08:01:00016 November 2011 08:01:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration Unusual Event Due to Drywell Leakage Greater than 10 Gpm ENS 459022010-05-05T15:44:0005 May 2010 15:44:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram Due to Reactor Feed Pump Trip ENS 457322010-02-27T06:58:00027 February 2010 06:58:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Core Isolation Cooling (Rcic) System Manually Started to Maintain Reactor Pressure Vessel Level Following a Pre-Planned Reactor Scram ENS 453752009-09-21T18:46:00021 September 2009 18:46:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Protection System and Primary Containment Isolation System Actuation After Placing Hpci System Inservice ENS 451902009-07-08T14:13:0008 July 2009 14:13:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Emergency Diesel Generator Actuation ENS 446852008-11-26T17:00:00026 November 2008 17:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram Due to Ehc Malfunction ENS 446472008-11-09T16:08:0009 November 2008 16:08:00 Other Unspec Reqmnt, 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Due to Spurious Srv Opening ENS 444532008-08-30T19:03:00030 August 2008 19:03:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Turbine Electro-Hydraulic Control Malfunction Leads to Reactor Scram ENS 430622006-12-25T10:39:00025 December 2006 10:39:00 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 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 2025-03-28T18:09:00 | |
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