ENS 44743
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ENS Event | |
|---|---|
20:18 Dec 27, 2008 | |
| Title | Automatic Reactor Trip as a Result of a Generator Trip |
| Event Description | At 1418 on 12-27-08 Braidwood Unit 2 experienced an automatic Reactor Trip. The Reactor Trip red first out annunciator was Turb[ine] Trip above P8 Rx Trip. At the time of the trip the Unit Aux Transformer [UAT] 241-1 sudden pressure relay actuated causing a main generator trip which resulted in a main turbine trip which resulted in a Reactor Trip. Also at the same time as the Reactor Trip, the 2C Heater Drain Pump tripped on phase A over current. Damage was subsequently noted on the pump motor terminal box. No fire or smoke was observed at UAT 241-1 or the 2C Heater Drain Pump.
After the Reactor Trip occurred, all four steam generators reached their low-2 Reactor Trip setpoints and the pressurizer reached its low pressure Reactor Trip setpoint all of which is an expected response on a trip from full power. Steam generator levels and pressurizer pressure have been restored. Both the 2A and the 2B Auxiliary Feedwater Pumps auto started on the low-2 steam generator levels as expected. All control rods fully inserted into the core. No secondary relief valves lifted and no secondary steam was released as a result of the Reactor Trip. Steam generators are now being filled by the Startup Feedwater Pump and the Auxiliary Feedwater Pumps have been placed in standby. The main steam dumps are in service to the main condenser to provide heat sink cooling. The plant is being maintained at normal operating pressure and temperature. This report is being made per 10CFR 50.72(b)(2)(iv)(B) for RPS actuation, 4 hr [notification], and per 10CFR 50.72(b)(3)(iv)(A) for automatic actuation of the Auxiliary Feedwater System, 8 hr [notification]. The electrical line up transferred to the normal shutdown configuration with standby diesel generators and safety systems available. There was no impact on Unit 1. The licensee plans on issuing a press release and has notified the NRC Resident Inspector. |
| Where | |
|---|---|
Braidwood  Illinois (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-1.7 h-0.0708 days <br />-0.0101 weeks <br />-0.00233 months <br />) | |
| Opened: | Mike Deboard 18:36 Dec 27, 2008 |
| NRC Officer: | Vince Klco |
| Last Updated: | Dec 27, 2008 |
| 44743 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
Braidwood with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 571072024-05-05T08:38:0005 May 2024 08:38:00
[Table view]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 Lowering Steam Generator Water Level ENS 553202021-06-21T05:51:00021 June 2021 05:51:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Trip on Generator Lockout Relay Trip ENS 542892019-09-23T16:06:00023 September 2019 16:06:00 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 Lowering Steam Generator Levels ENS 534432018-06-04T14:20:0004 June 2018 14:20:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip on Lowering Steam Generator Water Level ENS 533712018-04-30T16:24:00030 April 2018 16:24:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Following Turbine Trip ENS 533582018-04-22T21:46:00022 April 2018 21:46:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Undervoltage Actuation of the Engineered Safety Feature Bus ENS 533472018-04-19T16:52:00019 April 2018 16:52:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Undervoltage Actuation of the Engineered Safety Feature Bus ENS 514502015-10-05T06:05:0005 October 2015 06:05:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Specified System Actuations ENS 462622010-09-20T22:04:00020 September 2010 22:04:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip ENS 461782010-08-16T07:06:00016 August 2010 07:06:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trips at Both Units ENS 452382009-07-31T02:08:00031 July 2009 02:08:00 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 Unusual Event Declared Due to a Loss of Offsite Power for Greater than 15 Minutes ENS 450172009-04-24T16:41:00024 April 2009 16:41:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip During Instrument Calibration ENS 447432008-12-27T20:18:00027 December 2008 20:18:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip as a Result of a Generator Trip ENS 435902007-08-23T20:30:00023 August 2007 20:30:00 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)(3)(xiii), Loss of Emergency Preparedness Manual Reactor Trip Because of Lowering Condenser Vacuum ENS 434492007-06-27T14:21:00027 June 2007 14:21:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip Due to Off-Site Power Fluctuation ENS 415352005-03-28T18:46:00028 March 2005 18:46:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip Due to Generator Protection Circuitry ENS 412802004-12-22T19:07:00022 December 2004 19:07:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Rps Actuation Due to Steam Generator Low Level Signal ENS 403702003-12-03T09:36:0003 December 2003 09:36:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Plant Had an Auto Reactor Trip from 100% Power Due to Steam Generator Low Level ENS 402982003-11-05T03:32:0005 November 2003 03:32:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Braidwood 2 Afw Support System Actuation During Outage 2024-05-05T08:38:00 | |
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