ENS 43590
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ENS Event | |
|---|---|
20:30 Aug 23, 2007 | |
| Title | Manual Reactor Trip Because of Lowering Condenser Vacuum |
| Event Description | At 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> on 8/23/07, Braidwood Station Unit 2 was manually tripped due to lowering condenser vacuum. The lowering condenser vacuum resulted from the trip of two circulating water pumps. The cause of the two circulating water pump tripping is under investigation. All control rods inserted and there were no complications during the trip and all systems functions as required. Following the unit trip, the Auxiliary Feedwater System actuated as expected to maintain steam generator level. At the time of the unit trip, the Braidwood Station area was experiencing severe thunderstorms.
Additionally, at 1604 hours0.0186 days <br />0.446 hours <br />0.00265 weeks <br />6.10322e-4 months <br />, 19 of 70 emergency sirens for the Braidwood Station were declared inoperable due to a loss of power from storms in the area. As of 1704 hours0.0197 days <br />0.473 hours <br />0.00282 weeks <br />6.48372e-4 months <br />, 19 sirens (greater than 25%) remain inoperable. This event is considered a major loss of offsite response capability and applies to both Braidwood Station Unit 1 and Unit 2. These events are is being reported under: (1) 10 CFR 50.72(b)(2)(iv)(B) as an event that results in the actuation of the reactor protection system (RPS) when the reactor is critical, (2) 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the PWR auxiliary feedwater system. (3) 10 CFR 50.72(b)(3)(xiii) as a major loss of offsite response capability. All safety buses remained powered by offsite power throughout this event. Emergency diesel generators are available if needed. No steam generator PORV's lifted as a result of the trip. Decay heat is being discharged to the condenser via the steam dumps. The licensee informed 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 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness | |
| Time - Person (Reporting Time:+-0.27 h-0.0113 days <br />-0.00161 weeks <br />-3.69846e-4 months <br />) | |
| Opened: | Ralph Richard 20:14 Aug 23, 2007 |
| NRC Officer: | Pete Snyder |
| Last Updated: | Aug 23, 2007 |
| 43590 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| 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, 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness | |
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 563522023-02-06T11:30:0006 February 2023 11:30:00 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Loss of Communications and Assessment Capabilities ENS 553252021-06-24T14:01:00024 June 2021 14:01:00 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Loss of Technical Support Center Capability 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 540902019-05-26T00:30:00026 May 2019 00:30:00 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Loss of Main Control Room Area Radiation Monitors 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 531802018-01-23T10:00:00023 January 2018 10:00:00 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Loss of Assessment Capability Due to Technical Support Center Planned Maintenance ENS 521032016-07-18T20:00:00018 July 2016 20:00:00 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Loss of Offsite Communications Capability 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 511542015-06-15T12:00:00015 June 2015 12:00:00 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Tsc Ventilation to Be Removed from Service for Planned Maintenance ENS 510922015-05-27T14:45:00027 May 2015 14:45:00 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Technical Support Center Out of Service for Planned Maintenance ENS 509572015-04-06T13:09:0006 April 2015 13:09:00 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Technical Support Center Out of Service for Planned Maintenance ENS 509332015-03-27T14:41:00027 March 2015 14:41:00 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Seismic Monitor Not Available for Emergency Plan Assessment ENS 504312014-09-06T11:13:0006 September 2014 11:13:00 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Technical Support Center Air Conditioning Condensing Units Out of Service ENS 503972014-08-25T10:00:00025 August 2014 10:00:00 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Technical Support Center Planned Maintenance ENS 502472014-07-01T12:15:0001 July 2014 12:15:00 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Offsite Alert and Notification System Failure ENS 501622014-06-01T18:14:0001 June 2014 18:14:00 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Loss of Technical Support Center Cooling Capability ENS 497232013-10-16T19:20:00016 October 2013 19:20:00 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Technical Support Center Out of Service ENS 483282012-09-21T01:35:00021 September 2012 01:35:00 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Technical Support Center Ventilation Inoperable ENS 478452012-04-18T02:30:00018 April 2012 02:30:00 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Plant Process Computer Removed from Service for Planned Replacement ENS 476222012-01-26T03:00:00026 January 2012 03:00:00 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Technical Support Center Out of Service Due to Planned Maintenance ENS 467662011-04-19T04:09:00019 April 2011 04:09:00 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Plant Process Computer Removed from Service for Planned Replacement 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 431372007-02-01T15:25:0001 February 2007 15:25:00 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Loss of Offsite Phone Connections ENS 418582005-07-21T00:17:00021 July 2005 00:17:00 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Emergency Sirens Failed for One Hour 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 409222004-08-04T12:15:0004 August 2004 12:15:00 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Loss of Emergency Notification Due to Inoperable Sirens 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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