ENS 57839
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ENS Event | |
|---|---|
17:30 Jul 30, 2025 | |
| Title | Automatic Reactor Trip |
| Event Description | The following information was provided by the licensee via phone and email:
On July 30, 2025, at 1230 CDT, with Unit 1 in mode 1 at 100 percent power, the reactor automatically tripped due to an over temperature delta 'T' reactor protection system actuation while critical. This event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). Actuation of the auxiliary feedwater [system] occurred during the reactor trip response. The cause of the auxiliary feedwater auto-start was a LO-2 steam generator water level. The 1A and 1B auxiliary feedwater pumps started as designed when the LO-2 steam generator water level signal was received. This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the auxiliary feedwater system. Operators responded using procedures 1BwEP-0 and 1BwEP ES-0.1 to stabilize the unit in mode 3. Decay heat is being removed by discharging steam to the main condenser using the main steam dump valves. Unit 2 is not affected. All systems responded as expected with the exception of steam pressure channel 1Pl-545A and steam flow channel 1Fl-523A, which both failed high during the lightning storm and subsequent transient. Actions per 1BwOA lnstrument-2 are in progress to address these failures. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. |
| 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 | |
| LER: | 05000456/LER-2025-001 Over Temperature Delta Temperature Due to Lightning Strike |
| Time - Person (Reporting Time:+-0.17 h-0.00708 days <br />-0.00101 weeks <br />-2.32866e-4 months <br />) | |
| Opened: | Matthew Mchale 17:20 Jul 30, 2025 |
| NRC Officer: | Kerby Scales |
| Last Updated: | Jul 30, 2025 |
| 57839 - NRC Website
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Braidwood with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 578392025-07-30T17:30:00030 July 2025 17:30:00
[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 ENS 571072024-05-05T08:38:0005 May 2024 08:38:00 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 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 2025-07-30T17:30:00 | |
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