ENS 57987
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ENS Event | |
|---|---|
19:52 Oct 14, 2025 | |
| Title | Automatic Reactor Trip |
| Event Description | The following information was provided by the licensee via phone and email:
At 1552 EDT on October 14, 2025, with Unit 1 in mode 1 at 100 percent power, the reactor automatically tripped due to a turbine trip. The trip was not complex with all systems responding normally post-trip. Operations responded and stabilized the plant. Decay heat is being removed by the emergency feedwater system. Due to the reactor protection system actuation while critical, this event is being reported as a 4-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B) and an 8-hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A) for valid actuation of the reactor protection and emergency feedwater systems. There was no impact on the health and safety of the public or plant personnel. The NRC resident inspector has been notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: A generator field breaker lockout occurred. In addition, a small fire was observed in the generator field breaker and extinguished in less than 15 minutes by the onsite fire brigade. The unit is stable in hot standby with emergency feedwater and main condenser steam dumps in-service. |
| Where | |
|---|---|
Summer  South Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| Time - Person (Reporting Time:+-2.08 h-0.0867 days <br />-0.0124 weeks <br />-0.00285 months <br />) | |
| Opened: | Lauren Anderson 17:47 Oct 14, 2025 |
| NRC Officer: | Brian P. Smith |
| Last Updated: | Oct 25, 2025 |
| 57987 - NRC Website
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WEEKMONTHYEARENS 579872025-10-14T19:52:00014 October 2025 19:52:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip ENS 575402025-02-10T17:16:00010 February 2025 17:16:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Electrohydraulic Control System Leak ENS 564532023-04-05T10:51:0005 April 2023 10:51:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip ENS 555802021-11-15T22:28:00015 November 2021 22:28:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Main Transformer Fault ENS 530602017-11-08T00:57:0008 November 2017 00:57:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip on Turbine Trip ENS 529322017-08-28T12:37:00028 August 2017 12:37:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip on Turbine Trip ENS 528332017-06-29T12:57:00029 June 2017 12:57:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Trip Due to a Loss of Normal Feedwater Flow to B Steam Generator ENS 502932014-07-22T08:14:00022 July 2014 08:14:00 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 Low Steam Generator Level ENS 455772009-12-16T19:15:00016 December 2009 19:15:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Following a Failure of the Steam Dump System ENS 454042009-10-02T10:49:0002 October 2009 10:49:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip on Turbine Trip Possibly Caused by a Faulted Main Generator Breaker ENS 439322008-01-24T21:04:00024 January 2008 21:04:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Failure of the "C" Feedwater Flow Control Valve ENS 431412007-02-05T08:07:0005 February 2007 08:07:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Steam Leak During Main Feed Booster Pump Startup ENS 430042006-11-22T09:26:00022 November 2006 09:26:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Main Turbine Trip Due to High- High Steam Generator "B" Water Level During Feedwater Swap Over. ENS 406282004-03-30T16:29:00030 March 2004 16:29:00 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)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Automatic Reactor Trip Due to Lo-Lo Steam Generator Level 2025-02-10T17:16:00 | |
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