ENS 58101
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ENS Event | |
|---|---|
17:29 Dec 29, 2025 | |
| Title | Automatic Reactor Trip |
| Event Description | The following information was provided by the licensee via phone and email:
At 1229 EST on 12/29/2025, with Unit 1 in mode 1 at approximately 100 percent power, the reactor automatically tripped due to a lockout of the main generator. The trip was not complex, with all systems responding normally post-trip. Operations manually started the motor driven auxiliary feedwater pumps due to anticipation of automatic actuation and has stabilized Unit 1. Decay heat is being removed by the condenser. Unit 2 was not affected. Due to the reactor protection system actuation while critical and actuation of the motor driven auxiliary feedwater pumps, this event is being reported as a four-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). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. |
| Where | |
|---|---|
McGuire  North Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| Time - Person (Reporting Time:+-1.48 h-0.0617 days <br />-0.00881 weeks <br />-0.00203 months <br />) | |
| Opened: | Michael Grembecki 16:00 Dec 29, 2025 |
| NRC Officer: | Robert A. Thompson |
| Last Updated: | Dec 29, 2025 |
| 58101 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
WEEKMONTHYEARENS 581012025-12-29T17:29:00029 December 2025 17:29:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip ENS 579772025-10-10T05:00:00010 October 2025 05:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip ENS 557482022-02-18T09:59:00018 February 2022 09:59:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip and System Actuation ENS 540472019-05-03T19:54:0003 May 2019 19:54:00 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 Over Temperature Delta Temperature ENS 532172018-02-16T15:14:00016 February 2018 15:14:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip During Solid State Protection System Testing ENS 495382013-11-14T18:13:00014 November 2013 18:13:00 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 Indication of Dropped Control Rods ENS 487752013-02-21T14:57:00021 February 2013 14:57:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Turbine Trip on Loss of Both Main Feed Pumps ENS 465592011-01-20T20:18:00020 January 2011 20:18:00 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 Loss of Both Main Feed Pumps During Shutdown ENS 460032010-06-12T10:44:00012 June 2010 10:44:00 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 a Control Rod Drop Indication ENS 443182008-06-26T21:32:00026 June 2008 21:32:00 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 Loss of 1B Reactor Coolant Pump ENS 422112005-12-17T08:11:00017 December 2005 08:11:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip from Full Power Due to a Failed Feed Flow Channel ENS 414532005-03-01T20:45:0001 March 2005 20:45:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip During a Rapid Shutdown for Steam Leak Repair 2025-12-29T17:29:00 | |
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