ENS 57977: Difference between revisions
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Latest revision as of 06:20, 14 October 2025
ENS Event | |
|---|---|
05:00 Oct 10, 2025 | |
| Title | Manual Reactor Trip |
| Event Description | The following information was provided by the licensee via phone and email:
At 0100 EDT, on 10/10/2025, with McGuire Unit 2 in mode 1 at 5 percent power, the reactor was manually tripped due to an approximate 4 gpm leak associated with the chemical and volume control system. The motor driven auxiliary feedwater pumps were manually started due to anticipation of automatic actuation. The trip was uncomplicated with all systems responding normally post-trip. Due to the reactor protection system actuation while critical and manual start 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 eight-hour system actuation per 50.72(b)(3)(iv)(A). At 0211 on 10/10/25, it was determined the required train of the refueling water storage tank was inoperable due to insufficient borated water volume; therefore, this condition is also being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v). The safety function was restored at 0249 on 10/10/2025 and the required train has been declared operable. There was no impact to the other unit. 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: Decay heat is being removed via steam dump valves to the main condenser, and the auxiliary feedwater system. The cause of the leak is being investigated. |
| Where | |
|---|---|
McGuire  North Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| Time - Person (Reporting Time:+-0.25 h-0.0104 days <br />-0.00149 weeks <br />-3.4245e-4 months <br />) | |
| Opened: | Michael Grembecki 04:45 Oct 10, 2025 |
| NRC Officer: | Ian Howard |
| Last Updated: | Oct 10, 2025 |
| 57977 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | (5 %) |
| After | (0 %) |
WEEKMONTHYEARENS 579772025-10-10T05:00:00010 October 2025 05:00:00
[Table view]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 2025-10-10T05:00:00 | |