ENS 57540
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ENS Event | |
|---|---|
17:16 Feb 10, 2025 | |
| Title | Manual Reactor Trip Due to Electrohydraulic Control System Leak |
| Event Description | ?
The following information was provided by the licensee via phone and email: At 1216 EST, on 2/10/2025 with Unit 1 in mode 1 at 66.5 percent power, the reactor was manually tripped due to an electro-hydraulic control power system leak. 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 four-hour, non-emergency notification per 10 CFR50.72(b)(2)(iv)(B) and an eight-hour, non-emergency notification per 10CFR 50.72(b)(3)(iv)(A) resulting from a 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. |
| Where | |
|---|---|
Summer  South Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-1.92 h-0.08 days <br />-0.0114 weeks <br />-0.00263 months <br />) | |
| Opened: | Elvis Zimmerman 15:21 Feb 10, 2025 |
| NRC Officer: | Brian P. Smith |
| Last Updated: | Feb 10, 2025 |
| 57540 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (67 %) |
| After | Hot Standby (0 %) |
Summer with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
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 578592025-08-11T06:12:00011 August 2025 06:12:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Actuation of the 'A' Emergency Diesel Generator 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 569782024-02-19T07:36:00019 February 2024 07:36:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Start of 'B' Emergency Diesel Generator 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 531762018-01-18T17:02:00018 January 2018 17:02:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator Actuation Due to Loss of One of Two Offsite Power Supplies 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 529622017-09-11T20:48:00011 September 2017 20:48:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator Actuation on Low Voltage 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 488462013-03-24T08:58:00024 March 2013 08:58:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Start of an Emergency Diesel Generator Due to a Lightning Strike ENS 468992011-05-27T16:00:00027 May 2011 16:00:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Safety Injection Initiated Due to a High Differential Pressure Between Main Steam Lines 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 442312008-05-21T21:04:00021 May 2008 21:04:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator Shifted to Emergency Start During Post Maintenance Test 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 429982006-11-09T19:44:0009 November 2006 19:44:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator Actuation During Testing ENS 417062005-05-18T05:54:00018 May 2005 05:54:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of Balance of Plant Power Due to Transformers Lockout ENS 408112004-06-13T00:29:00013 June 2004 00:29:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Started and Loaded on Bus Undervoltage Signal 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 ENS 403482003-11-21T14:10:00021 November 2003 14:10:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Control Bank "C" Rods Tripped Due to Incorrect Digital Rod Position Indication (Drpi) 2025-08-11T06:12:00 | |
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