ENS 58100
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ENS Event | |
|---|---|
22:06 Dec 28, 2025 | |
| Title | Manual Reactor Scram Due to RCS Leak |
| Event Description | The following information was provided by the licensee via phone and email:
At 1606 CST with Unit 1 in mode 1 at 93 percent power, the reactor was manually tripped due to degrading containment parameters associated with a leak from the 'B' reactor recirculation pump line, which has been isolated. The trip was not complex, however the 'A' reactor recirculation pump tripped to OFF instead of down-shifting to slow speed. Due to the 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). Operations responded using emergency operations procedures and stabilized the unit in plant mode 3 (hot shutdown). Decay heat is being removed by discharging steam to the main condenser using the turbine bypass valves. Unit 2 is not affected. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. |
| Where | |
|---|---|
LaSalle  Illinois (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| Time - Person (Reporting Time:+-1.67 h-0.0696 days <br />-0.00994 weeks <br />-0.00229 months <br />) | |
| Opened: | Brock Pollmann 20:26 Dec 28, 2025 |
| NRC Officer: | Robert A. Thompson |
| Last Updated: | Dec 28, 2025 |
| 58100 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (93 %) |
| After | Hot Shutdown (0 %) |
WEEKMONTHYEARENS 581002025-12-28T22:06:00028 December 2025 22:06:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to RCS Leak ENS 580182025-11-02T19:46:0002 November 2025 19:46:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram ENS 561202022-09-26T07:38:00026 September 2022 07:38:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Reported Fire on Isophase Bus Duct ENS 535762018-08-31T05:00:00031 August 2018 05:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Main Condenser Degradation ENS 525642017-02-18T05:53:00018 February 2017 05:53:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Resulting from Feedwater Regulating Valve Failure ENS 525472017-02-14T05:09:00014 February 2017 05:09:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Unit 1 Automatic Reactor Scram Due to Main Generator Trip on Differential Current ENS 525052017-01-23T14:06:00023 January 2017 14:06:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Stator Water Cooling Runback Signal and Turbine Bypass Valve Opening ENS 503462014-08-05T22:34:0005 August 2014 22:34:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram ENS 489692013-04-26T01:19:00026 April 2013 01:19:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Following Trip of Circ Water Pumps ENS 489392013-04-17T20:11:00017 April 2013 20:11:00 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, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Notification of Unusual Event Declared Due to Loss of Offsite Power from a Lightning Strike ENS 465822011-02-02T01:18:0002 February 2011 01:18:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Scram After a Main Transformer Trip ENS 452652009-08-15T21:06:00015 August 2009 21:06:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to a Turbine Trip ENS 450872009-05-21T21:35:00021 May 2009 21:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Rps Actuation (Scram) Due to a Main Power Transformer Fault ENS 423482006-02-20T06:23:00020 February 2006 06:23:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Site Area Emergency - Reactor Scram ENS 403572003-11-27T06:52:00027 November 2003 06:52:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Manually Scrammed from 23% Due to Decreasing Reactor Vessel Water Level 2025-12-28T22:06:00 | |
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