ENS 56120
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ENS Event | |
|---|---|
07:38 Sep 26, 2022 | |
| Title | Manual Reactor Trip Due to Reported Fire on Isophase Bus Duct |
| Event Description | The following information was provided by the licensee via fax email:
At 0238 CDT on 9/26/2022 with Unit 2 in Mode 1 at 100 percent power, the reactor manually tripped due to a reported fire on the isophase bus duct. The trip was uncomplicated with all systems responding normally post-trip with the exception of the 2A reactor protection system power supply, which tripped and power was transferred to the alternate source. The fire was reported extinguished at 0240 CDT on 9/26/2022. 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 the emergency operating procedure LGA-001 and stabilized the plant in Mode 3. Decay heat is removed by discharging steam to the main condenser using the turbine bypass valves. Unit 1 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:+-0.98 h-0.0408 days <br />-0.00583 weeks <br />-0.00134 months <br />) | |
| Opened: | Jeff Nugent 06:39 Sep 26, 2022 |
| NRC Officer: | Bill Gott |
| Last Updated: | Sep 26, 2022 |
| 56120 - NRC Website | |
Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
WEEKMONTHYEARENS 561202022-09-26T07:38:00026 September 2022 07:38:00
[Table view]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 2022-09-26T07:38:00 | |
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