ENS 46582
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ENS Event | |
|---|---|
01:18 Feb 2, 2011 | |
| Title | Reactor Scram After a Main Transformer Trip |
| Event Description | At 1918 CST on February 1st 2011, LaSalle Unit 1 automatically scrammed due to a MPT [Main Power Transformer] trip and subsequent load reject, both RFP [Reactor Feed Pumps] tripped and [the reactor] scrammed on TCV [Throttle Control Valve] fast closure. 'U' safety relief valve actuated in the relief mode on the turbine trip and has subsequently reset with tailpipe temp returning to normal. As a result of the electrical transient, U1 and U2 RWCU [Reactor Water Cleanup] isolated, and this is not reportable due to being a single train system and there was no isolation in multiple systems. The plant is stable with reactor pressure control to the main condenser via the main steam isolation valves. Unit 2 remained at 96% in coastdown throughout the event. The plant is planned to remain in hot shutdown pending investigation of the cause of the MPT trip and load reject.
All control rods fully inserted on the reactor scram. The cause of the RFP trips was swelling of the reactor water level as expected after a scram. The first out alarm was "turbine control valve fast closure." The plant is experiencing severe weather which may have influenced the MPT trip. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Lasalle  Illinois (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| LER: | 05000373/LER-2011-001 |
| Time - Person (Reporting Time:+-2.4 h-0.1 days <br />-0.0143 weeks <br />-0.00329 months <br />) | |
| Opened: | Michael Fitzpatrick 22:54 Feb 1, 2011 |
| NRC Officer: | Mark Abramovitz |
| Last Updated: | Feb 1, 2011 |
| 46582 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (100 %) |
| After | Hot Shutdown (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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