ENS 45867
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ENS Event | |
|---|---|
10:03 Apr 19, 2010 | |
| Title | Rps and Afw Actuation Signals While Shutdown in Mode 4 |
| Event Description | Unit 2 was in Hot Shutdown [Mode 4] for a Refueling Outage. At 0503 [CDT] on April 19, 2010, a valid Lo-Lo Steam Generator level condition occurred during restoration of feedwater system testing. The feedwater test was a planned activity and included isolation of feedwater to the steam generators. During performance of the test, steam generator levels decreased and the Lo-Lo level setpoint was reached on the 2D steam generator. This generated a reactor trip signal and auxiliary feedwater system start signal. Since the Unit was in Hot Shutdown, the reactor trip breakers were already open, and the auxiliary feedwater system was already removed from service when the steam generator water level unintentionally reached the Lo-Lo level setpoint. Additionally, the open steam generator blowdown isolation valves closed as expected at the Lo-Lo steam generator level setpoint. Steam generator level was promptly restored above the Lo-Lo steam generator setpoint. There was no impact on the reactor cooldown that was concurrently in progress as part of the preparation for refueling. Initial screening of the condition determined as not reportable in accordance with 10 CFR 50.72(b)(3)(iv), however, based upon further review it has been determined the condition is reportable.
At the time of the event, both trains of shutdown cooling were in service and there were no challenges to offsite power. The licensee was not required to enter any Technical Specification LCO action statements as a result of the event, and the licensee is still investigating the cause of the decrease in steam generator level below the Lo-Lo level setpoint. The licensee has informed the NRC Resident Inspector. |
| Where | |
|---|---|
Byron  Illinois (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+77.23 h3.218 days <br />0.46 weeks <br />0.106 months <br />) | |
| Opened: | Blaine Peters 15:17 Apr 22, 2010 |
| NRC Officer: | Ryan Alexander |
| Last Updated: | Apr 22, 2010 |
| 45867 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Hot Shutdown (0 %) |
| After | Hot Shutdown (0 %) |
WEEKMONTHYEARENS 540202019-04-22T18:24:00022 April 2019 18:24:00
[Table view]10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Initiation of the Auxiliary Feedwater System in Response to a Loss of Feedwater ENS 534912018-07-06T05:00:0006 July 2018 05:00:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Transformer Failure Causes Loss of Offsite Power to Unit 2 ENS 522952016-10-12T18:38:00012 October 2016 18:38:00 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 Spurious Feedwater Isolation ENS 508592015-03-03T17:01:0003 March 2015 17:01:00 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 Main Power Transformer Bushing Short ENS 499192014-03-15T16:02:00015 March 2014 16:02:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Momentary Loss of Shutdown Cooling Due to a Loss of Offsite Power ENS 488382013-03-21T00:51:00021 March 2013 00:51:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Loss of Generator Stator Cooling Water ENS 477082012-02-28T23:31:00028 February 2012 23:31:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unusual Event Due to Loss of Offsite Power ENS 476442012-02-06T23:19:0006 February 2012 23:19:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Rps Actuation Due to Turbine Trip ENS 476242012-01-30T16:01:00030 January 2012 16:01:00 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)(i), Tech Spec Required Shutdown Unusual Event Due to Loss of Offsite Power Greater than 15 Minutes ENS 458672010-04-19T10:03:00019 April 2010 10:03:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Rps and Afw Actuation Signals While Shutdown in Mode 4 ENS 420632005-10-19T05:57:00019 October 2005 05:57:00 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 Low 2 Steam Generator Water Level 2019-04-22T18:24:00 | |
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