ENS 49429
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ENS Event | |
|---|---|
17:17 Oct 11, 2013 | |
| Title | Automatic Turbine and Reactor Trip Due to Station Service Transformer Lockout |
| Event Description | At 1317 hours0.0152 days <br />0.366 hours <br />0.00218 weeks <br />5.011185e-4 months <br /> on 10/11/2013, Unit 1 experienced an automatic turbine and reactor trip from 48% power. Unit 1 was in the process of increasing power level following a refueling outage when the 1C Station Service Transformer Lockout Relay actuated as the 'C' Condensate Pump was started. The 1C Station Service Transformer Lockout resulted in the turbine trip which subsequently tripped the reactor. All three station service electrical buses transferred to the Reserve Station Service Transformers. The 1C Station Service Transformer does not have any visible exterior damage. All control rods fully inserted into the core following the reactor trip. The actuation of the Reactor Protection System is reportable per 10CFR50.72(b)(2)(iv)(B).
The Auxiliary Feedwater Pumps actuated as designed following the trip and provided makeup flow to the steam generators. The steam generator levels were returned to normal operating level and the Auxiliary Feedwater Pumps were returned to automatic. The actuation of the Auxiliary Feedwater Pumps is reportable per 10CFR50.72(b)(3)(iv)(A). Due to low decay heat loads, the Main Steam Trip Valves were closed as the Reactor Coolant Tavg temperature decreased, as directed by the reactor trip response procedure and decay heat is being removed using the atmospheric steam dumps. Decay heat control will be transferred to the main condenser steam dump system. Unit 1 is stable in Mode 3 at normal Reactor Coolant System temperature and pressure. Unit 2 is operating at 100% power and was not affected by this event. The licensee has notified the NRC Resident Inspector and the local government. |
| Where | |
|---|---|
North Anna  Virginia (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:+-2.17 h-0.0904 days <br />-0.0129 weeks <br />-0.00297 months <br />) | |
| Opened: | Page Kemp 15:07 Oct 11, 2013 |
| NRC Officer: | Dong Park |
| Last Updated: | Oct 11, 2013 |
| 49429 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (48 %) |
| After | Hot Standby (0 %) |
North Anna with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 571482024-05-29T10:24:00029 May 2024 10:24:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip ENS 558432022-04-14T13:28:00014 April 2022 13:28:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip During Control Rod Testing ENS 552392021-05-06T16:23:0006 May 2021 16:23:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip ENS 539082019-03-03T03:37:0003 March 2019 03:37:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Degrading Main Condenser Vacuum ENS 535792018-09-03T04:00:0003 September 2018 04:00:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Start of the Emergency Diesel Generator ENS 518922016-04-30T02:14:00030 April 2016 02:14:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of Offsite Power to the a Reserve Station Service Transformer ENS 516782016-01-23T22:03:00023 January 2016 22:03:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Partial Loss of Power Results in Emergency Diesel Generators Starting ENS 509462015-04-02T08:26:0002 April 2015 08:26:00 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 Generator Voltage Regulator Failure ENS 508512015-02-26T20:11:00026 February 2015 20:11:00 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 Feedwater Regulating Valve Failing Closed ENS 501162014-05-15T23:20:00015 May 2014 23:20:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 1 and Unit 2 Emergency Diesel Generators Start and Load Due to Loss of One 34.5Kv Line ENS 497842014-02-02T13:59:0002 February 2014 13:59:00 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 Loss of the "a" Main Feedwater Pump ENS 494292013-10-11T17:17:00011 October 2013 17:17:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Turbine and Reactor Trip Due to Station Service Transformer Lockout ENS 490752013-05-28T19:07:00028 May 2013 19:07:00 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 a Feedwater Transient ENS 490202013-05-10T10:12:00010 May 2013 10:12:00 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 High Turbine Bearing Vibration ENS 484362012-10-24T05:47:00024 October 2012 05:47:00 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 Low Steam Generator Water Level ENS 463522010-10-22T10:36:00022 October 2010 10:36:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip During Physics Testing Due to Problems with the Rod Control in Hold Out Switch ENS 460202010-06-16T23:20:00016 June 2010 23:20:00 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 a Lightning Storm ENS 459602010-05-28T04:03:00028 May 2010 04:03:00 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 Loss of Reactor Coolant Pump ENS 458772010-04-27T20:37:00027 April 2010 20:37:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip Following a Generator Lockout During Automatic Voltage Regulator Testing ENS 455562009-12-09T19:23:0009 December 2009 19:23:00 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 Unit 2 and Edg Start on Both Units Due to Inadvertent Loss of "C" Reserve Station Service Transformer ENS 450262009-04-28T13:53:00028 April 2009 13:53:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Auto-Start Due to Loss of the "B" Reserve Station Service Transformer ENS 439722008-02-08T23:12:0008 February 2008 23:12:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Control Rod Position Deviation ENS 438662007-12-26T02:10:00026 December 2007 02:10:00 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 Trip of "B" Reactor Coolant Pump ENS 434622007-06-29T21:52:00029 June 2007 21:52:00 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)(iv)(A), System Actuation - ECCS Discharge Reactor Trip and Spurious Safety Injection ENS 432172007-03-07T08:05:0007 March 2007 08:05:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator Autostart on Loss of "B" Reserve Station Service Transformer ENS 430722007-01-03T23:03:0003 January 2007 23:03:00 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 a Card Failure ENS 429962006-11-16T07:26:00016 November 2006 07:26:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip ENS 424832006-04-08T02:31:0008 April 2006 02:31:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Group Step Counter Failure During Reactor Startup ENS 418982005-08-06T02:28:0006 August 2005 02:28:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Apparently Due to Lightning Strike ENS 408042004-06-10T17:13:00010 June 2004 17:13:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip While Performing Scheduled Solid State Protection Testing ENS 407842004-05-29T06:02:00029 May 2004 06:02:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Control Rod Position Indication Failure During Hot Rod Drop Test 2024-05-29T10:24:00 | |
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