ENS 43866
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ENS Event | |
|---|---|
02:10 Dec 26, 2007 | |
| Title | Automatic Reactor Trip Due To Trip Of "B" Reactor Coolant Pump |
| Event Description | On 12/25/07 at 2110 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.02855e-4 months <br /> EST, Unit 2 tripped from 100% power due to a trip of the 'B' Reactor Coolant Pump. The reactor trip 1st out annunciator was 'Loss of flow, power >30%'. All control rods fully inserted. This event is reportable per 10 CFR 50.72(b)(2)(iv)(B). The Auxiliary Feedwater [AFW] pumps auto started due to the event and the steam driven AFW pump subsequently tripped on overspeed. The steam driven AFW pump was reset and placed in service. The ESF [Engineered Safety Function] actuation is reportable per 10 CFR 50.72(b)(3)(iv)(A). The unit is currently in mode 3 and [the licensee is] investigating the cause of the ground on the 'B' reactor coolant pump.
The plant is at normal operating pressure and temperature. The electrical grid is stable and supplying plant loads through the startup transformer. Decay heat is being removed via the steam dumps to the condenser with feedwater being supplied via the normal path. The licensee has notified the NRC Resident Inspector. |
| 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:+-2.8 h-0.117 days <br />-0.0167 weeks <br />-0.00384 months <br />) | |
| Opened: | Page Kemp 23:22 Dec 25, 2007 |
| NRC Officer: | Howie Crouch |
| Last Updated: | Dec 25, 2007 |
| 43866 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (100 %) |
| 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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