ENS 40406
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ENS Event | |
|---|---|
14:27 Dec 22, 2003 | |
| Title | Reactor Trip Due to Main Turbine Trip |
| Event Description | At 0827 on 12/22/2003, Comanche Peak Unit Two (2) tripped due to a turbine trip > 50%. The turbine trip was caused by ingestion of a small metallic cover plate into the main generator exciter housing, as witnessed by maintenance personnel. A small fire ensued, which self-extinguished in five (5) minutes. An Aux Feedwater auto start (ESF actuation) occurred due to normal post-trip steam generator shrink. The turbine-driven and both motor-driven aux feedwater pumps started as designed.
All control rods inserted into the core upon trip. The local electrical grid is stable. The number one (1) steam generator atmospheric relief valve cycled as designed upon the secondary pressure transient. The number three (3) Reactor Coolant Pump tripped during the transfer of power sources post-trip. Unit 1 was not affected by the trip. Unit 2 is stable in Mode 3. Damage assessment is in progress which will determine future (near-term) plant mode of operation. RCPs are in operation transferring decay heat to the steam generators. Decay heat removal is through the MSIVs to the main condenser using the turbine steam dump valves. Both motor-driven AFW pumps are running to maintain Steam Generator levels. The trip of the number (3) Reactor Coolant Pump is being investigated. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Comanche Peak  Texas (NRC Region 4) | |
| 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: | Richard Brabec 11:39 Dec 22, 2003 |
| NRC Officer: | Jeff Rotton |
| Last Updated: | Dec 22, 2003 |
| 40406 - NRC Website | |
Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (99 %) |
| After | Hot Standby (0 %) |
Comanche Peak with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 570332024-03-17T20:15:00017 March 2024 20:15:00
[Table view]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 Feedwater Pump Trip ENS 570242024-03-12T13:16:00012 March 2024 13:16:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip ENS 565802023-06-16T23:32:00016 June 2023 23:32:00 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 LO-LO Steam Generator Level ENS 560912022-09-06T04:45:0006 September 2022 04:45:00 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 Turbine Trip ENS 552952021-06-07T20:27:0007 June 2021 20:27:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip on Turbine Trip Due to Fault and Fire in the Main Transformer ENS 544602020-01-01T18:53:0001 January 2020 18:53:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip and Specified System Actuation ENS 540642019-05-15T02:51:00015 May 2019 02:51:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Voltage Transient Due to Loss of Offsite Switchyard ENS 539062019-03-02T09:17:0002 March 2019 09:17:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip Due to Feedwater Isolation Valve Closure ENS 537672018-12-03T06:00:0003 December 2018 06:00:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Actuation of Blackout Sequencers Due to Loss of One Offsite Power Source ENS 535502018-08-13T05:00:00013 August 2018 05:00:00 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 Generator Lockout ENS 530912017-11-26T02:25:00026 November 2017 02:25:00 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 Main Feed Water ENS 529452017-09-02T02:40:0002 September 2017 02:40:00 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 Two Dropped Rods ENS 528982017-08-11T16:24:00011 August 2017 16:24:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Comanche Peak Automatic Turbine Trip from 10 Percent Power ENS 514442015-10-03T15:00:0003 October 2015 15:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip During Shutdown for a Refueling Outage ENS 497432014-01-18T14:40:00018 January 2014 14:40:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip Due to Turbine Trip ENS 496062013-12-04T19:50:0004 December 2013 19:50:00 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unusual Event - Loss of Startup Power Due to a Cut Cable ENS 494972013-11-02T02:47:0002 November 2013 02:47:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip During Solid State Protection System Testing ENS 485142012-11-17T16:23:00017 November 2012 16:23:00 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 Low Steam Generator Water Level ENS 484752012-11-02T06:42:0002 November 2012 06:42:00 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 Reactor Coolant Pump Motor Bearing Temperature ENS 468632011-05-19T19:07:00019 May 2011 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 After a Main Condenser Tube Leak ENS 467482011-04-13T03:15:00013 April 2011 03:15:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Esf Actuation Following Loss of a Safeguard Bus During Edg Testing ENS 458332010-04-12T12:21:00012 April 2010 12:21:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Actuation of Blackout Sequencers Due to Loss of One Offsite Power Source ENS 456172010-01-09T16:28:0009 January 2010 16:28:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Turbine Trip on Sudden Pressure in Output Transformer ENS 440672008-03-16T16:37:00016 March 2008 16:37:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip Due to Broken Sensing Line ENS 429452006-10-29T21:20:00029 October 2006 21:20:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Trip Due to Lowering Steam Generator Level ENS 429372006-10-27T08:08:00027 October 2006 08:08:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Due to Loss of Both Main Feed Pumps ENS 414322005-02-23T07:53:00023 February 2005 07:53:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Auxiliary Feedwater Action Following Momentary Power Interruption ENS 411342004-10-19T10:28:00019 October 2004 10:28:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of Normal Power Supply to "2E" Switchgear Resulted in Afw Autostart ENS 404062003-12-22T14:27:00022 December 2003 14:27:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip Due to Main Turbine Trip 2024-03-17T20:15:00 | |
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