ENS 44067
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ENS Event | |
|---|---|
16:37 Mar 16, 2008 | |
| Title | Reactor Trip Due to Broken Sensing Line |
| Event Description | At 1137 CDT, Comanche Peak NPP, Unit 2 reactor tripped due to a broken sensing line feeding the vacuum inputs to the 2/3 low vacuum turbine trip. With the reactor power steady at 100%, the turbine trip signal generated a valid RPS reactor trip signal. All control rods fully inserted. Both motor driven AFW pumps and the turbine driven AFW pump started as a result of low steam generator level following the trip.
Currently Unit 2 is in Mode 3, stable with RCS temperature at no-load program temperature of 557 degree F being maintained on the steam dumps. All 4 steam generators are at program level, being maintained by the motor driven AFW pumps. The turbine driven AFW pump has been returned to standby. 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:+-2.42 h-0.101 days <br />-0.0144 weeks <br />-0.00331 months <br />) | |
| Opened: | Pat Minahan 14:12 Mar 16, 2008 |
| NRC Officer: | John Knoke |
| Last Updated: | Mar 16, 2008 |
| 44067 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (100 %) |
| 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
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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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