ENS 40375
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ENS Event | |
|---|---|
21:32 Dec 4, 2003 | |
| Title | St. Lucie Unit 2 Manual Reactor Trip Due to Loss of Condensate Pump |
| Event Description | On December 4, 2003, at 1605 hours0.0186 days <br />0.446 hours <br />0.00265 weeks <br />6.107025e-4 months <br />, a down power was initiated due to a failing bearing on the 2A Condensate Pump. The pump bearing was hot and smoking. The plant fire team was deployed as a precautionary action. Due to continued degradation of the Pump bearing, a Manual Reactor Trip was initiated at approximately 60% power. Feed to the 2A and 2B Steam Generators was maintained via the 2B Main Feedwater Pump. All plant safety systems responded normally and plant safety functions were maintained throughout the event. The Plant was stabilized In Mode 3. Plant post trip anomalies include Steam Generator Blowdown isolation valves closed, Control Room ventilation system swapped to recirculation mode, the Fuel Handling Building ventilation system swapped to the Shield Building, and it was necessary to take Steam Bypass Control System to manual. An Emergency Response Team was formed to review these conditions prior to plant restart. This non-emergency notification is being made pursuant to 10 CFR 50.72(b)(2)(iv)(B) due to the manual initiation of the RPS Reactor Trip.
All control rods fully inserted into the reactor on the trip. The emergency diesel generators are available and the offsite electrical grid is in a normal configuration. No safety relief valves or power operated relief valves were known to have actuated during this event. St. Lucie Unit 1 was not affected and continues to operate in mode 1 at 100% rated thermal power. The licensee has notified the NRC Resident Inspector. |
| Where | |
|---|---|
Saint Lucie  Florida (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| Time - Person (Reporting Time:+-1.3 h-0.0542 days <br />-0.00774 weeks <br />-0.00178 months <br />) | |
| Opened: | Calvin Ward 20:14 Dec 4, 2003 |
| NRC Officer: | Gerry Waig |
| Last Updated: | Dec 4, 2003 |
| 40375 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
WEEKMONTHYEARENS 572492024-07-28T22:37:00028 July 2024 22:37:00
[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 571772024-06-18T07:17:00018 June 2024 07:17:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip ENS 571612024-06-04T17:52:0004 June 2024 17:52:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip ENS 560872022-09-03T02:48:0003 September 2022 02:48:00 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 Feed Pump ENS 556412021-12-10T15:24:00010 December 2021 15:24:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip ENS 550782021-01-20T23:22:00020 January 2021 23:22:00 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 Motor Control Center ENS 542622019-09-07T12:24:0007 September 2019 12:24:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip ENS 540272019-04-25T13:18:00025 April 2019 13:18:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip Due to Turbine Generator Trip ENS 537032018-10-29T04:00:00029 October 2018 04:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Inadequate Feedwater Flow ENS 536652018-10-12T04:00:00012 October 2018 04:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip ENS 530362017-10-26T06:12:00026 October 2017 06:12:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Following a Loss of Load ENS 521912016-08-21T23:37:00021 August 2016 23:37:00 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 Unusual Event - Loss of Offsite Power ENS 513022015-08-10T02:15:00010 August 2015 02:15:00 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 Testing ENS 506072014-11-12T20:48:00012 November 2014 20:48:00 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 Lowering Steam Generator Water Level ENS 495362013-11-14T17:18:00014 November 2013 17:18:00 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 Low Level in the 2B Steam Generator ENS 495282013-11-12T05:02:00012 November 2013 05:02:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Unisolable Leak in Digital Electro-Hydraulic System ENS 490822013-05-31T11:12:00031 May 2013 11:12:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to an Anticipated Loss of Condenser Cooling ENS 488182013-03-12T18:51:00012 March 2013 18:51:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip on Thermal Margin/Low Pressure ENS 479872012-06-02T23:35:0002 June 2012 23:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Trip Due to a Turbine Control System Failure ENS 479152012-05-11T07:55:00011 May 2012 07:55:00 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 Feedwater Control Valve Failure ENS 477932012-03-31T04:22:00031 March 2012 04:22:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Uncontrolled Cooldown ENS 477522012-03-19T03:36:00019 March 2012 03:36:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Control Element Assembly Anomalous Behavior ENS 473532011-10-19T09:28:00019 October 2011 09:28:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip on Loss of Condenser Vacuum ENS 471782011-08-22T19:13:00022 August 2011 19:13:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release, 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Rising Condenser Backpressure ENS 469282011-06-06T07:29:0006 June 2011 07:29:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Error During Reactor Protection System Surveillance Leads to Reactor Trip ENS 460182010-06-16T21:10:00016 June 2010 21:10:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip After Two Control Rods Dropped ENS 458432010-04-15T19:39:00015 April 2010 19:39:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unplanned Manual Reactor Trip ENS 449522009-04-01T22:05:0001 April 2009 22:05:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unplanned Manual Reactor Trip ENS 442762008-06-07T12:18:0007 June 2008 12:18:00 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 the Trip of a Condensate Pump ENS 442682008-06-04T21:30:0004 June 2008 21:30:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Following Loss of Main Feedwater Pump ENS 439412008-01-29T10:31:00029 January 2008 10:31:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Manual Reactor Trip to Repair Rcp "2B1" Seal Package ENS 426472006-06-16T02:23:00016 June 2006 02:23:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Digital Electro-Hydraulic Leak ENS 422772006-01-20T13:56:00020 January 2006 13:56:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Rps Actuation ENS 419112005-08-11T14:48:00011 August 2005 14:48:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip on a Condensate Pump Bus Lockout ENS 412972004-12-27T22:20:00027 December 2004 22:20:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Following Problem with Steam Generator Water Level Control ENS 412932004-12-25T11:52:00025 December 2004 11:52:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 2 Manually Tripped to Remove Failing Condensate Pump from Service ENS 410182004-09-04T05:56:0004 September 2004 05:56:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Steam Generator Level Oscillations ENS 404032003-12-20T14:49:00020 December 2003 14:49:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Rps Actuation Due to Loss of Turbine Generator Excitation ENS 403752003-12-04T21:32:0004 December 2003 21:32:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation St. Lucie Unit 2 Manual Reactor Trip Due to Loss of Condensate Pump 2024-07-28T22:37:00 | |
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