ENS 43941
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ENS Event | |
|---|---|
10:31 Jan 29, 2008 | |
| Title | Manual Reactor Trip To Repair Rcp "2B1" Seal Package |
| Event Description | St Lucie Plant, Unit 2, manually tripped the reactor at 0531 hrs. EST, as part of a controlled reactor plant shutdown, in response to an RCS leak rate of 0.28 gpm, indicated to be associated with the 2B1 Reactor Coolant Pump seal package. All systems functioned as expected, satisfactorily. All CEAs fully inserted. Decay Heat removal is with Steam Generators and Main Feedwater. This report is made pursuant to 10 CFR
50.72(b)(2)(iv)(B).
Unit 2 will cooldown to Mode 5 for repairs. The licensee informed the NRC Resident Inspector.
St. Lucie Plant, Unit 2, reported their manual reactor trip of 0531 hrs. EST, at 0630 hrs. EST, for an unidentified leak associated with the 2B1 RCP seal package (EN 43941). Subsequent investigation, reported to the STA [Shift Technical Advisor] at 1015 hrs. EST, determined that this leak constitutes an RCS Pressure Boundary Leak. This leak is at a pipe-to-flange weld on the outboard side of the first flanged coupling of the 2B1 RCP Upper Cavity Seal pressure sensing line. Investigation is in progress to determine the detailed configuration at the leak and root cause. There were NO ESFAS signals or actuations. Decay Heat Removal continues on Steam Generators, with MFW [Main Feedwater] and SBCS [Steam Bypass Control System]; Off-Site power continues [to be] available and stable; Unit 1 at 100% power with operations and conditions normal. This report is made pursuant to 10 CFR 50.72(b)(3)(ii)(A). The licensee informed the NRC Resident Inspector of this update. Notified R2DO (Bonser). |
| Where | |
|---|---|
Saint Lucie  Florida (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+-4.02 h-0.168 days <br />-0.0239 weeks <br />-0.00551 months <br />) | |
| Opened: | Alan Hall 06:30 Jan 29, 2008 |
| NRC Officer: | Steve Sandin |
| Last Updated: | Jan 29, 2008 |
| 43941 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (25 %) |
| After | Hot Standby (0 %) |
Saint Lucie with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
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 569122024-01-03T17:57:0003 January 2024 17:57:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Pressure Boundary Degraded / Both Trains of High Pressure Safety Injection Inoperable ENS 568932023-12-16T01:45:00016 December 2023 01:45:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Leak 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 535982018-09-11T04:00:00011 September 2018 04:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Weld Defect on Pressurizer Interface 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 525232017-01-31T17:00:00031 January 2017 17:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant Pressure Boundary Piping Defect 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 503102014-07-25T15:29:00025 July 2014 15:29:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Technical Specification Required Shutdown Due to a Safety Injection Valve Defect 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 452002009-07-13T11:00:00013 July 2009 11:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Pressure Boundary Leakage Identified 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 438632007-12-21T19:45:00021 December 2007 19:45:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Rcs Pressure Boundary Leakage on Rcp Seal Injection Line ENS 435802007-08-19T21:00:00019 August 2007 21:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Plant Shutdown Due to Unisolable Reactor Coolant System Leakage ENS 434102007-06-06T17:10:0006 June 2007 17:10:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Containment Isolation Valves Found Misaligned 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 414012005-02-10T21:00:00010 February 2005 21:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Rcs Leakage Identified During Plant Startup Walkdowns 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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