ENS 50310
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ENS Event | |
|---|---|
15:29 Jul 25, 2014 | |
| Title | Technical Specification Required Shutdown Due to a Safety Injection Valve Defect |
| Event Description | On July 25th, 2014 at 1129 EDT, during investigation of a small leak inside Saint Lucie Unit 2 containment, a defect was identified on a valve (V3811, Safety Injection Tank 281 Outlet Vent Valve). This valve is within the Q-Group A (ASME Class 1 equivalent) boundary of the safety injection line. The leak is currently isolated from the reactor coolant system by a Technical Specification credited isolation check valve. The affected Safety Injection Tank has been declared inoperable and the unit has entered 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> shutdown [Technical Specification] action statement 3.5.1.b. Unit shutdown is currently being planned for repair of the flaw.
This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(A). The licensee has notified the NRC Resident Inspector.
On July 26, 2014 at 0002 EDT, Saint Lucie Unit 2 commenced shutdown to repair the identified leak. This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(A) and 10 CFR 50.72(b)(2)(i). The NRC Resident Inspector has been notified. Unit 2 current power is 88% at 0105 EDT and expect to trip the unit at approximately 0400 EDT. Notified the R2DO (Musser). |
| Where | |
|---|---|
Saint Lucie  Florida (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown | |
| Time - Person (Reporting Time:+-1.45 h-0.0604 days <br />-0.00863 weeks <br />-0.00199 months <br />) | |
| Opened: | Tim Kudo 14:02 Jul 25, 2014 |
| NRC Officer: | Daniel Mills |
| Last Updated: | Jul 26, 2014 |
| 50310 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
Saint Lucie with 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
WEEKMONTHYEARENS 569122024-01-03T17:57:0003 January 2024 17:57:00
[Table view]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 556932022-01-07T00:37:0007 January 2022 00:37:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Shutdown Initiated in Accordance with Technical Specifications 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 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 521382016-08-01T07:42:0001 August 2016 07:42:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Plant Shutdown Due to Pressure Boundary Leakage Greater than Allowable Limit ENS 509772015-04-12T01:00:00012 April 2015 01:00:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Safety Injection Tank Outlet Piping Leak 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 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 444852008-09-14T06:41:00014 September 2008 06:41:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Dropped Control Element Resulting in Entry Into Technical Specification Required Shutdown Lco 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 438712007-12-28T09:50:00028 December 2007 09:50:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown - Dropped Cea 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 420522005-10-12T18:40:00012 October 2005 18:40:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Shutdown Based on Loss of Two Channels of Containment Isolation Radiation Monitor 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 2024-01-03T17:57:00 | |
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