ENS 45043
ENS Event | |
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07:30 May 5, 2009 | |
Title | 3C Main Steam Isolation Valve Problems |
Event Description | While preparing to perform main turbine testing prior to returning Unit 3 to service, a possible weld defect was identified by plant personnel during a main steam system walk down. This defect appears to be on a small bore section of pipe upstream of a steam trap on a socket weld. This resulted in a small steam leak on the upstream side of the 'C' main steam isolation valve. The repair must be completed with the steam line depressurized and, as such, the plant is in the process of reducing temperature to less than 200 degrees F. Based on previous interpretations of TS 3.4.10 and the applicability to ASME Class 2 piping, TS 3.0.3 has been entered based on current plant conditions.
At 0348 on 5/5/09, while bringing the Unit 3 to Mode 3 to comply with TSAS [Technical Specification Action Statement] 3.0.3, the 3C MSIV failed to close when demanded. The 3C MSIV was declared inoperable and Unit 3 entered TSAS 3.7.1.5 due to the inability to fulfill its safety function. The unit is required to be in Mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Mode 4 within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. At 0437, the 3C MSIV was closed. This is in compliance with TSAS 3.7.1.5. An investigation is in progress as to the cause of the failure of the 3C MSIV to close when demanded. Plant shutdown continues to comply with TSAS 3.0.3. All other safety systems are operable and there is no impact on Unit 4. The licensee notified the NRC Resident Inspector. |
Where | |
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Turkey Point Florida (NRC Region 2) | |
Reporting | |
10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
LER: | 05000250/LER-2009-002 |
Time - Person (Reporting Time:+-1.82 h-0.0758 days <br />-0.0108 weeks <br />-0.00249 months <br />) | |
Opened: | Ed Tremblay 05:41 May 5, 2009 |
NRC Officer: | Joe O'Hara |
Last Updated: | May 5, 2009 |
45043 - NRC Website
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Turkey Point with 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown | |
WEEKMONTHYEARENS 557852022-03-12T05:50:00012 March 2022 05:50:00
[Table view]10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Main Steam Isolation Valve Failed to Shut ENS 526232017-03-18T15:07:00018 March 2017 15:07:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Reactor Trip and Loss of Ability for Unit 4 to Supply Power to Unit 3 ENS 507142015-01-02T14:25:0002 January 2015 14:25:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Head Safety Injection Inoperable Due to Voids Identified in Piping ENS 504402014-09-09T23:36:0009 September 2014 23:36:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Failure of the Auto-Start Feature on Two Containment Coolers ENS 489482013-04-19T21:20:00019 April 2013 21:20:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unusual Event Due to Loss of Offsite Power Greater than 15 Minutes ENS 471472011-08-11T20:31:00011 August 2011 20:31:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Loss of Intake Cooling Water for 20 Minutes ENS 463032010-10-01T13:51:0001 October 2010 13:51:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Head Safety Injection Reduced Capability ENS 457912010-03-25T19:40:00025 March 2010 19:40:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Head Safety Injection Inoperable Due to Voids Identified in Piping ENS 450432009-05-05T07:30:0005 May 2009 07:30:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown 3C Main Steam Isolation Valve Problems ENS 444182008-08-15T20:04:00015 August 2008 20:04:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Shut Down Required by Technical Specifications ENS 441882008-05-05T16:37:0005 May 2008 16:37:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Head Safety Injection Manual Valve to Cold Leg Found Mispositioned During Heatup ENS 439192008-01-18T22:44:00018 January 2008 22:44:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Two Inoperable Rod Position Indicators in the Same Rod Group ENS 438962008-01-12T10:41:00012 January 2008 10:41:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Two Rod Position Indicators (Rpis) Out in One Rod Bank ENS 438882008-01-10T10:02:00010 January 2008 10:02:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Two Rod Position Indicators (Rpis) Out in One Rod Bank ENS 434082007-06-06T11:45:0006 June 2007 11:45:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Initiated on Unit 3 ENS 412322004-11-30T13:50:00030 November 2004 13:50:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Dropped Control Rod ENS 412292004-11-29T05:09:00029 November 2004 05:09:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specifications Required Shutdown Due to Dropped Control Rod ENS 411022004-10-07T18:00:0007 October 2004 18:00:00 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)(B), Unanalyzed Condition, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Single Point Vulnerability in Emergency Containment Filter Dousing System 2022-03-12T05:50:00 | |