ENS 50700
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ENS Event | |
|---|---|
03:30 Dec 23, 2014 | |
| Title | Unit 1 Technical Specification Shutdown Due to Rcs Pressure Boundary Leakage |
| Event Description | On December 22, 2014 at 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br /> [EST] while performing a containment walkdown due to increased RCS [Reactor Coolant System] unidentified leakage, a leak was identified upstream of 1-RC-68, B Loop Cold Leg Drain Isolation Valve. The source of this leakage cannot be isolated and is considered RCS pressure boundary leakage. [Unit 1] Entered TS LCO 3.4.13 RCS Operational Leakage, Condition B for the existence of pressure boundary leakage. TS 3.4.4 RCS Loops - Modes 1 and 2 condition A, TR 3.4.6 ASME Code Class 1, 2, and 3 components, Condition B. Unit 1 will be taken to Mode 5 for repair.
This event is reportable in accordance with 10 CFR 50.72(b)(2) for "initiation of plant shutdown required by Technical Specifications" and 10 CFR 50.72(b )(3)(ii)(A) for "any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded. The RCS leakage has been quantified as 0.053 gallons per minute from a containment sump in-leakage calculation. The exact location of the leak has not been identified due to the installation of lagging on the RCS components. The licensee anticipates entering Mode 3 (Hot Standby) within the next 30 minutes. There is no safety-related equipment out-of-service at this time. The licensee will inform Louisa County and has informed the NRC Resident Inspector. |
| Where | |
|---|---|
North Anna  Virginia (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+-2.55 h-0.106 days <br />-0.0152 weeks <br />-0.00349 months <br />) | |
| Opened: | Daniel Hunt 00:57 Dec 23, 2014 |
| NRC Officer: | Steve Sandin |
| Last Updated: | Dec 23, 2014 |
| 50700 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (30 %) |
| After | Power Operation (12 %) |
North Anna with 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
WEEKMONTHYEARENS 567742023-10-03T15:54:0003 October 2023 15:54:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition ENS 554572021-09-12T21:28:00012 September 2021 21:28:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Identified While Unit Shutdown ENS 546522020-04-09T05:00:0009 April 2020 05:00:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Reactor Coolant System Pressure Boundary Leakage ENS 521372016-07-30T15:52:00030 July 2016 15:52:00 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 Unisolable Reactor Coolant System Boundary Leakage ENS 507002014-12-23T03:30:00023 December 2014 03:30:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Unit 1 Technical Specification Shutdown Due to Rcs Pressure Boundary Leakage ENS 504572014-09-15T13:00:00015 September 2014 13:00:00 10 CFR 20.2201(a)(1)(ii), 10 CFR 74.11(a), 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Failed Fuel Assembly Identified During Core Off-Load ENS 489402013-04-17T20:00:00017 April 2013 20:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Due to Suspected Valve Body Leakage ENS 477672012-03-24T22:55:00024 March 2012 22:55:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degradation of Steam Generator Nozzle Weld Areas ENS 460942010-07-14T23:34:00014 July 2010 23:34:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Tech Spec Shutdown Due to Through Wall Flaws in S/G Sample Line, Secondary Side ENS 454602009-10-23T20:34:00023 October 2009 20:34:00 Other Unspec Reqmnt, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Plant Shutdown Due to Excess Letdown Heat Exchanger Tube Leak and After-The-Fact Unusual Event ENS 431952007-02-28T00:47:00028 February 2007 00:47:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Failed Surveillance Testing 2023-10-03T15:54:00 | |
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