ENS 54652
From kanterella
ENS Event | |
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05:00 Apr 9, 2020 | |
Title | Technical Specification Required Shutdown Due to Reactor Coolant System Pressure Boundary Leakage |
Event Description | On April 9, 2020 at 0100 EDT, while performing a containment walkdown due to a small increased Reactor Coolant System (RCS) unidentified leakage, a leak was identified on the 'A' Reactor Coolant Pump (RCP) seal injection piping. The source of the leakage cannot be isolated and is considered RCS pressure boundary leakage. At that time, Condition B of Technical Specification (TS) LCO 3.4.13, 'RCS Operational Leakage' was entered due to pressure boundary leakage. TS 3.4.4 'RCS Loops - Mode 1 and 2' and Technical Requirement (TR) 3.4.6 'ASME Code Class 1, 2, and 3 Components' are also applicable. Unit 2 is projected to be taken to Mode 5 for repairs.
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 principle safety barriers, being seriously degraded.' The licensee notified the NRC Resident Inspector. There is no effect on Unit 1 |
Where | |
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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:+-1.38 h-0.0575 days <br />-0.00821 weeks <br />-0.00189 months <br />) | |
Opened: | Neil Turner 03:37 Apr 9, 2020 |
NRC Officer: | Donald Norwood |
Last Updated: | Apr 9, 2020 |
54652 - NRC Website
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Unit 2 | |
---|---|
Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (35 %) |
WEEKMONTHYEARENS 546522020-04-09T05:00:0009 April 2020 05:00:00
[Table view]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 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 2020-04-09T05:00:00 | |
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