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On December 22, 2014 at 2230 hours (EST) w … On December 22, 2014 at 2230 hours (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. </br>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.</br>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.</br>The licensee will inform Louisa County and has informed the NRC Resident Inspector.d has informed the NRC Resident Inspector. +
03:30:00, 23 December 2014 +
50,700 +
00:57:00, 23 December 2014 +
03:30:00, 23 December 2014 +
On December 22, 2014 at 2230 hours (EST) w … On December 22, 2014 at 2230 hours (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. </br>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.</br>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.</br>The licensee will inform Louisa County and has informed the NRC Resident Inspector.d has informed the NRC Resident Inspector. +
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01:48:55, 2 March 2018 +
00:57:00, 23 December 2014 +
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-0.106 d (-2.55 hours, -0.0152 weeks, -0.00349 months) +
03:30:00, 23 December 2014 +
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