ENS 50700: Difference between revisions
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| event date = 12/22/2014 22:30 EST | | event date = 12/22/2014 22:30 EST | ||
| last update date = 12/23/2014 | | last update date = 12/23/2014 | ||
| title = Unit 1 Technical Specification Shutdown Due | | title = Unit 1 Technical Specification Shutdown Due to Rcs Pressure Boundary Leakage | ||
| event text = 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. | | event text = 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. | ||
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. | 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. | ||
Latest revision as of 21:48, 1 March 2018
| 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
| |
North Anna with 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |