ENS 52137: Difference between revisions
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| event date = 07/30/2016 11:52 EDT | | event date = 07/30/2016 11:52 EDT | ||
| last update date = 07/30/2016 | | last update date = 07/30/2016 | ||
| title = Technical Specification Required Shutdown Due | | title = Technical Specification Required Shutdown Due to Unisolable Reactor Coolant System Boundary Leakage | ||
| event text = On July 30, 2016 at 1152 hours [EDT] following a containment walkdown to investigate an increase in RCS unidentified leakage to 0.15 gpm, a leak was identified on the seal return line from 2-RC-P-1C, 'C' Reactor Coolant Pump. The source of the leakage cannot be isolated and is considered RCS pressure boundary leakage. [Technical Specification] LCO 3.4.13, RCS Operational Leakage, Condition B for the existence of pressure boundary leakage was entered. Technical Requirement TR 3.4.6, ASME Code Class 1, 2, and 3 Components is also applicable. Unit 2 is projected to be taken to Mode 5 for repair. | | event text = On July 30, 2016 at 1152 hours [EDT] following a containment walkdown to investigate an increase in RCS unidentified leakage to 0.15 gpm, a leak was identified on the seal return line from 2-RC-P-1C, 'C' Reactor Coolant Pump. The source of the leakage cannot be isolated and is considered RCS pressure boundary leakage. [Technical Specification] LCO 3.4.13, RCS Operational Leakage, Condition B for the existence of pressure boundary leakage was entered. Technical Requirement TR 3.4.6, ASME Code Class 1, 2, and 3 Components is also applicable. Unit 2 is projected to be taken to Mode 5 for repair. | ||
This event is reportable in accordance with 10 CFR 50.72(b)(2) for 'the initiation of any nuclear plant shutdown required by the plant's Technical Specifications' and 10 CFR 50.72(b)(3)(ii)(A) for 'any event or condition that results in the condition of the nuclear plant including its principal safety barriers, being seriously degraded.' | This event is reportable in accordance with 10 CFR 50.72(b)(2) for 'the initiation of any nuclear plant shutdown required by the plant's Technical Specifications' and 10 CFR 50.72(b)(3)(ii)(A) for 'any event or condition that results in the condition of the nuclear plant including its principal safety barriers, being seriously degraded.' | ||
Latest revision as of 20:44, 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:+-0.58 h-0.0242 days <br />-0.00345 weeks <br />-7.94484e-4 months <br />) | |
| Opened: | Don Taylor 15:17 Jul 30, 2016 |
| NRC Officer: | Howie Crouch |
| Last Updated: | Jul 30, 2016 |
| 52137 - 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 | |