ENS 52573
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ENS Event | |
|---|---|
00:22 Feb 24, 2017 | |
| Title | Technical Specification Shutdown Due to Rcs Pressure Boundary Leakage |
| Event Description | On February 23, 2017, a containment visual inspection was performed to identify the source of elevated RCS [Reactor Coolant System] leakage. A leak was identified at the nozzle connection of the boron injection line to 2D RCS cold leg at 1922 [EST]. It was determined that the leak cannot be isolated and is considered RCS pressure boundary leakage. Unit 2 entered TS LCO 3.4.13, RCS Operational Leakage, Condition B, for the existence of pressure boundary leakage.
This event is reportable in accordance with 10CFR50.72(b)(2)(i) (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) for 'initiation of plant shutdown required by Technical Specifications' and 10CFR50.72(b)(3)(ii)(A) (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) for 'any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.' The unit will shutdown and repairs will be performed in Mode 5. This condition has no impact on public health and safety. The licensee has informed the NRC Resident Inspector. At the time of the event notification, Unit 2 was at 33 percent power. Unidentified RCS leakage is estimated at 0.28 gpm. Unit 2 is expected to be in Mode 3 by 0122 EST on 02/24/2017. Unit 1 is not affected by this event. |
| Where | |
|---|---|
Mcguire  North Carolina (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:+-2.35 h-0.0979 days <br />-0.014 weeks <br />-0.00322 months <br />) | |
| Opened: | Ryan Whisnant 22:01 Feb 23, 2017 |
| NRC Officer: | Jeff Rotton |
| Last Updated: | Feb 23, 2017 |
| 52573 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (33 %) |
McGuire with 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
WEEKMONTHYEARENS 546142020-03-26T07:00:00026 March 2020 07:00:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 525732017-02-24T00:22:00024 February 2017 00:22:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Technical Specification Shutdown Due to Rcs Pressure Boundary Leakage ENS 518172016-03-22T23:34:00022 March 2016 23:34:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Found in Reactor Coolant System Piping ENS 504972014-09-27T20:16:00027 September 2014 20:16:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Safety Injection Line Ultrasonic Test Indication ENS 499912014-04-03T05:00:0003 April 2014 05:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Safety Injection Line Ultrasonic Test Indication ENS 465572011-01-20T16:10:00020 January 2011 16:10:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown ENS 456272010-01-13T06:59:00013 January 2010 06:59:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Control Room Chillers Out of Service ENS 420462005-10-08T11:20:0008 October 2005 11:20:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Inoperable Control Room Chiller Train 2020-03-26T07:00:00 | |
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