ENS 52894
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ENS Event | |
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20:06 Aug 9, 2017 | |
Title | Technical Specification Required Shutdown for Reactor Coolant System Leakage |
Event Description | On 8/9/17, a Unit 1 containment entry was made in order to investigate increased Reactor Coolant System (RCS) unidentified leakage. The team noted a through-wall leak from the tubing/socket weld area of 'C' Hot Leg Sample Valve. The sample valve and RCS pressure boundary were declared inoperable, and a 6-hour action statement to place Unit 1 in Hot Shutdown was entered at 1338 [EDT] hours as required by Technical Specification 3.1.C.3.
At 1606 [EDT] hours on 8/9/17, Unit 1 shutdown was commenced, and at 1637 [EDT], Unit 1 was at Hot Shutdown. This report is being submitted pursuant to 10CFR50.72(b)(2)(i) as a result of power reduction required by Technical Specifications. Further, this report is being submitted pursuant to 10CFR50.72(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 NRC Resident [Inspector] has been notified of this event and is on site. There was no radiation release associated with this event, nor were there any personnel injuries or contamination events. |
Where | |
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Surry 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:+-2.52 h-0.105 days <br />-0.015 weeks <br />-0.00345 months <br />) | |
Opened: | Alan Bialowas 17:35 Aug 9, 2017 |
NRC Officer: | Dong Park |
Last Updated: | Aug 9, 2017 |
52894 - NRC Website
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Unit 1 | |
---|---|
Reactor critical | Critical |
Scram | No |
Before | Power Operation (32 %) |
After | Hot Shutdown (0 %) |
Surry with 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
WEEKMONTHYEARENS 528942017-08-09T20:06:0009 August 2017 20:06:00
[Table view]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 for Reactor Coolant System Leakage ENS 407722004-05-23T09:26:00023 May 2004 09:26:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specifications Required Cooldown 2017-08-09T20:06:00 | |
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