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.
