REACTOR COOLANT SYSTEM (RCS) PRESSURE BOUNDARY DEGRADED
"At 0130 [EDT] on April 24, 2020, during the Beaver Valley Power Station, Unit 2 refueling outage, while performing examinations of the 66 reactor vessel head penetrations, it was determined that one penetration could not be dispositioned as acceptable per ASME Code Section XI. Penetration 37 will require repair prior to returning the vessel head to service. The indication was not through wall and there was no evidence of leakage based on inspections performed on the top of the reactor vessel head. The examinations were being performed to meet the requirements of 10 CFR 50.55a(g)(6)(ii)(D) and ASME Code Case N-729-4 to find potential flaws/indications before they grow to a size that could potentially jeopardize the structural integrity of the reactor vessel head pressure boundary. This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A).
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
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