PRIMARY CONTAINMENT DEGRADED
"At 1109 [EST] on 01/04/2020, it was determined that the primary containment leakage rate did not meet value La, defined in 10 CFR 50, Appendix J, 'Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors'. An additional, tested valve has been closed to maintain leakage below maximum allowable leakage, La. 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." |