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| Entered date | Event description | |
|---|---|---|
| ENS 53272 | 19 March 2018 13:09:00 | Emergency Assessment Capability cannot be performed in the Technical Support Center due to an equipment deficiency in the HVAC system which could impact facility habitability. An Alternate Technical Support Center is in place at the Emergency Offsite Facility. Priority maintenance is in progress to correct the deficiency. The licensee notified the NRC Resident Inspector. |
| ENS 53185 | 26 January 2018 13:06:00 | On January 26, 2018, a containment entry was made to identify the source of elevated Unidentified Reactor Coolant System (RCS) operational leakage. A through-wall leak was identified on a Class 1 piping weld on the letdown line at 0853 EST. It was determined that the leak was RCS pressure boundary leakage. Ginna entered Technical Specification (TS) LCO (Limiting Condition for Operation) 3.4.13, RCS Operational Leakage, Condition B. for the existence of pressure boundary leakage. This condition requires the plant to be in MODE 3 within 6 hours and MODE 5 within 36 hours. The leak was isolated and TS LCO 3.4.13 exited at 1015 EST. This event is reportable within 8 hours in accordance with 10CFR50.72(b)(3)(ii)(A) for 'Any event or condition that results in: (A) The condition of the nuclear power plant, including its principal safety barriers, being seriously degraded'. The Station (Ginna) is developing an evaluation and a repair plan at this time. This condition has no impact on public health and safety. The licensee has informed the NRC Resident Inspector. |