ENS 53185

v t e ENS Event
13:53 Jan 26, 2018
Title	Reactor Coolant System Operational Leakage
Event Description	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 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The leak was isolated and TS LCO 3.4.13 exited at 1015 EST. This event is reportable within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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.

ENS 53185 +/-
Where
Ginna New York (NRC Region 1)
Reporting

10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded
Time - Person (Reporting Time:+-0.78 h-0.0325 days <br />-0.00464 weeks <br />-0.00107 months <br />)
Opened:	Justin Knowles 13:06 Jan 26, 2018
NRC Officer:	Jeff Herrera
Last Updated:	Jan 26, 2018
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v • d • e

v t e Emergency Notification System
Ginna with 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded
WEEKMONTHYEAR2018-01-26T13:53:00 [Table view]
[ENS list for Ginna]

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