On April 9, 2020 at 0100 EDT, while performing a containment walkdown due to a small increased
Reactor Coolant System (
RCS)
unidentified leakage, a leak was identified on the 'A'
Reactor Coolant Pump (
RCP) seal injection piping. The source of the leakage cannot be isolated and is considered
RCS pressure boundary leakage. At that time, Condition B of Technical Specification (TS)
LCO 3.4.13, '
RCS Operational Leakage' was entered due to
pressure boundary leakage.
TS 3.4.4 '
RCS Loops - Mode 1 and 2' and Technical Requirement (
TR) 3.4.6 '
ASME Code Class 1, 2, and 3 Components' are also applicable. Unit 2 is projected to be taken to Mode 5 for repairs.
This event is reportable in accordance with 10 CFR 50.72(b)(2) for 'Initiation of plant shutdown required by Technical Specifications' and 10 CFR 50.72(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 licensee notified the NRC Resident Inspector. There is no effect on Unit 1