On March 30, 2016, at 1715 EDT, with the Unit shutdown and in Mode 6 for refueling, evidence of leakage was identified on a 3/4-inch flexible braided piping connection on
Reactor Coolant Pump (
RCP) 1-1, and this issue was determined to be
reactor coolant system pressure boundary leakage. This flexible piping is for
RCP 1-1 first stage seal cavity vent line, and is categorized as
ASME Section III Class 2 piping. The leakage was identified due to the discovery of a small amount of
boric acid (approximately 1/2 teaspoon) on the welded end connection of the flexible piping. No active leakage was identified at the
time of discovery with the
Reactor Coolant System depressurized and approximately 110 degrees F.
Technical Specification (TS) Limiting Condition for Operation (LCO) 3.4.13, '
RCS Operational Leakage,' does not apply in the current plant condition (Mode 6). The cause and resolution of the leakage are under evaluation. 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 /> per 10 CFR 50.72(b)(3)(ii)(A). The NRC Resident Inspector has been notified.
