During performance of Unit 1 vessel leak test in accordance with 1-SI-3.3.1.A -
ASME Section XI System Leakage Test of the
Reactor Pressure Vessel and Associated Piping, a
pressure boundary leak was discovered on an instrument line connected to the
reactor pressure vessel. This instrument line is a
ASME Code Class 1 equivalent component (nozzle safe end) on pressure vessel
nozzle N11B and connecting upstream of
primary containment penetration X-29B. This caused entry into Technical Requirements Manual (
TRM) 3.4.3 - Structural Integrity - Condition A - in which the applicability is at all times and the required action is to immediately restore the structural integrity of the affected component to within its limit or maintain the reactor in MODE 4 or 5 or the
reactor coolant system less than 50?F above the minimum temperature required by
NDT considerations, until each indication of a defect has been investigated and evaluated. The plant is currently in MODE 4.
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 /> under 10CFR50.72 (b)(3)(ii)(A) Any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded. This event is also a reportable within 60 days under 10CFR50.73(a)(2)(ii)(A) any event or condition that resulted in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded. The NRC Resident Inspector has been notified. This condition has been documented in the BFN Corrective Action program as PER# 157918.
Unit 2 and 3 remain at 100% power and are not affected by this event.
