While reactor 1 is in Mode 6 for a scheduled refueling outage an inspection revealed a possible leak in the ‘B’ outlet control line. Although the line is isolable from the Reactor Coolant System (RCS), this condition represents a Reactor Vessel Pressure Boundary leak, a reportable condition. Presumably, the condition will be repaired prior to reactor restart after refueling is completed.
|Power Reactor||Event Number: 51792|
|Facility: POINT BEACH
Region: 3 State: WI
Unit:  [ ] [ ]
RX Type:  W-2-LP, W-2-LP
NRC Notified By: KILE HESS
HQ OPS Officer: HOWIE CROUCH
|Notification Date: 03/15/2016
Notification Time: 15:14 [ET]
Event Date: 03/15/2016
Event Time: 06:49 [CDT]
Last Update Date: 03/15/2016
|Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) – DEGRADED CONDITION
ROBERT ORLIKOWSKI (R3DO)
|Unit||SCRAM Code||RX CRIT||Initial PWR||Initial RX Mode||Current PWR||Current RX Mode|
|IDENTIFIED PRESSURE BOUNDARY LEAKAGE
“During a scheduled refueling outage, an inspection of containment components revealed a suspected through wall leak on 1CV-200B, Letdown Orifice ‘B’ Outlet Control. Non-destructive engineering inspection has been completed and determined that an indication exists.”10 CFR 50.2(2)(i) defines the reactor coolant pressure boundary as being connected to the reactor coolant system, up to and including the outermost containment isolation valve in system piping which penetrates primary reactor containment. 1CV-200B is isolable from the Reactor Coolant System (RCS) by a single motor operated valve, 1RC-427, Reactor Coolant Loop ‘B’ Leg to CVCS Letdown Isolation valve.
1CV-200B is located inside of containment between 1RC-427 and the two containment isolation valves for the letdown line, 1CV-371 and 1CV-371A. Based on the definition provided in 10 CFR 50.2, the condition is considered pressure boundary leakage and is considered reportable under 10 CFR 50.72(b)(3)(ii).