Crystal River 3 has determined that an existing condition in the Decay Heat (DH) System is reportable under
10 CFR 50.72(b)(3)(ii)(B), an
Unanalyzed Condition. Two valves in question are in series in the DH System drop leg from the
Reactor Coolant System (
RCS). They are Appendix R High-Low pressure interface valves, where 3 phase
hot shorts from another power cable must be considered. A review of cable routing concluded that one of the valve's power cables and one of the valve's control power cables do not meet required separation criteria. There is a low probability that both could open due to
hot shorts under normal operating
RCS pressure and temperature conditions, therefore a rupture of the downstream piping in the Reactor Building or Auxiliary Building is possible. The postulated event is a Loss of Coolant Accident (
LOCA) in the Auxiliary Building, which is an
unanalyzed condition. This condition is similar to the one reported in
EN 43098 on 01/12/2007. Cables in question are for the same valves, however, they are in a different area of the plant.
The licensee will notify the NRC Resident Inspector.