Crystal River Unit 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 Decay Heat (DH) System drop leg from the
Reactor Coolant System (
RCS). These valves are High-Low pressure interface valves, where three phase
hot shorts from another power cable must be considered under Appendix R. A review of cable routing concluded that the two valve's power cables do not meet required Appendix R separation or protection criteria. As such, there is a low probability that both valves could open due to
hot shorts under normal operating
RCS pressure and temperature conditions, resulting in a rupture of the downstream piping in the Reactor Building or Auxiliary Building. This event could result in a Loss of Coolant Accident (
LOCA) in the Auxiliary Building, which is an
unanalyzed condition.
The licensee will notify the NRC Resident Inspector.