The inspectors identified a
NCV of
10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, for the licensee failing to have in place adequate heavy load handling procedures that would control and limit the likelihood of a heavy load drop in the containment building. The licensee entered the finding in their corrective action program for resolution as condition report 2007-14366. The finding is greater than minor in accordance with
IMC 0612, Power Reactor Inspection Reports,Appendix B, Issue Screening. Specifically, the finding is related to the
Initiating Events cornerstone attribute of equipment performance in that the subject reactor vessel maintenance procedures did not control or limit the likelihood of a load drop event in containment that could challenge plant stability while shutdown. This finding is not suitable for an
SDP evaluation but has been reviewed by NRC management and was determined to be of very low safety significance (Green). The finding was not greater than Green because no actual load drop accident had taken place. No cross-cutting aspect associated with this finding was identified. (Section 4OA5
