A finding of very low safety significance was identified by the inspectors associated with a non-cited violation of
10 CFR 50.59(d)(1). The issue involved an inadequate evaluation under
10 CFR 50.59 with respect to introduction of a new manual action in place of a previously automatic action. This issue was entered into the licensees corrective action system and the licensee prepared a new evaluation in accordance with
10 CFR 50.59
This finding was assigned a significance level of very low safety significance based on management review. The violation was categorized as
Severity Level IV based on the underlying technical issue for the finding having screened out as having very low significance using the Phase 1 worksheet of
Inspection Manual Chapter 0609, Appendix A, Significance Determination of Reactor Inspection Findings for At-Power Situations.
