The team identified a finding involving a Non-Cited Violation of
10 CFR 50.59, \"Changes, Tests, and Experiments.\" The finding involved a failure to perform an adequate review of operations procedure changes in accordance with
10 CFR 50.59 associated with the operation of motor-operated valves for the
auxiliary feedwater suction source from the
service water system. The team determined that the licensee's approval of changes to Procedure E-0-05, with the introduction of adverse effects, and a determination that
10 CFR 50.59 was not applicable was a violation of
10 CFR 50.59. The licensee subsequently performed additional evaluations of the procedure changes.
Because the issue affected the NRC's ability to perform its regulatory function, this finding was evaluated with the traditional enforcement process. The finding was determined to be of very low safety significance since the design basis safety-related function of the
AFW system, to remove reactor decay heat following a loss of normal
feedwater, was not adversely affected. This was determined to be a
Severity Level IV NCV of
10 CFR 50.59.
