A non-cited violation of
10CFR50.59 was identified by the inspectors for changing the design of the
auxiliary feedwater system as described in the
Updated Final Safety Analysis Report without performing a safety evaluation or obtaining a Technical Specification change. The change reduced the required number of trains of
auxiliary feedwater from three independent trains to two independent trains to safely shutdown the reactor.
This failure to perform a safety evaluation and submit a Technical Specification change is more than minor because it would require an NRC review prior to implementation. Because there was no evidence to indicate that the licensee had used the change the safety significance was determined to be very low. Consequently, the regulatory significance was categorized as a
Severity Level IV violation.
