The inspectors identified a noncited violation of Technical Specification 5.4.1.a for an inadequate procedure for securing a reactor
feedwater pump. Specifically, the licensee failed to incorporate internal operating experience into the procedure. As a result, a reactor recirculation flow control valve runback resulting from a known
reactor vessel water level loop tolerance issue recurred, resulting in an unplanned power reduction. This issue was entered into the licensees corrective action program as Condition Report
RBS-2007-4749. The finding is more than minor since it affects the human performance area of the
initiating events cornerstone and affects the cornerstone objective to limit the likelihood of those events that upset plant stability and challenge critical safety functions. Using the
NRC Manual Chapter 0609, Significance Determination Process, Phase 1 worksheet, the finding has very low safety significance since it did not contribute to both the likelihood of a reactor
scram and the likelihood that mitigating equipment would not have been available (Section 1R19.1).
