A self-revealing noncited violation of
Technical Specification 5.4.1.a occurred when River Bend Station reactor operators failed to comply with General Operating Procedure
GOP 000-1, Plant Start Up. Specifically operators withdrew six
control rods two notches past the target out notch position specified in Reactivity Control Plan RCP-15-03. No fuel damage resulted from these errors. This issue was entered into the licensees corrective action program as Condition Report
RBS-2008-2174. This finding was more than minor because the finding affected the barrier integrity cornerstone attributes of configuration control and human performance and adversely impacts the cornerstones objective to provide reasonable assurance that physical design barriers (
fuel cladding) protect the public from radio nuclide releases caused by accidents or events. The inspectors completed a Phase 1 significance determination using Manual Chapter 0609 Appendix A,
Significance Determination Process Phase 1 screening worksheet, and determined the finding to be of very low safety significance (Green) because the performance issue only degraded the
fuel cladding barrier. This finding had crosscutting aspects associated with human performance in the area of work practices in that the reactor operators failed to use self-check and peer-check during
control rod reactivity manipulations (
H.4.a) (Section 40A2).