The following violation of very low safety significance (Green) was identified by the licensee and is a violation of NRC requirements which meet the criteria of the
NRC Enforcement Policy, for being disposition as a Non-Cited Violation.
10 CFR 50, Appendix B, Criterion XVI, Corrective Action requires, in part, that in the case of
significant conditions adverse to quality corrective actions shall be taken to preclude repetition. Contrary to this requirement, corrective actions taken after the Containment Pre-Entry Purge Outside Containment Isolation Valve (
1CP-1) failed EST-220, Type C Local Leak Rate Test on February 23, 2004 failed to preclude repetition (
AR #119086). Specifically, the licensee failed to incorporate adequate guidance to re-torque the stud bolts on the seat clamping ring into procedure CMM0225. This resulted in
1CP-1 failing EST-220, Type C Local Leak Rate Test due to excessive leakage again on December 3, 2012. This violation was determined to be of very low safety significance (Green) because the finding did not represent an actual open pathway and did not involve an actual reduction in function of
hydrogen igniters in the reactor containment. The licensee entered this issue into their
CAP as
AR #575878. As corrective actions, the licensee revised the seat replacement procedure, properly torqued the stud bolts and satisfactorily tested
1CP-1.
