05000373/FIN-2017001-01
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Finding | |
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| Description | Green . The inspectors identified a finding of very-low safety significance with an associated NCV of Title 10 of the Code of Federal Regulations (CFR) , Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, because the licensee failed to establish a procedure that ensured the American Society of Mechanical Engineers (ASME) Code VT 3 examination of the internal surface of valves or pumps occurred in the as -found condition (e.g., prior to repairs). Consequently, the licensee repaired internal damage to the 2B33 F067B valve prior to the Code VT 3 examination which potentially resulted in an ineffective VT 3 examination. The licensee entered this issue into their corrective action program (CAP) as Action Request (AR) 3972620, initiated actions to complete another VT 3 examination of valve 2B33 F067A or valve 2B33 F067B during the current outage and was evaluating additional controls for scheduling VT 3 internal examinations of pumps and valves. The performance deficiency was determined to be more- than- minor because it affected the Initiating Events cornerstone attribute of equipment performance and adversely affected the cornerstone objective to l imit the likelihood of events that upset plant stability and challenge critical safety functions during shutdown as well as power operations. Specifically, if left uncorrected, this finding would lead to a more significant safety concern because it increa sed the likelihood of an operational challenge to the plant caused by a recirculation system line break initiated from undetected service -induced defects left in service inside pumps or valves as a result of ineffective VT 3 examinations. The finding was screened in accordance with Inspection Manual Chapter 0609, Appendix A, and the inspectors answered No to the applicable Phase 1 Initiating Events Screening question because the finding did not result in a reactor trip and/or loss of mitigation equipment relied upon to transition the plant from the onset of the trip to a stable shutdown condition. Therefore, this finding was determined to have very- low safety significance (Green) . The finding had a cross -cutting aspect of Work Management in the Human Performance cross -cutting area because licensee managers failed to establish an adequate process of planning, controlling, and executing 3 work activities such that nuclear safety is the overriding priority as evidenced by the lack of appropriately controls for scheduling the VT 3 internal examination of the 2B33 F067B valve (H.5) |
| Site: | LaSalle  |
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| Report | IR 05000373/2017001 Section 1R08 |
| Date counted | Mar 31, 2017 (2017Q1) |
| Type: | NCV: Green |
| cornerstone | Mitigating Systems |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71111.08 |
| Inspectors (proximate) | C Hunt G Hansen J Cassidy K Stoedter M Domke M Holmberg R Ruiz R Zuffa T Go L Torres |
| Violation of: | 10 CFR 50 Appendix B Criterion V |
| CCA | H.5, Work Management |
| INPO aspect | WP.1 |
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Finding - LaSalle - IR 05000373/2017001 | |||||||||||||||||||||||||||||||||||
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Finding List (LaSalle) @ 2017Q1
Self-Identified List (LaSalle)
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