05000298/FIN-2016001-01
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Finding | |
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| Title | Failure to Follow ASME Code Requirements when taking Corrective Actions for a Pump in the Required Action Range |
| Description | The inspectors identified a non-cited violation of 10 CFR 50.55a, Codes and Standards, for the licensees failure to follow the ASME Code for Operation and Maintenance of Nuclear Power Plants when addressing the performance of reactor equipment cooling pump A within the high required action range of the inservice testing program. Specifically, on February 11, 2016, the licensee failed to follow ASME Subsection ISTB 6200(b) when engineering personnel, taking corrective action to address pump performance, failed to either correct the cause of the deviation or establish new reference values for the pump. Instead of establishing new reference values, the licensee performed an analysis to administratively raise the upper required action range limit, creating a wider range of acceptable pump operation than allowed by Table ISTB-5100-1, Centrifugal Pump Test Acceptance Criteria. The licensee entered this issue into the corrective action program as Condition Report CR-CNS-2016-00920, took action to reevaluate and rebaseline the pump with new reference values, and performed an extent of condition review to determine if other equipment was impacted by similar interpretations of the code. The licensees failure to establish new reference values for reactor equipment cooling pump A in accordance with the ASME Code was a performance deficiency. The performance deficiency was determined to be more than minor, and therefore a finding, because it was associated with the human performance attribute of the Mitigating Systems Cornerstone, and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, the actions initially taken by the licensee would have required a relief request; could have delayed identification of a degrading pump trend due to the creation of a wider range of acceptable operation; and the licensees generic interpretation, that the Table ISTB-5100-1 acceptable range could be administratively expanded, represented a programmatic vulnerability. The inspectors used Manual Chapter 0609, Appendix A, The Significance Determination Process (SDP) for Findings At-Power, and determined that the finding had very low safety significance (Green) because it did not represent a design or qualification deficiency, did not represent a loss of safety function for a single train for greater than its technical specification allowed outage time, and did not screen as potentially risk significant due to a seismic, flooding, or severe weather initiating event. This finding had a cross-cutting aspect in the area of problem identification and resolution associated with evaluation. Specifically, the licensee failed to thoroughly evaluate performance of reactor equipment cooling pump A in the required action range to ensure that the resolution correctly addressed the causes of the degraded performance [P.2]. |
| Site: | Cooper  |
|---|---|
| Report | IR 05000298/2016001 Section 1R22 |
| Date counted | Mar 31, 2016 (2016Q1) |
| Type: | NCV: Green |
| cornerstone | Mitigating Systems |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71111.22 |
| Inspectors (proximate) | C Henderson G Warnick J O'Donnell M Phalen P Voss W Sifre |
| Violation of: | 10 CFR 50.55a Technical Specification |
| CCA | P.2, Evaluation |
| INPO aspect | PI.2 |
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Finding - Cooper - IR 05000298/2016001 | ||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Cooper) @ 2016Q1
Self-Identified List (Cooper)
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