05000313/FIN-2016007-15
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Finding | |
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| Title | Failure to Maintain Structural Design Clearances inside the Unit 1 and 2 Reactor Containment Buildings |
| Description | The team identified a Green finding and an associated non-cited violation of 10 CFR Part 50, Appendix B, Criterion III, Design Control, for the licensees failure to ensure that numerous structural components located inside Units 1 and 2 reactor containment buildings were installed per structural drawings. The team identified numerous sections of floor grating and 14 inch plate steel supports that came in direct contact with the containment liner. In some cases, contact between the containment liner and the components resulted in damage to the liner and the liner protective coating. The licensees corrective actions included performing an operability determination and determining that the Units 1 and 2 containment liner was operable but degraded and nonconforming, establishing plans to correct the deficiencies in each units upcoming outage, and documenting the issue in the corrective action program as condition reports CR-ANO-1-2016-00492, CR-ANO-2-2016-00397, and CR-ANO-2-2016-00413. The failure to ensure that numerous structural components inside Units 1 and 2 reactor containment buildings were properly installed was a performance deficiency. The performance deficiency was determined to be more than minor because, it was associated with the configuration control attribute of the Barrier Integrity cornerstone and adversely affected the cornerstone objective to provide reasonable assurance that physical design barriers protect the public from radionuclide releases caused by accident or events. Specifically, the failure to ensure that items inside the Units 1 and 2 reactor containment buildings were installed per structural drawings could result in damage to the safety-related containment liner and challenge its function to protect the public from radionuclide releases. The finding was evaluated using Inspection Manual Chapter 0609, Significance Determination Process, Attachment 0609.04, Initial Characterization of Findings, and Appendix A, The Significance Determination Process (SDP) for Findings At-Power, Exhibit 3 Barrier Integrity Screening Questions, dated June 19, 2012. The team determined the finding was of very low safety significance (Green) because the finding did not represent as actual open pathway in the physical integrity of reactor containment and did not involve an actual reduction in function of hydrogen ignitors. This finding had a problem identification and resolution cross-cutting aspect of Identification because the licensee failed to implement a corrective action program with a low threshold for identifying issues. Specifically, the licensee failed to identify numerous containment liner stand-off clearance deficiencies during the required containment liner inspections over the operating life of the plant [P.1]. |
| Site: | Arkansas Nuclear  |
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| Report | IR 05000313/2016007 Section 4OA4 |
| Date counted | Mar 31, 2016 (2016Q1) |
| Type: | NCV: Green |
| cornerstone | Barrier Integrity |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 95003 |
| Inspectors (proximate) | B Correll C Osterholtz D Betancourt D Lackey D Willis E Duncan G Hansen J Brand J Dixon J Mateychick L Mckown M Holmberg M Keefe M Phalen N O'Keefe P Mckenna R Alexander R Deese R Kopriva R Kumana S Graves S Morrow S Rich S Smith T Hartman W Sifre Z Hollcraft |
| Violation of: | 10 CFR 50 Appendix B 10 CFR 50 Appendix B Criterion III, Design Control |
| CCA | P.1, Identification |
| INPO aspect | PI.1 |
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Finding - Arkansas Nuclear - IR 05000313/2016007 | ||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Arkansas Nuclear) @ 2016Q1
Self-Identified List (Arkansas Nuclear)
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