05000259/FIN-2013011-03
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Finding | |
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| Title | Failure to Perform 10 CFR 50.59 Evaluation Intergranular Stress Corrosion Cracking Examination on ASME Code Class 1 Piping Weld |
| Description | The team identified a Severity Level IV non-cited violation of 10 CFR 50.59, Changes, Tests, and Experiments, for the licensees failure to perform an evaluation of a change to the facility as described in the Updated Final Safety Analysis Report (UFSAR) and an associated Green Finding for the licensees failure to perform an acceptable Ultrasonic (UT) examination in accordance with American Society of Mechanical Engineers (ASME) Code,Section XI requirements. Specifically, this change resulted in a departure from the method of evaluation used to inspect for intragranular stress corrosion cracking (IGSCC) in reactor coolant pressure boundary components at BFN as described in the UFSAR and therefore, required a 10 CFR 50.59 evaluation to determine if the change would have required a license amendment request pursuant to 10 CFR 50.90. The licensee performed the required 10 CFR 50.59 evaluation and entered this issue of concern in their corrective action program (CAP) under SR 743380 and PER 744849. The team determined the underlying PD was more than minor and a Finding, because the PD affected the Barrier Integrity cornerstone and if left uncorrected, could become a more significant safety concern. Absent NRC identification of this PD, the licensee could have continued to perform UT examinations to detect IGSCC on safety-related components without obtaining the minimum required examination volume. This could result in IGSCC susceptible welds on ASME Code Class 1 piping being only partially examined for IGSCC flaws and could lead to safety-related components with potentially unacceptable service-induced flaws not detected during UT examinations being returned to service. The team evaluated the Findings significance in accordance with IMC 0609, Appendix G, Shut-down Operations Significance Determination Process, because the PD occurred while Unit 2 was in cold shutdown. The team reviewed IMC 0609, Appendix G, Attachment 1, Checklists 5, 6, 7, and 8 and determined this Finding did not require a quantitative assessment. Therefore the Finding screened as having very low safety significance. The team determined the traditional violation was more than minor because of reasonable likelihood the departure from weld inspection methodology as described in the UFSAR would have required Commission review and approval prior to implementation. The team concluded that the violation of 10 CFR 50.59 was a Severity Level IV because the underlying PD screened Green under the SDP. The team also concluded that this Finding had a cross-cutting aspect in the area of Human Performance, Decision Making, because the licensee did not make safety significant or risk-significant decisions using a systematic process when faced with uncertain or unexpected plant conditions, to ensure safety was maintained. |
| Site: | Browns Ferry  |
|---|---|
| Report | IR 05000259/2013011 Section 4OA4 |
| Date counted | Jun 30, 2013 (2013Q2) |
| Type: | NCV: Green |
| cornerstone | Barrier Integrity |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 95003 |
| Inspectors (proximate) | C Even C Moore E Guthrie J Eargle J Heinly R Skokowski |
| Violation of: | 10 CFR 50.59 10 CFR 50.90 |
| CCA | H.13, Consistent Process |
| INPO aspect | DM.1 |
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Finding - Browns Ferry - IR 05000259/2013011 | ||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Browns Ferry) @ 2013Q2
Self-Identified List (Browns Ferry)
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