05000373/FIN-2014002-01
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Finding | |
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| Title | Untimely Test, Evaluation, and Report on Reactor Vessel Surveillance Material |
| Description | The inspectors identified a finding of very low safety significance (Green) and an associated Severity Level IV non-cited violation of 10 CFR 50.60, Acceptance Criteria for Fracture Prevention Measures for Lightwater Nuclear Power Reactors for Normal Operation, for the licensees failure to conduct a timely test, evaluation, and report on the material contained in the 120 RV surveillance capsule within one year of capsule withdrawal to validate the RV pressure-temperature (P/T) limits. Specifically, in February 2010, the licensee withdrew the RV capsule at the 120 azimuth but did not report test results until November 2011 and did not report the impact of these results on P/T limits until January 2013. The licensee entered this issue into its CAP as action request (AR) 01598777 and submitted a request for a Technical Specification (TS) amendment with revised P/T curves that reflected the surveillance capsule test results. This issue was more than minor in accordance because it adversely affected the Barrier Integrity Cornerstone attribute of design control. The finding was determined to be more than minor because, if left uncorrected, the performance deficiency had the potential to lead to a more significant safety concern. Specifically, the failure to conduct a timely test, evaluation, and report on the material in the 120 RV surveillance capsule could have resulted in plant operation in an unacceptable region that would increase the possibility of vessel failure by brittle fracture (similar to pressurized thermal shock event for a pressurized water reactor). A Region III senior reactor analyst performed a detailed risk-evaluation of this finding, yielding a delta risk of 1 x 10-8 per year. Therefore, this finding is of very low safety significance (Green). This violation was similar to an example of a SL IV violation identified in Section 6.9.d.9 of the NRC Enforcement Policy, which identifies an example related to failure to make a required report under 10 CFR 50.72 or 10 CFR 50.73. Because the report timeliness requirements were not met for reporting the 120 RV surveillance capsule results, the NRC did not have the opportunity to review and approve the revised P/T curves prior to the plant exceeding the 21 effective full power years (EFPY) limit for application of the existing NRC approved P/T curves. Therefore, the failure to provide a timely report on this surveillance capsule had the potential to have impeded the regulatory process. Because of the very low risk significance, this issue was considered a SL IV violation. This finding has a cross-cutting aspect in the area of Problem Identification and Resolution (PI&R), Resolution, because the licensee did not take appropriate corrective actions to address safety issues in a timely manner, commensurate with their safety significance (P.3) Specifically, the licensee failed to develop a procedure or process for monitoring the timeliness of surveillance capsule testing, analysis and reporting. |
| Site: | LaSalle  |
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| Report | IR 05000373/2014002 Section 1R08 |
| Date counted | Mar 31, 2014 (2014Q1) |
| Type: | NCV: Green |
| cornerstone | Barrier Integrity |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71111.08 |
| Inspectors (proximate) | R Schulz F Ramirez J Beavers J Cassidy M Holmberg M Kunowski R Ruiz |
| Violation of: | 10 CFR 50.60 Technical Specification - Procedures 10 CFR 50.72 10 CFR 50.73 Technical Specification |
| CCA | P.3, Resolution |
| INPO aspect | PI.3 |
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Finding - LaSalle - IR 05000373/2014002 | |||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (LaSalle) @ 2014Q1
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