05000416/FIN-2017007-04
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Finding | |
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| Title | Failure to Update the Final Safety Analys is Report |
| Description | The team identified three examples of a Severity Level IV, non-cited violation of 10 CFR 50.71, Maintenance of Records, Making of Reports, Section (e), which states, in part, Each person licensed to operate a nuclear power reactor shall update periodically the final safety analysis report originally submitted as part of the application for the license, to assure that the information included in the report contains the latest information developed. This submittal shall contain all the changes necessary to reflect information and analyses submitted to the Commission by the applicant or licensee, or prepared by the applicant or licensee pursuant to Commission requirement since the submittal of the original or the last update to the final safety analysis report. Specific ally, prior to September 29, 2017, the licensee failed to ensure the final safety analysis report reflected the current plant configuration. In response to this issue, the licensee created a corrective action to update the final safety analysis report. The finding was entered into the licensees corrective action program as Condition Reports CR -GGN -2017- 09154, CR- HQN- 2017- 01356, and CR -GGN -2017 -09747. 5 The team determined that the failure to update the final safety analysis report in accordance with 10 CFR 50.71(e) was a performance deficiency. Following the Reactor Oversight Process (ROPs) significance determination process, the team determined this violation was associated with a minor performance deficiency. The ROPs significance determination process does not specifically consider the regulatory process impact in its assessment of licensee performance. Therefore, it is necessary to also address this violation which impedes the NRCs ability to regulate using traditional enforcement to adequately deter non- compliance. Assessing the performance deficiency in accordance with the NRC Enforcement Policy, the team determined it to be a Severity Level IV violation because the lack of up- to-date information in the final safety analysis report has not resulted in any unacceptable change to the facility or procedures. This finding did not have an assigned cross-cutting aspect because cross-cutting aspects are not assigned to traditional enforcement violations |
| Site: | Grand Gulf  |
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| Report | IR 05000416/2017007 Section 1R21 |
| Date counted | Dec 31, 2017 (2017Q4) |
| Type: | TEV: Severity level IV |
| cornerstone | Mitigating Systems |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71111.21M |
| Inspectors (proximate) | W Sifre C Stott N Okonkwo N Day S Hedger C Baron S Gardner T Farnholtz |
| Violation of: | 10 CFR 50.71(e) |
| INPO aspect | |
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Finding - Grand Gulf - IR 05000416/2017007 | |||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Grand Gulf) @ 2017Q4
Self-Identified List (Grand Gulf)
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