05000445/FIN-2016007-01
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Finding | |
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| Title | Failure to Update Final Safety Analysis Report Section 8.3.1.1.11 |
| Description | The inspectors identified a Severity Level IV violation of 10 CFR 50.71(e) which states, in part, that the licensee 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. The submittal shall include the effects of all changes made in the facility or procedures as described in the final safety analysis report, or all safety analyses and evaluation performed by the licensee either in support of approved license amendments or in support of conclusions that changes did not require a license amendment in accordance with 10 CFR 50.59 (c)(2). Specifically, from October 9, 2012, to September 29, 2016, the licensee did not include the effects of changes to the K300 voltage relay setpoint or the safety evaluation in submittals to the Final Safety Analysis Report, Section 8.3.1.1.11, that supported the conclusion that the changes did not require a license amendment. In response to this issue, the licensee planned a corrective action to initiate a licensing document change request to update the final safety analysis report. This finding was entered into the licensees corrective action program as Condition Report CR-2016-008177. The inspectors determined that the licensees failure to initiate a Licensing Document Change Request, in accordance with Procedure STA-116, Maintenance of CPNPP Licensing Basis Documents, Operating License conditions and Technical Specifications, Revision 14, Instruction 6.1, to update the Final Safety Analysis Report, Section 8.3.1.1.11, for the setpoint revision of the K300 voltage relays was a performance deficiency. In accordance with Inspection Manual Chapter 0612, Appendix B, Issue Screening, dated September 7, 2012, this was determined to be a minor performance deficiency. This violation was evaluated using the traditional enforcement process because it had the potential for impacting the NRCs ability to perform its regulatory oversight function. The reactor oversight processs significance determination process does not consider violations that impact the NRCs regulatory oversight function. This violation was determined to be a Severity Level IV violation, consistent with the example in paragraph 6.1.d.3 of the NRC Enforcement Policy, dated August 1, 2016. Specifically, the licensee failed to update the final safety analysis report as required by 10 CFR 50.71(e), but the lack of up-to-date information has not resulted in any unacceptable change to the facility or procedures. The inspectors determined that this violation did not have a cross-cutting aspect because traditional enforcement violations are not assessed for cross-cutting aspects. |
| Site: | Comanche Peak  |
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| Report | IR 05000445/2016007 Section 1R17 |
| Date counted | Sep 30, 2016 (2016Q3) |
| Type: | TEV: Severity level IV |
| cornerstone | Other |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71111.17 |
| Inspectors (proximate) | G George N Okonkwo R Latta T Farnholtz |
| Violation of: | 10 CFR 50.59 10 CFR 50.71 10 CFR 50.71(e) |
| INPO aspect | |
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Finding - Comanche Peak - IR 05000445/2016007 | |||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Comanche Peak) @ 2016Q3
Self-Identified List (Comanche Peak)
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