05000416/FIN-2015007-09
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Finding | |
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Title | Failure to Obtain a License Amendment for Use of Probabilistic Methods to Evaluate Tornado Missile Hazards |
Description | The team identified a Green, Severity Level IV non-cited violation of 10 CFR 50.59, Changes, Tests, and Experiments, paragraph c(2), (1995 version) which requires that a licensee who desires to make a change in the facility described in the final safety analysis report, which involve an unreviewed safety question shall submit an application for amendment of the license pursuant to 10 CFR 50.90. Specifically, on August 31, 1995, the licensees incorporation of the use of probabilistic methods for evaluation of tornado missiles into the Grand Gulf Final Safety Analysis Report Section 3.5.2.5 involved an unreviewed safety question because it increased the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the safety analysis report. In response to the issue, the licensee prepared a license amendment request to obtain approval to use probabilistic methods for tornado missile evaluations. This finding was entered into the corrective action program as Condition Reports CR-GGN-2015-04615 and CR-GGN-2015-4760. The team determined that the failure to obtain a license amendment prior to implementing a proposed change to the tornado missile protection design requirements was a performance deficiency. This performance deficiency was determined to be more than minor, and therefore a finding, because there was a reasonable likelihood the change would require NRC review and approval. This finding was evaluated using traditional enforcement, because the violation may impact the ability for the NRC to perform its regulatory oversight function. In accordance with the NRC Enforcement Policy, the significance determination process was used to inform the significance of the failure to obtain a license amendment prior to implementing a proposed change to the main control room design requirements. Using Inspection Manual Chapter 0609, Appendix A, The Significance Determination Process (SDP) for Findings At-Power, the inspectors determined the finding involves the total loss of a safety function, identified by the licensee through a probabilistic risk analysis, individual plant examination for external events, or similar analysis, that contributes to external event initiated core damage accident sequences. Therefore, detailed risk evaluation was necessary. The senior reactor analyst reviewed the Grand Gulf Individual Plant Examination for External Events because it was the best available information on missile damage to exposed safety-related equipment. The senior reactor analyst determined that the finding had very low safety significance (Green) because the probability of damage occurring to the exposed safety-related equipment was 7.7E-9/year, which is below the threshold for additional probabilistic risk evaluation. Since the violation was associated with a Green reactor oversight finding, the traditional enforcement violation was determined to be a Severity Level IV violation, consistent with paragraph 6.1.d(2) of the NRC Enforcement Policy. This finding did not have a crosscutting aspect because the most significant contributor did not reflect current licensee performance. |
Site: | Grand Gulf |
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Report | IR 05000416/2015007 Section 1R21 |
Date counted | Dec 31, 2015 (2015Q4) |
Type: | NCV: Green |
cornerstone | Mitigating Systems |
Identified by: | NRC identified |
Inspection Procedure: | IP 71111.21 |
Inspectors (proximate) | D Loveless H Leake J Watkins L Brandt R Latta T Farnholtz W Sherbin J Mchugh |
Violation of: | 10 CFR 50.59 10 CFR 50.90 |
INPO aspect | |
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Finding - Grand Gulf - IR 05000416/2015007 | |||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Grand Gulf) @ 2015Q4
Self-Identified List (Grand Gulf)
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