05000416/FIN-2016008-01
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Finding | |
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Title | Failure to Have Alternate Decay Heat Removal Capability |
Description | The team identified two examples of a non -cited violation of 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, for the licensees failure to have adequate procedures for activities affecting quality. Specifically, Grand Gulf Nuclear Station failed to have adequate procedures for feedwater, condensate, and shutdown cooling activities. The licensee implemented corrective actions to revise the procedures. The licensee entered this issue into their corrective action program as Condition Reports CR- GGN -2016- 08334, 08273, and 08290. The failure to have adequate procedures for activities affecting quality was a performance deficiency. Example (1) of this performance deficiency was more than minor, and therefore a finding, because it was associated with the procedure quality attribute of the Mitigating Systems Cornerstone and affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, not having procedural guidance for the alternate decay heat removal system alignment resulted in misalignment of the system and its subsequent inability to perform its required function if needed. A detailed risk evaluation (Attachment 2) calculated an increase in core damage frequency of 3.2E -7/year and an increase in large early release frequency of 7.3E -8/year, which has a very low safety significance (Green) . Example (2) of this performance deficiency was more than minor, and therefore a finding, because it was associated with the procedure quality attribute of the Initiating Events Cornerstone and affected the cornerstone objective to limit the likelihood of events that upset plant stability and challenge critical safety functions during shutdown operations. Specifically, not having procedural guidance for feedwater isolation valve operation resulted in inadvertent over fill of the reactor vessel. This violation is associated with a finding having very low safety significance (Green). The team did not assign a cross -cutting aspect because the performance deficiency was not reflective of current plant performance . |
Site: | Grand Gulf |
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Report | IR 05000416/2016008 Section 4OA3 |
Date counted | Jun 30, 2017 (2017Q2) |
Type: | NCV: Green |
cornerstone | Initiating Events |
Identified by: | NRC identified |
Inspection Procedure: | IP 71153 |
Inspectors (proximate) | M Haire D Proulx N Day D Loveless J Kozal |
Violation of: | 10 CFR 50 Appendix B 10 CFR 50 Appendix B Criterion V |
INPO aspect | |
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Finding - Grand Gulf - IR 05000416/2016008 | ||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Grand Gulf) @ 2017Q2
Self-Identified List (Grand Gulf)
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