05000456/FIN-2013002-10
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Finding | |
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Title | Licensee-Identified Violation |
Description | Title 10 CFR Part 50.55a(g)(6)(ii)(D), Reactor Vessel Head Inspections, required that all licensees of pressurized water reactors augment their inservice inspection program with American Society of Mechanical Engineers (ASME) Code Case N-729-1 subject to the conditions specified in paragraphs (g)(6)(ii)(D)(2) through (6) of this section. Contrary to the above, the licensee failed to perform a required volumetric examination for Unit 1 Control Rod Drive Mechanism Penetration Number 4 during their Spring 2012 Unit 1 refueling outage. This issue was identified during this inspection period when Braidwood Station was notified by Westinghouse that due to equipment issues not known at the time, the inspection data was not fully collected for Penetration Number 4. This issue was determined to be of very low safety significance (Green), in part, because the licensee performed a technical evaluation that provided assurance that Penetration Number 4 would provide its pressure boundary function assuming an indication and maximum projected growth until the Fall 2013 Unit 1 refueling cycle. The licensee entered this issue into their CAP as IR 1479975, A1R16 CRDM [Control Rod Drive Mechanism] Penetration #4 Inspection Volume Coverage Not Met. |
Site: | Braidwood ![]() |
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Report | IR 05000456/2013002 Section 4OA7 |
Date counted | Mar 31, 2013 (2013Q1) |
Type: | NCV: Green |
cornerstone | Mitigating Systems |
Identified by: | Licensee-identified |
Inspection Procedure: | |
Inspectors (proximate) | A Garmoe E Duncan J Benjamin M Holmberg M Perry R Jickling R Ng T Daun |
Violation of: | 10 CFR 50.55a |
INPO aspect | |
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Finding - Braidwood - IR 05000456/2013002 | ||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Braidwood) @ 2013Q1
Self-Identified List (Braidwood)
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