10 CFR 50.55a(g)(4) requires, in part, that pressurized water-cooled nuclear power facility components which are classified as
ASME Code Class 1, Class 2, and Class 3 must meet the requirements set forth in
ASME Section XI.
ASME Code,
Section XI, Subsection IWB, Article
IWB-2500, Table
IWB-2500-1, Item B5.10 requires a volumetric examination of all reactor vessel nozzle-to-safe end butt
welds NPS 4 or larger each inspection interval. Contrary to this, the licensee failed to achieve the required examination coverage for eight
welds during their 2005 examination effort due to a measurement discrepancy. This was identified in the licensees corrective action program as PER 203409. This finding is of very low safety significance because supplemental examinations performed in 2009 revealed no indications in the above
welds 