Examination of steam generator tube R45C52 from the Ginna nuclear power plant. Final report

Tube R45C52 from the Ginna Station B steam generator was examined at hot leg zones on the top of the tube sheet, at tube support plate intersections, and at antivibration bar contact points. These examinations, coupled with extensive SEM and EDAX studies, did not establish the presence of an identified process that would develop into tube leakage.