Interim Technical Report on BWR Feedwater and Control Rod Drive Return Line Nozzle Cracking.

摘要

Recent reactor operating experience has revealed cracking of the inner surface of BWR feedwater and control rod drive return line nozzles. The cracks are thermal fatique initiated and in some instances have propagated through the cladding into the base metal. This report provides guidance as to interim inspection criteria and procedural measures for operating reactors.