Abstract
This paper discusses the criteria currently used by the US Nuclear Regulatory Commission in dealing with repairs and replacement of BWR piping and steam generator tubing and provides the bases for these criteria. As a result of extensive cracking in BWR pipes caused by intergranular stress corrosion, a program of augmented inspection and leak testing has been instituted. Emphasis is placed on returning such piping to original design conformance either by replacement with non-susceptible material or by a combination of stress improvement and environmental control. As a result of a number of degradation mechanisms in steam generator tubes, inspection and criteria for plugging or sleeving have been instituted along with broad recommendations aimed at an integrated program for resolving steam generator tube problems.
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