[en] This system consists of a series of stainless-steel, safety-related pipelines, 1/2 to 2 in. in diameter, which run from the control room to the reactor tank. The alternate analysis criteria were developed for the seismic qualification of the piping system, according to the requirements of the 1967 Housner criteria. The application of alternate analysis criteria is a widely employed and accepted procedure for the seismic qualification of large lengths of nuclear power plant small-diameter piping (generally 2 in. in diameter and smaller). Objective of this procedure is to eliminate the need for extensive and costly individual mathematical modeling and dynamic analysis of a great number of small-bore piping systems. The procedure used to develop the alternate analysis criteria consisted of applying equivalent static seismic loading to the various pipe sizes to determine maximum support spacings for each pipe size based on the allowable stress or deflection limits. Guidelines were also developed to provide for sufficient thermal growth capacity, which is typically in direct conflict with seismic requirements