The Working Group is charged with the development of analysis methodology and acceptance criteria for those regions of the primary pressure boundary relating to safety limits for nuclear plant operation, and in particular, the operating pressure-temperature limits. The reactor vessel beltline will be the limiting region in most cases due to the effects of radiation embrittlement on the vessel materials and because of the thickness of the vessel. Other components will be considered when these regions are determined to be limiting. In addition to embrittlement effects, other life limiting issues, such as fatigue, thermal ratcheting, etc. for primary pressure boundary components, may be addressed by this Working Group. All service conditions will be considered that impact the structural integrity of primary system components under normal plant operation, unanticipated plant operation, and for the purpose of plant life extension.
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