Methods of compliance with fracture toughness and operational requirements of 10 CFR 50, appendix G

This report describes B and W's practices, methods, and criteria for compliance with the requirements of Appendix G to 10 CFR 50, ''Fracture Toughness Requirements.'' The ferritic materials and the operational parameters of the reactor coolant system for nuclear power plants designed by B and W are described as are the methods for obtaining and estimating the reference temperature and the Charpy upper shelf energy. The design curves used to predict radiation effects and the acceptance criteria for unirradiated Charpy upper shelf are given. The adequacy of fracture toughness properties of bolting materials and type 403 materials are demonstrated. The methods employed to determine the reactor coolant system pressure-temperature limit curves are given for each of the loading conditions required by Appendix G to 10 CFR 50. The pressure-temperature limit curves imposed by several regions of the reactor vessel are illustrated as is the development of the composite limit curves. The Technical Specifications pressure-temperature limit curves and the Preservice System Hydrostatic Test limit curve of a typical Oconee-type plant are also described