The report provides a framework for a basis to significantly reduce the degree of conservatism in RPV safety assessments according to NRC Regulation 10CFR50.61 and 10CFR50, Appendix G. Procedures and rationale are proposed to address regulatory concerns with the application of the Master-Curve based fracture toughness characterization methodologies. This report address the continued development of strategies for using direct characterization of fracture toughness of a reactor pressure vessel (RPV) for integrity assessments. The development of a fracture toughness-based integrity assessment framework will allow for a more realistic assessment of vessel integrity that provides greater operating flexibility while maintaining appropriate safety margins.