Information on Licensing Applications for Fracture Toughness Requirements for Ferritic Reactor Coolant Pressure Boundary Components
The U.S. Nuclear Regulatory Commission (NRC) is seeking public comment on draft regulatory issue summary (RIS) 2014-XX. This draft RIS would provide guidance to applicants for, and holders of, nuclear power reactor licenses, construction permits, standard design approvals, and manufacturing licenses, and applicants for standard design certifications, on the scope and detail of information that should be provided in licensing applications regarding reactor vessel fracture toughness and associated pressure-temperature limits.
Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft NUREG, NUREG/CR-6909, Revision 1, ``Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials.'' This report summarizes the results of NRC research efforts and work performed at Argonne National Laboratory on the fatigue of piping and pressure vessel steels in light water reactor environments. Revision 1 of this report provides updates and improvements to the environmental fatigue correction factor approach based on an extensive update to available laboratory fatigue data from testing and results available since this report was first published in 2007.