Immobilization of high-level radioactive waste (HLW) in borosilicate glass is acknowledges world-wide as an acceptable method for preparing HLW for geologic disposal. A waste acceptance process is underway in the United States that will provide specifications and procedures for waste producers well in advance of the availability of a federal repository. Extensive experimental data and rigorous quality assurance and control for plant operation are expected to provide convincing evidence that borosilicate glass waste forms produced in the vitrification plants meet the specifications and can be disposed of safely in a geologic repository.