[en] Alternative flowsheets were reviewed and design basis flowsheets selected for the separation and recovery of radioisotopes from commercial nuclear fuel wastes at reprocessing plants for the five isotope recovery cases of: cesium recovery; strontium recovery; cesium and strontium recovery; cesium, strontium, americium, curium, promethium, neptunium, technetium, rhodium, and palladium recovery; and xenon and krypton recovery. Processes were selected to recover isotopes from the high-level waste (HLW) and krypton/xenon off-gas of a 2100 MT/yr reprecessing heat processing PWR fuel originally at 3.3% ²³⁵U enrichment and exposed to an average burnup of 33,000 MWD/MT at 300 MW/MT and having a cooling time of 150 days. A titanium phosphate cation exchange cesium recovery process and a solvent extraction strontium recovery process were selected as the design basis flowsheets for the αesium, strontium, and cesium plus strontium revovery cases. These same cesium and strontium recovery processes were used in the multi-isotope case, in addition to the selected design basis flowsheets of precipitation and ion exchange for rhodium recovery and solvent extraction for americium, curium, promethium, neptunium, technetium, and palladium recovery. A cryogenic distillation process was selected as the design basis flowsheet for xenon and krypton recovery. Detailed process flow diagrams and stream data sheets were prepared for each of the five selected design flowsheets), and equipment and facility arrangement drawings were prepared in sufficient quantity and detail to support capital and operating cost estimation