The introduction of 236U to an enriching plant by recycling spent fuel uranium results in enriched products containing 236U, a parasitic neutron absorber in reactor fuel. Convenient approximate methodology determines 235U, 236U, and total uranium flowsheets with associated separative work requirements in enriching plant operations for use by investigators of the light water reactor fuel cycle not having recourse to specialized multicomponent cascade technology. Application of the methodology has been made to compensation of an enriching plant product for 236U content and to the value at an enriching plant of spent fuel uranium. The approximate methodology was also confirmed with more exact calculations and with some experience with 236U in an enriching plant.