Burnup Credit - Technical Basis for Spent-Fuel Burnup Verification

Present regulatory practices provide as much burnup credit flexibility as can be currently
expected. Further progress is achievable by incorporating the negative reactivity effects of a
subset of neutron-absorbing fission-product isotopes, and by optimizing the procedural approach
for establishing the burnup characteristics of the spent fuel to be loaded in burnup-creditdesigned
storage and transportation systems. This report describes progress toward developing a
technical basis for a cost-effective burnup credit methodology for spent nuclear fuel with initial
U-235 enrichment up to 5%. The report concludes that burnup verification can be met through
standard audit procedures.