The purpose of this analysis is to estimate the peak fuel assembly cladding temperature within the transportation casks that will be received in the WHF and RF, and to compare this value with established temperature limits. Thermally limiting scenarios are evaluated for both normal and off-normal operating conditions, with the off-normal condition defined as a loss of active ventilation. A second purpose of this analysis is to identify a specific room in the surface facilities as thermally limiting of all the rooms, with respect to the potentially highest temperatures on the concrete walls.

The radionuclide characteristics of light-water-reactor (LWR) spent fuel play key roles in the design and licensing activities for radioactive waste transportation systems, interim storage facilities, and the final repository site.

The Monitored Geologic Repository (MGR) Waste Package Operations of the Civilian Radioactive Waste Management System Management & Operating (CRWMS M&O) contractor performed calculations to provide input to the design of a waste package (WP). This document analyzes the degradation processes of two types of pressurized water reactor (PWR) spent nuclear fuel (SNF): • Fuel fabricated from low enriched uranium oxide, which has been used, or will ~ used, in commercial nuclear power plants.

The purpose of this calculation is to evaluate the transient behavior and consequences of a worstcase criticality event involving intact pressurized water reactor (PWR) mixed-oxide (MOX) spent nuclear fuel (SNF) in a degraded basket configuration inside a 21 PWR waste package (WP). This calculation will provide information necessary for demonstrating that the consequences of a worst-case criticality event involving intact PWR MOX SNF are insignificant in their effect on the overall radioisotopic inventory and on the integrity of the repository.

This DQR uses the technical assessment methods according to Attachment 2 of AP-SIII.2Q, Rev. 0, ICN 3, to qualify DTN LADB831321AN98.002. The data addressed in this DQR have been cited in CRWMS M&O (2000b) to support the Site Recommendation in determining the suitability of Yucca Mountain as a repository for high level nuclear waste. CRWMS M&O (2000b) refers to mineral analyses that are unqualified.