This validation report supports the issuance of Version 6.0 of the Total System Model (TSM, BSC 2007a) that is described in the TSM User Manual (UM, BSC 2007b) and the TSM Preprocessor (TSMPP) User Manual (BSC 2007c). This report assumes the reader has detailed, working knowledge of the TSM functions and the Civilian Radioactive Waste Management System (CRWMS) operations. This report is based on an earlier document, Validation Report: Total System Model Version 5.0 Report Generators (BSC 2007d) that supported TSM Version 5.0.

The Total System Model Preprocessor (TSMPP) is a part of the Total System Model (TSM),
which is a PC-based simulator that is a decision aid to achieve overall Office of Civilian
Radioactive Waste Management (OCRWM) disposal objectives. The TSM is identified as Level
3, i.e., not Important To Safety (ITS) and not Important To Waste Isolation (ITWI), software in
the Bechtel SAIC Company, LLC (BSC) Controlled Software Report.
The TSMPP combines information about existing conditions, such as waste inventory estimates

This report evaluates the potential for directly disposing of licensed commercial Dual Purpose
Canisters (DPCs) inside waste package overpacks without reopening. The evaluation considers
the principal features of the DPC designs that have been licensed by the Nuclear Regulatory
Commission (NRC) as these relate to the current designs of waste packages and as they relate to
disposability in the repository. Where DPC features appear to compromise future disposability,
those changes that would improve prospective disposability are identified.

The "Summary Report of Commercial Reactor Criticality Data for Davis-Besse Unit 1" contains the detailed information necessary to perform commercial reactor criticality (CRC) analyses for the Davis-Besse Unit 1 reactor.

The "Summary Report of SNF Isotopic Comparisons for the Disposal Criticality Analysis Methodology" contains a summary of the analyses that compare SNF measured isotopic concentrations (radiochemical assays) to calculated SNF isotop~c concentrations (SAS2H module ·orScale4.3). The results of these analyses are used to support the validation of the isotopic models for spent commercial light water reactor (LWR) fuel.

The purpose of this calculation is to simulate the processing of an incoming waste stream into waste packages, simulating the required aging as applicable, and the emplacement of the waste packages into the Yucca Mountain repository.

This report provides details of dry storage cask systems and contents in U.S. for commercial light water
reactor fuel. Section 2 contains details on the canisters used to store approximately 86% of assemblies in
dry storage in the U.S. Transport cask details for bare fuels, dual purpose casks and canister transport
casks are included in Section 3. Section 4 details the inventory of those shutdown sites without any
operating reactors. Information includes the cask type deployed, transport license and status as well as

The "Summary Report of Commercial Reactor Criticality Data for LaSalle Unit 1" contains the detailed information necessary to perform commercial reactor criticality (CRC) analyses for the LaSalle Unit 1 (LS 1) reactor.

The U.S. Department of Energy (DOE) submitted to the Nuclear Regulatory Commission (NRC) the Dry Transfer System (DTS) Topical Safety Analysis Report (TSAR) on

This validation report supports the issuance of Version 6.0 of the Total System Model (TSM BSC-2007a) that is described in the TSM User’s Manual (UM) (BSC-2007b) and the TSM Preprocessor (TSMPP) UM (BSC 2007c). This report assumes the reader has detailed working knowledge of the TSM functions and Civilian Radioactive Waste Management System (CRWMS) operations.
This validation was performed in accordance with AP-ENG-006, Total System Model (TSM)- Changes to Configuration Items and Base Case.