The "Summary Report of Commercial Reactor Criticality Data for Sequoyah Unit 2" contains the detailed information necessary to perform commercial reactor criticality (CRC) analyses for the Sequoyah Unit 2 reactor.

This report defines issues that need to be addressed by a development program recently initiated to establish the viability of a transuranic program recently initiated to establish the viability of a transuranic burning concept application that would achieve a substantial delay to the need date for a second geologic repository. The visualized transuranic burning concept application is one in which spent fuel created after a date in the 2010 timeframe or later would be processed and the separated plutonium used to start up liquid metal reactors.

The purpose of this validation is to compare TSM simulation results using the manually calculated work orders (WO) for the transportation cask fleet to simulation results using an automated WO algorithm developed to estimate the cask fleet.

Dear Members of the South Carolina Congressional Delegation:
Thank you all for your letter of October 27th. We appreciate hearing your views on the
Yucca Mountain project, the safety benefits of deep geologic disposal, and the
importance of the retaining the H Canyon facility at the Department of Energy’s
Savannah River Site.
In our draft report, the Commission finds that deep geologic disposal is an essential
component of a comprehensive nuclear waste management system. Your comments

This Plan outlines the Department of Energy’s (DOE) current strategy and planning for
developing and implementing the transportation system required to transport spent nuclear fuel
(SNF) and high-level radioactive waste (HLW) from where the material is generated or stored to
the proposed repository at Yucca Mountain, Nevada. The Plan describes how DOE’s Office of
Civilian Radioactive Waste Management (OCRWM) intends to develop and implement a safe,
secure and efficient transportation system and how stakeholder collaboration will contribute to

Because there is currently no designated disposal site for used nuclear fuel in the United States, the nation faces the prospect of extended long‐term storage (i.e., >60 years) and deferred transportation of used fuel at operating and decommissioned nuclear power plant sites. Under U.S. federal regulations contained in Title 10 of the Code of Federal Regulations (CFR) 72.42, the initial license term for an Independent Spent Fuel Storage Installation (ISFSI) must not exceed 40 years from the date of issuance. Licenses may be renewed by the U.S.

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 purpose of this document is to provide waste quantity and sequencing information that serves as the design basis for commercial spent nuclear fuel (CSNF) arriving at the repository, and the information on the transportation systems that will be used to deliver this fuel. It is intended as input for waste package and repository design analyses needed to ensure that facilities are flexible enough to be capable of receiving, unloading, handling, and emplacing the amounts and types of CSNF expected for receipt under realistic bounding conditions.