If policymakers decide to launch a new repository-siting effort, an understanding of previ¬ous repository-siting efforts, both in the United States and abroad, might help to inform decisions defining and implementing the siting process. For this reason and to apprise the public of a critical issue associated with the long-term management of HLW and SNF, the U.S. Nuclear Waste Technical Review Board has written this report.

Safety Analysis report for the NAC International, Legal Weight Truck spent fuel shipping cask (NAC-LWT.) Shipment of the NAC-LWT cask can be made by truck, ISO container, and/or by railcar, as a Type B(U)F-96 package, as defined in 10 CFR 71.4. The NAC-LWT cask is a stainless steel and lead shielded cask with a surrounding water-ethylene glycol neutron
shield. The cask, which has capacity to ship 1 PWR or 2 BWR used nuclear fuel assemblies, is designed to be transported using legal-weight trucks having a fully loaded gross vehicle weight that does not exceed 80,000 lbs.

The Congressional Research Service prepared a report in August titled "Civilian Nuclear Waste Disposal." It contains a summary of the radioactive waste management program, and includes an update with recent developments on YM licensing, consent based siting, legislation, volunteer private storage sites, and current policy.

The National Research Council established the Panel on Public Participation in Environmental Assessment and Decision Making at the request of U.S. Environmental Protection Agency, the U.S. Department of Energy, and the U.S. Food and Drug Administration, with additional support from the U.S. Forest Service, to assess whether, and under what conditions, public participation achieves the outcomes desired.

On July 17, 2003, the U.S. Department of Energy (DOE) completed the movement of 125 commercial spent nuclear fuel (SNF) assemblies from the West Valley Demonstration Project (WVDP) to the Idaho National Engineering and Environmental Laboratory (INEEL). The assemblies were transported by rail in two dual-purpose shipping and storage casks specifically designed for the one shipment to the INEEL and for interim storage.

This report documents an initial evaluation of integrating standardized canisters into the nuclear waste management system, which is an intermediate step in the quantitative assessment of standardization. This is a technical report that does not take into account the contractual limitations under the Standard Contract (10 CFR Part 961) that DOE has in place with nuclear utilities. Under the Standard Contract, DOE is obligated to accept only bare UNF. Acceptance of canistered UNF would require a mutual agreement to modify the contract.

This issue brief explores options for providing states and federal agencies with new regulatory
authorities as one potentially critical element in making a consent-based siting regime for
nuclear waste facilities work. It summarizes key points from a longer analysis prepared by Van
Ness Feldman LLC (VNF) for the Bipartisan Policy Center’s Nuclear Waste Initiative, which is
exploring ways to advance the BRC recommendations. Specifically, VNF looked at whether an
arrangement, in which federal agencies give a state some form of regulatory authority over

This issue brief is one in a series being developed by the Bipartisan
Policy Center’s Nuclear Waste Initiative, which is exploring ways
to advance progress toward durable solutions for managing and
disposing of the nation’s inventory of spent nuclear fuel and highlevel
radioactive waste. This brief focuses on options for moving
forward with the development of one or more facilities for the
consolidated storage of spent fuel from commercial nuclear power
plants. It is based on a longer analysis prepared for the Bipartisan

Performance Specification: This performance specification document addresses use of a standardized transportation, aging, and
disposal (STAD) canister system in the spent nuclear fuel (SNF) waste management system. This
document was developed to support STAD canister system studies and potential research, development,
and demonstration activities. Requirements in this specification may evolve with time based on results
from analyses, experiments, design studies, system evaluations and demonstrations, as well as other
factors.

This report (PNL-6906 Vol. 1) documents activation measurements and comparison with calculations for spent fuel assembly hardware.