This report is concerned with how America's public sector is handling the challenge of implementing a technical, environmental policy, that of managing the nation's high-level nuclear waste, as reflected in the attempt of the U.S. Department of Energy (DOE) to site a Monitored Retrievable Storage Facility (MRS) for high-level radioactive waste in Tennessee.

The U.S. Department of Energy is responding to the U.S. Nuclear Regulatory Commission staff's comments on the topical report, "Evaluation of the Potentially Adverse Condition 'Evidence of Extreme Erosion During the Quaternary Period' at Yucca Mountain, Nevada" and providing additional information supporting the conclusions reached in the report.

The U.S. Congress authorized the development of a monitored retrievable storage facility (MRS) as part of the high-level radioactive waste management system. The MRS will be used to receive, store, and stage shipments of intact spent fuel to the permanent repository. Early development of the MRS is crucial to honoring the long-standing Federal commitment to timely and adequate waste acceptance. The Department of Energy's (DO E) objective is initial waste acceptance at the MRS beginning in 1998.

The concept of Geosphere Perfonnance Indices (GPis) is proposed. The &quot;performance&quot;<br/>refers to the geosphere&#39;s capacity to retain/contain radionuclides in the event of their accidental<br/>release at some point in time. The GPis are based on the Lagrangian stochastic-analytical<br/>framework for transport in the subsurface and are believed to render useful tools in performance<br/>assessment studies in general and in the site selection process in particular.

In this paper, the major elements of the site selection and characterization processes used in the U.S. high level waste program are discussed. While much of the evolution of the site selection and characterization processes have been driven by the unique nature of the U.S. program, these processes, which are well-defined and documented, could be used as an initial basis for developing site screening, selection, and characterization programs in other countries. Thus, this paper focuses more on the process elements than the specific details of the U.S. program.

RD&D Programme 2007 presents SKB’s plans for research, development and demonstration during<br/>the period 2008–2013. The plans for the first three-year period are for natural reasons more detailed<br/>than those for the next one.

This study evaluated the technical suitability of Yucca Mountain, Nevada, as a potential site for a mined geologic repository for the permanent disposal of radioactive waste. The evaluation was conducted primarily to determine early in the site characterization program if there are any features or conditions at the site that indicate it is unsuitable for repository development. A secondary purpose was to determine the status of<br/>knowledge in the major technical areas that affect the suitability of the site.

Presented to the Blue Ribbon Commission on America&#39;s Nuclear Future Subcommittee on Disposal

In response to your request, and as a follow-up to the ACNW Working Group meeting with you and your staff on June 17, 1992, we offer the following comments on the Early Site Suitability Evaluation (ESSE) for the proposed Yucca Mountain high-level waste repository site. Our comments relate both to the ESSE, as prepared by Science Applications International Corporation (SAIC), a contractor to the U.S. Department of Energy (DOE), and to the draft review prepared by your staff.

In an international perspective, Sweden has come a long way in the development of safe and accepted systems for the management and disposal of radioactive waste. <br/><br/>A complete system for sea transport of spent nuclear fuel from the twelve Swedish nuclear reactors has been in operation since 1982. The spent nuclear fuel will be stored in CLAB for a period of about 40 years up until final disposal. The facility has been in operation since 1985. A final repository for low- and intermediate-level short-lived waste, SFR, has been in operation since April 1988.

The preceding RD&D-Programme from 2001 was concentrated on research and technology development. Research with a focus on the assessment of long-term safety was emphasized and viewpoints from previous reviews of SR 97 and RD&D-Programme 98 were dealt with in depth. SR 97 was an assessment of the long-term safety of a deep repository for spent nuclear fuel. This RD&D-Programme 2004 focuses its attention on the development of technologies for fabrication and sealing of canisters for final disposal of spent fuel.

The siting of the facilities for the disposal of spent nuclear fuel and other long-lived<br/>nuclear waste is one of the central remaining tasks within the Swedish waste programme.<br/>Work relating to the siting of the repository is being conducted in stages and will<br/>continue for most of the 1990:ies. This report describes the background to, the goals<br/>for and structure of SKB &#39;s activities relating to the siting of a deep geological<br/>repository.

The goal of radioactive waste management in Sweden is to dispose of all radioactive waste products generated at the Swedish nuclear power plants in a safe manner. Furthermore, all other radioactive waste that arises in Sweden shall be safely disposed of.<br/>The Act on Nuclear Activities requires that the owners of the Swedish nuclear power plants adopt the measures that are needed to achieve this goal. The owners of the Swedish nuclear power plants have commissioned the Swedish Nuclear Fuel and Waste Management Company (SKB) to implement the measures that are needed.<br/>

This report is a background to RD&D-Programme 98 /1-11. The report gives an account of most of the research and development being conducted by SKB. The current state of knowledge is described, along with the goals and programmes that govern the continued work. The period of immediate concern comprises the next three years, 1999-2001. Particulars for the three years following that are for natural reasons less detailed and mainly indicate a direction.

The U.S. Geological Survey&#39;s program for geologic and hydrologic evaluation of physiographic provinces to identify areas potentially suitable for locating repository sites for disposal of high-level nuclear wastes was announced to the Governors of the eight States in the Basin and Range Province on May 6, 1981. Representatives of Arizona, California, Idaho, New Mexico, Nevada, Oregon, Texas, and Utah, were invited to cooperate with the Federal Government in the evaluation process.

The present report discusses the implications of the terms &quot;alternative design&quot; and &quot;alternative barriers&quot;. Furthermore, different schematic methods for final disposal and different components that can be included in a system for final disposal are presented. The ideas for the different methods, components or designs come from many sources.

Current U.S. nuclear waste law and policy is bankrupt. The 1982 Nuclear Waste Policy Act (NWPA) set a 1998 deadline for opening a deep geologic repository to receive spent nuclear fuel (SNF) and high-level waste (HLW) from reprocessing. In 1987, Congress amended the Act to designate Yucca Mountain in Nevada as the only potential site, and severely restricted the development of any federal facility for consolidated storage of nuclear waste. Nevada’s unrelenting opposition to the Yucca repository eventually succeeded with the election of Barack Obama as President.

The United States of America ratified the Joint Convention on the Safety of Spent Fuel<br/>Management and on the Safety of Radioactive Waste Management (Joint Convention) on<br/>April 9, 2003. The Joint Convention establishes an international peer review process among<br/>Contracting Parties and provides incentives for nations to take appropriate steps to bring their<br/>nuclear activities into compliance with general safety standards and practices.

The Nuclear Waste Policy Act of 1982 (the NWPA) (42 USC Sections 10101-10226) requires the environmental assessment to include a detailed statement of the basis for nominating a site as suitable for characterization. This detailed statement is to be an evaluation of site suitability under the DOE siting guidelines; the evaluation will be the basis for the comparison of sites reported in Chapter 7. Such an evaluation for the Richton Dome site is presented in Sections 6.2, 6.3, and 6.4 of this chapter, and is based in part on impacts associated with the reference repository design.

Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management on the Safety of Radioactive Waste Management, Answers to the Questions of Contracting Parties on the National Report submitted by Luxembourg