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Baseline Radionuclide Inventory for the Remote-Handled Low-Level Waste Disposal Facility for Use in the Facility Performance Assessment

The purpose of this engineering calculations and analysis report is to document the baseline radionuclide inventory anticipated for disposal in the Remote-Handled Low-Level Waste Disposal Facility at Idaho National Laboratory. This inventory will be used in the updated facility performance assessment to obtain an operational disposal authorization statement. This document contains the inventory for the first 20 years of operation (i.e., the capacity of the current as-built Remote-Handled Low-Level Waste Disposal Facility) and the inventory for a full 50 years of operation. The inventory is presented by waste generator and waste form, and separated into the vault type that will receive the waste. This information is necessary for conducting the dose and exposure assessment for the facility performance assessment. The inventory estimates in this engineering calculations and analysis report were taken from other sources. All adjustments to the inventories from those other sources to define a 20-year inventory; and any decay calculations of legacy waste inventories in those other sources, is explained in this ECAR.

99 GENERAL AND MISCELLANEOUS↗

Long-Term Surveillance Plan for the Naturita, Colorado, Disposal Site

This Long-Term Surveillance Plan (LTSP) explains how the U.S. Department of Energy (DOE) will fulfill general license requirements of Title 10 Code of Federal Regulations Part 40.27 (10 CFR 40.27) as the licensee at the Naturita, CO, Disposal Site (site) and revises the original LTSP (DOE 1999). This revision incorporates changes that reflect the U.S. Nuclear Regulatory Commission (NRC) concurrence on April 15, 2014, with a request from the DOE Office of Legacy Management (LM) to terminate groundwater monitoring at the site (Appendix D). In addition, the title of the LTSP has been changed from Long-Term Surveillance Plan for the Upper Burbank Disposal Cell, Uravan, Colorado , because the town of Uravan no longer exists and the Upper Burbank disposal cell is now referred to as the Naturita disposal cell. Appendix B has been revised to include documentation of a 2003 agreement in which the Bureau of Land Management provides a right-of-way to DOE for the east and west toe drains (identified in the agreement as two storm water drainage structures) and a 2011 agreement in which Umetco Minerals Corporation (Umetco) allows DOE access to the west toe drain outlet (identified in the agreement as a diversion channel). These agreements were put in place after acceptance of the original LTSP, and they are included in this revised LTSP as a best management practice to maintain protectiveness and to inform all stewards of site conditions and controls.

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Updated Estimate of Tritium Permeation from TPBAR Disposal Containers in ILV (U)

A tritium source term analysis was performed for TPBAR disposal in the E-Area Intermediate Level Vaults for the E-Area Low-Level Waste Facility Performance Assessment (PA). This analysis is based on an earlier source term analysis which treated the bulk oft he tritium residual as tightly bound by the TPBAR getter material, with only a small fraction existing as tritiated moisture in the lithium aluminate ceramic pellets. Together with atmospheric moisture trapped in the free volume, the tritiated water vapor is assumed to corrode steel surfaces inside the disposal container, covering them with a magnetite film while generating hydrogen. The carbon steel walls of the disposal container are permeable to hydrogen, providing a path way for tritium to escape containment. The rate of hydrogen generation is assumed to be limited by the rate of corrosion, which is assumed to be governed by parabolic reaction kinetics obtained from the literature. This relies on the further assumption that the water vapor consumed by the corrosion reaction is continually replaced by moisture from the lithium aluminate pellets until all of that moisture is gone. In addition to tritium permeation, the analysis also includes a slow leak through the disposal container walls at the maximum allowable leak rate, 1 x 1CH standard cm3/s. Results were obtained for four different combinations of internal and container wall temperatures, established in an earlier thermal analysis that considered two different vault loadings and two different TPBAR activity levels. Instantaneous release rates for these four cases are plotted in Figure ES-1 below

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Tri-Agency Reliability Engineering Guidance: Post Mission Disposal and Extension Assessment

The Trilateral partners — the European Space Agency (ESA), Japan Aerospace Exploration Agency (JAXA), and National Aeronautics and Space Administration (NASA) and the United States Government (USG) in their execution of safe and successful missions, have a long-standing history of sustaining the shared space environment of operational Earth-Moon orbits with their global space-stewardship, or spacekeeping, of these areas. This has driven missions to limit the generation of new and long-lived debris, control debris releases, minimize accidental explosions and collisions, and ensure Post-Mission Disposal of space systems, so that the environment remains safe for future operations and explorations. Given the continued need for space systems to support global mandatory infrastructure and commercial enterprise, spacefarers are extending beyond the Trilateral partners, more and smaller satellites are being deployed, and current assets are being utilized much longer than expected. This is making space more congested than ever; therefore, the Trilateral partners are evaluating potential future debris mitigation strategies, evolving technology, developing on-orbit servicing capabilities, and advancing their abilities to assess disposal and mission extension plans. They are also sharing their lessons learned and identifying opportunities for future state-of-the-art advancements for current and future space enterprises. Sustaining the space environment cannot be ensured by any one agency or country. Thus, the Trilateral authors have shared their lessons learned, insights, and guidance, herein, on disposal and mission extension assessment strategies with the gratitude of each agency. As such, this document is not prescriptive, but was formulated to enhance value-and-risk-balanced operational decision-making, support policy refinement, and guide spacefaring partners beyond these agencies to assess their activities in space with safety and a global space-stewardship, or spacekeeping, in mind. This includes not only the disposal and mission extension assessment addressed herein, but also preserving space history, ensuring collaboration/interoperability of technology, supporting fellow operators without interfering, and the utilization of in-situ resources for the common benefit of humankind. It is the intention of the Trilateral partners that this document evolves based on community lessons learned and the introduction of new assessment methodologies. So, all readers are encouraged to share their insights with the authors from their own application of this guidance or other strategies to ensure each mission has a successful, safe, and judicious life and conclusion.

ESA↗

Hazard Classification of the Remote Handled Low-Level Waste Disposal Facility

The Battelle Energy Alliance (BEA) at the Idaho National Laboratory (INL) is constructing a new facility to replace remote-handled low-level radioactive waste disposal capability for INL and Naval Reactors Facility operations. Current disposal capability at the Radioactive Waste Management Complex (RWMC) will continue until the facility is full or closed for remediation (estimated at approximately fiscal year 2015). Development of a new onsite disposal facility is the highest ranked alternative and will provide RH-LLW disposal capability and will ensure continuity of operations that generate RH-LLW for the foreseeable future. As a part of establishing a safety basis for facility operations, the facility will be categorized according to DOE-STD-1027-92. This classification is important in determining the scope of analyses performed in the safety basis and will also dictate operational requirements of the completed facility. This paper discusses the issues affecting hazard classification in this nuclear facility and impacts of the final hazard categorization.

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Disposal Activities and the Unique Waste Streams at the Nevada National Security Site (NNSS)

This slide show documents waste disposal at the Nevada National Security Site. Topics covered include: radionuclide requirements for waste disposal; approved performance assessment (PA) for depleted uranium disposal; requirements; program approval; the Waste Acceptance Review Panel (WARP); description of the Radioactive Waste Acceptance Program (RWAP); facility evaluation; recent program accomplishments, nuclear facility safety changes; higher-activity waste stream disposal; and, large volume bulk waste streams.

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Are We Serious in the US about the Disposal of HLW? - 13561

Since all efforts to date to dispose of HLW in the US have been unsuccessful, the following specific actions need to be taken if we are serious about such disposal: - The requirement in the EPA environmental radiation protection standards to predict the behavior of these unwanted residuals for one million years is meaningless. The Standards must be revisited. - Characterize two sites. There are myriad ways a site can be found to be unacceptable. Additionally, the existing HLW inventory requires a second repository. - Congress should specify incentives to states under consideration for a site. Perhaps 5% of total cost would be appropriate. - An independent technical review group should be established in such states to evaluate a proposed repository similar to the New Mexico Environmental Evaluation Group (EEG) for the WIPP Project because the state's interests are not necessarily the same as DOE's. - Acceptance or rejection of a proposed site should be based on technical issues, not social ones. Professionals in this field should present papers identifying the merits of HLW disposal in their own state. The scarcity of such research suggests Not In My Back Yard (NIMBY) syndrome. - Medical diagnostic ionizing radiation exposure to the US public is now 8,000 times greater than radiation exposure from nuclear energy. People accept this believing the benefits outweigh any risks. A major effort needs to focus on both benefits as well as risks of radioactive waste disposal. - DOE needs to announce preferences of host rock formations, incentives for states, and potential consequences should we fail to act. (author)

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Development of an Integrated System for the Long-term Preservation of Records, Knowledge and Memory relating to Radioactive Waste Disposal Facilities - 17099

The Nuclear Energy Agency (NEA) has co-ordinated an international initiative to develop a common approach to the preservation of records, knowledge and long-term memory (RK and M), focused on radioactive waste disposals. The work programme has run in two phases, starting in 2011, with the current phase of the project due to be completed in 2018. Preparations for final reporting are now underway. The detailed implementation of an approach to RK and M preservation for any disposal facility will always remain a national decision. However, the NEA project has produced a 'menu' of tools and techniques that can be accessed and adapted to suit national needs. The common source of these menu components will help to ensure that the memory of the repository is kept alive, that messages to future populations can be clearly understood, and that evidence derived from the disposal environment can be properly interpreted. This paper describes the vision for implementation of the RK and M initiative within national programmes. Practical testing of some components of the menu of tools and techniques is currently underway in France, Sweden and USA, with encouraging results. Other disposal facilities, both under development or in planning, are invited to 'road test' the products and provide feedback. Refinement and maintenance of the tools remains important, and the NEA is committed to ensuring the continued accessibility and availability of the project outputs into the future. (authors)

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Update on Cigeo, the French geological disposal project - 15067

Cigeo, the French geological disposal project, is the result of 20 years of studies and research led by Andra. Following a nation-wide selection and siting process, research focused on an argillaceous formation near Bure, a village on the boundary of the Meuse and Haute-Marne departments in eastern France, for the construction of an underground research laboratory. Based on the results submitted to the French Government and Parliament in 2005, a planning act was passed in 2006, establishing geological disposal as the reference solution for managing high-level and intermediate-level long-lived waste. The act sets out guidelines for managing this waste and includes a road-map leading up to the commissioning of the geological disposal facility in 2025. A public debate was held in 2013 and the project team took note of the ensuing change requests. Meanwhile, studies and design work continue, with a particular focus on the need for optimisation and an assessment of the cost of disposal.(authors)

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Separation and recovery of uranium from residues to allow disposal as VLLW - 15379

During fabrication of uranium fuel, significant amounts of uranium contaminated wastes are generated. The uranium concentration in the waste is typically 1-10% in weight. With this uranium concentration, the residues constitute long lived Low Level Waste (LL-LLW) which need to be disposed of in a repository specifically for this type of waste. Through recovery of uranium from the primary waste, the potential for reducing the concentration of uranium to such low levels that the remaining waste qualifies as Very Low Level Waste (VLLW) are significant. The remaining waste could then be disposed of in a less costly disposal than the primary waste. A method for recovery of uranium from waste has been developed and used in Sweden and includes leaching with sulphuric acid, solvent extraction and precipitation. The final result is ammonium di-uranate (ADU). The remaining waste typically has residual uranium content in the range of 100 g uranium per tonne of waste. In several countries this would permit disposal at a hazardous waste landfill site after conditional clearance. During the development process, it has been shown that for certain types of waste it's possible to reduce the uranium concentration even further. The paper gives an overview of the technology, its applications as well as advantages and limitations. (authors)

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A Collaborative Regulatory Effort for Sealed Source Disposal - 15735

The State of Utah, Department of Environmental Quality, Division of Radiation Control (DRC), EnergySolutions, the Conference of Radiation Control Program Directors (CRCPD), and the Department of Energy's Global Threat Reduction Initiative (GTRI) collaborated on a truly innovative effort to expand opportunities for cost-effective sealed source disposal. These entities developed a first-of-its-kind initiative to dispose of certain sealed sources at the EnergySolutions disposal facility near Clive, Utah, which normally cannot accept sealed sources of any type. This creative and collaborative effort to improve radiation health, safety, and security was recognized by the Richard S. Hodes, M.D. Honor Lecture Award. This award is presented annually by the Southeast Compact Commission at the Waste Management Symposia to encourage environmental professionals and political leaders to develop innovative approaches to waste management in the United States. The participants in the collaborative initiative are honored to receive special recognition for this effort. They also recognize that the hard work remains to be done in order to ensure the continued safe management and disposal of sealed sources. (authors)

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Innovative Approach for Technetium-99 Disposal Reduces Operational Impacts - 16460

The Environmental Management Waste Management Facility (EMWMF) on the Oak Ridge Reservation began receiving and disposing waste with elevated technetium-99 (Tc-99) activities on November 11, 2013. Prior to receipt, the Tennessee Department of Environment and Conservation expressed concerns about potential releases of this highly mobile radionuclide into the environment and requested additional safeguards to minimize potential releases. Several additional requirements were negotiated to address these concerns and allow this waste lot to be safely disposed at EMWMF. Because of the 130-cm (51-inch) annual average precipitation at the landfill, the potential release of Tc-99 (above the release criterion) to surface water during the EMWMF water management activities was of the greatest concern. The EMWMF Operations staff developed an innovative approach to resolve regulator concerns regarding disposal of low-level waste containing elevated levels of Tc-99 at EMWMF. This approach minimized the spread of contamination and the generation of water that contacted the Tc-99 waste. Lessons learned and recommendations are being implemented for the next, more challenging elevated Tc-99 waste from the K-27 Building, currently scheduled for early 2016. These lessons learned are also applicable to other sites looking to minimize operational impacts from disposal of waste with elevated activities of Tc-99 or other highly mobile contaminants. (authors)

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Recovering New Type of Sources by Off-Site Source Recovery Project for WIPP Disposal - 16604

OSRP uses two types of eligible packaging configurations for Cm-244 and Cf-252 disposal to WIPP: an S-100 drum and a 12'' Pipe Overpack (POC) drum. Both types of packaging are WIPP accepted configurations for Contact Handled (CH) waste, which offer different advantages and disadvantages when used in the case of the two isotopes. The S-100 is a poly-shielded type A, 55 gallon drum, containing a 6'' diameter POC. The 12'' POC drum is a type A, 55 gallon drum without the internal poly-shield and with a pipe component of 12'' diameter. The S-100 drum presents the advantage of poly-shielding which is very important for neutron sources, such as the Cf-252, or Cm-244Be, at the expense of reduced internal volume. The 12'' POC drum presents a larger pipe component accommodating many more sources, like Cm-244 alpha emitters or shielded Cf-252, for which the CH dose rate is not an issue. All the sources prepared for disposal to WIPP are required to be special form, as defined in 49 CFR 173.403. When OSRP recovers normal form sources, these can be packaged in a field closable DOT certified Special Form Capsule (SFC) model II or model III, thus becoming special form. These capsules are then packaged in the type-A containers. The difference between the two types of packaging is that the 12'' POC can hold more sources, or a mix of sources and capsules at the expense of less shielding. This becomes important when the TRU content criteria of 100 nCi/g of TRU waste has to be met for the drums that are packaged for WIPP disposal. Measured neutron dose rates for Cm-244 packaged in S-100 agree reasonably well with calculated dose rates based on the models developed with MCNP. Future work will include validating the model for Cm-244 packaged in 12'' POC. A 1:1 ratio of neutron to gamma is expected for Cm-244Be dose rates packaged in S-100 drums. For Cf-252 packaged in S-100 and 12'' POC, the contribution of Cf-250 to the total emission neutron rate had to be taken into account due to the increasing role of Cf-250 as sources age. The uncertainty in the measurement of Cf-252 neutron dose rate for S-100 drum was quite high due to a high neutron background. A larger Cf- 252 source needs to be used for measurements in the future, in order to fully validate the model developed. A better agreement for measured versus calculated rate was obtained for a Cf-252 packaged in 12'' POC. For the WIPP disposal of these sources, OSRP will use the best packaging configuration for these isotopes in order to minimize the dose rate and maximize the TRU content. The S-100 packaging will be used for Cf-252 and Cm-244Be sources, when neutron dose reduction by the poly-shielding is important. Neutron dose rates will be estimated using the new MCNP correlations.

07 ISOTOPE AND RADIATION SOURCES↗

A Modelling Framework for Understanding the Impacts of Radioactive and Chemo-toxic Waste Disposals - 18199

In order to assess the compliance of a radioactive waste disposal facility against regulatory requirements, it is usual to develop a numerical model that provides estimates of quantities such as effective dose, radiological risk and environmental concentrations at times in the future after disposal of the wastes. An important aspect of a safety case based on the results of the numerical assessment model is to develop understanding and confidence in the results. This understanding includes determining why the magnitudes of the results are as they are, determining the key controlling parameters on the model outputs, providing confidence that the model outputs are credible, providing an alternative and complementary modelling approach, undertaking sensitivity analyses and facilitating communication of the safety case results with stakeholders. In this paper we present a modelling approach that addresses these issues for a wide range of disposal concepts. The approach captures the key processes that affect contaminant migration and transport, and uses analytical solutions to provide insight and understanding about the behaviour of a disposal system. The approach has been tested against a wide range of concepts for LLW, ILW, HLW and SF. In all cases, agreement with the results from numerical assessment models is found to be very good, with estimates of peak radiological risk and other metrics within a factor of two or better, compared with those from numerical assessment models. This agreement is achieved for assessment results that can potentially span many orders of magnitude. (authors)

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Developing Waste Characterization Capabilities in Support of the Near Surface Disposal Facility - 19245

Upon approval from the Canadian Nuclear Safety Commission, Canadian Nuclear Laboratories (CNL) Proposed Near Surface Disposal Facility (NSDF) to be constructed at CNL's Chalk River Laboratories will be the first permanent disposal facility in Canada for the disposal of low level radioactive waste. The NSDF is currently in the approval process and as such, a preliminary Waste Acceptance Criteria (WAC) has been implemented for the proposed facility. Waste currently generated at CNL is being characterized to verify that it meets the WAC and will be 'disposal ready' once the NSDF is operational. A robust waste characterization program is required for the following reasons: 1. Improved waste segregation to support waste minimization and recycling to ensure non-radioactive waste is reliably segregated and removed from radioactive waste streams destined for the NSDF. This includes characterization and discrimination of Naturally Occurring Radioactive Material (NORM) and anthropogenic radioactive material. 2. To ensure low level waste (LLW) is properly characterized as per the limits stipulated within the WAC to ensure criteria is met for NSDF packaging requirements 3. To ensure intermediate level waste is reliably segregated from NSDF destined wastes streams The purpose of this paper is to provide a review of the development of a waste characterization program strategy at Chalk River Laboratories and applicability of various waste streams; including consideration of important factors such as measurement methods, techniques, and the management of data. Emphasis is necessarily placed on non-destructive gamma spectrometry systems which are central to CNL's approach. A review of near-term developments is also provided. (authors)

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Site Selection Criteria for Deep Borehole Disposal of Intermediate Level Waste in Australia - 19615

Disposal of long-lived intermediate-level waste (ILW) and long-lived spent sealed sources (SSS) requires a high degree of containment and isolation deep underground. Disposal in medium-depth (several hundreds of metres) boreholes in suitable hard rock formations can provide adequate isolation and containment for safe and cost-effective disposal of relatively small volumes of ILW and SSS. In this paper we outline recommended site selection criteria for the purpose of (i) identifying regions that would be excluded from further consideration, and subsequently for the non-excluded regions, (ii) to identify sub-regions that could be developed into a deep borehole disposal site. The CSIRO approach builds on siting guidelines previously developed by the Sandia National Laboratory which have been revised to suit the Australian context. (authors)

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Panel Session 134: Stakeholder Involvement in Consolidated ISF Storage, Disposal, and Transportation Initiatives

Planning of activities related to waste storage, transportation, and disposal requires involvement and engagement on the parts of both regulators and stakeholders. There have been challenges felt by both parties, which has led to discussions about how to best proceed with projects not just from a technical perspective, but how to create better relationships between the general public and scientific community. This panel was designed to highlight lessons learned, best practices, and next steps in anticipated projects. This panel focused on the current efforts undertaken by initiatives to involve stakeholders for the success of ISF Storage and Disposal facilities. For example, two license applications were submitted to the US NRC by two private entities - Interim Storage Partners (WCS, Inc, and Orano) and Holtec, Inc./ELLA - for consolidated ISF in West Texas and in NM (respectively). This panel discussed elements needed for success in engaging various stakeholders at all levels of the project life cycle, and can include lessons learned from previous projects. Panelists with presentations: Stakeholder Engagement in SNF Storage and Disposal (Miriam Juckett); Stakeholders, Siting and Nuclear Waste Disposal -Thoughts on a Path Forward (Jim Hamilton)

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Quest for Continuous Design and Safety Optimization: A Look at Cires, the French Very Low Level Waste Disposal - 20010

Cires, the French repository for very low-level waste (VLLW) managed by Andra, has a fifteen-year history of enhancing design and disposal operations, responding to producers' needs by optimizing existing facilities and providing new facilities as needed. Its flexibility allows the facility to adapt to changes in waste delivery flows, to dispose of larger waste volumes without using more space, to integrate new concepts and even envisage disposal capacity extension. The article traces the ever evolving history of technical and operational optimization of this unique disposal facility situated in Eastern France. (authors)

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