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A Bottom's-Up Model for Siting and Developing Consent-Based Disposal Solutions for SNF and HLW in the USA - 17332

At the end of 2016, the licensing and continued development of the USA's only candidate HLW-repository since 1987 at the Yucca Mountain (YM) site in Nevada had been on hold since 2010 pending the enactment of enabling legislation for one or more of the following paths forward: 1. Re-start of the YM HLW repository. 2. Consent-based siting and development (S and D) of new HLW-repositories for commingled disposal of commercially- (CHLW) and defense-generated (DHLW) HLW. 3. Consent-based S and D of a repository and/or deep boreholes for DHLW only. Public trust in the implementing and regulating entities and a definitive say in an apolitical S and D process by the directly affected parties (DAPs) are historical imperatives for gaining public acceptance and maintaining sustained support of any or all of them. However, due to the widespread negative legacy currently attributed to past politically-controlled S and D organizations, an even more politically controlled organizational structure and an amorphous, 'consent-based', S and D model like that introduced twice in proposed Senate bills since June 2013 will exacerbate, rather than mitigate, the main root causes to past contentions, lawsuits, delays, and cost-increases. We therefore recommend: 1) Assigning the responsibility for safe disposal of CHLW to an independent, chartered public corporation with requisite subject-matter expertise and adequate financial resources. 2) Enacting a related law that: a. Defines 'consent-based' in measurable terms; b. Assigns irrevocable veto rights to facility host state(s) based upon the majority opinion of its legal residents at pre-determined S and D milestones. c. Requires Congressional approval before the facility can open and close. (authors)

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Implementation of Glycolic Acid Flowsheet in the Defense Waste Processing Facility (DWPF) - 17348

The disposition of high level waste (HLW) into canistered waste forms began at Savannah River Site (SRS) in 1996. For its entire processing history, DWPF has added formic acid as a pretreatment step in producing acceptable melter feed from incoming waste sludges sent from the HLW Tank Farms. While this process has been used to successfully produce more than 4,000 radioactive canisters, the addition of formic acid and its tendency to catalytically decompose in the presence of trace quantities of noble metals adds substantial process complexity in order to safely accommodate hydrogen generation and pH shifting during batch operations. Research efforts have been in progress for several years to identify a chemical surrogate for formic acid which performs the essential process functions without the associated negative consequences. The final analytical work to demonstrate the effectiveness of glycolic acid in the DWPF is nearly complete and a project team has been created to safely integrate the new acid into the chemical process. The project team is currently executing an implementation schedule which addresses safety basis development, revision to operations procedures and training, facility modifications, chemical procurement, and updated process monitoring. Introduction of glycolic acid into DWPF is currently scheduled to take place in early 2017, beginning with a blended flowsheet of glycolic and formic acid and ultimately transitioning to glycolic-only processing. This paper provides an overview of planned glycolic acid flowsheet implementation in the DWPF. This paper discusses several issues related to implementing such a significant change to the chemical process including: 1) Process chemistry differences between the two flowsheets with quantitative comparison for several properties of interest; 2) Technical approach to hazards analysis and safety basis development strategy; 3) Status of project execution for major deliverables; and 4) Path forward for facility modifications related to legacy formic acid support equipment. (authors)

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Hanford's Double-Shell Tank AY-102 Recovery Project - 17416

Since at least August 2012, Hanford Tank 241-AY-102 (AY-102) has been leaking from its primary tank into its secondary containment. A pumping plan was developed in 2013 to provide a path forward for recommended remediation actions to be implemented as part of the AY-102 Recovery Project. On March 21, 2014, the Washington State Department of Ecology issued Administrative Order No. 10618 requiring Washington River Protection Solutions and the United States Department of Energy to conduct actions related to and including the removal of waste from AY-102. The three parties agreed to resolve the appeal of the Administrative Order through a Settlement Agreement which addresses the remaining requirements and implements enforceable milestone dates, including initiation of waste retrieval by March 4, 2016 and completion of waste retrieval operations by March 4, 2017. The AY-102 Recovery Project was developed to address the Settlement Agreement requirements. While retrieval of waste from Single-Shell Tanks has been performed at Hanford for decades, retrieval from Double-Shell Tank AY-102 required adaptation of the existing technologies to a new environment on a larger scale than previously encountered. A significant number of obstructions and in-tank equipment limit accessibility to the high source term AY-102 waste and the location of the selected receiver tank required installation of an extensive, heavily-shielded above-ground transfer line. Despite countless challenges and obstacles encountered throughout, the project successfully completed system design, fabrication, installation, testing, and the first phase of operations within a highly compressed, aggressive schedule. Waste retrieval operations in AY-102 commenced on March 3, 2016 and the initial operating phase concluded on April 30. Additional sluicing capability was required to complete the mission and four Extended Reach Sluicers were installed to support the second operating phase, which began on December 8, 2016. As of December 31, 2016, approximately 97% of the original waste volume had been removed, resulting in an estimated remaining waste volume of about 75,000 liters. (authors)

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Hydrophobic Filter Material for Nuclear Material Transportation and Storage Containers - 17518

Los Alamos National Laboratory has begun development of hydrophobic or super-hydrophobic inorganic filter materials that resist water ingress after exposure to radiation and/or elevated temperature. Filters that are currently available depend on carbon composites and/or organic polymers for their water resistant/hydrophobic properties to minimize water ingress. However, facility and transportation accident scenarios often include fire, impact and subsequent water spray or flooding conditions. A purely inorganic hydrophobic filter material could have enhanced resistance to fire and radiation damage, and continue to minimize water ingress after such an accident. Such filters could broaden the use of filtered containers in the transportation and storage of nuclear materials, and could have broader implications in other industrial applications. The goal is to create a porous inorganic material with hydrophobic properties that maintains or exceeds the current performance criteria for particulate filtration efficiency, pressure differential, air flow and hydrogen diffusion. The materials developed in this project show promise in evaluations for use as enhancements to the SAVY 4000 nuclear storage container that is becoming widely used around the DOE complex. Preliminary results indicate that the treated filters provide resistance to a water column pressure test and have filtration efficiencies and air flow pressure drops that meet the current performance criteria. There are various treatment options being tested to help determine the best path forward. (authors)

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Engaging the Public on Complex Issues: Communication challenges and Solutions - 17521

Public buy-in and support can make or break a project that has local environmental effects and implications, especially if that project takes place in a large community that is in-touch with its local and national government. Because of this, effective public communication is essential to the future of projects that can have an impact on a local community. This paper addresses the challenges and methods of communicating complex, scientific and/or technical issues with the public in an easy-to-understand, engaging manner while still accomplishing the communication goals of the organization. For consideration in particular is the challenge of communicating the proposed path forward and ongoing progress being made at ORP's tank farms and Waste Treatment and Immobilization Plant project to help build support and acceptance with local and national audiences. By using a variety of engagement opportunities and communication tools, we are able to educate the public on the issues being addressed by the organization, the possible solutions to these issues, and the challenges involved. An engaged and well-informed public can assist the organization in accomplishing its mission by educating and influencing audiences that have an impact on the organization. (authors)

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Maintaining department of energy (DOE) waste disposition pathways in today's uncertain budgetary environment - 15129

For many years the Department of Energy (DOE) and its prime contractors have worked collaboratively with commercial waste transportation, treatment, and disposal providers to develop and implement outlets for the efficient management and disposition of radioactive wastes, particularly 'no-path-forward' or 'difficult-to-treat' wastes. Both the DOE and commercial providers have made substantial investments to develop capabilities and infrastructure to address these wastes and both have benefited from this collaboration. For example, DOE realized significant cost savings and avoidances when a commercial facility became available that allowed closure of the TSCA incinerator in Oak Ridge or when commercial capabilities were expanded that precluded the need to build a new Hanford M-91 waste treatment facility, estimated at $540 million for design, permitting, and construction. In addition, expanded capabilities developed at commercial facilities ensured a known, if not guaranteed, source for managing waste and improving efficiencies for wastes which previously had no viable disposition outlet or that required extended schedules and cost for completion. Such wastes include sodium- and mercury-bearing wastes, classified shapes, or many forms of suspect transuranic (TRU) wastes. (authors)

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Laying the groundwork for a large-scale spent nuclear fuel transportation system - 15408

The US Department of Energy Office of Nuclear Energy established the Nuclear Fuels Storage and Transportation Planning Project to lay the groundwork for implementing an interim storage facility, including associated transportation activities. Efforts include the development of a system for the large-scale transport of spent nuclear fuel that will be necessary in an integrated waste management system. Progress is being made on long lead time, destination-independent aspects of the transportation infrastructure. The large-scale transportation system for spent nuclear fuel is divided into three elements: institutional, operational, and hardware. The institutional element refers to the various forms of stakeholder interaction that must occur for this type of transportation system to be successful. It includes activities like development of a national transportation plan, work on policy development for Section 180(c) of the Nuclear Waste Policy Act, and identification of a preliminary suite of national transportation routes that reflect the interests of a broad cross section of stakeholders while meeting regulatory requirements. The operational element refers to the activities that must be undertaken to run a large-scale transportation system. This element is currently focused on development of a new SNF transportation routing analysis tool, study of the infrastructure near SNF storage sites that may be de-inventoried first, and development of tools for modeling transportation activities. The hardware element refers to the casks, railcars, and other items necessary to operate the system. This element currently focuses on development of railcars compliant with Association of American Railroads Standard S-2043, as well as studies related to the use of rail casks and their ancillary equipment. The Nuclear Fuels Storage and Transportation Planning Project is making significant progress in all three of these areas along the path forward to a fully operational transportation system. (authors)

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In-service inspection of radioactive waste tanks at the Savannah River Site - 15410

Liquid radioactive wastes from the Savannah River Site (SRS) separation process are stored in large underground carbon steel tanks. The high level wastes are processed in several of the tanks and then transferred by piping to other site facilities for further processing before they are stabilized in a vitrified or grout waste form. Based on waste removal and processing schedules, many of the tanks, will be required to be in service for times exceeding the initial intended life. Until the waste is removed from storage, transferred, and processed, the materials and structures of the tanks must maintain a confinement function by providing a barrier to the environment and by maintaining acceptable structural stability during design basis events, which include loadings from both normal service and abnormal (e.g., earthquake) conditions. A structural integrity program is in place to maintain the structural and leak integrity functions of these waste tanks throughout their intended service life. In-service inspection (ISI) is an essential element of a comprehensive structural integrity program for the waste tanks at the Savannah River Site (SRS). The ISI program was developed to determine the degree of degradation the waste tanks have experienced due to service conditions. As a result of the inspections, an assessment can be made of the effectiveness of corrosion controls for the waste chemistry, which precludes accelerated localized and general corrosion of the waste tanks. Ultrasonic inspections (UT) are performed to detect and quantify the degree of general wall thinning, pitting and cracking as a measure of tank degradation. The results from these inspections through 2013, for the 27 Type III/IIIA tanks, indicate no reportable in-service corrosion degradation in the primary tank (i.e., general, pitting, or cracking). The average wall thickness for all tanks remains above the manufactured nominal thickness minus 0.25 millimeter and the largest pit identified is approximately 1.70 millimeter deep (i.e., less than 10% through-wall). Improvements to the inspection program were recently instituted to provide additional confidence in the degradation rates. Thickness measurements from a single vertical strip along the accessible height of the primary tank have been used as a baseline to compare historical measurements. Changes in wall thickness and pit depths along this vertical strip are utilized to estimate the rate of corrosion degradation. An independent review of the ISI program methodology, results, and path forward was held in August 2009. The review recommended statistical sampling of the tanks to improve the confidence of the single strip inspection program. The statistical sampling plan required that SRS increase the amount of area scanned per tank. Therefore, in addition to the baseline vertical strip that is obtained for historical comparisons, four additional randomly selected vertical strips are inspected. To date, a total of 104 independent vertical strips along the height of the primary tank have been completed. A statistical analysis of the data indicates that at this coverage level there is a 99.5% confidence level that one of the worst 5% of all the vertical strips was inspected. That is, there is a relatively high likelihood that the SRS inspection program has covered one of the most corroded areas of any of the Type III/IIIA waste tanks. These data further support the conclusion that there are no significant indications of wall thinning or pitting. Random sampling will continue to increase the confidence that one of the worst 5% has been inspected. In order to obtain the additional vertical strips, and minimize budget and schedule impacts, data collection speed for the UT system was optimized. Prior to 2009, the system collected data at a rate of 32 square centimeters per minute. The scan rate was increased to 129 - 160 square centimeters per minute by increasing the scanner step and pixel sizes in the data acquisition set-up. Laboratory testing was utilized to optimize the scan index/pixel size such that the requirements for wall thinning and pit detection were still maintained. SRS continues to evaluate improvements to ultrasonic equipment. (authors)

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U.S. department of energy safety design strategy review and approval beyond critical decision 3 for the high-level waste facility - 15525

The Waste Treatment and Immobilization Plant (WTP) in Hanford, Washington, is the nation's largest environmental remediation construction project. In 2012, at the WTP's High-Level Waste (HLW) Facility, the U.S. Department of Energy (DOE), Office of River Protection (ORP) restricted construction work at the Hazard Category 2 nuclear facility because of unresolved technical issues associated with the facility and of misalignment of the design and nuclear safety basis. By 2013, as additional issues were discovered, ORP limited HLW design and procurement activities. Addressing the technical issues and the misalignment of the design basis with the Preliminary Documented Safety Analysis (PDSA) is a priority for ORP. A proposal was developed to use the concept of a safety design strategy (SDS), as documented in DOE-STD-1189-2008, Integration of Safety into the Design Process, as a planning mechanism to support facility design and PDSA alignment. The standard provides the processes to develop an SDS that will ensure safety is integrated into design early in the project, by the start of preliminary design. Ultimately, as design progresses, an SDS is intended to support development of the project's PDSA. However, in this unique case, the HLW Facility design and construction phase has progressed beyond Critical Decision 3 and DOE-STD-1189-2008 was issued in 2008; 6 years after ORP approved the first WTP PDSA. In July 2013, ORP and the contractor recognized that the unresolved technical issues and design - safety basis misalignment should be addressed through a renewed look at nuclear safety requirements, and agreed that developing an SDS tailored to the criteria in DOE-STD-1189-2008 provided the best path forward to better integrate design and safety. Development of the SDS for the HLW Facility was one of many goals ORP established in a plan that describes how ORP will determine whether, and under what conditions, the contractor should be authorized to proceed with production engineering, procurement, and construction activities for the HLW Facility. Over the next several months, the contractor developed the draft SDS, identifying design basis accidents and control strategies for those accidents. ORP monitored progress and, when appropriate, provided recommendations. In April 2014, the contractor provided a draft SDS to ORP for initial review by an independent DOE Review Team. The Review Team was comprised of representatives from nuclear safety, criticality safety, engineering, fire protection, the Office of Environmental Management, the Assistant Manager WTP, and the DOE Chief of Nuclear Safety. A unique draft document review and interactive review process, facilitated through work sessions and continuous communication with the contractor, culminated in the development of 147 technical comments on topics varying from SDS implementation to hydrogen deflagration in vessels. Comment resolution sought to improve project clarity, delineation of control strategies, and, holistically, facilitate integration of safety into design in the SDS, as it will guide the restart of the HLW Facility production engineering and limited procurement and construction activities. All comments were resolved in support of a contractor submission of the final SDS to ORP at the end of June 2014. Successful resolution of these comments was achieved by continuing the real-time response and incorporation interaction with the contractor to ensure that mutual objectives were satisfied. The response times were facilitated through telephone, E-mail, and a shared file server accessible to contractor and DOE reviewers across the DOE complex. As a measure of success of this process, the Safety Basis Approval Authority (ORP Manager) and the WTP Federal Project Director approved the SDS on August 1, 2014, with no conditions of approval. DOE and the contractor recognized that it would be difficult to implement the SDS without changes to the existing contractor's engineering and nuclear safety processes. Accordingly, the contractor developed or revised a significant number of engineering and nuclear safety plans and procedures to implement the SDS into the design process. Over the coming year, the contractor will conduct a gap analysis between the SDS and the presently approved PDSA to incorporate the design basis accidents and preferred control strategies developed from the SDS into the PDSA. In addition, ORP will conduct an assessment of the contractor's implementation of the SDS into the design process at the appropriate stage of implementation, within 6 to 12 months of approval. Although the SDS was developed late in the HLW project timeline, the document will facilitate alignment of design and the safety basis, and is a key step in the return to full production engineering for the HLW Facility. (authors)

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Progress updates for the Hanford waste treatment and immobilization plant project - 15593

The Waste Treatment and Immobilization Plant (WTP) Project is vital to the U.S. Department of Energy's (DOE) mission to clean up radioactive waste at the Hanford Site in southeastern Washington State. The overall WTP Project objective is to design, build, and commission the facilities and systems that will treat and immobilize approximately 211 983 m{sup 3} (56 million gallons) of radioactive waste stored in 177 underground storage tanks. The combination of technologies in the WTP makes it a first-of-a-kind facility at a scale larger than ever built for radioactive waste processing. In recent years, the project has encountered issues that affected project design completion, especially in the Pretreatment and High-Level Waste Facilities. These included technical issues, changes in requirements, changes in funding, weaknesses in the nuclear supply chain, identification of new hazards, and new information about the tank waste. The combination of these issues led to a suspension of construction of the Pretreatment Facility and a partial suspension of construction of the High-Level Waste Facility in mid-2012. Since then, the WTP Project has made significant progress in establishing and implementing a strategy for resolving these issues. This strategy focuses on resuming full production work in a sequence that fully supports the DOE plan for a phased approach for starting treatment of the Hanford tank waste, beginning with the low-activity waste streams. Concurrent with the technical and programmatic issues, the DOE Office of River Protection has made numerous changes in the processes it uses to manage and oversee the WTP Project. These changes have had a beneficial impact on the progress the project has made in establishing a path forward for resuming production activities, and on planning for the necessary contract and baseline changes needed to complete the project. (authors)

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Knowledge management information tool analytics with distributed database engine - 15737

The D and D KM-IT is a web-based knowledge management information tool custom built for the deactivation and decommissioning (D and D) user community. The system allows interested users to post information which goes through a custom work flow. To better improve the performance and user experience, the analysis of server logs is being conducted using MongoDB. MongoDB is a document database that provides high performance, high availability, and easy scalability. Objectives: - Feasibility study of Distributed Database Engine, MongoDB for web analytics; - Analyze server logs to evaluate D and D KM-IT module usage; - Generate useful information from the analysis. Method: - The server logs were loaded and stored in MongoDB for analysis; - Analysis and visualization was performed using NodeJS and Java Script library. Results: - It was possible to store log files in MongoDB; - Log files with different time stamps and groups from different servers can be aggregated; - Queries can be written to extract meaningful information from aggregated log files (e.g. users from different countries/organizations). Conclusions: - MongoDB is useful for server log analytics as the analyst can immediately access, analyze, and visualize MongoDB data based on the requirements; - The information can be extracted to develop custom reports; - Optimized queries can be run for fast data access. Path forward: - Custom queries need to be developed to extract information leading to improved user information.

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Salt Rock - the 60-Year-Old Prodigy Host Rock for Consent-Based Disposal of Long-Lived Radioactive Waste - 16010

The USA's HLW-disposal program has been on hold since 2010 pending enabling legislation for its only candidate HLW-repository since 1987 at the Yucca Mountain site in Nevada and/or other, 'consent-based', HLW-disposition solutions. Related projections in 2008 and 2012 suggested they might open 9-12 years and 35 years after being adequately enabled, respectively. In 2014, domestic HLW arisings exceeded the capacity of the candidate repository by >4,000 metric tons (MT) and they were projected to grow by 2,000-2,300 MT/year. One or more new HLW repositories are thus highly-likely in the future. In the meantime, the DOE should make every effort to promptly take title to civilian-generated HLW by other means. Historical evidence in the USA and abroad during the past 30+ years shows that all HLW-repository siting and development schedules and costs are governed by the inherent, intricate, relationships and related domino effects of the: 1. Maturity/robustness of the disposal concept; 2. Related levels of relevant domestic repository-sciences/engineering expertise, data, institutional knowledge, and applicable regulations; 3. Abundance and 'ease' of physical access to potentially-suitable host-rock sites; 4. 'Trust' in the implementing and regulating organizations; 5. Timely resolution of inevitable contentions and lawsuits; 6. Facility-host-acceptance level; 7. Timely and adequate enabling legislation, and therefore, ultimately, by 8. Prevailing Political Will. Based upon their respective status at the end of 2015, salt rock still offers the most, but not the only, promising path forward for new, mined, HLW repositories in the USA, and ∼5-km-deep boreholes offer the most-promising disposal-solution for small HLW containers/packages/pellets. (authors)

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Remote-Handled TRU Storage Challenges at Sandia National Laboratories/ New Mexico - 16071

The events at the Waste Isolation Pilot Plant (WIPP) in February 2014 had a significant impact on the packaging, storage, and disposal options at Sandia National Laboratories/New Mexico (Sandia) as with other transuranic generator sites. In 2012, Sandia had identified accountable material for disposal, fresh and irradiated mixed oxide (MOX) and uranium oxide (UO{sub 2}), which had been used in experiments conducted in the 1970's and 1980's. During the 2012/2013 timeframe, discussions with WIPP determined the samples and experimental vessels qualified as remote-handled (RH) transuranic (TRU) waste for disposal at WIPP. Sandia began discussions with WIPP to determine the process to repackage and characterize the material for disposal at WIPP in addition to obtain funding to complete the project. By January 2014, Sandia had contracted with Nuclear Waste Partnerships, LLC (NWP) to provide Central Characterization Program (CCP) certified visual examination (VE) and dose-to-curie (DTC) support to package and certify the accountable material/waste. Work began on February 3, 2014 with the arrival of two VE operators. On February 5, 2014, a salt truck caught fire in the underground and on February 14, 2014, the radiological release occurred at WIPP initiating a suspension of shipments. The length of the suspension was not known at the time. Sandia was only a couple of days into this long-term project, had signed a contract with NWP for support, and was still responsible for meeting earlier negotiated milestones. There were 37 parent containers which included experimental vessels from 3 to 10 feet long and unused material pieces. The original plan was to package each of the 37 parent containers separately, but several issues, including the suspension of shipments, made it imperative that a new path forward be developed. Because space is limited in the Auxiliary Hot Cell Facility (AHCF), the storage configuration for criticality safety and material-at-risk was of the highest importance. Therefore, packaging in the fewest number of containers without exceeding WIPP limits, keeping the accountable items together, and not violating any safety basis requirements was Sandia's goal. (authors)

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Niagara Falls Storage Site - Interim Waste Containment Structure - 16199

The Niagara Falls Storage Site (NFSS) is a 77.3-hectare (ha) (191-acre) property that is owned by the United States Government and located in the township of Lewiston, Niagara County, New York. The NFSS is part of the former Lake Ontario Ordnance Works (LOOW) that was used by the War Department beginning in 1942 for the production of trinitrotoluene (TNT). During the 1940's and 1950's, the Manhattan Engineer District and the Atomic Energy Commission brought various radioactive wastes and uranium processing byproducts (residues) resulting from our nation's atomic energy program to the LOOW for storage. Site operations caused soil, sediment, and groundwater contamination that lead to several remedial actions, which culminated in the construction of the Interim Waste Containment Structure (IWCS) on the NFSS. The U.S. Army Corps of Engineers (USACE)-Buffalo District is the lead Federal agency for Formerly Utilized Sites Remedial Action Program (FUSRAP) remediation of the NFSS. As the lead agency, USACE is conducting a remedial investigation/feasibility study (RI/FS) pursuant to the protocols set forth in the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). CERCLA activities at the NFSS have transitioned from the site RI activities to the FS evaluation of potential remediation alternatives. USACE recognizes the need to implement a focused CERCLA FS process and, therefore, has established three separate operable units (OUs) for NFSS: the IWCS OU, the Balance of Plant (BOP) OU [i.e., all on-site areas outside the boundary of the IWCS], and the Groundwater OU. This paper will discuss the following: - Provide background information on the NFSS including the nature of the materials within the IWCS. - Explain the steps of the CERCLA and associated processes the Formerly Utilized Sites Remedial Action Program (FUSRAP) employs. - Describe the OUs for the NFSS property and the subunit designations used in the FS evaluations for the IWCS OU. - Provide the current project status within the CERCLA framework and path forward for all OUs and Vicinity Properties (VPs). Identify the Applicable or Relevant and Appropriate Requirements (ARARs) preferred by USACE and the regulatory agencies and explain the differences between the two positions. - Provide the comparative evaluation of the remedial alternatives assessed in the FS. - Identify the justifications for the USACE - Buffalo District selecting the preferred remedial alternative within the Proposed Plan. The remedial action objectives for the IWCS OU are designed to provide short- and long-term protection of human health and the environment. CERCLA requires that any action taken be protective of human health and the environment as well as be compliant with identified ARARs. USACE evaluated 'No Action' and four potential remedial alternatives for the IWCS OU that ranged from leaving all of the wastes in-place and installing a final cover to partial and full removal of the contents. The four alternatives met the remedial action objectives defined identified for the IWCS OU. In accordance with the statutory requirements of CERCLA Section 121, remedial alternatives must comply with two threshold criteria, overall protection of human health and the environment and compliance with ARARs, in order to be carried forward for further evaluation. If a remedial alternative meets the threshold criteria, it is evaluated against the following five balancing criteria: - Long-term effectiveness and permanence; - Reduction in toxicity, mobility, or volume through treatment; - Short-term effectiveness; - Implementability; and, - Cost. The Feasibility Study evaluation led to the preferred remedial alternative selection and this will be the focus of this paper. (authors)

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Endpoint Evaluation for 200-PW-1 Operable Unit Soil Vapor Extraction, Hanford Site, Washington - 16478

On the Central Plateau of the Hanford Site in semi-arid southeast Washington State, the 216-Z-9 Trench, 216-Z-1A Tile Field, and 216-Z-18 Crib were used from 1955 to 1973 for soil column disposal of liquid wastes containing carbon tetrachloride. The geological setting underneath these disposal areas consists of an approximately 70 m thick vadose zone with a nominally 5 m thick low-permeability layer at a depth of 30 m. Infiltration of the liquid waste through the vadose zone to the groundwater was driven by the liquid volume introduced during disposal. Carbon tetrachloride readily volatilises in the vadose zone, making soil vapor extraction (SVE) the preferred remediation technology. Between 1992 and 2012, SVE recovered 80,107 kg of carbon tetrachloride from the vadose zone below the three waste sites. Of this total recovery, 93 percent was removed during the first 5 years of operations. The last 7 percent was recovered in the last 16 years of operation. In 2011, a final cleanup level of 100 ppmv for carbon tetrachloride in soil vapor was established in the record of decision for the 200-PW-1 Operable Unit, which includes the three carbon tetrachloride waste sites. The final cleanup decision specified that soil vapor concentrations and the cleanup level would be further refined and assessed in the future to ensure groundwater protection. A subsequent treatability test was conducted and the results were used to further refine the definition of vadose zone source conditions that are protective of groundwater. Based on this treatability test, predictions indicate that current and future vadose zone conditions will meet groundwater protection objectives. SVE operations were not performed in 2013, 2014, and 2015, and soil vapor concentrations in all SVE wells (and all but two monitoring probes installed using direct-push technology) remained below the 100 ppmv cleanup level during this time. SVE endpoint guidance was prepared in 2013 as a joint effort between Pacific Northwest National Laboratory, U.S. Army Corps of Engineers, and U.S. Environmental Protection Agency. This SVE guidance was used to develop a path forward for the 200-PW-1 Operable Unit SVE remedy. The guidance asks the following questions: 1. Are data collected to date adequate to support a well-defined conceptual site model? 2. Have remediation goals (cleanup levels) been defined? 3. Are environmental pathways and risk understood well enough to support site closeout? 4. Will remaining contamination in the vadose zone cause groundwater cleanup levels to be exceeded? If the answer to the first three questions is 'Yes', and the answer to the fourth question is 'No', then the site is ready for closure. At this time, the site has compiled appropriate information to answer these questions to support a remedy decision to terminate SVE operations. The U.S. Environmental Protection Agency recently provided concurrence that termination of SVE operations within the 200-PW-1 Operable Unit is appropriate. (authors)

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Evaluation of Options for Disposition of Mk-42 Materials - 18034

In the late 1980's, the DOE defense programs identified a need to recover special isotopes of americium, curium, and plutonium from Mark-42 (Mk-42) targets that had been irradiated at the SRS. Eighty Mk-42 target segments were transferred from SRS to ORNL for recovery of these special isotopes. Approximately 65% of the target material has been processed, and the recovered material converted to solids. The remaining Mk-42 materials are stored either as targets in their irradiated forms or as target material from various stages of processing. The Pu, Am-243 and Cm-244 in these targets are valuable materials; for example, the Am/Cm materials are potential feedstocks for production of heavy actinides (Cf-252, Bk-249, etc.). In addition, rare long-lived fission product (LLFP) isotopes present in the targets in much smaller quantities, such as Zr-93, also have value to the research community. Although the isotopes in the Mk-42 materials have value, there is continual pressure to de-inventory the material in storage and only retain the most valuable materials needed to meet mission needs and provide inventory space for other materials to be added as they become available. Evaluations are underway for potential disposition options for the Mk-42 materials. Previous studies have included identification and evaluation of disposition options for the various Mk-42 materials in storage at ORNL [1]. Evaluations have included options for recovering the major isotopes and evaluating the waste that would be sent to disposal facilities. This paper summarizes the next steps in the evaluation process to develop an optimum path forward for the disposition of the Mk-42 materials. It includes an evaluation of the future programmatic need for the materials, the impact of storage on facility operations, and additional evaluations of options for dispositioning the materials. In addition to recovery of the major isotopes previously evaluated, it also looks at the potential to recover rare LLFP isotopes present in the targets in small quantities. (authors)

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Minority Serving Institutions Partnership Program (MSIPP) - 18108

The DOE-EM recognizes that successfully completing its legacy environmental cleanup mission will require maintaining a well-trained, technically skilled, and diverse workforce. Minority representation in critical science and engineering fields is an important part of EM's vision for the future workforce. The Minority Serving Institutions Partnership Program (MSIPP) has been created and designed to increase the numbers of minorities with science and engineering experience in areas important to the success of the DOE-EM mission. MSIPP will provide financial assistance for science, technology, engineering, and mathematics (STEM) activities at Minority Serving Institutions (MSI) engaged in research and related STEM efforts supporting EM's needs. The program offers research internship opportunities at DOE National Laboratories across the DOE complex. MSIPP also encourages research collaborations between MSI Universities and DOE National Laboratories by funding research in areas relevant to DOE-EM needs. Based on current DOE-EM missions, there are two research focus areas: Tank Waste and Site Restoration. Tank Waste includes priority areas of current DOE tank waste and waste processing approaches, alternative DOE tank waste processing options, and tank management and closure. Site Restoration research concentrates in the areas of Soil and Groundwater with priority areas of attenuation-based remedies for the subsurface, deep vadose zone, remediation of mercury and industrial contaminants, and advanced simulation capability for environmental management; and, in the areas of Deactivation and Decommissioning, with priority areas of unique sensor networks for remote monitoring of entombed facilities and tanks, interactions between radiological and chemical contaminants of concern to DOE and facility materials, incombustible fixatives and decontamination agents, acceptability of DeconGel and various contaminant mixtures and robotics, remote systems with plug-and-play interchangeable components, and models for facility decommissioning. This paper gives an overview of the opportunities available to MSI students and universities and outlines the progress this program has made since its inception, and the path forward to further enhance efforts to create a pipeline into the DOE-EM workforce. (authors)

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Waste Retrieval and Inspection Operations in Hanford Tank 241-AY-102 - 18234

In August 2012, a periodic annulus inspection of tank 241-AY-102 (AY-102) identified a leak from the primary tank into the secondary containment. A pumping plan was developed in 2013 to provide a path forward for recommended remediation actions to be implemented as part of the AY-102 Recovery Project. On March 21, 2014, the Washington State Department of Ecology issued an Administrative Order requiring Washington River Protection Solutions and the United States Department of Energy to conduct actions related to and including the removal of waste from AY-102. The parties agreed to resolve the appeal of the Administrative Order through a Settlement Agreement which addressed the remaining requirements and implemented enforceable milestone dates, including completion of waste removal operations, and performance of an inspection aimed at determining the cause of the leak. The AY-102 Recovery Project was developed to address the Settlement Agreement requirements. While retrieval of waste from Single-Shell Tanks has been performed at Hanford for decades, retrieval from Double-Shell Tank AY-102 required adaptation of the existing technologies to a new environment on a larger scale than previously encountered. Despite countless challenges and obstacles encountered throughout, the project successfully completed system design, fabrication, installation, testing, and retrieval operations within a highly compressed, aggressive schedule. Waste removal activities in AY-102 completed in February 2017. Subsequent inspection activities were completed as part of a multi-step process aimed at determining the likely cause of failure and assessing the feasibility of repair. A variety of input data were used in evaluating the likely failure mechanism, such as video examinations that revealed numerous through-floor penetrations and significant degradation across the visible surface area. Based on the operational history of the tank, corrosion testing and analysis, and the visual appearance of the confirmed leak sites, service-induced pitting corrosion due to the historic waste composition and operating conditions appears to be the primary degradation mechanism leading to failure of the tank. The inspection data has demonstrated that repairing and returning AY-102 to service would likely introduce substantial technical, logistical, and financial challenges due to the extent of bottom-plate damage. As a result, tank AY-102 will ultimately be closed. (authors)

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