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Incorporating climate and regional setting into realistic-efficacious end states for contaminated sites - 15386

Data from former uranium milling and processing sites in the arid western United States (US) exemplify a conceptual model in which climate and geomorphology, and the associated geochemical and hydrological conditions, control the fate and transport of contaminants. In arid settings, shallow groundwater is transferred to the vadose zone and atmosphere via evaporation, transpiration and seepage. During these transfers, dissolved constituents accumulate in the vadose zone near the capillary fringe and around the roots of phreatophyte plants. In areas where the water table is shallow, minerals will also accumulate at the surface as a result of capillarity and evaporation. Two western-semiarid former milling sites, Tuba City AZ and Riverton WY, represent deep and shallow water table cases, respectively. At Tuba City, hydrological and geochemical factors limit the size of the groundwater plume and reduce the potential for contaminated water to crop at the locally significant Moenkopi Wash. At both sites, minerals that have formed in the groundwater and vadose zone in the near-field and mid-field areas will sustain elevated groundwater concentrations of anthropogenic contaminants, such as sulfate and uranium, for an extended time frame. The presence of secondary source mineral accumulations in the vadose zone in the mid-field area at Riverton is significant because episodic flooding occurs at this site. The contaminant distributions and plume dynamics observed at arid sites contrast with sites in the eastern US with stronger hydrologic driving forces and weaker evaporative processes. In both arid and non-arid settings, long term contaminant behaviors and concomitant exposure, risk and remediation time frames are controlled by regional conditions and climate and by local modifying factors. As a result, incorporating these conditions and factors into environmental management decisions provides new opportunities to develop more robust, sustainable and technically-defensible end states. (authors)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Addressing an aging facility: improving reliability of the defense waste processing facility at the Savannah River Site - 15539

The High Level Waste program at the Savannah River Site significantly reduces environmental risks associated with the storage of radioactive waste from legacy efforts to separate fissionable nuclear material from irradiated targets and fuels. The Defense Waste Processing Facility treats and immobilizes High Level Waste into a durable borosilicate glass for safe, permanent storage. Construction of the facility began in 1983 and radioactive operations commenced in 1996. In an effort to support the disposition of radioactive waste and accelerate tank closure for the balance of the Savannah River Site mission, the Defense Waste Processing Facility recently underwent an extensive reliability review in 2013 to understand future needs as well as to address aging infrastructure. As a product of this review, a Performance Improvement Plan was developed to systematically address three major focus areas including, a) asset preservation, b) facility housekeeping, and 3) process improvements. Since issuance of the plan, significant progress has been made in each of these areas to improve the reliability and predictability of the Defense Waste Processing Facility. Providing consistent, constructive, and concise communications is vital in the face of a changing budgetary environment. The Savannah River Site case study provides an example of the U.S. Department of Energy - Savannah River (DOE-SR) and SRR partnering to inform stakeholders about cleanup progress at the site. DOE-SR and SRR periodically and consistently provide both annual written progress reports under the Federal Facility Agreement and quarterly written progress reports under the landfill permit to the government regulators. Through the Liquid Waste System Plans, DOE-SR and SRR constructively and concisely summarize both the significant progress made and explain how a changed budget can impact the goals moving forward. Furthermore, DOE-SR and SRR informs the community and general public about the Site's progress and future during Citizens Advisory Board meetings. In addition, through the new proposed model for complex-wide communications, stakeholders can better understand how budget constraints will affect them. The set-aside program would also encourage stakeholder participation and involvement in helping each state and site obtain extra funding through performance evaluations. Waste management organizations can benefit in a number of ways from an effective partnership approach to communicate with stakeholders about available funding. Keeping an open and honest dialogue with regulatory agencies can help preserve confidence, thus mitigating or completely avoiding costly and distracting fines and penalties. Informing the public not only promotes trust, but also spurs the public to exercise its right to demand more information and voice any concerns to elected or DOE officials. With this approach, DOE can receive better understanding and cooperation from stakeholders in a changing budgetary landscape. Furthermore, a set-aside competitive program would encourage efficiency and innovation that could lead to further cost savings for the government while providing extra funding for cleanup efforts. (authors)

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Radioactive contamination from 1920-50's at an urban site of the New York City and interim remedial action - 15630

The former Wolff-Alport Chemical Company operated at the location in densely populated urban area in Queens, New York, between 1920 to about 1954. The company imported, stored on-site and processed monazite sand ores from the Belgium Congo. The extracted refined products enriched in rare-earth metals were sold on the commercial market. The process residues, rich in thorium and its progeny, were originally disposed of directly to the city sewer line and probably on-site also. The site's buildings are currently occupied by the auto shops, corner delicatessen store, light construction company, ice maker/distributor, and two residential apartments. Preliminary site investigations found multiple areas with elevated levels of direct gamma radiation with the maximum reported rates of 22 micro-sievert/hour (2.2 milli-rem/hour) at surface level and 40 micro-sievert/hour (4 milli-rem/hour) inside sewer manhole access. The thoron (Rn-220) gas air concentration in outdoor areas was reported reaching 13.5 kBq/m{sup 3} (366 pCi/L) and the radon (Rn-222) gas air concentrations was reported exceeding 148 Bq/ m{sup 3} (4 pCi/L) in some buildings. The dose assessments indicated that, under realistic scenarios, some members of the public were likely to receive the radiation exposure from this contamination in excess of the New York City and Nuclear Regulatory Commission general public radiation dose limit of 1 milli-sievert /yr (100 milli-rem/yr). The interim remedial action was planned and conducted by the U.S. Environmental Protection Agency (U.S. EPA) Region 2 in close cooperation with the New York City and New York State in 2012-13. The purpose of the action was to take necessary interim measures to reduce annual public dose below limit of 1 milli-sievert/yr (100 milli-rem/yr) and reduce radon gas concentration levels in impacted indoor spaces below U.S. EPA Action Level for residencies of 148 Bq/ m{sup 3} (4 pCi/L). In order to achieve these goals, the following actions were taken: detailed radiological and occupancy surveys; development of realistic exposure scenarios; dose assessments; installation of the fence and gates around the 'backyard' portion of the site; vegetation removal; development and detailed assessment of the radiation shielding options; application of the multilayer radiation shielding in some buildings, portions of the sidewalk and unpaved areas; mitigation of radon/thoron gas entry point; and installation of the radon mitigation system in one of the buildings. The preliminary post-action analyses indicated that the action goal would likely be achieved. The interim remedial action was conducted in a tight urban setting; it has significantly reduced public health risk from radiation without closure of businesses that continued operating within the site perimeter. (authors)

61 RADIATION PROTECTION AND DOSIMETRY↗

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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Survey and Remediation Project at the DOE Bannister Site - 16280

The Department of Energy Kansas City office has operated the Bannister site with a variety of contractors since the late 1940's. This facility has had a number of missions, some of which included using natural and depleted uranium. In order to prepare for the demolition of the site, ANTECH was contracted to perform radiometric surveys of the areas where these uranium operations took place. In the process of performing these surveys, areas with low levels of fixed radioactive contamination were identified; ANTECH then remediated these areas using a variety of techniques. In all areas surveyed, the only radioactive contaminant of interest was uranium and members of its decay chain. In no cases were other radionuclides found. The detection equipment used for the surveys included a Ludlum model 239- 1F Floor Monitor, a Ludlum 2360 Alpha Beta Data Logger Scaler/Ratemeter, and an ORTEC IDM-200-V High Purity Germanium Detector. The Ludlum instruments were used for bulk surveys and the ORTEC instrument was used to determine an accurate radioactive background spectra and subsequent spectra for areas where radioactive contamination was identified. Contamination was located on concrete floors and columns, cinder block walls, steel beams, inside ductwork and in floor drain piping. After these areas were identified, a number of methods were used to remove the contamination for disposal including scabbling, core drilling and wholesale removal. Extensive use of Pentek scabbling equipment on the concrete sections proved to be very effective at removing the contaminated layer. Upon completion, the waste materials were consolidated and packaged in a strong tight sea land container and shipped to the Energy Solutions waste facility in Utah. The completed work at the Bannister site serves as an example and demonstration of an effective and comprehensive decommissioning project. It involved the integration of a variety of decommissioning activities all executed and managed by a single contractor. These included radiometric measurement surveying using a variety of detection technologies to identify and locate uranium contamination, decontamination and removal of low level radioactive waste including some deconstruction activities and finally the management of low level radioactive waste including packaging, consignment and shipping of waste to a remediation site. The effective and efficient identification and removal of radioactive contamination at the Bannister site has contributed to the overall goal of returning the site to unrestricted use. (authors)

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Colonie FUSRAP Site - Radioactive Dust Sampling of Residential and Commercial Properties - 16384

The Colonie Formerly Utilized Sites Remedial Action Program (FUSRAP) Site is located in the Town of Colonie, Albany County, New York. The U.S. Army Corps of Engineers (USACE) is currently addressing environmental contamination associated with the Site. The area surrounding the Site consists of residential and commercial properties, known as vicinity properties (VPs). Cleanup activities have been completed on many of these VPs under the FUSRAP to address depleted uranium contamination. Soil remediation activities have been substantially completed at the Colonie FUSRAP Site and its VPs under the FUSRAP. Recent studies performed by an independent party and under FUSRAP identified uranium within indoor dust in residencies and businesses in the immediate vicinity of the Site. The studies were limited to non-living areas such as basement window sills, garages, and attics. This paper discusses the indoor dust sampling and analysis, in support of the Remedial Investigation (RI) for the VPs, and presents sampling results. The indoor dust sample media presented many technical challenges regarding sampling design, data reduction, and data interpretation. In addition, because the RI is focused on numerous resident-owned, rental, and commercial properties, challenges where presented regarding right-of-entry to sample. Isotopic uranium ratios observed in the majority of the samples are indicative of the depleted uranium contaminant, even at trace levels. While the sampling and analysis methods were effective at identifying depleted uranium in the majority of the samples, preliminary property-specific risk assessment results do not indicate the presence of depleted uranium in sufficient concentrations to pose unacceptable risk to VP inhabitants. (authors)

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Integrated Methodology for the Impact Assessment of an Uranium Mill Contaminated Site - 19031

This work describes the development of mathematical models for radionuclides distribution and transport in the environment. The applicability of the models involves an integrated approach to assess the quantitative dispersion of the radionuclides in different environmental compartments when released from uranium tailings or from other low-activity mining wastes storages. For every compartment the important pathways of contamination and the radionuclides of major concern are identified and selected, based on their chemical, physical, radiological and toxic properties. Each compartment represents an environmental media: air, soil, water, vegetation and biota. Depending on the characteristics of the sources different types of possible releases are evaluated using phenomenological models. Models of environmental release, dispersion, transport and fate within each environmental compartment, as well as models of transfer between them, are applied to a specific site. The model outputs are the radionuclides activities for each one of the environmental compartments, where relevant exposure end-points are previously identified. The methodology was applied to a specific Uranium Mill Site, referred here as the 'Mill'. The site comprises approximately 3.2 km and includes two inactive mills, former ore stockpiles areas, a partially reclaimed tailings pond disposal area and a current tailings pond disposal area. The Mill site began operations in the late 1950's extracting uranium ore by alkaline leaching. Later on, a new facility using acid leaching for extracting uranium begun to operate in 1980. The mill operated first continuously and after intermittently until its closure, in March 2006. The data required for the model input was acquired from different sources: direct measurements from this particular site and available from multiple site investigation reports (in particular, environmental data for groundwater, soil, surface water, sediments and biota); other, were selected from published data. For the unknown data, assumptions were made. (authors)

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Pilot Test Remediation of a Fractured Bedrock Aquifer at the Maywood Superfund Site, Maywood, New Jersey - 19217

The U.S. Army Corps of Engineers (USACE) and Cabrera Services are conducting a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) Pilot Test treatment of a fractured bedrock aquifer at the Formerly Utilized Sites Remedial Action Program (FUSRAP) Maywood Superfund Site (FMSS) located in Maywood, New Jersey (NJ), USA. The Maywood Chemical Company Superfund Site in Bergen County, NJ is listed on the United States Environmental Protection Agency (USEPA) Superfund National Priorities List (NPL). The National Superfund Comprehensive Environmental Response, Compensation, and Liability Information System (CERCLIS) identification number is NJD980529762. The Maywood Chemical Company Superfund Site (hereafter referred to as the FMSS) consists of 92 designated properties in the communities of Maywood, Lodi and Rochelle Park, NJ. These are collectively known as FMSS 'Vicinity Properties' and include property owned by the federal government (the Maywood Interim Storage Site, or MISS); the Stepan Company (former location of the Maywood Chemical Works, or MCW); 62 residential properties; three properties owned by the state or federal government; four municipal properties; and 21 commercial properties. The Stepan Company property includes contaminated buildings and three remediated U.S. Nuclear Regulatory Commission (NRC) licensed burial pits; the MISS also includes a contaminated building. Contamination on the FMSS is being addressed under three separate actions coordinated by the lead regulator USEPA Region 2. The USACE is addressing thorium (Th) and other wastes at the site defined as 'FUSRAP waste' in the Soils and Buildings and Groundwater Records of Decision (ROD) for the FMSS. Stepan Company is addressing other chemical wastes (non-FUSRAP waste) at the FMSS. The Groundwater ROD [1] was signed into agreement by USACE Division Commander in June 2012 and USEPA Region 2 Administrator in July 2012 and presents the selected remedial actions for Operable Unit (OU) 2 groundwater at the MISS and adjacent properties. The selected remedial action is removal of non-radiologically contaminated soils on the MISS containing arsenic, lithium, and benzene with concentrations above cleanup levels, and monitored natural attenuation (MNA) of arsenic, lithium, and benzene in groundwater. In situ treatment of arsenic in the overburden aquifer using oxidation reduction (redox) alteration will also be performed if needed to meet the groundwater cleanup levels after the source soil is removed. The need for in situ treatment will be determined during the Groundwater ROD review at least three to four years after the contaminated source soil removal is completed. The third action addressing non-FUSRAP chemical wastes will be the responsibility of the Stepan Company as a primary responsible party in this action. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Panel Session 11: Featured Country Canada - Remediation of Contaminated Sites

Canada has several unique sites requiring environmental remediation of radiological contaminants. This panel was designed to outline the remediation of contaminated sites across Canada from several perspectives. Remote legacy uranium mining operations, small scale residential locations, and large impacted soil sites all pose different challenges, however there are some common solutions and keys to success. This panel addressed several of those challenges and provided lessons learned on how to successfully plan and execute large scale environmental remediation in both remote and residential locations. This panel focused on the cleaning up several contaminated sites in Canada and monitoring the long-term performance of sites that have already been remediated. Panelists addressed the technical and social challenges associated with various cleanup initiatives North of the 49. Parallel and the solutions that have been adopted to enable these projects to move forward. The panel offered the perspectives of owners, contractors and regulators on current projects and how they are leveraging past experience and learning from others to ensure future undertakings are successful. Presentations proposed include: 1 - Regulating Environmental Remediation in Canada (Michael Rinker, Canadian Nuclear Safety Commission (Canada)); 2 - Integration of Local Knowledge and Engagement/Capacity Building Legacy Uranium Mine Sites (Joe Muldoon, Saskatchewan Research Council (Canada)); 3 - The Path to Institutional Control - Safe, Secure and Stable (R. Liam Mooney, Cameco Corporation (Canada)); 4 - Port Hope Area Initiative: Project Challenges (Scott Parnell, Canadian Nuclear Laboratories (Canada))

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Panel Session 31: US DOE Featured Site: 30 Years of Environmental Management at the Idaho National Laboratory (1/5)

This panel highlighted the cleanup challenges and successes at the Idaho site, including the landmark Idaho Settlement Agreement, effective collaborative regulatory strategies, worker involvement, stakeholder involvement, and looking ahead. 2019 marks 30 years since the start of the DOE-EM mission at the Idaho National Laboratory Site. This panel focused on the cleanup successes and challenges at the Idaho National Laboratory (INL) Site (Idaho, USA) over the last 30 years. The INL was added to the National Priorities List of Superfund Sites in 1989. Since that listing, the INL has been focused on meeting the cleanup milestones outlined in the Site Treatment Plan, 1991 Federal Facility Agreement and Consent Order, 1995 Idaho Settlement Agreement, and other agreements between the Department of Energy (DOE) and State of Idaho. Presentation proposed: 30 Years of Cleanup at Idaho National Laboratory Site (Nolan Jensen, US DOE - Idaho Operations Office - Idaho Cleanup Project (USA), Kliss McNeel, Fluor Idaho (USA), Mark Clough, Idaho Department of Environmental Quality (USA), Darrell Early, Office of the Idaho Attorney General (USA), Rebecca Casper, City of Idaho Falls (USA))

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Pilot Test Remediation of a Fractured Bedrock Aquifer at the Maywood Superfund Site, Maywood, New Jersey - 20073

The U.S. Army Corps of Engineers (USACE) and Cabrera Services are conducting a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) Pilot Test treatment of a fractured bedrock aquifer at the Formerly Utilized Sites Remedial Action Program (FUSRAP) Maywood Superfund Site (FMSS) located in Maywood, New Jersey (NJ), USA. The Maywood Chemical Company Superfund Site in Bergen County, NJ is listed on the United States Environmental Protection Agency (USEPA) Superfund National Priorities List (NPL). The National Superfund Comprehensive Environmental Response, Compensation, and Liability Information System (CERCLIS) identification number is NJD980529762. The Maywood Chemical Company Superfund Site (hereafter referred to as the FMSS) consists of 92 designated properties in the communities of Maywood, Lodi and Rochelle Park, NJ. These are collectively known as FMSS 'Vicinity Properties' and include property owned by the federal government (the Maywood Interim Storage Site, or MISS); the Stepan Company (former location of the Maywood Chemical Works, or MCW); 62 residential properties; three properties owned by the state or federal government; four municipal properties; and 21 commercial properties. The Stepan Company property includes contaminated buildings and three remediated U.S. Nuclear Regulatory Commission (NRC) licensed burial pits; the MISS also includes a contaminated building. Contamination on the FMSS is being addressed under three separate actions coordinated by the lead regulator USEPA Region 2. The USACE is addressing thorium (Th) and other wastes at the site defined as 'FUSRAP waste' in the Soils and Buildings and Groundwater Records of Decision (ROD) for the FMSS. Stepan Company is addressing other chemical wastes (non-FUSRAP waste) at the FMSS. The Groundwater ROD [1] was signed into agreement by USACE Division Commander in June 2012 and USEPA Region 2 Administrator in July 2012 and presents the selected remedial actions for Operable Unit (OU) 2 groundwater at the MISS and adjacent properties. The selected remedial action is removal of non-radiologically contaminated soils on the MISS containing arsenic, lithium, and benzene with concentrations above cleanup levels, and monitored natural attenuation (MNA) of arsenic, lithium, and benzene in groundwater. In situ treatment of arsenic in the overburden aquifer using oxidation reduction (redox) alteration will also be performed if needed to meet the groundwater cleanup levels after the source soil is removed. The need for in situ treatment will be determined during the Groundwater ROD review at least three to four years after the contaminated source soil removal is completed. The third action addressing non-FUSRAP chemical wastes will be the responsibility of the Stepan Company as a primary responsible party in this action. (authors)

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Panel Session 34: US DOE Featured Site: Savannah River Operations Office: 70 Years of Service

The Savannah River Site celebrates its 70. anniversary on November 28, 2020. On this date in 1950, President Harry S. Truman requested the Dupont Company to design, build and operate what was then known as the Savannah River Plant in response to the Soviet Union's detonation of its first atomic weapon, which set the Cold War into motion. During the 1950's, six South Carolina towns were relocated for the construction of SRS and by 1953, the 310 square mile site was complete. Nearly 40,000 workers were employed t build five nuclear reactors and support facilities, two chemical separations plants, heavy water extraction plant, nuclear fuel and target fabrication facility tritium extraction facility and waste management facilities. SRS played a key role in winning the Cold War and for seven decades, SRS has been a leader within the DOE complex. Today, the site supports environmental stewardship and maintains the nation's nuclear deterrent while ensuring the safekeeping and disposal of domestic and international nuclear materials. The site continues to support the nation's nuclear defense as it explores new potential NNSA missions. SRS has a proud 70- year history and looks forward to a future of service as a national asset and strong community partner. The session was kicked off with a video message from Secretary of Energy, Dan Brouillette, who thanked employees past and current for their efforts. The video also provided an overview of the history and future of the Site. This panel provided an overview of the Savannah River Site's 70 years of service (history, challenges, opportunities, and future) presented by the SRS's Senior leadership and the local Aiken, South Carolina Mayor. Panelists with presentations: US DOE Secretary Dan Brouillette's Overview of DOE and SRS - A Legacy of 70 Years of Service (Amy Boyette); 70 Years of Service (Michael Budney); 70 Years of Service (Stuart MacVean); SRS Liquid Waste (Thomas Foster); National Nuclear Security Administration (Nicole Nelson-Jean)

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The Port Hope Areas Initiative's Port Granby Project: The Decontamination of Site Equipment from a Low Level Waste Facility - 20330

The Port Hope Area Initiative (PHAI) is the Government of Canada's response to the community recommended solutions for the remediation and safe, long-term management of historic low-level radioactive waste (LLRW) that was the result of uranium and radium processing operations in the Municipality of Port Hope, Ontario from the 1930's to the 1980's. The Eldorado refinery, on the shores of Lake Ontario, began refining radium-226 from pitchblende ore, later transitioning to the refining of uranium ore. Process residues were deposited at the Welcome Waste Management Facility in Port Hope until the mid-1950's switching to the Port Granby Waste Management Facility (PGWMF), which continued to accept waste until the late 1980's. The Port Granby Project involves the construction of a new, secure long-term waste management facility (LTWMF) and supporting infrastructure, and the excavation and relocation of approximately 1,200,000 m{sup 3} of historic low-level radioactive waste and marginally contaminated soil from the PGWMF to the newly constructed LTWMF. Since the project's inception in 2016, the bulk of the material has since been moved to the final long term storage cell. This has taken over 500,000 person-hours and a large amount of one site heavy equipment to accomplish including excavators, bulldozers, rock trucks, baker tanks and vacuum trucks. While many of the pieces of heavy equipment and water management equipment has further work to do on site, several of the sites larger items have already undergone the decontamination process prior to release from the site. This process has posed a serious challenge as the waste has a caustic nature to it and over the last few years it has had time to work its way into the metallic structures and framework of the equipment. Coupled with the tight work spaces and in some cases confined work areas there have been many issues that needed to be addressed to successfully reach a state where items can be free released to the unrestricted limits of the sites license. This ongoing process has led to a more refined decontamination program at the Port Granby Facility and has had a rather high success rate considering the length of time the equipment has been exposed to the waste materials on site. This paper discusses the varied challenges of decontamination faced at a low-level radioactive waste facility with a focus on the following aspects: - Challenges faced regarding different equipment types and the solutions implemented by Wood to address these challenges; - An examination of various decontamination methods employed throughout the project; and - Lessons learned over three years of remediation work and how they impact the decontamination process. (authors)

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Updates to a Preliminary Probabilistic Performance Assessment Model for Radiological and Chemical Contamination at the West Valley Site, New York - 20420

The New York State Energy Research and Development Authority (NYSERDA) is the owner of the Western New York Nuclear Service Center (WNYNSC), a 1,351-ha site located approximately 48 km south of Buffalo, New York. In 1962, Nuclear Fuel Services, Inc. (NFS) entered into agreements with the Atomic Energy Commission and New York State to construct the first commercial reprocessing plant of nuclear fuel in the United States at the WNYNSC. NFS built and operated the spent fuel reprocessing plant and waste disposal facilities, processing 640 Mg (640 metric tons) of spent nuclear fuel from 1966 to 1972 under an Atomic Energy Commission license. Nuclear fuel reprocessing operations halted in 1972 and never restarted, leaving behind radioactive and chemical wastes. The U.S. Department of Energy (DOE) was required to complete certain waste management activities under the West Valley Demonstration Project (WVDP) Act of 1980 including decommissioning of WVDP facilities. As collaborating agencies, NYSERDA and the DOE are tasked with making decisions about decommissioning and risk reduction for the West Valley Site. Neptune and Company, Inc. (Neptune) was contracted to develop a probabilistic performance assessment (PPA) model to assist the agencies in their decision making process for decommissioning the WVDP and WNYNSC. One important tool that is needed in order to inform the decision-making process is a science-based model of the West Valley Site that evaluates potential future consequences for human health and the environment. This forms the core of the spatial domain of the West Valley PPA Model. The PPA Model, developed using the GoldSim system modeling software, is a tool intended to provide support for decision making that evaluates uncertainty, in a manner that is transparent, defensible, and robust. The PPA Model includes contaminant transport and health effects components, and is organized around geographically-grouped contaminated facilities. These include the waste disposal areas licensed by the U.S. Nuclear Regulatory Commission and the State of New York, a waste tank farm for storage of high level radioactive waste resulting from reprocessing operations, and several areas contaminated with radioactive and chemical constituents. The PPA Model evaluates contaminant transport from these sources to points of exposure across the site and into receiving surface waters and sediments. Hypothetical people and wildlife could be exposed to contamination at these locations, and the effects of these exposures are evaluated. Contaminant transport processes to be evaluated in the PPA Model include groundwater and surface water transport, contaminant translocation by plants and animals, diffusion, and erosion. The evaluation of exposures to people in this preliminary model is limited to a resident farmer scenario, and ecological assessment is performed at the level of a screening analysis. The results of these preliminary evaluations inform future model developments. PPA Model results are subjected to sensitivity analysis in order to determine those pathways and parameters that are most significant in influencing the results. This information allows analysts and decision makers to focus on those aspects of Site behavior and processes. With this information, the decision makers can drive informed, defensible decisions regarding decommissioning of the Site. This paper includes an update of the information presented at WM2019 [1]. (authors)

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Covalent Organic Framework (COF) Derived Ni–N–C Catalysts for Electrochemical CO 2 Reduction: Unraveling Fundamental Kinetic and Structural Parameters of the Active Sites

Electrochemical CO 2 reduction is a potential approach to convert CO 2 into valuable chemicals using electricity as feedstock. Abundant and affordable catalyst materials are needed to upscale this process in a sustainable manner. Nickel-nitrogen-doped carbon (Ni-N-C) is an efficient catalyst for CO 2 reduction to CO, and the single-site Ni-N x motif is believed to be the active site. However, critical metrics for its catalytic activity, such as active site density and intrinsic turnover frequency, so far lack systematic discussion. In this work, we prepared a set of covalent organic framework (COF)-derived Ni-N-C catalysts, for which the Ni-N x content could be adjusted by the pyrolysis temperature. The combination of high-angle annular dark-field scanning transmission electron microscopy and extended X-ray absorption fine structure evidenced the presence of Ni single-sites, and quantitative X-ray photoemission addressed the relation between active site density and turnover frequency.

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗

Atomically Dispersed CuN x Sites from Thermal Activation of Boron Imidazolate Cages for Electrocatalytic Methane Generation

Atomically dispersed metal sites (ADMSs) have been recognized as promising candidates for electrochemical conversion. Among a diverse range of molecular precursors for ADMS synthesis, framework materials are particularly interesting due to their high degree of tunability and control over the primary coordination sphere of the metal ions. In this work, we demonstrate that a copper boron imidazolate cage, BIF-29(Cu), is a convenient precursor for a competent catalyst with isolated Cu sites coordinated by N donors for carbon dioxide electroreduction (CO 2 RR). Although BIF-29(Cu) exhibited moderate methane selectivity over hydrogen evolution reaction (HER), the methane selectivity is significantly enhanced by 2 times (55% CH 4 at –1.25 V vs RHE) after mild thermal activation. Extensive characterization methods indicate the transformation of crystalline BIF-29(Cu) into an amorphous carbonaceous material comprising isolated CuN x sites. Moreover, in situ X-ray absorbance spectroscopy indicates stable CuN x sites that are reduced during CO 2 RR. This work encourages the discovery of single-site electrocatalytic systems through a rational selection of molecular precursor and calcination parameters for promoting product selectivity.

10 SYNTHETIC FUELS↗

Annual Site Environmental Report: 2010 (ASER)

This report provides information about environmental programs during the calendar year of 2010 at the SLAC National Accelerator Laboratory (SLAC), Menlo Park, California. Activities that overlap the calendar year - i.e., stormwater monitoring covering the winter season of 2010/2011 (October 2010 through May 2011) are also included. SLAC is a federally-funded research and development center with Stanford University as the M&O contractor. Under Executive Order (EO) 13423, Strengthening Federal Environmental, Energy, and Transportation Management, EO 13514, Federal Leadership in Environmental, Energy, and Economic Performance, and DOE Order 450.1A, Environmental Protection Program, SLAC effectively implements and integrates the key elements of an Environmental Management System (EMS) to achieve the site's integrated safety and environmental management system goals. For normal daily activities, SLAC managers and supervisors are responsible for ensuring that policies and procedures are understood and followed so that: (1) Worker safety and health are protected; (2) The environment is protected; and (3) Compliance is ensured. Throughout 2010, SLAC continued to improve its management systems. These systems provided a structured framework for SLAC to implement 'greening of the government' initiatives such as EO 13423, EO 13514, and DOE Orders 450.1A and 430.2B. Overall, management systems at SLAC are effective, supporting compliance with all relevant statutory and regulatory requirements. During 2010, there were no reportable releases to the environment from SLAC operations. In addition, many improvements in waste minimization, recycling, stormwater management, groundwater restoration, and SLAC's chemical management system (CMS) were continued. The following are among SLAC's environmental accomplishments for 2010. To facilitate management and identification of future potential greenhouse gases (GHG) reduction opportunities, SLAC voluntarily completed GHG inventories for calendar year (CY) 2008 and CY 2009 and submitted the results to The Climate Registry. A Lead Management Plan was completed to reduce the potential of lead impacting the environment, and two large legacy tube-trailer modules, each containing 38 tubes of compressed ethane, were reused or recycled by an outside contractor, resulting in hazardous waste avoidance and cost savings of approximately $100,000 in transportation and disposal costs. SLAC continues to make progress on achieving the sustainability goals of EOs 13423 and 13514, which include, but are not limited to reductions in the use of water, energy, and fuel, building to green standards and reductions in GHG emissions. Phase I of the SLAC Advanced Metering project for electrical and natural gas systems was completed. Phase I included the design of the metering system and purchase of the enterprise software. The planning, design, and installation of an advanced water metering system for select buildings, landscape, and process systems were completed. In addition, the last major onsite chiller containing a Class I ozone-depleting substance was taken out of service, and SLAC continued to replace conventional vehicles with electric vehicles. In 2010, there were no radiological impacts to the public or the environment from SLAC operations. The potential doses to the public were negligible and far below the regulatory and SLAC administrative limits. No radiological incidents occurred that increased radiation levels to the public or released radioactivity to the environment. In addition to managing its radioactive wastes safely and responsibly, SLAC worked to reduce the amount of waste generated. SLAC shipped 2,891 cubic feet of low-level radioactive waste, half of which was legacy waste, to appropriate treatment and disposal facilities for low-level radioactive waste. SLAC also continued its efforts to reduce the inventory of materials no longer needed for its mission by permanently removing 125 sealed radioactive sources from the inventory. Ninety-seven of the sealed sources were returned to the manufacturer, and 28 were sent to Energy Solutions for processing before being sent to the Nevada Test Site for burial. In addition, 87 concrete blocks which had been stored in an area known as the Bone Yard were surveyed for potential surface contamination and volumetric activation prior to off-site release. Based on the comprehensive measurements, all 87 blocks were qualified for release and were disposed of as ordinary materials at a landfill. In 2010, the SLAC Environmental Restoration Program personnel continued work on site characterization and evaluation of remedial alternatives at four sites with volatile organic compounds in groundwater and several areas with polychlorinated biphenyls and low concentrations of lead in soil.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Process for Transition of Uranium Mill Tailings Radiation Control Act Title II Disposal Sites to the U.S. Department of Energy Office of Legacy Management for Long-Term Surveillance and Maintenance

This document presents guidance for implementing the process that the U.S. Department of Energy (DOE) Office of Legacy Management (LM) will use for assuming perpetual responsibility for a closed uranium mill tailings site. The transition process specifically addresses sites regulated under Title II of the Uranium Mill Tailings Radiation Control Act (UMTRCA) but is applicable in principle to the transition of sites under other regulatory structures, such as the Formerly Utilized Sites Remedial Action Program.

and Guidance↗