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DOE OSTI2019

Panel Session 12: Featured Country Canada - Engaging the Public and Indigenous Groups in Canadian Waste and D and D Projects

This panel will share insights from those directly involved in the dialogue among members of the Canadian public, elected officials of host communities, indigenous groups, project proponents, and the Canadian regulator. History has shown time and again that the early and meaningful engagement of stakeholders must go hand-in-hand with technical solutions in order to assure the successful start and finish of waste management and decommissioning projects. In this panel discussion, the requirements for consultation and communication, the tools and strategies used, the results of efforts to date, and plans will be addressed by those at the center of some of Canada's biggest and most controversial radioactive waste projects. Presentations proposed include: 1 - Engaging the Public and Indigenous Groups in Canadian Waste and D and D Projects (Candida Cianci, Canadian Nuclear Safety Commission (Canada)); 2 - Indigenous Engagement (Bob Watts, Nuclear Waste Management Organization (Canada)); 3 - Engaging the Public and Indigenous Groups Related to Canadian Waste and D and D Projects (Patrick Quinn, Canadian Nuclear Laboratories (Canada)); 4 - Engaging the Public and Indigenous Groups in Canadian Waste and D and D Projects Canadian Association of Nuclear Host Communities Point of View (Blair Skinner, Local Government District of Pinawa, Manitoba (Canada))

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DOE OSTI2019

Panel Session 37: Featured Country Canada - Whiteshell Laboratories Decommissioning Successes and Challenges (4/5)

This panel focused on the decommissioning of the AECL Whiteshell Laboratories in Pinawa, Manitoba. The discussion presented successes as well as remaining challenges, including the proposed in-situ disposal of the organic-coated nuclear reactor shell. The panel included representatives from the Owner, the operator, the Canadian regulator, the local municipality and a representative of the indigenous community in the area. Presentations proposed include: 1 - Whiteshell Laboratories - Decommissioning Successes and Challenges (Craig Michaluk, Atomic Energy of Canada Limited (Canada)); 2 - Whiteshell Laboratories Decommissioning: Successes and Challenges (Kavita Murthy, Canadian Nuclear Safety Commission (Canada)); 3 - Successes and Challenges of the Whiteshell Laboratories Closure Project (Brian Wilcox, Canadian Nuclear Laboratories (Canada)); 4 - Whiteshell Laboratories Decommissioning Successes and Challenges - Community Point of View (Blair Skinner, Local Government District of Pinawa, Manitoba (Canada))

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DOE OSTI2019

Panel Session 68: Small Business Procurement and Contracting Opportunities Within the DOE Complex and USACE FUSRAP Program

This panel session was held in the Panel Zone in the Exhibit Hall and focused on small business procurement and contracting opportunities within the DOE Complex as well as the US Army Corps of Engineers (USACE) National Formerly Utilized Sites Remedial Action Program (FUSRAP) projects. Each panelist provided a general overview of their respective organization, small business goals and the success in meeting those goals. They further discussed recently awarded procurement, upcoming opportunities and provided additional contact information for individual small business program managers within their organization. This panel was open to all WM participants, including Exhibitors. This panel session focused on small business procurement and contracting opportunities within the DOE Complex and the USACE FUSRAP Program. The DOE and USACE contract directly with small businesses and encourage prime contractors to obtain goods and services from small and disadvantaged businesses (Tier 2) and often tie these goals to contract award fee. Goods and services being considered for these procurements include decontamination and decommissioning, remediation, transportation and disposal of radioactive waste, health physics, emergency response planning and training, lab services, R and D products, waste treatment, maintenance, A/E and professional consulting. This panel complemented Session 21 and Session 48, US DOE Spring Quarterly Forum, and Session 88 on Doing Business with the DOE. Presentations proposed include: 1 - Small Business Procurement and Contracting Opportunities Within the DOE Complex (Aaron Deckard, US DOE (USA)); 2 - Small Business Procurement and Contracting Opportunities Within the DOE Complex (William Badger, AECOM (USA)); 3 - Engineering the Extraordinary (Lisa Tribuce-Leoung Tat, Bechtel National, Inc. (USA)); 4 - Fluor Small Business Procurement and Contracting Opportunities (Debra Sampson, Fluor Government Group (USA)); 5 - HII Technical Solutions Division Small Business Opportunities (Kela Lofton, HII Nuclear Inc. (USA)); 6 - U. S. Army Corps of Engineers Radiological Remediation Work (Nicki Fatherly, USACE (USA))

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DOE OSTI2019

Panel Session 75: US NRC - Current and Emerging US NRC Regulatory Topics

The panel addressed several current and emerging NRC regulatory issues impacting the radioactive waste arena. The panelists provided different perspectives on several key issues such as the revision of 10 CFR Part 61, scoping study on very low-level waste and consolidated interim storage of spent nuclear fuel among other timely regulatory topics. Co-Chairs, John Tappert and Larry Camper, introduced the session panel members and provided a summary of the purpose of the session. The panel focused on several current and emerging US NRC regulatory issues impacting the radioactive waste arena and stakeholders. The panelists provided different perspectives on several key regulatory issues such as: the revision of 10CFR Part 61, the Greater-than-Class C (GTCC) and Transuranic (TRU) waste disposal, coping with studies on very low-level waste and waste classification system, as well as other timely regulatory topics. Presentations proposed include: 1 - Overview of NRC Low-Level Radioactive Waste Activities and Initiatives (Christepher McKenney, US NRC (USA)); 2 - Is the Grass Really Greener? Canadian Regulatory Perspective (Karine Glenn, Canadian Nuclear Safety Commission (Canada)); 3 - EPRI Perspectives on 10CFR61 Revision (Lisa Edwards, EPRI (USA)); 4 - State of Nuclear Industry and Radwaste Management (Janet Schlueter, Nuclear Energy Institute (USA)); 5 - Concrete Steps the U.S. NRC Can Take to Improve LLW Disposal (Tom Magette, Talisman International (USA))

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DOE OSTI2019

Panel Session 94: Nuclear and Industrial Robotics, Remote Systems and Emerging Technologies

This panel focused on the use and benefits of robotics in different nuclear environments. Examples of robotics deployed in nuclear environments that come from industry, academia, and the government were presented. It is through these varying perspectives that the panel participants will show the breath of nuclear robotics used across the world. Presentations proposed include: 1 - Robotics and Emerging Technologies at Assystem (Fanny Fouin, Assystem Energy and Infrastructure (United Kingdom)); 2 - An Undergraduate Perspective (Michael DiBono, Applied Research Center - FIU (USA)); 3 - US-ROK International Collaboration on Robotics and Remote Systems for D and D of NPPs (Young Soo Park, Argonne National Laboratory (USA)); 4 - EM's Historical Engagement with Robotics and Universities (Genia McKinley, US DOE (USA)); 5 - Robotic Systems for Environmental Remediation Applications (Leonel Lagos, Applied Research Center - FIU (USA)); 6 - Remote and Nuclear Challenges and Solutions at the Savannah River Site - SRS (Jean Plummer, Savannah River National Laboratory (USA)); 7 - Nuclear and Industrial Robotics, Remote Systems and Emerging Technologies Challenges, Opportunities and Prognostications (Kim 'KD' Auclair, KD Auclair and Associates LLC (USA))

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DOE OSTI2019

Panel Session 110: Collaboration Across Borders to Deliver Cleanup and Decommissioning Challenges

This panel session engaged panelists from multiple countries on the issues with the implementation of in situ decommissioning/disposal and how to communicate more effectively with stakeholders. Presentations proposed include: 1 - Collaboration Across Borders to Deliver Cleanup and Decommissioning Challenges (Laurie Judd, Longenecker and Associates (USA)); 2 - Collaboration Across Borders to Deliver Cleanup and Decommissioning Challenges (Kavita Murthy, Canadian Nuclear Safety Commission (Canada))

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DOE OSTI2019

In Situ Cold-Spray Repair of Environmental Mission Infrastructure for Component Life Extension - 19424

Cold spray offers a potential option for performing in situ repair of U.S. Department of Energy (DOE) complex infrastructure critical to the Office of Environmental Management cleanup mission. Application to the DOE complex has the potential to reduce cost, schedule, and safety risk impacts associated with component failures and would negate the need to procure and construct replacement infrastructure. A concept and technical basis are presented for developing remotely deployable cold-spray systems for performing in situ repairs in hazardous environments such as nuclear waste tanks, piping, and process vessels to extend component service life or return critical infrastructure to service. (authors)

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DOE OSTI2019

Design, Construction, and Commissioning of the RH LLW Disposal Facility at INL - 19445

The newly-commissioned Remote-Handled Low-Level Waste (RH LLW) Disposal Facility at Idaho National Laboratory (INL) provides permanent disposal capability critical for continuing INL nuclear research and Naval Reactors missions at the Idaho site. The facility mission need [critical decision (CD)- 0] was approved in 2009. Alternative selection (CD-1) was finalized in 2011. The project performance baseline (CD-2/3) was approved and design was initiated in 2014 and construction began in 2015. Construction was completed and transitioned to Materials and Fuels Complex (MFC) Operations in 2017. The facility successfully achieved readiness with authorization to begin operations (CD-4) in 2018. The $77 M line-item capital-acquisition project was completed six months ahead of the congressional commitment date and significantly under budget. This paper presents highlights of the RH LLW Disposal Facility project delivery and a summary of facility features and critical characteristics. Highlights include: - As a hazard category II nuclear facility, the project complied with United States Department of Energy (DOE) requirements for incorporation of nuclear safety into facility design and construction as identified in DOE-STD-1189 as well as 10 CFR 835 Subpart K requirements for incorporation of ALARA principles in facility design. - From an environmental compliance perspective, the facility was subject to National Environmental Policy Act requirements resulting in a Finding of No Significant Impact as determined by an Environmental Assessment. An operating disposal authorization statement from the Low-Level Waste Disposal Facility Federal Review Group (LFRG) authorizing waste disposal operations in accordance with DOE Order 435.1 was obtained. - The project was delivered using a design-build delivery method with a firm-fixed price with incentive fee contracting mechanism. The project was executed as a line-item capital-acquisition project, in full compliance with DOE Order 413.3B under INL's certified Earned Value Management System (EVMS) program. - The facility supports twenty years of waste disposal operations with five disposal vault configurations in four vault arrays supporting six different cask/canister system configurations. Three of the six cask/canister systems currently exist and three will be developed to support future operations. There are a total of 446 waste disposal vaults that will accommodate disposal of a total of 939 stainless steel radioactive waste canisters. The facility is designed to accommodate canisters with contact radiation dose rates as high as 600 Sievert/hour (60,000 Rem/hour). - The facility underwent a rigorous readiness review process in accordance with DOE Order 425.1D. Readiness activities included rigorous facility testing and shakedown activities, a management-self assessment, a contractor operational readiness review, and a DOE operational readiness review. Readiness was demonstrated for an existing cask/canister system (the MFC HFEF-5 cask). Separate readiness activities will be conducted for each cask/canister system as they are brought online for facility operations. INL's successful delivery of the project has provided waste disposal capability to ensure long-term viability of planned and current facilities and missions associated with both INL and the Naval Reactors Facility. Successful execution of the project has proven to be strategically important to future capital investments in capabilities necessary to advance INL's mission. (authors)

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DOE OSTI2019

Management of Documents and Information on Radioactive Waste - 19455

The assurance of the safety of a repository for low- and intermediate-level radioactive waste, during the 300 years of institutional control after closure, depends on assuming that the responsible institution will be capable to control the documents with information regarding the facility, the disposed of waste and the established measures for counteracting events that could breach the isolation of the radioactive material. Management of documents or information does not represent a major challenge in itself in view of consolidated practices and international standards, such as ISO 15489. However, considering the time scale involved in the disposal of the radioactive wastes, efforts should be made to ensure the preservation and proper access to documents and information. In this matter, the technological aspect of document production can be a complicating factor. In fact, it is common to be unable to access electronic documents produced 20 or 30 years ago, due either to problems related to the media where the information is stored, or to a lack of compatible systems for reading the files. This is just one example of complication when thinking about production, organization, representation, preservation and retrieval of recorded information that is to last for centuries. In this way, this work seeks to present the situation of the management of documents and information on radioactive waste in the scope of the Institute of Energy and Nuclear Research (IPEN) and with national regulation in Brazil. (authors)

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DOE OSTI2019

Analysis of Radiation Damage in Electronics of Unmanned Aerial and Ground Robotic Platforms - 19470

Gamma ray measurements are important for monitoring of nuclear facilities. Robotic platforms are used to carry radiation detectors and cameras to enable remote sensing and visual surveillance, allowing for the operation in hazardous, hard to reach zones. The prediction of radiation damage in electronic components of robots is vital. The radiation damage analysis was carried out for two robotic platforms exposed to neutron and gamma ray flux: a ground hexapod platform PhantomX (a 'spider robot') and an aerial platform - the DJI S1000+ octocopter. The FLUKA code was used to analyze the displacement per atom values in electronic components of these robots. The packaging of the components and the shielding design was determined to increase the robot's lifetime in areas where radiation dose levels are high. (authors)

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DOE OSTI2019

Collaborative Robots vs. Master/Slaves - 19522

This paper will discuss the feasibility, application, and economy of applying collaborative robots (co-bots) in lieu of traditional through-the-wall tele-operated manipulator systems, traditionally used within hazardous (radioactive) environments. Both fixed facility and mobile applications will be discussed. Both single- and dual-armed co-bot systems will be employed. The six-axis, plus gripper, single-armed co-bots will provide for machine vision enhanced pick-n-place applications within shielded rooms and also include force-reflecting (haptic) teleoperations controls for non-routine materials-handling operations. The dual-armed system will be mounted to a motorized stand with motorized adjustment both vertically and rotationally (around its base). To complement these co-bots, both two-dimensional and three-dimensional vision technologies will be implemented. The vision technologies, in these applications, are used in lieu of traditional radiation shielding windows. two-dimensional video systems will provide for large area viewing, incorporating pan, tilt, and zoom capabilities. Three-dimensional video systems will be mounted to the dual-armed robot stand and provide viewing, including depth-of-perception, to the operator, performing material handling and other tasks, from an operator workstation located outside the hazardous environment. The unique workstation used with the dual-armed systems will also be described. (authors)

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DOE OSTI2019

Derivation of Monitoring Parameters based on the Long-term Safety Assessment - 19529

This paper discusses monitoring in the context of the Swiss geological disposal programme and presents a methodology to identify parameters that would be both useful from the point of view of demonstrating long-term safety and technically feasible to monitor. The methodology also serves as a contribution to the EC project on Development and Demonstration of monitoring strategies and technologies for geological disposal - Modern2020. The methodology consists of the following five steps: - STEP 1: Identify key, safety-relevant parameters, - STEP 2: Consider (without consideration of technical feasibility) whether monitoring of these parameters would be of interest, and set priorities, - STEP 3: Consider the technical practicability of monitoring those parameters identified as being of first and secondary priority, - STEP 4: Identify whether models exist for the evolution of those parameters that can be monitored and whether safety-relevant criteria exist that the parameters should meet, - STEP 5: Assess the overall rationale for monitoring those parameters identified in Steps 1 through 4. Key candidate parameters for monitoring, provisionally identified by applying the methodology and that have associated safety-relevant criteria include: - Temperature in the Opalinus Clay host rock and, - Fluid pressure, also in the Opalinus Clay host rock. A number of other high priority parameters not associated with safety-relevant criteria, as well as parameters with lower priority (with and without associated safety relevant criteria), have also been identified. The methodology, as well as its trial application, are to be considered as first iterations, and are likely to be refined over the forthcoming years as experience is gained. (authors)

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DOE OSTI2019

Review Guidelines for Biosphere Safety Assessment of Low-Level Waste Disposal Repository in Taiwan - 19606

Conducting reviews of radiological dose assessments is a crucial step toward the approval of long-term radiological safety requirements for low-level radioactive waste (LLW) disposal facilities. However, the concentration of radionuclides released from the near field into the biosphere and the radiation exposure levels to an individual can influence the performance acceptability of the LLW disposal facility and safety of the disposal environment. Therefore, all LLW must be managed and disposed of such that it minimizes risk to individuals and the environment. A dose of 0.25 mSv/year is the limit for individuals expected to receive the highest level of exposure to residual radioactivity. In Taiwan, a review for license applications has been proposed for LLW disposal facilities. These review guidelines are based on the Standard Review Plan (NUREG-1200) and are amended according to the environmental conditions in Taiwan. These guidelines can help reviewers to perform safety assessment reviews of applications for the construction and operation of LLW disposal facilities. The review guidelines for biosphere safety assessment include radiological dose assessment, description of waste characteristics, radionuclide transport characteristics, radiation dose under normal and unusual conditions, radionuclide release into the biosphere, and interpretation of evaluation results in various transfer mechanisms. These guidelines can also serve as references for regulatory departments conducting safety assessments of radiological doses in LLW disposal facilities in Taiwan. (authors)

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DOE OSTI2019

Guidance Development: Management of Low Activity Waste After a Radiological Incident - 19616

The EPA, as the coordinating federal agency for long-term environmental recovery under the National Response Framework, is considering working with other Federal agencies, states and others to develop planning guidance for the management of the large volumes of waste that could result from a radiological incident. The 2017 revision of the PAG Manual contained, for the first time, limited generalized planning guidance on waste disposal; however, more detailed guidance that supports federal, state, and local planning efforts and can be initiated at the earliest stages of an incident would be desirable. This paper provides some of the considerations that EPA is exploring. (authors)

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DOE OSTI2019

Sustainable Security through International Source Repatriation - 19659

Ensuring that there is a viable pathway for characterizing, transporting, and disposing of disused radioactive sealed sources (sources) is essential to any end-of-life management strategy. The Off-Site Source Recovery Program, sponsored by the Department of Energy National Nuclear Security Administration's Office of Radiological Security, provides permanent and sustained threat reduction through the secure removal and repatriation of disused sealed radioactive sources of United States origin at international locations. With over two decades of operations, the Off-Site Source Recovery Program has developed source removal processes and techniques to ensure the compliant, effective and timely disposition of the material. For device disassembly support, the program subcontracts vendors qualified and experienced in source extraction from devices. United States origin source repatriations provide for permanent threat reduction and reduce their overall global footprint. (author)

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DOE OSTI2019

Optimizing the WIPP Safety Significant Confinement Ventilation System - 19691

A large exhaust ventilation system has been designed to provide continuous HEPA filtration of the exhaust from the WIPP underground while meeting the demand for expanded waste emplacement and mining operations over the next 40 years. The WIPP Safety Significant Confinement Ventilation System design provides safety significant secondary confinement to mitigate the consequences of postulated radiological releases in the underground. The integration of nuclear safety requirements into the design was accomplished during Safety Design Integration Team meetings. During these meetings, safety functions, boundaries and potential failure modes were reviewed to ensure that nuclear safety requirements were being effectively integrated into the design. Equally important to making final design decisions was ensuring that the maintenance and operation of the Safety Significant Confinement Ventilation System would not pose unnecessary burden to Technical Safety Requirements. This paper discusses the thought processes and decisions that justified a more concise safety significant boundary in the final design. (authors)

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DOE OSTI2019

Adapting Online Fiber Optic Colorimeter Systems for Process Measurements in H Canyon

A filter-based photometric analyzer, commonly referred to as a colorimeter, is an important instrument for monitoring uranium concentrations for nuclear safety control in SRS's H-Canyon facility. These instruments are effective but technologically out of date, and the facility does not have spare instruments on hand. Newly developed spectrophotometers will replace them and be capable of more accurate and reliable performance than the current colorimeters. However, the installation of the spectrophotometers will take some time. To make sure that the H-Canyon facility can continue processing operations and reduce the risk of a colorimeter going out of service, spare colorimeters previously configured for Pu monitoring in HB-Line will be reconfigured and calibrated for uranium. These spare colorimeters are readily available and their operating procedures are already known to the H-Canyon facility. This reconfiguration is an efficient and cost-effective means to meet a facility need. Both instruments have a linear response and accurately measure U over the range of concentrations expected in the H Canyon process. The instruments are functionally identical and can be used interchangeably. Changes of acidity within the expected process range will not introduce a bias in the measurement. Higher acidity solutions result in a positive bias, but this is conservative with respect to maintaining nuclear safety.

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DOE OSTI2019

Disposal of a pretreated oil sludge by the cementation method

Radioactive oil sludge is generated in oil production rigs worldwide and in large quantities. However, in Brazil, there is no disposal route or well-defined treatment option for this waste. This sludge is classified as TENORM due to the presence of Potassium-40 and the radionuclides of the natural decay chains of thorium and uranium. The management of this radioactive waste has been in situ packaging on the offshore platforms, followed by its transport to storage facilities onshore. Long term storage is problematic due to the high content of hydrocarbons, sulfur and water, which generates the toxic gas H{sub 2}S and the corrosive sulfuric acid. Ozonation, an advanced oxidation process (AOP) can be considered an attractive option of treatment, and followed by cementation can improve safety in long-term storage. This work aims at investigating if the ozone process was able to enhance the immobilization capacity of oil sludge. Oil sludge from different drums and mixed oil sludge (obtained by mixing equal parts of each drum) were analyzed by ICP. Solidification of oil sludge with Portland cement enhances safety of the waste disposal. In addition, ozonation treatment is efficient in the degradation of organic compounds, increasing the resistance of the solidified material.

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