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DOE OSTI2013

Lessons Learned in the Design and Use of IP1 / IP2 Flexible Packaging - 13621

For many years in the USA, Low Level Radioactive Waste (LLW), contaminated soils and construction debris, have been transported, interim stored, and disposed of, using IP1 / IP2 metal containers. The performance of these containers has been more than adequate, with few safety occurrences. The containers are used under the regulatory oversight of the US Department of Transportation (DOT), 49 Code of Federal Regulations (CFR). In the late 90's the introduction of flexible packaging for the transport, storage, and disposal of low level contaminated soils and construction debris was introduced. The development of flexible packaging came out of a need for a more cost effective package, for the large volumes of waste generated by the decommissioning of many of the US Department of Energy (DOE) legacy sites across the US. Flexible packaging had to be designed to handle a wide array of waste streams, including soil, gravel, construction debris, and fine particulate dust migration. The design also had to meet all of the IP1 requirements under 49CFR 173.410, and be robust enough to pass the IP2 testing 49 CFR 173.465 required for many LLW shipments. Tens of thousands of flexible packages have been safely deployed and used across the US nuclear industry as well as for hazardous non-radioactive applications, with no recorded release of radioactive materials. To ensure that flexible packages are designed properly, the manufacturer must use lessons learned over the years, and the tests performed to provide evidence that these packages are suitable for transporting low level radioactive wastes. The design and testing of flexible packaging for LLW, VLLW and other hazardous waste streams must be as strict and stringent as the design and testing of metal containers. The design should take into consideration the materials being loaded into the package, and should incorporate the right materials, and manufacturing methods, to provide a quality, safe product. Flexible packaging can be shown to meet the criteria for safe and fit for purpose packaging, by meeting the US DOT regulations, and the IAEA Standards for IP-1 and IP-2 including leak tightness. (authors)

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DOE OSTI2012

Lessons Learned from the Application of Bulk Characterization to Individual Containers on the Brookhaven Graphite Research Reactor Decommissioning Project at Brookhaven National Laboratory - 12056

When conducting environmental cleanup or decommissioning projects, characterization of the material to be removed is often performed when the material is in-situ. The actual demolition or excavation and removal of the material can result in individual containers that vary significantly from the original bulk characterization profile. This variance, if not detected, can result in individual containers exceeding Department of Transportation regulations or waste disposal site acceptance criteria. Bulk waste characterization processes were performed to initially characterize the Brookhaven Graphite Research Reactor (BGRR) graphite pile and this information was utilized to characterize all of the containers of graphite. When the last waste container was generated containing graphite dust from the bottom of the pile, but no solid graphite blocks, the material contents were significantly different in composition from the bulk waste characterization. This error resulted in exceedance of the disposal site waste acceptance criteria. Brookhaven Science Associates initiated an in-depth investigation to identify the root causes of this failure and to develop appropriate corrective actions. The lessons learned at BNL have applicability to other cleanup and demolition projects which characterize their wastes in bulk or in-situ and then extend that characterization to individual containers. (authors)

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DOE OSTI2017

Challenges and Lessons Learned Performing Subsurface Investigations at a Radiologically Contaminated Site in an Urban Area - 17391

At the Formerly Utilized Sites Remedial Action Program (FUSRAP) Maywood Superfund Site (FMSS) the U.S. Army Corps of Engineers (USACE) has performed minimally intrusive (i.e. non-excavation) sub-surface investigations in soils, underneath roadways, and within buildings to generate information needed to determine whether contaminated material was present and to delineate the nature and extent. Given that thorium-232 (Th-232) contaminated material is present below various surfaces and that the current iteration of the Multi-Agency Radiation survey and Site Investigation Manual (MARSSIM) has only marginal guidance on evaluating and releasing subsurface data, survey design and implementation required detailed up front planning and post investigation analysis and reporting. This paper will discuss the approaches USACE utilized during a recent roadway investigation, some of the challenges encountered, a discussion of techniques used and results obtained, and an overall summary of pitfalls identified and lessons learned for future efforts. In order to evaluate selected areas, direct push technology was utilized in conjunction with plastic tubing to facilitate core capture and sample collection. PVC piping was inserted in each bore hole to prevent borehole collapse and facilitate downhole gamma logging. Soil samples were collected from the surface, from native material or the bottom of the boring, and from the interval or intervals which exhibited elevated downhole gamma readings, and from areas with an identifiable marker of contamination (i.e. soil discoloration) at the judgement of the field staff. Data was collected and evaluated using the approaches laid out in MARSSIM as best possible. As MARSSIM was developed to only address surface contamination, USACE, in agreement with regulators and stakeholders, utilized a 'varying plane' approach, where samples are evaluated as if on a single plane, and only the highest concentration encountered at any point is considered. Because the areas investigated were not easily cast into simple geometric shapes adhering to MARSSIM design criteria, it was important to ensure that Survey Unit design for Class 1 Survey Units were reasonable. All Class 1 SUs were contiguous survey units. Class 2 survey units were allowed to be non-contiguous provided that they are situated in close proximity to one another and share the same geology, conceptual site model, history, and radionuclide concentrations. The information contained in this paper will benefit Projects working with subsurface contamination which may require subsurface investigation and an understanding of the logistical, technological, and regulatory challenges. The ultimate outcome of this effort was the successful delineation of areas of contamination which will facilitate current utility work and guide future remediation. (authors)

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DOE OSTI2017

A Comparison of Social and Economic Engagement Approaches: Lessons from Recent International Radioactive Waste Projects - 17478

The central challenge of any proposed radioactive waste management project is securing not only regulatory permissions, but also a social license to operate. 'Social license' generally refers to a community's acceptance or approval of a specific project. Oftentimes development of social license occurs outside of, or in parallel to, formal regulatory or permitting processes, and requires sustained commitment and proposed economic benefits to communities by proponents to acquire, build, and sustain social capital in the context of trust-based relationships. Historically, radioactive waste management projects have defaulted to demagoguery and 'siege warfare' modes of thinking and action by both proponents and opponents. While radioactive waste management projects are always inherently controversial, it is only recently that project owners and developers have experimented with alternative forms of social engagement outside of, or in addition to, formal regulatory processes. This paper compares and contrasts recent projects in Canada, Australia, the United Kingdom, and the United States, by examining distinct approaches to social engagement, with a focus on new methods that have been used to promote mutual understanding, foster rational debate, build confidence, promote economic development, and secure social license. The projects examined span the life-cycle of radioactive waste management development, from ones that are purely aspirational, to ones in early planning stages, to ones seeking a host community, to one that is focused on sustainment of existing social license. Several notable lessons and innovative practices are identified that will be of interest to radioactive waste management project owners and developers, non-governmental organizations, potential host communities, and political decision-makers for such projects. (authors)

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DOE OSTI2015

25 years of environmental remediation in the general separations area of the Savannah river site: lessons learned about what worked and what did not work in soil and groundwater cleanup - 15270

The Savannah River Site, which is owned and administered by the US Department of Energy, covers approximately 900 square kilometers. The General Separation Area is located in the center of the site and includes: radioactive material chemical separations facilities, radioactive waste tank farms, radioactive seepage basins, and the radioactive waste burial grounds. Radioactive wastes were disposed in the General Separation Area from the mid-1950's through the mid-1990's. Operations at the F Canyon began in 1954 and at H Canyon began in 1955. Waste water disposition to the F and H Seepage Basins began soon after operations started in the canyons. The Old Radioactive Waste Burial Ground began operations in 1952 to manage solid waste that could be radioactive from all the site operations, and ceased receiving waste in 1972. The Mixed Waste Management Facility and Low Level Radioactive Waste Disposal Facility received radioactive solid waste from 1969 until 1995. Environmental legislation enacted in the 1970's through 1990's led to changes in waste management and environmental cleanup practices. The US Congress passed the Clean Air Act in 1970 and the Clean Water Act in 1972; the Resource Conservation and Recovery Act was enacted in 1976; the Comprehensive Environmental Response Compensation, and Liability Act was enacted by Congress in 1980; and the Federal Facilities Compliance Act was signed into law in 1992. Environmental remediation at the Savannah River Site essentially began with a 1987 Settlement Agreement between the Savannah River Site and the State of South Carolina. The site manages several of the larger groundwater remedial activities under the Resource Conservation and Recovery Act for facilities recognized early on as environmental problems. All subsequent remediation projects are managed under a tri-party agreement (Department of Energy, Environmental Protection Agency, and South Carolina Department of Health and Environmental Control) through the Federal Facilities Agreement. Environmental remediation activities during the past 25 years have stabilized and capped seepage basins as well as consolidated and capped waste units and burial grounds in the General Separation Area. Groundwater activities include: pump and treat systems in the groundwater, installation of deep subsurface barrier systems to manage groundwater flow, in situ chemical treatments in the groundwater, and captured contaminated groundwater discharges at the surface for management in a forest irrigation system. Concentrations of contaminants in the aquifers beneath the General Separation Area and in surface water streams in the General Separation Area have decreased over the past 25 years. Closure of 65 waste sites and 4 Resource Conservation and Recovery Act facilities has been successfully accomplished. Environmental clean-up has progressed to the stage where most of the work involves monitoring, optimization, and maintenance of existing remedial systems. Many lessons have been learned in the process of remediating the General Separations Area. Geo-textile covers outperform low permeability clay caps, especially with respect to the amount of repairs required to upkeep the drainage layers as the caps age. Passive and enhanced natural processes to address contamination are much more cost effective than pump and treat systems. Forest irrigation can be very effective in water management situations with non-accumulative contaminants such as tritium and volatile organic contaminants. (authors)

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DOE OSTI2015

Lessons learned in the hot cell at the transuranic waste processing center - 15336

The hot cell at the Transuranic Waste Processing Center (TWPC) has been in operation for seven years. Its mission is to empty, process, and repackage the contents Remote Handled (RH) concrete waste casks. The sequence of operation for processing the RH casks includes using a remotely operated manipulator (manipulator) to remove the cask contents and deliver them to a work table where operators process the waste into RH-TRU, CH-TRU, LLW drums using Master Slave Manipulators (MSMs). The manipulator is the only piece of equipment that can remove material from the cask and represents a single point failure that can shut down hot cell processing should it fail. During the first six years of operation the project processing goals were constantly in jeopardy due to the high frequency and extent of manipulator failures that forced unplanned down time in the hot cell to facilitate repairs. In 2013 a hot cell maintenance outage was planned and executed to improve the operability and reduce the equipment failure rate. A new remotely operated manipulator, purchased as a spare before the outage, was installed in the hot cell during the outage. Prior to installing the manipulator into the hot cell several major and minor modifications were made to the manipulator to incorporate improvements manipulator reliability and maintainability based upon operating and maintenance lessons learned from the previous years of operation. Additionally a maintenance glovebox was added to the hot cell for servicing the removable manipulator components. (authors)

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DOE OSTI2023

Passive Safety System Reliability Analysis: Lessons Learned and Open Items

Passive safety systems have multiple benefits, largely stemming from their high functional reliability due to their simplicity and lack of dependencies. However, accurately assessing the reliability of passive systems can be challenging due in large part to the possibility of functional failures. Argonne National Laboratory (Argonne) has been involved in several recent efforts concerning the reliability assessment of passive safety systems for advanced, non-light water reactors (non-LWRs). These efforts have focused on the development and application of mechanistic methods for the evaluation of passive system reliability, which rely on system modelling and uncertainty analyses to derive reliability values for use in probabilistic safety assessments (PSAs). Further information on these efforts is provided in ref [1]. The current paper reviews key lessons learned through these projects, along with outstanding open items regarding the reliability assessment of passive systems.

Grabaskas, David↗
DOE OSTI2016

Sharing Lessons Learned 'Across the Pond' on Two Major Construction Projects: Evaporator D and SWPF - 16050

This paper compares and contrasts two projects, the Salt Waste Processing Facility at Savannah River in the US and Evaporator D at Sellafield in the UK, to highlight the similar challenges that each project has experienced since contract award and how these challenges have been addressed. The paper compares the life-cycles of the projects, project strategy, design, construction, and regulatory issues, along with cost and schedule performance. There is also some discussion about the anticipated challenges in the future as the projects move into the startup and commissioning phase. Overall, the paper identifies some of the common areas that have affected these projects and how these similarities have been the subject of sharing and collaborating lessons learned on a broader scale, even though the delivery organizations operate in different countries under different regulatory and Government frameworks. (authors)

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DOE OSTI2016

Lessons Learned in Implementation of Radiological Investigations of Small-Scale Sites in Port Hope, Ontario - 16534

The Port Hope Area Initiative is a $1.28 billion project for the remediation of historic low-level radioactive waste resulting from the operation of Eldorado Nuclear Limited and its private-sector predecessors between 1932 and 1988 in Port Hope and Port Granby, Ontario, approximately 100 km east of Toronto. Included in the project is the investigation of all 4,800 privately and publicly owned properties in Port Hope in order to identify and remediate an estimated 375 properties containing LLRW exceeding clean-up criteria. This paper discusses the progress of the investigations, the development of clean-up criteria, methodologies used to identify historic LLRW, and lessons learned to date. This paper will be of greatest interest to future project managers of similar investigations. (authors)

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DOE OSTI2016

Lessons Learned - New Resin Processing System Selection, Procurement, Delivery, Set-up, Training, and Operation - 16615

Energy Northwest's first resin dewatering and drying system was purchased in 1989. Although the system functions acceptably, parts are no longer available and containers are no longer off-the shelf items, which require special manufacturing, thus higher cost, as compared to those used by many plants today. The decision was made to procure a new resin processing system (Self-Engaging Rapid Dewatering System, or SERDS). This paper provides lessons learned regarding each aspect of pre-planning, to procurement, acceptance testing, procedure development, and operation, including challenges as well as successes, which could help others in their decision making when contemplating procurement of a similar system. (authors)

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DOE OSTI2016

The Importance of Getting it Right - Lessons from the Failure and Subsequent Approval of the LLWR Environmental Safety Case - 16691

The Low Level Waste Repository (LLWR) in the UK submitted an Environmental Safety Case in 2002 which was rejected by the Environment Agency 3 years later. Almost a decade after the rejection, the LLWR submitted a completely different document which was approved in November 2015. This paper looks at the lessons learned from the failed submission and documents the strategy employed by the Site's new contractor to overcome both the challenging technical issues that led to the initial rejection and overcome the resistance to long term disposal by the local community. It will describe the journey it has taken to move from a flawed safety case, to a technically sound safety case, to one that is approved by the regulator, and accepted by the community. (authors)

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DOE OSTI2018

Need for an Independent Monitoring of Nuclear Waste Repository: Lessons from WIPP Experience - 18130

The Waste Isolation Pilot Plant (WIPP) is the only operating deep geological repository for the permanent disposal of defense transuranic (TRU) waste in the world. The facility recently resumed waste disposal operations after recovering from a February 2014 accident involving a radiological release from a waste container in the WIPP underground. WIPP had been a DOE success story, operating nearly 15 years with no significant incidents or accidents. Many factors contributed to this success, one of the most important being the overwhelming support exhibited by the local community and the local elected officials. One component of the broad public acceptance by the citizens of Southeast New Mexico has been the concept of independent, third party monitoring of environmental effluents at the site. Independent environmental monitoring ensures a role for the local community in ongoing evaluation of the safety and performance of the site. At WIPP this has been achieved through an independent environmental monitoring program operated by the Carlsbad Environmental Monitoring and Research Center (CEMRC). The CEMRC has been conducting independent environmental monitoring activities on and around the WIPP site since 1991 and makes the results of monitoring activities available and easily accessible to members the general public. The public's free and open access to this data and their direct participation in the CEMRC's whole body counting program provides transparency, which is key to maintaining public trust and confidence. The circumstances following the 2014 radiological release event at WIPP reinforced the value of independent environmental monitoring in order to maintain the high level of transparency necessary for long term local acceptance and support for nuclear facilities. Following what was a minor radiological release event, there were understandably fearful reactions from a number of citizens residing in Carlsbad and the nearby communities of Hobbs, Loving, and Artesia. CEMRC's independent environmental monitoring program and their early public engagement proved invaluable in providing timely and accurate environmental data to local community leaders and members of the general public. The data, and open communication from CEMRC, helped reassure citizens in Carlsbad and the surrounding area that the release was extremely low and the extent was very limited. CEMRC further communicated that the probability of any environmental or health impacts from the release was extremely low. It is unlikely the local community would have placed the same level of trust in similar assurances of safety coming from DOE or other State and Federal regulators. The CEMRC's performance in the days following the release meant the local community had access to independent monitoring data and an independent voice in the dialogue with DOE and state officials that shaped the recovery and eventual re-opening of the WIPP facility. The WIPP radiological release event yielded a plethora of lessons learned that will frame the next phase of operational, oversight, and emergency planning surrounding the facility. In this presentation we will be discussing the value and viability of federally-funded, university-housed independent monitoring programs in maintaining trust of state officials and the local communities. (authors)

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DOE OSTI2018

Lessons Learned From Decommissioning B411 Decontamination Centre at Whiteshell Laboratories - 18211

Whiteshell Laboratories, located in Manitoba, Canada, provided research facilities for the Canadian nuclear industry since the early 1960's. The facility was centered on the largest organically cooled, heavy water moderated nuclear reactor in the world, the WR-1. It is now operated by Canadian Nuclear Laboratories (CNL) and is the first major decommissioning project of a nuclear research establishment in Canada. One of the major projects to support the closure of Whiteshell Laboratories (WL) is the decommissioning and demolition of the Building 411 (B411) Decontamination Centre, which provided a decontamination service for maintaining research and development of experimental rigs, equipment and tools in a safe usable state. It also provided a laundry service for radioactively contaminated clothing. The team successfully self-performed their first demolition of a nuclear facility, but not without challenges. The baseline decommissioning strategy assumed most of the facility would meet unconditional clearance levels; however when characterization revealed the extent of contamination exceeded initial assumptions projected from process knowledge, in conjunction with resource challenges and a waste disposal pathway not firmly established, active remediation of the facility was undertaken. With an unknown waste acceptance criteria for the future waste disposal facility, sludge that had accumulated in a tank used to collect xylene and organic coolant from contaminated tools and equipment and the selection of appropriate waste packages for waste storage, transportation and disposal forced the project team to adjust their demolition timeline. This, coupled with developing an open air demolition plan and managing an uncertain end state criteria, were just some of the major tasks the team successfully navigated. The impact on both schedule and cost performance caused by the change in strategy, and the lessons learned experienced by the WL Decommissioning Project Team that are being applied as the Whiteshell Laboratories Closure Project (WLCP) moves forward with the next major decommissioning challenge, are highlighted in this paper. (authors)

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DOE OSTI2018

Lessons Learned from the Remote Reactor Vessel Internals Segmentation at Barsebaeck 2 - 18231

Westinghouse is performing a decommissioning project at Barsebaeck in Sweden that was awarded in June 2015. Barsebaeck is an ABB-designed boiling water reactor (BWR) plant (2 units of 615 MW) located 30 kilometers from Malmoe. The first reactor, Barsebaeck 1, was permanently shut down on Nov. 30, 1999, and the second one, Barsebaeck 2, ceased operation on May 31, 2005. The scope of work covers the underwater segmentation and packaging of the Reactor Vessel internals at Barsebaeck 1 and 2, including the up-front engineering studies and equipment manufacturing and qualification. The Barsebaeck Unit 2 was selected for starting the site work in August 2016. Cutting was performed with different types of Westinghouse designed cutting equipment (hydraulic shears, band saw, disc saw). All segmentation tools are remotely controlled due to the high radiation levels and ALARA and personal safety is the number one priority during the site work. The cutting equipment proved to be reliable and flexible which is very valuable for the execution of such a challenging project. The Barsebaeck Unit 2 cutting activities have been finished end of October 2018 and its lessons learned will be taken into consideration for the Unit 1 activities. (authors)

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DOE OSTI2018

FUSRAP Case Study - Benefits and Lessons Learned from Implementation of a Modern Data Solution at Maywood - 18399

This paper focuses on data production and management practices dating back to 1999 that continue to evolve to support the project today. In 2000, the FUSRAP Maywood Project began using a software environmental data management system and laboratory information management system, developed by a single database administrator (DA) and authored in Microsoft Access{sup TM} (MS Access). The original databases included basic functionality including sample number assignment and label generation, tracking of LIMS gamma spec QC and assignment of basic qualifiers and basic database queries. The DA continued over the next fifteen years to refine the EDMS/LIMS by integrating project-specific data evaluation guidance document processes and Quality Assurance/Quality Control (QA/QC) charting and excursion warning tools. With the retirement of the original DA, the U.S. Army Corps of Engineers (USACE)-Cabrera Team procured and implemented a commercial-leaning solution using modern database tools and an established EDMS vendor. For the database transition process, the project team established and configured the new EDMS/LIMS with basic architecture and accessibility; evaluated existing workflows; established/revised LIMS and EDMS-related documentation (manuals and procedures); and conducted dry runs and validation testing. The overall team coordinated closely to facilitate a seamless transition from initial assessment and authoring, to data migration, and finally to resumption of normal ongoing operations. Key features of the new EDMS Subcontractor's software included lookup tables, an import wizard, data checking options and unique indexes. Since the database systems became operational, the technical staff gathered useful feedback from end users (e.g., lab staff, field engineers, task managers, and the third-party data validator) to refine the EDMS/LIMS operation. This feedback triggered improvements in the performance of onsite laboratory qualification forms, promoted consistency in sample ID numbers between the database sample planning screens and field chain-of-custodies, corrected bugs in the LIMS Duplicate Evaluation Report, eliminated data import issues such as blank, inconsistent or missing data from key fields. One of the advantages of the commercial database solution was that it allowed the project to cut cost over time due to the lower cost of database maintenance provided by the commercial database vendor versus the cost of an on-staff DA. Cost savings are estimated at $40,000 per year. There were also indirect cost savings resulting from implementation of the new database since it allowed better integration of the LIMS and EDMS. While there will always be challenges associated with long term records/data management for any old remediation site, the Maywood Team's approach to an upgraded EDMS/LIMS implementation serves as one element of the overall effort to enhance the integrity and reproducibility of critical data that supports the remediation program while at the same time, more effectively using available resources. These lessons-learned will enhance implementation of cost-effective solutions for similar environmental remediation sites. (authors)

97 MATHEMATICS AND COMPUTING↗
DOE OSTI2018

Observations and Lessons Learned from Testing of the Hanford Waste Treatment Plant Standard High Solids Vessel Design - 18635

The Hanford Waste Treatment and Immobilization Plant (WTP) recently completed qualification testing of the mixing system for the standard high solids vessel design the U.S. Department of Energy (DOE) proposed to replace several vessels in the design of the plant Pretreatment Facility. Testing was split into two phases. The first phase exercised the pulse jet mixer control system to ensure that the control software could accommodate fluids across the complete range of expected densities and viscosities within the vessel for all operational modes. The second phase of testing was focused on the mixing performance of the vessel, specifically, whether mixing was adequate to support the transfer, de-inventory, throughput, and sampling functions of the vessel. Key observations and lessons learned from testing include: - Successful transfer of waste within and beyond the design basis slurry solids concentration; - Successful resuspension and transfer of large, heavy particles; - Effective performance of multi-level bubblers for process control and monitoring; - Effective controls performance; - Reduction of sparger flowrate from nominal design flow; - Liquid blending within about 15 minutes; - Insights into sample representativeness and uniformity of transfers to inform process control strategies. (authors)

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DOE OSTI2019

Successes and Lessons Learned in the Design, Construction and Use of a Tool for Sampling the WR-1 Reactor Core - 1900z

Whiteshell Laboratories, located in Manitoba, Canada, provided research facilities for the Canadian nuclear industry since the early 1960's. The facility was centered on an organically cooled, heavy water moderated nuclear reactor in the world, Whiteshell Reactor 1 (WR-1). WR-1 was safely shut down in 1985, de-fueled and drained, and has been in a safe Storage with Surveillance (Deferred Decommissioning) state until present day. In support of an Environmental Assessment for proposed In Situ Decommissioning of WR-1, detailed characterization information regarding the reactor core components (calandria, calandria tubes, pressure tubes) was necessary to verify inventory estimates and neutron activation models produced circa 1992. The Fuel Channels of WR-1 (pressure tubes) were expected to be the most activated components of the reactor core, and to account for about 60% of the reactor core inventory. The interior surface of the fuel channel is also the most readily accessible surface within the reactor core. As such the decision was made to collect a sample of one of each of 3 Fuel Channel material types (Stainless Steel, Zr-2.5Nb, Ozhenite) for comparison to modelled estimates of neutron activation of various core materials. The expected dose rates from the samples were between 5 and 100 mSv (500-10,000 mrem) on contact based on a 200 mg sample. Sampling the Fuel Channels required verification the Fuel Channel was drained of organic coolant, removal of residual organic coolant from the Fuel Channel wall, removal of material from the interior surface of the Fuel Channel at the centerline of flux (∼25' below the operator position), and extraction of that material from the core. Several options for existing tooling and technologies, including hydraulic scrapers, and horizontal drill technologies, were looked at for their applicability to WR-1. While suitable approaches to higher radiation field sample collection, they were overly complex, costly and time consuming for the configuration at WR-1. In an effort to reduce costs, and to simplify the sampling process, a specialized and simple tool was developed to mechanically scrape a small sample of the interior wall of the Fuel Channels, collect the sample into a vial, and remove the sample from the core for analysis. The tool was designed, constructed, tested and implemented in the field entirely by Canadian Nuclear Laboratories Staff. The tool required no powered components, or electronic guidance or measurements; and was designed and constructed for a fraction of the cost of other commercially available technologies for sample collection within reactor cores. The samples were successfully collected without any injuries, contamination events or equipment failures. The tool remains operational in the event additional sampling is required. This paper provides additional details of the design, construction, testing and use of the tool and the successes and lessons learned during the various stages of design and implementation. (authors)

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DOE OSTI2019

Site Characterization and Adaptation - Lessons Learned from the Port Granby LLRW Project in Canada - 19255

The Port Hope Area Initiative (PHAI) is a community-based solution for the long-term management of historic low level radioactive waste (LLRW) resulting from 60 years of uranium and radium processing operations in the Town of Port Hope, Ontario. 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 the Town of 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 is part of the broader PHAI being completed by Canadian Nuclear Laboratories (CNL). The scope of remediation activities at Port Granby includes: 1) constructing a new, secure long-term waste management facility (LTWMF) and supporting infrastructure, and 2) excavating and relocating LLRW and marginally contaminated soil from the Port Granby Waste Management Facility (PGWMF) to the newly constructed LTWMF. Remediation design required extensive site investigations of waste buried in unmarked and unlined trenches across the PGWMF area. Investigations included reviews of historical records, interviews with past staff of Eldorado and Atomic Energy Canada Limited (the entity managing the PHAI cleanup prior to CNL), radiological surveys, and the advancement of boreholes across the site to facilitate the physical sampling of soil and groundwater contaminants indicative of the presence of LLRW. This paper describes the challenges associated with characterizing and quantifying waste prior to remediation and lessons-learned to adjust procedural adaptations during the characterization phase of a project to better anticipate the unanticipated nature and growth of the contamination profile that often occurs during remediation. Despite substantial pre-remediation investigative efforts, current PGWMF remediation activities have resulted in growth of both the areal and vertical extent of contamination. The contamination profile was shown to be dramatically influenced by leaching of contaminants deeper into native soils. In addition, remedial excavation discovered specific waste types such as unidentified compressed gas cylinders outside of the location indicated by historical records, as well as a quantity of unknown liquids and unmarked drums. These discoveries have resulted in higher waste quantity estimates and have required a partial redesign of the LTWMF mound (a higher final elevation and steeper slopes) to accommodate the increased waste volume. In addition, the means and methods necessary to execute the remedial construction had to be modified to account for the new conceptual model developed from the new contamination data. Despite extensive historical review and site characterization to define the nature and extent of LLRW buried at the PGWMF, actual conditions encountered during remediation efforts necessitated taking an adaptive approach to both the design of the LTWMF and the means and methods used for excavation and transport of waste. (authors)

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