Plan for Sterilization of Voyager Capsule
Sterilization plan for Voyager capsule
SPACECRAFT STERILIZATION↗
SEARCH · Engineering Papers
Results for “DECONTAMINATION”
Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.
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Microbiological studies relating to clean environments. Part I - Evaluation of the efficiency of a class 100 laminar-flow clean room for viable contamination cleanup
Laminar flow clean room efficiency for viable contamination cleanup
CLEAN ROOM↗
A sequential decision model of planetary quarantine primary objectives
Noncontamination requirements for planetary exploration mission derived by sequential decision model
MATHEMATICAL MODEL↗
Microbial Burden Approach : New Monitoring Approach for Measuring Microbial Burden
Advantages of new approach for differentiating live cells/ spores from dead cells/spores. Four examples of Salmonella outbreaks leading to costly destruction of dairy products. List of possible collaboration activities between JPL and other industries (for future discussion). Limitations of traditional microbial monitoring approaches. Introduction to new approach for rapid measurement of viable (live) bacterial cells/spores and its areas of application. Detailed example for determining live spores using new approach (similar procedure for determining live cells). JPL has developed a patented approach for measuring amount of live and dead cells/spores. This novel "molecular" method takes less than 5 to 7 hrs. compared to the seven days required using conventional techniques. Conventional "molecular" techniques can not discriminate live cells/spores among dead cells/spores. The JPL-developed novel method eliminates false positive results obtained from conventional "molecular" techniques that lead to unnecessary delay in the processing and to unnecessary destruction of food products.
microbial monitoring↗
Charging Experiments and Filtration Testing on Facemask Materials: Towards Goals of Full Performance Restoration of Used N95 Masks and Enhancement of Common-Fabric Facemasks
Different techniques have been developed for sanitizing N95 masks while retaining whatever charge remains on them. However, these sanitizing methods do not address the fact that the electrical charge, filtration efficacy, and breathability of such masks may be expected to degrade during long-term use based on mechanisms known in the literature. In this study, approaches to electrically (re)charging facemask filter materials were explored in response to the COVID-19 induced shortage of N95 masks. The effort consisted of charging experiments followed by filtration testing conducted at the coupon level during a month-long period (May 2020). The main focus of the work was to develop a recharging technique which could eventually be adapted and used as part of a broader full-performance restoration process for used N95 masks, e.g., which might employ simple washing by alcohol or soapy water as a preceding step for sanitization and declogging. Most tested coupons were therefore nonwoven meltblown fibrous polypropylene (PP) filter media extracted from decades old N95 masks. Keeping in mind commonly used cloth facemasks, limited trials were also performed with some commercially available fabrics. Charging was done at elevated temperature and was followed by cooling to freeze in the applied charges produced from corona discharges using different electrode configurations and parameter combinations, or from triboelectric rubbing. Charging was also focused on using potentially scalable equipment, e.g., Van de Graaff generators or consumer ionic hair products. Some degree of success was achieved with one of the fabrics and the PP filter media which was first purposefully discharged to have typical filtration efficiency (FE) of ~35%. Numerous attempts at corona charging discharged media resulted in filtration efficiency (FE) ≥ 80 – 85%. Some measure of charge robustness was also established via stable performance during loading testing. However, results where FE ≥ 90% were not reliably repeatable and no results met the FE ≥ 95% goal due to shortcomings of the charging process. The best three trials for PP media statistically met the FE ≥ 90% criteria, amounted to a small percentage of the trials relying on an ionic hair dryer, and are attributed to good embedding of charges via aerodynamic force. Triboelectric charging significantly enhanced the viability of one of the polyester fabrics –measured FE increased from 19% up to 46% while maintaining a reasonably low pressure drop.
N95↗
Building a Better Gas Mask
Berkeley Lab scientists have been putting the X-ray spotlight on composite materials in respirators used by the military, police, and first responders, work that could eventually lead to more advanced gas masks as well as protective gear for civilian applications.
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Taking Closure to the Next Level - 13030
The River Corridor Closure Project (RCCP) is the Hanford Site's first closure project and when it is complete, in 2015, it will have cleaned up 220 mi{sup 2} of contaminated land adjacent to the Columbia River. Washington Closure Hanford (WCH) was selected by the DOE to manage the removal and cleanup of Hanford's nuclear legacy along the River Corridor. Work began in 2005 and is now more than 85% complete with more than 2 years left in the contract. A Closure Team was commissioned in December 2009 and has since issued a closure strategy and a disciplined three-phase approach to transition land parcels to DOE, Richland Operations Office (DOE-RL) as cleanup is completed. This process supports DOE-RL objectives for progressive footprint reduction based on the division of the River Corridor into geographical land parcels. It also allows for incremental area-by-area transition and turnover to the Long-Term Stewardship program. Several important milestones stand between now and the successful end of the RCCP. They include overall funding impacts, working with DOE-RL on new scope additions, meeting regulatory milestones, and maintaining a strong safety performance. (authors)
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Achieving Accelerated Cleanup of Cesium Contaminated Stream at the Savannah River Site; Collaboration between Stakeholders, Regulators, and the Federal Government - 13182
The Savannah River Site (SRS) is a 310-square-mile United States Department of Energy (US DOE) nuclear facility located along the Savannah River near Aiken, South Carolina that contains six primary stream/river systems. The Lower Three Runs Stream (LTR) is one of the primary streams within the site that is located in the southeast portion of the Savannah River Site and is a large black water stream system that originates in the northeast portion of SRS and follows a southerly direction before it enters the Savannah River. During reactor operations, secondary reactor cooling water, storm sewer discharges, and miscellaneous wastewater was discharged and contaminated a 36 kilometer stretch of Lower Three Runs Stream that narrows providing a limited buffer of US DOE property along the stream and flood plain. Based on data collected during 2009 and 2010 under Recover Act Funding, the stream was determined to be contaminated with cesium-137 at levels that exceeded acceptable risk based limits. As efficiencies were realized within the SRS Recovery Act Program, funding was made available to design, permit and execute remediation of the LTR. This accelerated Project allowed for the remediation of 36 kilometers of LTR in only nine months from inception to completion, contributing significantly to the Foot Print Reduction of SRS. The scope consisted of excavation and disposal of more than 2064 cubic meters of contaminated soil, and installing 11 kilometers of fence and 2,000 signs at 1000 locations. Confirmatory sampling and analysis, and radiological surveying were performed demonstrating that soil concentrations met the cleanup goals. The project completed with a very good safety record considering the harsh conditions including, excessive rain in the early stages of the project, high summer temperatures, swampy terrain, snakes, wild boar, insects and dense vegetation. The regulatory approval process was compressed by over 75% and required significant efforts from SRS's stakeholders including the regulators, U. S. Environmental Protection Agency (US EPA) and the South Carolina Department of Health and Environmental Control (SCDHEC), and the public including local property owners and the SRS Citizens Advisory Board. Stakeholder buy-in was critical in the up-front planning in order to achieve this challenging cleanup. (authors)
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Comparison of Statistically Modeled Contaminated Soil Volume Estimates and Actual Excavation Volumes at the Maywood FUSRAP Site - 13555
As part of the ongoing remediation process at the Maywood Formerly Utilized Sites Remedial Action Program (FUSRAP) properties, Argonne National Laboratory (Argonne) assisted the U.S. Army Corps of Engineers (USACE) New York District by providing contaminated soil volume estimates for the main site area, much of which is fully or partially remediated. As part of the volume estimation process, an initial conceptual site model (ICSM) was prepared for the entire site that captured existing information (with the exception of soil sampling results) pertinent to the possible location of surface and subsurface contamination above cleanup requirements. This ICSM was based on historical anecdotal information, aerial photographs, and the logs from several hundred soil cores that identified the depth of fill material and the depth to bedrock under the site. Specialized geostatistical software developed by Argonne was used to update the ICSM with historical sampling results and down-hole gamma survey information for hundreds of soil core locations. The updating process yielded both a best guess estimate of contamination volumes and a conservative upper bound on the volume estimate that reflected the estimate's uncertainty. Comparison of model results to actual removed soil volumes was conducted on a parcel-by-parcel basis. Where sampling data density was adequate, the actual volume matched the model's average or best guess results. Where contamination was un-characterized and unknown to the model, the actual volume exceeded the model's conservative estimate. Factors affecting volume estimation were identified to assist in planning further excavations. (authors)
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Risk-based Prioritization of Facility Decommissioning and Environmental Restoration Projects in the National Nuclear Legacy Liabilities Program at the Chalk River Laboratory - 13564
Chalk River Laboratory (CRL), located in Ontario Canada, has a large number of remediation projects currently in the Nuclear Legacy Liabilities Program (NLLP), including hundreds of facility decommissioning projects and over one hundred environmental remediation projects, all to be executed over the next 70 years. Atomic Energy of Canada Limited (AECL) utilized WorleyParsons to prioritize the NLLP projects at the CRL through a risk-based prioritization and ranking process, using the WorleyParsons Sequencing Unit Prioritization and Estimating Risk Model (SUPERmodel). The prioritization project made use of the SUPERmodel which has been previously used for other large-scale site prioritization and sequencing of facilities at nuclear laboratories in the United States. The process included development and vetting of risk parameter matrices as well as confirmation/validation of project risks. Detailed sensitivity studies were also conducted to understand the impacts that risk parameter weighting and scoring had on prioritization. The repeatable prioritization process yielded an objective, risk-based and technically defendable process for prioritization that gained concurrence from all stakeholders, including Natural Resources Canada (NRCan) who is responsible for the oversight of the NLLP. (authors)
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Successful Characterization and Remedial Contour of Highly Contaminated Mercury Soil at the Y-12 National Security Complex - 13593
An area known as the 81-10 pad within the footprint of the Y-12 National Security Complex, suspected to be heavily contaminated with mercury, was slated for characterization in support of a Federal Facilities Agreement (FFA) milestone to be accomplished by September 30, 2012. A full remedial design report (RDR) required the soil in Exposure Unit -9 (EU-9) to be fully characterized for a number of contaminates of concern including mercury. The goal of this characterization effort was to determine what soil, if any, would need to be removed for the protection of industrial workers and impacts to the surface and ground water. Funding for this project was made available using buy-back scope under the American Recovery and Reinvestment Act (ARRA). The EU-9 soil unit involved 3 different classifications which were determined as follows: Class 1: Known to have been impacted, contamination is likely; Class 2: Suspected to have been impacted, contamination is unknown; Class 3: Area not known to have been impacted, contamination unlikely. Due to various sampling and analysis events since the 1980's, significant mercury contamination was expected under the concrete pad of an area known as 81-10. Mercury contamination outside of the boundary of this pad within the EU-9 footprint was not known and therefore an original planned estimate of 1,461 cubic meters of material were expected to be heavily contaminated with mercury requiring removal, treatment and disposal. Through the use of a highly effective nature and extent sampling and analysis design that involved a hybrid of statistically-based and judgmental sampling, the actual remedial contour requiring removal was approximately 717 cubic meters, roughly 12% of the original estimate. This characterization approach was executed in full compliance with the Record of Decision (ROD) [1] documents that were agreed upon by the U.S. Department of Energy, Environmental Protection Agency and Tennessee Department of Environment and Conservation. In addition, the RDR was completed ahead of the FFA milestone date of September 30, 2012. (authors)
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Long-term stewardship - surveillance and maintenance at Hanford - 15155
In FY 2015, Hanford's Long-Term Stewardship (LTS) Program is tasked to complete the required entries into five cocooned plutonium production reactors (105-C, 105-D, 105-F, 105-H and 105-N), which sit adjacent to the Columbia River. The first reactor entered in October 2014, the cocooned plutonium production reactor, 105-F, signaled the LTS Program's entry into the Surveillance and Maintenance (S and M) era. Reactor entries at Hanford are conducted at 5-year intervals to assess the condition of the structures and evaluate potential deterioration of the reactor core, shield walls and roof. The cocooned structures are designed to protect the reactor core for up to 75 years while radioactive decay continues, ultimately making the structures safe for demolition and removal. The 105-F entry demonstrates that the LTS program at Hanford is shifting from a program focused on transitioning cleaned up land and waste sites to a program focused primarily on S and M activities. The entry process is carefully planned, choreographed and monitored to ensure safety of the workers and minimize the time the reactor structure is opened. The process includes controlled opening of the reactor, air quality monitoring, structural safety inspections, and radiological clearance. Once the structure is cleared for entry, assessments of the structural integrity and radiologic conditions are completed. Evaluation of the interior temperature and flood monitoring equipment is conducted. Facility visits by regulators and DOE personnel close out the process prior to welding the door closed until the next assessment, five years later. This paper will document execution of the entry work package, identify challenges overcome, and provide video documentation as reference material for future workers and the public. The current LTS program has responsibility for approximately 100,000 acres, over 200 waste sites and six cocooned reactors. Just over 5,600 documents have been identified, indexed and tagged for storage in the LTS document library. The program has successfully completed seven consecutive transitions since July 2011, with six more transitions planned in the next 18 months to support the U.S. Department of Energy Richland Operations Office's (DOE-RL) near-term cleanup objectives to significantly reduce the footprint of active cleanup operations for the River Corridor. (authors)
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Technetium and iodine getters to improve Cast Stone performance - 15420
Technetium-99 ({sup 99}Tc) and iodine-129 ({sup 129}I) have been determined to be tank waste components contributing most to the environmental impacts associated with the cleanup of the Hanford site. Cast Stone, which has the ability to immobilize {sup 99}Tc, {sup 129}I, and other contaminants of concern, is being considered as a low temperature waste form for solidification of aqueous secondary liquid effluents from the Hanford Tank Waste Treatment and Immobilization Plant (WTP) An environmental assessment of Cast Stone performance, using measured diffusivities of the radionuclides from the Cast Stone product, calculates groundwater at the 100 m down-gradient in excess of the allowable maximum permissible concentrations for both radionuclides. Therefore, an opportunity exists to improve the performance of Cast Stone. One method for improvement is through the addition of immobilizing agents known as 'getters' that selectively sequester Tc and I. In the present paper, we report on seven getter materials that have been tested for Tc and five materials that have been tested for I to determine their effectiveness for radionuclide removal in a series of batch sorption tests in 18.2 MΩ DI H{sub 2}O and a 7.8 M Na Ave LAW waste simulant. Contact experiments have been carried out in anoxic conditions at room temperature, with varying solid-to-solution ratios, and in the presence and absence of competing species. Results indicate that most materials perform better in the 18.2 MΩ DI H{sub 2}O compared to the 7.8 M Na LAW waste simulant for both Tc and I getter. Radionuclide sequestration may be affected by the presence of the redox sensitive Cr(VI) in the simulant. The top performing Tc getter materials, Sn(II)-apatite, BFS-2, KMS-2 and Sn-hydroxyapatite, were examined through various solid-state characterization techniques such as SEM/XEDS, XANES and EXAFS. Tc removal is theorized to occur through reduction of the highly soluble Tc(VII) species to the less soluble Tc(IV). Solution results from the series of I tests show that iodide is effectively removed from solution via, most likely, a precipitation reaction of AgI. A wide range of I getter materials and the silver exchanged zeolite getter performed well in both DI water and the simulant. (authors)
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CEA decommissioning and clean-up activities legacy waste management and lessons learned - 15506
The CEA has generated radioactive waste in both liquid and solid form for more than 50 years within the scope of its R and D, clean-up and dismantling programs. The vast majority of the waste produced is transferred to disposal centers in approved waste packages. Nonetheless, a large quantity of legacy waste still remains in ageing facilities in which the storage conditions are sometimes no longer satisfactory with respect to the safety requirements that are constantly evolving. As part of a broad clean-up and dismantling process focusing on these ageing facilities managed by the CEA, the top priority is to shut down nuclear activities on two symbolic sites: Grenoble and Fontenay-aux-Roses, which are both located in a dense urban environment. After about ten years of dismantling, the nuclear facilities on the Grenoble site are on their way to be completely decommissioned in the regulatory sense of the term. Furthermore, the radwaste issue on this site has raised no specific problems, though it did require developing innovative and sometimes costly waste outlets. The older Fontenay-aux-Roses site is where the first experimental research on minor actinide separation took place. The facilities on this site have reached a stage in dismantling which necessitates the recovery of irradiating legacy waste containing alpha, beta and gamma emitters. The transfer of this waste to interim storage centers more than 600 kilometers away is a decisive factor in reducing the site's nuclear source term and in ensuring the satisfactory progress of the dismantling operations. This paper details the issues raised by the recovery of legacy waste, which requires greater characterization to better understand its radiological and chemical status. This waste also requires better characterization to meet the storage requirements of new sites designed for storage periods exceeding 50 years prior to its final disposal in a deep geological repository. The issue of transporting waste on public roads is specifically covered, along with the strategy defined to securely transfer all legacy waste resulting from the CEA's very diverse R and D programs. Emphasis is placed on finding the right balance between collecting the necessary data on the waste to be transported, ensuring the reconditioning of this waste so it can be transported safely, and maintaining an efficient industrial-scale waste transfer process to limit the lead times and costs related to legacy waste recovery operations. (authors)
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Conservation and Recycling for Radiological-Contaminated Laundry Applications - 16044
Recovery and reuse of materials exposed to radioactive environments is a critical element for those whom are involved with processing such materials. In order to minimize the disposal of radiological-contaminated Personal Protective Equipment (PPE, laundry, respirators, etc.) the need for environmentally-friendly and cost-effective technologies to provide laundering services is needed for current and future processes. A by-product of the laundry process is contaminated water. In order to reduce waste generation, we developed a radiological water filtration system custom-designed for laundry applications, which is used as both a filtration device as well as a water recycling system. The filtration process utilizes membrane filtration, suspended solids and organic filtration, ion-exchange capture, and ozonization/UV as germicidal reducers. In addition, ultrafiltration is used as a final step in order to return clean water back to the washing process system. The system was originally designed for non-radiological industrial laundry applications (hospitality, health care, correctional and governmental settings, etc). This process reduces the water consumption and discharge by up to 75% while retaining heat to minimize energy input costs. Principle components of the system include lint shakers and collection tanks with ozone injection, suspended solids filter, activated charcoal, ultraviolet lamp treatment cell, ion exchange columns, ultrafiltration filters, and final holding tank with ozone injection. Although up-front equipment costs are required, we believe that the reduction in waste generated through recycle and reuse of the water, along with avoiding premature disposal of PPE as radioactive waste, greatly outweighs up-front effort. (authors)
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Results of Modeling and Simulation Support to Specia Nuclear Material Handling Facility Operations - 16053
Newport News Shipbuilding (NNS) is the sole designer and provider of nuclear powered aircraft carriers and one of only two companies in the United States to build nuclear powered submarines. As part of the upkeep of aircraft carriers, the ships return to NNS once in their lifetime for a complex overhaul and to be refueled. In support of overhaul operations NNS maintains a state of the art Special Nuclear Material (SNM) handling facility. Due to the complex nature of the operations that occur within this facility, during the design and initial operation of the building NNS developed a facility simulation model to provide decision support during the project planning and operational phases. This tool allows users to experiment with process times, process order, equipment utilization, personnel utilization and spatial utilization. By capturing the planned operations, time distributions for operations, equipment sizes and uses and personnel requirements, the tool accurately reflects the planned use of the facility. This realism allows the user to experiment with any aspect of the facility, in a controlled and cost effective space, and determine how changes or potential delays may impact overall facility operations. Thus the model allows for rapid exploration of multiple scenarios to determine likely outcomes, allowing a user to identify risks well ahead of their realization and explore mitigation strategies in a controlled space, to determine the ideal path forward. The tool was successful during the initial operation of the facility in helping to identify and mitigate risks related to the complex operations occurring during SNM handling. The tool is now in use to support planning for the next series of operations that will occur within the facility. The initial operations the model supported occurred during the deactivation of the USS Enterprise, and future operation will focus on the overhaul of Nimitz class aircraft carriers. The NNS planning team is currently using the tool to assess potential risks and challenges that are identified as potentially impacting the schedule and timelines for these overhaul processes. In addition, the NNS development team is working to add new operational steps to the model, capturing work that is occurring near the facility, but which directly impacts the facilities operational abilities. In conjuncture with the engineering planning division, the NNS development team has run over 20 complex scenarios through the tool. The team has provided output from these scenarios to both NNS personnel and government representatives. To date the model has successfully supported the identification of several feasible paths to incorporate new processes, dictated by the work to support a overhaul vs a deactivation. The model also provides a spatial arrangement component that allows users to experiment with different equipment placement within the facility. Due to the fidelity of the model, arranging equipment with the spatial component allows a user to set up the facility in an experimental layout and run the processes inside the facility to determine if the layout will be feasible, or if it would impact operational capabilities. Additionally, the spatial component allows for visual collaboration between stakeholders to ensure all operational personnel are aware of the current and planned layout, and that they do not locate equipment or work stations in locations that would interfere with facility operations. The spatial component, in combination with the simulation component, has resulted in several documented improvements in process. These include: the identification of additional equipment which could be stored outside the facility, without impacting operations, to increase space; confirmation of the ideal placement of a large water tank; and identification of several risks related to planned equipment storage area, allowing the team to develop new plans and avoid realizing the risk. (authors)
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Shipping Grossly Dewatered resins in the RT-100 Type B Transportation Cask - 16068
Ion-exchange resins are used in the purification of coolant water in boiling water reactor nuclear power plants. The spent resins are a form of low-level or intermediate-level radioactive waste. These resins may have a relatively high specific activity level and are normally transported to a disposal facility within a secondary container placed in a Type B transportation cask. During transportation, hydrogen gas may build up in the cask due to radiolysis of the hydrogenous material in the contents. In the licensing process, a Type B cask is carefully analyzed to ensure that the maximum amount of hydrogen gas generated does not exceed 5%. The calculation to determine the mole fraction of hydrogen gas generated is a function of many variables, including the properties of the contents and the volume ratios of the contents. Because water generates hydrogen gas when it undergoes radiolysis, the amount of water present in the waste is normally limited. Typically, Type B transportation casks are allowed to carry dewatered resins, meaning less than 1% free-standing water by volume. To ensure compliance with this limitation, the dewatering process requires specialized equipment to pump the water from the secondary container. In an effort to enhance the usability of the RT-100 Type B transportation cask, Robatel Technologies re-analyzed the hydrogen gas generation calculation for contents including 'grossly dewatered' resins. Grossly dewatered resins are defined as resins containing less than 20% free-standing water by volume. This higher limit is made possible by a more thorough hydrogen gas generation calculation, which ensures that the flammability limit is not reached during shipment. In July 2015, The USNRC issued Revision 1 of the Certificate of Compliance for the Robatel Technologies RT-100 Type B transportation cask. This revision allows the cask to be used for grossly dewatered resins. With the revised Certificate of Compliance, the RT-100 is the first of its kind whose authorized contents include greater than 1% free liquids by volume. As a result of this change, the cask user can meet the 20% maximum free-standing water volume with a much simpler gravity-driven dewatering process. It is no longer necessary to have a complex dewatering system to ensure compliance with regulatory requirements. (authors)
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Brownfields to Brightfields: A Sustainability Initiative at DOE'S East Tennessee Technology Park Cleanup - 16120
As DOE works toward completing their cleanup mission at the East Tennessee Technology Park (ETTP), the ultimate goal is to return property no longer needed for government use to the community for beneficial re-use. The vision for ETTP is to transform the former gaseous diffusion facility into a commercial industrial park, leveraging the site's infrastructure to attract businesses to the site. While hundreds of acres at ETTP have been transferred for re-use, areas within the former production footprint of the site have future use restricted due to the presence of residual contamination, underground structures and utilities and/or physical features that limit their reuse potential. Brownfield redevelopment with solar energy generation has proven to be an excellent option for beneficial reuse and sustainability thanks to the flexible nature of solar photovoltaic technology and design that can address the restrictions and limitations of the site. Developing a solar project on a cleanup site can be challenging due to a large number of stakeholders and regulatory compliance issues of the environmental legacy at DOE cleanup sites; however, the challenges can be offset by the available infrastructure and low cost property. The requirement for large amounts of land or surface area is a major constraint to the growth of photovoltaic solar systems. An average solar generating facility requires 2 or more hectares (5 acres) for each megawatt (MW) of power generated. Re-using land that is otherwise un-developable provides a cost effective site for renewable energy generation to innovative solar developers. At ETTP, DOE's Oak Ridge Office of Environmental Management and the community reuse organization (Community Reuse Organization of East Tennessee - CROET) supported a local small business (Restoration Services, Inc. - RSI) familiar with the site and environmental regulations to secure a power purchase agreement with the regional electric provider (Tennessee Valley Authority - TVA) for a 1 MW utility-scale photovoltaic solar facility. The solar facility, Powerhouse Six, was developed through a commercial partnership (RSI and Vis Solis, Inc.) that worked closely with the lead ETTP site cleanup contractor (URS-CH2M Oak Ridge LLC - UCOR) and the local government. The selected site at ETTP had limitations on subsurface disturbance to 10 feet below ground surface because of utility ducts and residual contamination. Near surface relics (facility foundation remnants) were also found to prohibit ground penetration. A photovoltaic solar design using a ballasted ground mount system was developed to conform to the restrictions. The ballasted system could follow existing land contours, eliminating the need for any extensive site preparation and avoiding the risk of ground penetration. The lead cleanup contractor's role in facilitating the completion of this project included making the necessary environmental assessment documentation available to obtain the construction notice to proceed from the regional electric provider. They accelerated the transfer of ETTP power lines and electric demand to the city electric department to accommodate connection to the electric grid and supplied the communication connection required for metering the electric power generation. DOE's support along with their cleanup contractor's re-industrialization program and power integration group provided regular communication with the project stakeholders for more than six months to facilitate the early transfer of the utility infrastructure. Powerhouse Six sustainability benefits: - Generates enough clean energy to power more than 100 homes or prevents pollution equivalent to removing 240 cars from the road annually (1,141 metric tons of carbon dioxide); - Provides Brownfield reuse/redevelopment at ETTP; - Eliminates the generation of wastes through excavation and saves money to cleanup other areas for re-use; - Supports regional electric provider's renewable energy initiative; - Offers community economic development/ jobs and property tax income to the City of Oak Ridge; - Demonstrates benefit of ETTP re-industrialization; - Provides long-term lease payments to the community reuse organization; - Supports DOE renewable energy goals; - Demonstrates collaboration between DOE and a public utility for renewable energy development. (authors)
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