This study was undertaken to determine the technical feasibility of upgrading the Waste Experimental Reduction Facility (WERF) to meet the offgas emission limits proposed in the Maximum Achievable Control Technologies rule. Four practicable offgas treatment processes were identified, which, if installed, would enable the WERF to meet the anticipated MAC" emission limits for dioxins and furans @/F), hydrochloric acid (Ha), and mercury (Hg). Due to the three-year time restraint for MAC" compliance, any technology chosen for the upgrade must be performed within the general plant project funding limit of $5 M. The option selected consists of a partialquench evaporative cooler with dry sorbent injection for HCl removal followed by a sulfur-impregnated activated carbon bed for Hg control. The planning cost estimate for implementing the option is $4.17 M (with 24% contingency). The total estimated cost includes capital costs, design and construction costs, and project management costs. Capital costs include the purchase of a new offgas evaporative cooler, a dry sorbent injection system with reagent storage, a new fabric filter baghouse, a fixed carbon bed adsorber, and two offgas induced draft exhaust fans. It is estimated that 21 months wiU be required to complete the recommended modification to the WERF. The partialquench cooler is designed to rapidly cool the offgas exiting the secondary combustion chamber to minimize D/F formation. Dry sorbent injection of an alkali reagent into the offgas is recommended. The alkali reacts with the HCl to form a salt, which is captured with the fly ash in the baghouse. A design HC1 removal efficiency of 97.2% allows for the feeding 20 lbs/hr of. chlorine to the WERF incinerator. The sorbent feed rate can be adjusted to achieve the desired HC1 removal efficiency. A fixed bed of sulfur-impregnated carbon was conservatively sized for a total Hg removal capacity when feeding 10 g/hr Hg to the WERF incinerator. An added benefit for using carbon adsorption is that the activated carbon will also capture a large fraction of any residual D/F present in the offgas.
This report identifies and evaluates three options for treating newly generated liquid waste at the Idaho Nuclear Technology and Engineering Center of the Idaho National Engineering and Environmental Laboratory. The three options are: (a) treat the waste using processing facilities designed for treating sodium-bearing waste, (b) treat the waste using subcontractor-supplied mobile systems, or (c) treat the waste using a special facility designed and constructed for that purpose. In studying these options, engineers concluded that the best approach is to store the newly generated liquid waste until a sodium-bearing waste treatment facility is available and then to co-process the stored inventory of the newly generated waste with the sodium-bearing waste. After the sodium-bearing waste facility completes its mission, two paths are available. The newly generated liquid waste could be treated using the subcontractor-supplied system or the sodium-bearing waste facility or a portion of it. The final decision depends on the design of the sodium-bearing waste treatment facility, which will be completed in coming years. iv v SUMMARYThe Idaho Nuclear Technology and Engineering Center (INTEC) has completed its mission in reprocessing spent nuclear fuel and is managing and disposing of wastes from those reprocessing operations. Part of dealing with this legacy is treating and disposing of liquid wastes remaining in various storage tanks at INTEC. This waste is designated as sodium-bearing waste (SBW). The Idaho National Engineering and Environmental Laboratory (INEEL) also manage newly generated liquid waste (NGLW), which continues to be generated from ongoing operations.Presently, the SBW is stored in large underground tanks in the Tank Farm Facility (TFF) at INTEC. A 1995 Settlement Agreement between the State of Idaho, Department of Energy (DOE), and U.S. Navy requires that treatment of the SBW be completed by December 31, 2012. The DOE Idaho Operations Office (DOE-ID) has also mandated that transfer of NGLW to the TFF cease by September 2005. The Idaho Tank Farm Project (ITFP) is responsible for treating the current inventory of SBW, safely closing the tanks in which the SBW is stored, and remediating the radioactively contaminated soils adjacent to the storage tanks. The ITFP is also responsible developing a management scheme for NGLW.This report discusses the evaluation of options for managing NGLW at INTEC. The options considered are: Hold for SBW processing, which involves storage of the NGLW in Resource Conservation and Recovery Act (RCRA)-compliant tanks until the facility for treating SBW is available for treating NGLW Treat and dispose of the NGLW by employing a subcontractor with a commercial process to treat the NGLW on an intermittent basis Design and construct a new facility at INTEC to treat NGLW.Prior to evaluating these options, some estimate of the quantity and characteristics of the NGLW was needed, as well as a scheme for storing the NGLW until it is processed. Estimating the quantity and charac...
This feasibility study report presents a draft design of the Vitrified Waste Interim Storage Facility (VWISF), which is one of three subprojects of the Idaho Waste Vitrification Facilities (IWVF) project. The primary goal of the IWVF project is to design and construct a treatment process system that will vitrify the sodium-bearing waste (SBW) to a final waste form. The project will consist of three subprojects that include the Waste Collection Tanks Facility, the Waste Vitrification Facility (WVF), and the VWISF. The Waste Collection Tanks Facility will provide for waste collection, feed mixing, and surge storage for SBW and newly generated liquid waste from ongoing operations at the Idaho Nuclear Technology and Engineering Center. The WVF will contain the vitrification process that will mix the waste with glass-forming chemicals or frit and turn the waste into glass. The VWISF will provide a shielded storage facility for the glass until the waste can be disposed at either the Waste Isolation Pilot Plant as mixed transuranic waste or at the future national geological repository as high-level waste glass, pending the outcome of a Waste Incidental to Reprocessing determination, which is currently in progress. A secondary goal is to provide a facility that can be easily modified later to accommodate storage of the vitrified high-level waste calcine. The objective of this study was to determine the feasibility of the VWISF, which would be constructed in compliance with applicable federal, state, and local laws. This project supports the Department of Energy's Environmental Management missions of safely storing and treating radioactive wastes as well as meeting Federal Facility Compliance commitments made to the State of Idaho. Two scenarios were evaluated during this study. The first scenario includes individual storage tubes for the vitrified waste canisters (two canisters per tube) and a passive ventilation system. This option is called the "Hanford Option," because it is modeled after the Hanford vitrified waste storage design. The second scenario includes racks for holding the vitrified waste canisters and a mechanical ventilation system. The second option is labeled the "Savannah River Option," since it is modeled after the Savannah River Site's vitrified waste storage facility. The report includes sketches, a description, and cost estimates for each option.
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