APPENDIX H: ENVIRONMENTAL MANAGEMENT This appendix provides: an overview of the Department of Energy (DOE) environmental restoration and waste management program including the categories of waste streams managed by the Department; the applicable Federal statutes and DOE orders; waste minimization and pollution prevention; waste treatment, storage, and disposal; transportation of wastes; and, finally, facility transition management. Site-specific waste management activities will follow in section H.2. Project-specific waste management activities are addressed in appendix section A.2. H.1 Overview H.1.1 Waste Categories Wastes are generated in gaseous, liquid, and solid forms and are categorized by their health hazard and handling requirements. The categories are listed in table H.1.1.-1. Table H.1.1.-1.-Spent Nuclear Fuel and Waste Categories Category Characterization Spent nuclear fuel Nuclear reactor fuel that has been irradiated to the extent that it has undergone significant isotopic change to the point that fission-product poisons have reached an uneconomic threshold. DOE is no longer reprocessing spent nuclear fuel solely to recover fissile and fertile material. High-level Highly radioactive waste that results from the reprocessing of spent nuclear fuel used to make nuclear weapons or energy, including liquid waste produced directly in reprocessing, and any solid waste derived from the liquid that contains a combination of transuranic waste and fission products in concentrations requiring permanent isolation. Transuranic Radioactive waste contaminated with alpha-emitting elements with a higher atomic number than uranium, half lives greater than 20 years, and in concentrations greater than 100 nanocuries per gram. Such wastes result primarily from fuel reprocessing and from the fabrication of plutonium weapons components and plutonium-bearing reactor fuel. Generally, little or no shielding is required ("contact-handled" transuranic waste), but energetic gamma and neutron emissions from certain transuranic nuclides and fission- product contaminants may require shielding or remote handling ("remote- handled" transuranic waste). Low-level Radioactive waste that is not spent nuclear fuel, high-level waste, transuranic waste, or by-product material as defined by DOE Order 5820.2A. Includes research and development fissionable test specimens with transuranic less than 100 nanocuries per gram. The radiation level from this waste may sometimes be high enough to require shielding for handling and transport. In 10 CFR 61, NRC defines four disposal categories of LLW that require differing degrees of confinement and/or monitoring: classes A, B, C, and Greater-Than-Class C. Hazardous Nonradioactive waste which has characteristics identified by either or both of the following Federal statutes: the RCRA, 40 CFR 261, as amended, or the Toxic Substances Control Act. These toxic, corrosive, reactive, or ignitable substances, or RCRA-listed wastes have been identified as posing health or environmental risks. Hazardous waste includes chemicals, such as chlorinated and nonchlorinated hydrocarbons, explosives, leaded oil, paint solvents, sludges, acid, organic solvents, heavy metals, and pesticides. Mixed Waste containing both hazardous and radioactive constituents. Nonhazardous (Sanitary) Solid sanitary waste includes garbage and is routinely generated by normal housekeeping activities and does not have a defined health risk (neither radioactive nor hazardous). Solid sanitary waste is regulated under RCRA, Subtitle D. Liquid sanitary waste includes sewage and industrial waste, which are treated in a wastewater process before discharge to a publicly owned treatment works or surface waters. The management of liquid sanitary waste is regulated by the Clean Water Act and the National Pollutant Discharge Elimination System. Nonhazardous (Other) Other wastes that do not have a defined health risk such as process wastewater. H.1.2 Applicable Federal Statutes and Department of Energy Orders In order to operate at most of its facilities, DOE has entered into numerous agreements with states and the Environmental Protection Agency (EPA) to address compliance issues concerning certain aspects of environmental regulatory requirements that have arisen due either to the age of the DOE facilities or the uniqueness of DOE operations. For the most part, the DOE facilities are in compliance with the major portion of all environmental regulatory requirements and these compliance agreements address only a few specific situations. At the same time, most of these compliance agreements include a commitment from DOE to achieve compliance with specific requirements by a certain date, and a schedule and milestones for achieving that compliance. These agreements guide DOE activities, at the sites, under applicable environmental laws, regulations, and other standards. Compliance with the terms of these negotiated agreements is one of the highest DOE priorities. Site operations will be conducted consistent with the commitments DOE has made. DOE will work with the regulators to amend existing agreements and to develop new agreements to ensure continued compliance. Under no circumstances will DOE's performance, pursuant to any existing compliance agreement, be compromised or diminished as a result of the proposed action. Most of the regulations that impact the storage, treatment, and disposal of wastes were promulgated since the original Nuclear Weapons Complex (Complex) was established. In many cases, the technology available at the time the Complex was constructed does not meet current requirements for full compliance and, as a result, interim agreements have been made with the regulatory agencies. Through continuous upgrade programs, processes have been improved or added to meet the new regulations. Operations continue on the basis of using "best available technology" for facilities that were in operation before the regulation came into effect. In the siting and construction of new facilities, the intent is to meet current regulations and to reach the goal of maximum recycle, minimal waste generation, no liquid discharges to the surface, and to treat and stabilize unavoidable wastes sufficient for long-term storage or permanent disposal either onsite or offsite. The following summarizes the applicable Federal statutes and DOE orders: Atomic Energy Act. The Atomic Energy Act gives DOE the authority to manage and regulate nuclear materials handled and generated at its facilities; however, DOE seeks to make its internal guidelines consistent with standards applied to commercial nuclear facilities regulated by the Nuclear Regulatory Commission (NRC). Pursuant to the Atomic Energy Act, DOE is committed to the practice of "as low as reasonably achievable" exposure to radiation from its operations whereby exposures and resultant doses are maintained as low as social, economic, technical, and practical considerations permit. Resource Conservation and Recovery Act. The Resource Conservation and Recovery Act (RCRA) was passed in 1976 as an amendment to the Solid Waste Disposal Act of 1965. RCRA regulates the "cradle to grave" management (generation, accumulation, storage, treatment, recycle, transport, and disposal) of hazardous waste, nonhazardous waste, underground storage tanks containing petroleum products and hazardous substances, and medical waste. Subtitle C of RCRA mandates that hazardous wastes be treated, stored, and disposed of in a manner that will minimize the threat to human health and the environment. To carry out this mandate, RCRA requires that owners and operators of hazardous waste treatment, storage and disposal facilities obtain operating or post-closure care permits for certain waste management activities. RCRA defines the requirements for treatment, storage, and disposal facilities. Subtitle D of the law addresses the management of nonhazardous solid waste. Title 40 of the Code of Federal Regulations implements the statutory provisions of RCRA. Land Disposal Restrictions. The Hazardous and Solid Waste Amendments to RCRA enacted in 1984 required EPA to evaluate all listed and characteristic hazardous wastes according to a strict schedule and to develop requirements by which disposal of these wastes would be protective of human health and the environment. The implementing regulations for accomplishing this statutory requirement are established with the Land Disposal Restrictions program. The Land Disposal Restrictions regulations (40CFR268) impose significant requirements on waste management operations and environmental restoration activities. For hazardous wastes restricted by statute from land disposal, EPA is required to set levels or methods of treatment that substantially reduce the waste's toxicity or the likelihood that the waste's hazardous constituents will migrate. After the Land Disposal Restrictions effective date, restricted wastes that do not meet treatment standards are prohibited from land disposal unless they qualify for certain variances or exemptions. EPA has promulgated standards for each of the five statutorily designated categories through the following Land Disposal Restrictions rulemakings: Solvent Dioxin Rule. Land Disposal Restrictions and corresponding treatment standards for solvents and dioxins, including mixed wastes containing solvents and dioxins, went into effect on November 8, 1986, and November 8, 1988, as set forth in 40 CFR 268.30 and 40 CFR 268.31, respectively. California List Rule. Land Disposal Restrictions and corresponding treatment standards for California list wastes, including mixed wastes containing California list wastes, went into effect on July8, 1987, as set forth in 40 CFR 268.32. For the remaining listed or identified wastes, the Hazardous and Solid Waste Amendments directed EPA to establish a three-phased schedule for the effective date of Land Disposal Restrictions and the promulgation of treatment standards by EPA. Land Disposal Restrictions and corresponding treatment standards for these scheduled wastes are set forth in 40CFR 268.33 through 268.35. For the "scheduled wastes" that were the hazardous waste component in mixed waste, EPA deferred issuing treatment standards until the issuance of the last phase (the Third Thirds Rule) on June 1, 1990. This rule established a national capacity variance for mixed wastes identified as hazardous because they contain a component that was a first third, second third, or third third scheduled hazardous waste. In addition to prohibiting disposal before appropriate treatment, Land Disposal Restrictions prohibit any storage of Land Disposal Restrictions-prohibited hazardous wastes (including mixed waste) except "for the purpose of the accumulation of such quanti- ties of hazardous waste as are necessary to facilitate proper recovery, treatment, or disposal" (40CFR268.50). EPA has determined that storage of hazardous waste pending development of treatment capacity does not constitute storage to accumulate sufficient quantities to facilitate proper recovery, treatment, or disposal. Underground Storage Tank Provisions. The requirements for the facilities that use tank systems for storing or treating hazardous waste are outlined in 40CFR 264, Subpart J. These requirements include the assessment of the existing tank system's integrity, the design and installation of new tank systems or components, and secondary containment. Hazardous wastes or treatment reagents are not placed in a tank system if they could cause the tank, its ancillary equipment, or the containment system to rupture, leak, corrode, or otherwise fail. Controls and practices to prevent spills and overflows from tank or containment systems are also required. Inspection requirements, procedures for response to leaks or spills, the disposition of leaking or unfit-for-use tanks, and closure and post-closure care requirements are also outlined in 40 CFR 264, Subpart J. Ignitable or reactive and incompatible hazardous wastes have special requirements. Resource Conservation and Recovery Act Corrective Action Program. Hazardous waste permits require sites to institute corrective action programs for investigating Solid Waste Management Units. This program applies to all operating, closed, or closing RCRA facilities. Federal Facility Compliance Act. The Federal Facility Compliance Act was passed in 1992 and includes provisions concerning DOE compliance with RCRA land disposal restrictions requirements for mixed waste. The Federal Facility Compliance Act requires DOE to have approved site-specific mixed waste treatment plans and related orders in place three years from the date of enactment in order to avoid the imposition of fines and penalties (except for sites already subject to a permit, agreement, or order addressing compliance with the RCRA land disposal restrictions storage prohibition). In an April 6, 1993, Federal Register notice (58FR17875), DOE published its schedule for submitting plans for treating mixed wastes for each facility at which DOE generates or stores mixed waste. DOE has published two interim versions of the plans required by the Federal Facility Compliance Act for each of its sites to facilitate discussions among states and other interested parties. DOE is working on the plans with the regulatory agencies and will continue to do so throughout the process. For mixed waste for which identified treatment technologies exist, the plans must provide a schedule for submitting permit applications, entering into contracts, initiating construction, conducting systems testing, starting operations, and processing mixed wastes. For mixed waste without an identified treatment technology, the plans must include a schedule for identifying and developing technologies, identifying the funding requirements for research and development, submitting treatability study exemptions, and submitting research and development permit applications. In cases where DOE proposes radionuclide separation, the plan must also provide an estimate of the volume of waste that would exist without such separation, and cost estimates and underlying assumptions. DOE sites will provide treatment plans in three phases during the development process: Conceptual plans were completed in October 1993 and draft plans in August 1994. Final proposed plans are due to be completed no later than February 1995. DOE will also prepare summary documents of the conceptual, draft, and final plans to provide a national picture of DOE's technology needs and possible options for treatment of its mixed waste. The summaries will be provided to all states and made available to other interested parties. Comprehensive Environmental Response, Compensation, and Liability Act. The Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended by the Superfund Amendments and Reauthorization Act (SARA) of 1986, provides liability, compensation, cleanup, and emergency response for hazardous substances (including radionuclides) released to the environment. The cleanup of inactive waste disposal sites is one of the major requirements of CERCLA. It provides for prioritization of cleanup actions (National Priorities List (NPL) or Superfund List), and directs that a Federal Facility Agreement be negotiated with EPA and the state to coordinate CERCLA and RCRA compliance activities in one comprehensive strategy for each Federal facility. CERCLA also requires public participation in the selection of remediation alternatives, and this involvement or participation usually addresses the requirements of CERCLA, RCRA and the National Environmental Policy Act (NEPA). Title III of CERCLA further requires that the National Response Center (operated by the U.S. Coast Guard) be notified in the event that a non-permitted release of a reportable quantity of hazardous substance or radionuclide occurs. In the case of such a release, the National Response Center alerts the appropriate Federal emergency personnel who assess the event, formulate response, and notify cognizant local emergency agencies. SARA requires industries to report the hazardous substances used at their facilities to include reporting inventories of these substances. National Contingency Plan. The National Contingency Plan is an implementation regulation that sets forth requirements necessary to comply with CERCLA and SARA. For every site that is targeted for remedial response action under Section 104 of CERCLA, the National Contingency Plan requires that a detailed Remedial Investigation/Feasibility Study be conducted. The Remedial Investigation emphasizes data collection and site characterization. Its purpose is to define the nature, extent, and significance of contamination at a site in order to evaluate, select, and design a cost-effective remedial action. The Feasibility Study emphasizes analysis of data and decision making; it uses results from the Remedial Investigation to develop response objectives and alternative remedial responses. These alternatives are then evaluated in terms of their engineering feasibility, public health protection, environmental impacts, and costs. The Remedial Investigation/Feasibility Study leads to a decision which sets forth the method selected for remedial action to clean up the National Priorities List site. Under the provisions of CERCLA, Federal facilities have the lead for CERCLA actions. Toxic Substances Control Act. TSCA was enacted in 1976 to ensure that the manufacture, sale, storage, and disposal of toxic chemical substances do not present an unreasonable risk of injury to health or the environment. Its applicability to DOE sites deals principally with the management and disposal of polychlorinated biphenyls (PCBs), asbestos, and dioxin. The problem created by radioactively contaminated PCBs, asbestos, and dioxin is that currently there is a limited capability to treat these materials. Although the concentrations of radionuclides are relatively low, approximately 2 million pounds of radioactively contaminated PCBs and PCB-contaminated material are destroyed annually by the K-1435 TSCA Incinerator at K-25 at Oak Ridge Reservation (ORR). Clean Air Act. The original Clean Air Act (CAA) was passed in 1955 and was wholly replaced by the Air Quality Act of 1967, although the name Clean Air Act is still used. It has been recently reauthorized. The CAA establishes air quality requirements and pollutant emission limits. The National Emissions Standards of Hazardous Air Pollutants (NESHAP) is a section of the CAA that sets air quality standards for air emissions such as radionuclides, benzene, beryllium, and asbestos. NESHAP regulations require the use of EPA-approved monitoring instrumentation, sampling methodology, calculations, and modeling for each Federal facility. Clean Water Act. The Federal Water Pollution Control Act (CWA), as amended by the Clean Water Act of 1977 (commonly referred to as Clean Water Act), establishes a Federal/state scheme for controlling the introduction of pollutants into the Nation's water. The CWA created the National Pollutant Discharge Elimination System (NPDES) program. This program regulates nonradiological effluent discharges to ensure that surface water bodies meet applicable water quality standards. Each discharge point (outfall) is permitted through the NPDES program. New NPDES permit regulations for storm-water discharges will require DOE to characterize surface runoff during rain events. Safe Drinking Water Act. The Safe Drinking Water Act (SDWA) was enacted in 1975 and is designed to protect drinking water resources. Primary drinking water standards set by the SDWA apply to drinking water "at the tap" as delivered by public water systems. Of equal significance is that drinking water standards are used to determine groundwater protec- tion regulations under a number of other statutes. The SDWA requires DOE to obtain permits and complete sample analyses and site inspections of public/industrial water supplies and sources of drinking water. It also imposes requirements on installation and maintenance of drinking water wells. Department of Energy Orders. The primary DOE orders governing waste management are as follows: DOE Order 5400.1, General Environmental Protection Program. Establishes environmental protection program requirements, authorities, and responsibilities for DOE operations for assuring compliance with applicable Federal, state, and local environmental protection laws and regulations, Executive orders, and internal department policies. Requires the preparation of waste minimization plans that describe how waste minimization activities will be promoted and implemented. DOE Order 5400.4, Comprehensive Environmental Response, Compensation and Liability Act Requirements. Establishes DOE's instructions for implementing CERCLA program and defines actions to identify and evaluate inactive waste sites at DOE installations. Directs the custodian to take action to improve control of substance migration from such sites. DOE Order 5480.3, Safety Requirements for the Packaging and Transportation of Hazardous Materials, Hazardous Substances, and Hazardous Wastes. Establishes the requirements for the packaging and transportation of hazardous materials, hazardous substances, and hazardous wastes. DOE Order 5820.2A, Radioactive Waste Management. Establishes policies and guidelines by which DOE manages its radioactive waste, waste by-products, and radioactively-contaminated surplus facilities. H.1.3 Waste Minimization and Pollution Prevention Waste minimization is the reduction, to the extent feasible, of radioactive and hazardous waste that is generated before treatment, storage, or disposal of the waste. Pollution prevention fully utilizes source reduction techniques in order to reduce risk to public health, safety, welfare, and the environment, and environmentally sound recycling to achieve these same goals. When planning for facilities to be constructed by 2010, it will be necessary to consider currently available technology while providing modular, flexible designs that can incorporate process improvements as they become available. In accordance with Executive Orders 12856, 12873, and DOE policy, the tritium supply and recycling facilities would be designed for waste minimization with an overall operating philosophy of pollution prevention. This waste minimization program will contribute to decreases in waste treatment, storage, and disposal costs and lower health risks to workers and the public. Technical approaches are being sought to optimize the number of production operations required, increase the use of nonhazardous chemicals and environmentally benign waste-producing chemicals, increase the use of recyclable chemicals and materials, and implement the new design or redesign of existing processes and products. Some criteria useful in determining successful technology include improved processing yield, reduced quantities of scrap, reduced waste and processing of by-products, reduced use of hazardous chemicals, positive return on investment, and continued product quality. H.1.4 Waste Treatment, Storage, and Disposal Treated waste is waste that, following generation, has been altered chemically or physically to reduce its toxicity or prepare it for storage or disposal. Waste treatment can include volume reduction activities, such as incineration or compaction, which may be performed on a waste prior to either storage or disposal or both. Stored waste is a waste that, following generation (and usually some treatment), is being (temporarily) retained in a retrievable manner and monitored pending disposal. Disposed waste is a waste that has been put in final emplacement to ensure its isolation from the environment, with no intention of retrieval. Deliberate action is required to regain access to the waste. Disposed wastes include materials placed in a geologic repository and buried in landfills. Waste that is staged for processing will be stored according to its characterization and form. The disposal of waste from the Complex will be managed by the DOE Office of the Assistant Secretary for Environmental Management (EM). A facility for disposal of retrievable and newly generated transuranic (TRU) waste near Carlsbad, NM, is planned. All surface facilities at the Waste Isolation Pilot Plant (WIPP) have been completed. To date, only underground excavations for the test phase have been done and the remaining excavation will be completed once the facility is operational. The original planned test phase has been abandoned and in its place an experimental program, at INEL, will be conducted to develop the technical data to support the permit application under 40 CFR 191 and 40 CFR 268. Once operational, WIPP would become a permanent disposal site. The total projected capacity of WIPP is 229,600 yd3, of which 9,260 yd3 can be remote- handled. Options for the interim storage of TRU waste will be evaluated in the EM PEIS. Yucca Mountain is a site being studied to determine its suitability for the disposal of commercial spent nuclear fuel and defense high-level waste (HLW). Since the availability of offsite disposal sites for HLW, TRU waste, mixed waste, and spent nuclear fuel is uncertain at this time, this PEIS has evaluated the storage of mixed waste and spent fuel within the Complex for the life of the facilities that generate the waste. No HLW or TRU waste will be generated as part of tritium supply and recycling. The remainder of this section discusses some of the treatment, storage, and disposal options that may be utilized with the various waste streams from Complex facilities. Gaseous Waste. Gaseous wastes can be nonhazardous (e.g., inert gases and air), hazardous (chlorinated hydrocarbon vapor, polyaromatic hydrocarbon vapor), or radioactive (e.g., tritium and xenon). Most hazardous gaseous wastes are combustible, and may be incinerated to destroy the hazardous constituents, converting the combustibles into carbon dioxide and water vapor, while capturing any particulates that may result. When a particulate (ash) is contaminated with heavy metals, the end product must be stabilized into an approved solid form suitable for disposal. Gaseous radioactive wastes are held for interim storage in tanks; adsorbed on surfaces in filters, molecular sieves, or active beds; refrigerated and liquefied or solidified; or reacted to an aqueous solution. A minimal quantity of radioactive gas below the permitted limits will escape into the atmosphere because it is not possible to retain every atom of gas within the process with today's technology. The expected release of radioactive gases is listed in the project descriptions in appendix section A.2. Gaseous waste may be oxidized, mixed with other liquid wastes, or solidified in a stable form for long-term disposal. Reactive gases such as tritium are captured on reactive beds, in molecular sieves, or in cryogenic traps for recycling back to the process. Inert radioactive gases such as xenon and argon can be separated by cryogenic capture and held in storage tanks until they decay sufficiently to permit release. Gases that decay to metals can be captured on activated charcoal beds and held until they can be stabilized, packaged, and disposed of as solid waste. When sufficiently decayed, gases may be released to the atmosphere. Liquid Waste. Liquid radioactive wastes are processed according to their chemical nature and radiological sources and activities. Liquid wastes that meet release criteria in applicable regulations can be released at permitted discharge points. Where conditions permit, liquids can be processed and recycled to replace virgin feedstocks. Waste process- ing removes the hazardous or radioactive contaminants from the releasable or recyclable liquids. The largest volume of liquid radioactive waste is LLW, typically in aqueous solution from process operations. Some of this waste is contaminated with hazardous compounds such as solvents or resins and the result is a liquid mixed waste. Liquid HLW or TRU waste will not be generated in tritium supply and recycling facilities, but will be part of the reference conditions at candidate sites where spent fuel or target processing was conducted. This includes wastes containing TRU, as from the extraction of plutonium. The desired final waste form for liquid wastes is a stable solid that is resistant to stresses from heat generation and from internal and external physical loads. The form must remain stable while stored and not allow the radioactive constituents to migrate to the surroundings. Mixed waste will often have combustible constituents. These are most readily decomposed in thermal treatment (incineration) or chemical reaction resulting in the creation of an ash. The resulting material will be granular and suitable for stabilization in a cemented form in which the hazardous constituents (radionuclides and heavy metal compounds) are bound in compounds which have an affinity for heavy metals and radionuclides. These processes have been utilized in various forms, and their retention properties have been credibly demonstrated. Liquid LLW is normally processed to reclaim or remove the excess water, leaving a saturated salt solution. This can be accomplished by clarification processes normal to water treatment, or by evaporation. This usually results in the greatest volume reduction for liquid waste. The subsequent stabilization and solidification of the concentrated solution results in a waste form that will not leach its active constituents for a time sufficient to allow the radioactive constituents to decay. A method for stabilizing HLW for disposal is to process it into borosilicate glass cast within stainless steel cylinders. These are shock-resistant, elastic forms suitable for permanent disposal in an engineered repository. They also provide excellent retention during long-term interim storage. In the preferred practice, the liquid waste stored in large tanks is pumped directly into the vitrification process where the liquid is evaporated and the remaining salt is fused with borosilicate into the glass waste form. In some processes (i.e., at INEL's Idaho Chemical Processing Plant), the waste is evaporated to calcine which is stored in a granular form for later processing. The disadvantage of this process is that airborne particulate matter is generated when the product is handled. The advantage is that the calcine can be stored safely in a stable form until it can be vitrified. Liquid radioactive and hazardous wastes are usually stored in tanks where they are staged for further processing. Processes are employed to concentrate the hazardous constituents. These processes result in very significant volume reductions, with the reclaimed water processed to a purity sufficient for permitted discharge or recycle. Liquid hazardous waste concentrates may contain combustive hydrocarbons and/or heavy metal contaminants. These can be treated by incineration to produce a dry waste. If this waste is still hazardous after treatment, it can then be processed into a stabilized solid that will not leach its hazardous constituents while in storage or in a repository. Liquid low-level and noncombustible hazardous waste can also be processed into a stabilized solid form for storage and disposal. Solid Waste. Solid radioactive wastes typically consist of contaminated materials (e.g., filters, clothing, storage vessels, cleaning materials, and tools) that have been used in or contaminated by nuclear materials processing. The term is also applied to those stabilized forms resulting from gaseous or liquid waste processing. In solid waste handling, forms and materials are segregated, combustibles are incinerated, and the resultant materials are reduced in volume, stabilized if necessary, and packaged in specified containers for storage or disposal. HLW is stored at two of the sites considered for tritium supply and recycling. It is stored as calcine granules at Idaho National Engineering Laboratory (INEL) in underground vaults and in tanks as liquid at Savannah River Site (SRS). It will be processed to a glass/ceramic (INEL) and borosilicate glass (SRS), stored in an engineered facility onsite, and eventually shipped to a Federal repository. Dry LLW that consists of protective clothing, containers, process materials, and equipment is stored in specified containers designed to retain the waste constituents for a time sufficient to permit decay of the radioactive constituents. Solid hazardous wastes may contain combustible hydrocarbon compounds or mixtures with heavy metal contamination. These wastes are often treated by incineration and disposed of in a landfill if the ash is nonhazardous. If the ash contains heavy metals it can be stabilized with cement and binders and disposed of in a RCRA-permitted facility. Wastes that retain their hazardous constituents after processing must be packaged into forms that will retain the hazardous constituents safely within the waste form. For LLW or hazardous waste that results from liquid waste processing or incineration, the accepted form is a cemented solid. Some mixed waste can be processed to remove its hazardous constituents and be disposed of as LLW. Otherwise, it can be processed into stabilized forms and packaged for retrievable storage in an engineered facility until a licensed facility is available for permanent disposal. Solid nonhazardous wastes from process wastewater evaporation ponds or from sanitary waste treatment plants are usually deposited as sludge in a landfill. Spent Nuclear Fuel. As described in each of the technology descriptions in appendix section A.2, spent nuclear fuel from the reactor-based tritium supply alternatives will be stored within the tritium supply facility. The fuel will be kept in water-cooled storage until its decay heat has decreased sufficiently to permit dry storage. Several commercially available options for dry storage have been licensed by the NRC, and the facilities required will be relatively small, utilizing a small percentage of the land area required for the tritium supply plant. Spent nuclear fuel will not be reprocessed but will eventually be placed in a Federal repository. Spent nuclear fuel is considered a resource, not categorized with nuclear waste, and thus is not included in waste inventories. Since it is radioactive material that must be stored, managed and handled, it is included here for each site to provide baseline information on its impact on land and facility use. H.1.5 Transportation DOE complies with applicable Department of Transportation (DOT) regulations (10 CFR 71 and 49CFR) when shipping hazardous materials over public roads. Transportation, especially for radioactive material, is highly regulated by Federal, state, and local laws. The stringent packaging requirements, combined with strict regulations and procedures governing the shipment of hazardous and radioactive material, ensure that transport is a safe activity. Federal DOT regulations require the use of appropriate warning placards on vehicles and labels on packages to alert workers, officials, and the public to the hazardous nature of the shipped material. The use of placards on vehicles and warning labels on packages is a joint responsibility of the carrier and the shipper. The labels and placards are familiar to emergency response personnel and are valuable in determining content and hazard information. Shipments of hazardous materials, including radioactive materials, must be accompanied by properly completed shipping papers such as bills of lading and cargo manifests, which contain detailed information on the material being transported. These papers must be kept in the vehicle transporting the material and must be available for inspection by responsible officials at any time. The shipper must certify on the shipping papers that the hazardous material offered for transportation is properly classified, packaged, marked, labeled, and made ready for transportation according to all DOT regulations. Radioactive material is shipped in secure packages. Type A packages contain small amounts of radioactive material and are designed to withstand normal conditions of transport. Type A packages are subjected to rigorous water spray, free-fall compression, and penetration tests carried out in sequence to ensure that radioactive materials are contained. Type B packaging is designed to contain more hazardous, and larger amounts of, radioactive waste. It can withstand severe accident conditions and contain radioactive materials under any credible circumstance. All DOE sites under consideration for the tritium supply and recycling facilities except Pantex either have or have planned an onsite LLW disposal facility. For the purposes of analysis in this PEIS, it is assumed that all LLW to be generated at Pantex would be shipped to NTS per current practice. As shown in table H.1.5-1, data from the DOE Inte- grated Database Program was used to calculate LLW disposal land usage factors from 1990 to 1993 for INEL, NTS, and SRS. To determine a usage factor in the waste management impact analysis, an average value was calculated and then rounded down to the nearest hundred cubic yard. Therefore, the following disposal land usage factors were used for the impact assessments: 3,300 yd3 per acre (INEL), 3,200 yd3 per acre (NTS), and 4,500 yd3 per acre (SRS). For the proposed Class II LLW disposal facility at ORR, a 1,700 yd3 per acre usage factor was assumed (OR DOE 1995e). The additional shipments of LLW from Pantex as a result of locating tritium supply and recycling functions at Pantex were estimated. All LLW would be transported in a solid form. A typical shipment consists of eighty 55-gallon (208-liter) drums loaded into an enclosed semi-trailer type truck. Each drum is assumed to be fully loaded, resulting in a total shipment volume of 21.7 yd3. The truck is assumed to operate as an "exclusive-use" vehicle. The risks associated with these additional shipments are discussed in section 4.7 and appendixG. Table H.1.5-1.-Low-Level Waste Disposal Land Usage Factors Site Total Estimated Land Cumulative Area Usage Volume Utilized Factor (yd3) (acres) (yd3/acre) 1993 INEL 192,379 79.8 2,411 NTS 599,610 430.4 1,393 SRS 870,099 167.8 5,185 1992 INEL 191,353 52.4 3,652 NTS 575,106 135.9 4,232 SRS 849,775 193.2 4,398 1991 INEL 190,045 52.4 3,627 NTS 548,816 135.9 4,038 SRS 832,772 193.2 4,310 1990 INEL 188,345 52.4 3,594 NTS 534,167 a SRS 801,512 INEL NA NA 3,321 NTS NA NA 3,221 SRS NA NA 4,598 H.1.6 Facility Transition Management Any transition activities of facilities from a production mode to a cleanup mode that are part of the baseline for this PEIS are discussed in the facility impacts section of chapter 4 and in section H.2 of this appendix. Decontamination and decommissioning (D&D) considerations of Complex facilities will be planned for in the design. Existing Facilities. The DOE Office of the Assistant Secretary for Defense Programs (DP) is responsible for the safe operation, shutdown, and ultimate disposition of facilities used to support the nuclear weapons program. EM is responsible for final facility disposition, which may include decontamination and decommissioning of inactive facilities or refurbishing them for further economic development. Transition activities will require appropriate NEPA evaluation and will proceed consistent with the PEISs within EM and DP. Depending on the site, facility transition activities are in different stages of planning. The dominant time-intensive activities are building characterizations of the environmental hazards related to the building and the deactivation of the facility. Complex Facilities. At the end of their useful life, all potential facilities would require decommissioning. The transition process begins when DOE management decides to no longer operate the production facility and ends when responsibility for the facility is formally turned over to EM. Transition plans will be required for all facility transfers to EM. These plans define the actions necessary to bring the identified facilities into a condition acceptable for transfer to EM. Some facility transition issues raised in EM's scoping process for its PEIS which would be considered in the facilities design process are: Land use criteria defined for the period after cleanup. Interim storage of mixed waste and spent nuclear fuel. Disposal facilities for hazardous waste and LLW. The cleanup of Complex facilities will be significantly less difficult because consideration for waste minimization and ease of decontamination will be included in the facility design. The Complex will be significantly smaller, consume less material, and generate far less contamination during process operations. The elimination of spent fuel processing and plutonium production would greatly reduce waste and contamination volumes. Large storage facilities will not be necessary for liquid radioactive wastes. The surfaces that come in contact with potential contaminants will be easier to decontaminate. In-process decontamination (to reduce operational exposures) will significantly reduce the cleanup required at the end of life. In spite of the best design and process practices, many of the Complex facilities will require decontamination efforts at the end of life. Because of the necessity of working inside contaminated areas during the cleanup phase, the potential for exposure to cleanup workers is higher than during the operations phase. Workers would wear protective clothing and would be supplied breathing air to minimize their exposure. Technologies for cleanup are established and are improving as the experience in working with nuclear facilities increases. The use of robotics, improved task planning, and new materials to prevent the spread of contamination has already improved current cleanup activities. By the time the Complex facilities are decommissioned, DOE will have gained 40 more years of cleanup experience; thus, further improvements should be expected. H.2 Waste Management Activities H.2.1 Idaho National Engineering Laboratory The activities associated with the development of reactor technology and the extraction of useful nuclear materials at INEL have produced radioactive, mixed, and hazardous wastes that are treated, stored, or disposed of onsite. The ROD from the Programmatic Spent Nuclear Fuel and INEL Environmental Restoration and Waste Management Programs EIS published in the Federal Register (60 CFR 28680) on June 1, 1995, addresses cleaning up existing waste units and bringing operations into compliance with current applicable regulations. It deals with the current conditions, waste management, plans for remediation, and the development and funding of processes to minimize waste generation and to develop a process to dispose of future waste generation. Pollution Prevention. The Idaho Operations Office has an active Waste Minimization and Pollution Prevention program to reduce the total amount of waste generated and disposed of at INEL. This is accomplished by eliminating waste through source reduction or material substitution, by recycling potential waste materials that cannot be minimized or eliminated, and by treating all waste that is generated to reduce its volume, toxicity, or mobility prior to storage or disposal. The Idaho Operations Office published its first waste minimization plan in 1990 which defined specific goals, methodology, responsi- bility, and achievements of programs and organizations. The achievements and progress have since been updated at least annually. Spent Nuclear Fuel. The inventory of spent nuclear fuel is cited here in metric tons of heavy metal based on current sources. One hundred and seventy-seven metric tons of spent nuclear fuel are in storage at the Idaho Chemical Processing Plant and 124 metric tons are stored at the Test Area North. Spent nuclear fuel is stored in facilities designed for a specific fuel type; therefore, storage capacities are not additive for the site. There are 11.6 metric tons of graphite reactor fuel, 10 metric tons of naval reactor fuel, and 279metric tons of commercial and research reactor fuels in the inventory (DOE 1993r:b-2). Continued receipt of naval reactor and Ft. St. Vrain gas-cooled reactor fuel would add to this inventory. Spent nuclear fuel is stored at the Power Burst Facility, Test Reactor Area, Test Area North, Idaho Chemical Processing Plant, Argonne National Laboratory-West, and the Naval Reactor Facility. Naval Reactor Facility and Test Reactor Area fuel will be sent to the Idaho Chemical Processing Plant for storage. The Test Area North fuel pool is nearing its design life expectancy. The Three Mile Island core debris stored there will be repackaged and placed in dry storage. Alternatives are being considered to repackage fuel elements and provide long-term storage at INEL until a Federal repository (Yucca Mountain, NV) is ready to receive them. The receipt of additional fuel elements is also being considered. The treatment of spent nuclear fuel for long-term storage and disposal is expected to continue at INEL for the next 40 years. Existing rulings designate spent nuclear fuel as a recoverable resource, and as such, waste regulations for treatment, storage, and disposal do not apply. There are no plans to dispose of spent nuclear fuel at INEL (DOE 1994e:2-8). Figure H.2.1-1 illustrates spent nuclear fuel management at INEL. The inventories and current plans for the treatment and storage of spent nuclear fuel are discussed in 60 FR 28680. High-Level Waste. HLW has been generated in the reprocessing of spent nuclear fuel at the Idaho Chemical Processing Plant. Most of this fuel was from the naval reactors program. The liquid HLW is concentrated by evaporation and converted by calcination in a fluidized bed to metallic oxides which are stored in a stable granular solid form. This waste form is stored in stainless steel bins in concrete vaults, where it can be held long enough that the short half-life isotopes have decayed and its activity reduced. This waste form is a mixed HLW because of the toxic metals it contains. Liquid HLW in acidic solution is stored in stainless steel tanks that may not meet all seismic regulations and do not have a secondary containment system that is acid resistant. The Idaho Operations Office entered into a Consent Order in April 1992 to resolve secondary containment issues. This Consent Order requires continued calcination, thus reducing waste volume and resulting in a material that is much easier to handle and store. The calcine, however, does not meet RCRA treatment standards for land disposal. Options for treatment of this waste are under study, and a facility is proposed where this waste will be prepared for disposal (IN DOE 1994a:5-6). The HLW inventory and treatment and storage facilities at INEL are listed in tables H.2.1-1, H.2.1-2, and H.2.1-3. Figure H.2.1-2 illustrates HLW management at INEL. Transuranic Waste. TRU and mixed TRU wastes are stored at the Radioactive Waste Management Complex. Prior to 1970, when the Atomic Energy Commission determined that TRU wastes required segregation from other wastes, TRU wastes were buried in earthen trenches. Since that time, TRU wastes have been categorized as contact-handled and remote-handled, and packaged and stored for ultimate retrieval and transport to an offsite repository at WIPP. INEL contains more than 50 percent of DOE's TRU wastes. The majority of TRU wastes at INEL were shipped from other sites, particularly Rocky Flats Plant (now known as the Rocky Flats Environmental Technology Site), but this practice was stopped in 1989. The receipt of TRU waste at INEL for treatment is being considered on a case-by-case basis. The existing treatment facilities for TRU wastes are limited to testing, characterization, and repackaging. The Idaho Waste Processing Facility, now in the planning phase, will process TRU wastes and either reclassify it (if it is found to be LLW) for disposal onsite, or prepare it so that it meets the WIPP Waste Acceptance Criteria. The use of commercial treatment facilities is also being considered. Approximately 60 percent of the TRU waste will require reprocessing. Volume reduction and the destruction of hazardous constituents in the mixed TRU wastes are being studied. Some of the TRU wastes have radioactivity levels high enough to require remote handling. No certified or licensed transportation capabilities exist for this waste, so this is another matter under study. TRU wastes are being stored onsite pending the outcome of the WIPP program. Assuming WIPP is determined to be a suitable repository for these wastes, pursuant to the requirements of 40 CFR 191 and 40 CFR 268, these wastes will be transported there for disposal. If WIPP proves not suitable for a repository, then INEL would develop the treatment processes necessary to meet the criteria of the selected repository. Tables H.2.1-4, H.2.1-5, and H.2.1-6 list the TRU and mixed TRU waste inventory, and treatment and storage facilities at INEL. Figure H.2.1-3 illustrates TRU waste management at INEL. INEL is not expecting to generate or receive mixed TRU wastes in the next 5 years. Some TRU wastes at INEL will never meet WIPP waste acceptance criteria, and therefore cannot be sent to WIPP. Other options will have to be developed for these wastes. Approximately one-half of the TRU wastes are expected to be reclassified as alpha-contaminated LLW in the future. These wastes do not meet INEL waste acceptance criteria for LLW, and therefore will be managed as TRU waste until they can be repackaged to contain the alpha-type contamination to permit disposal as LLW. Low-Level Waste. LLW is generated in various forms at INEL facilities. This waste is disposed of at the Radioactive Waste Management Complex. Most of this waste is processed before disposal by incineration, compaction, or sizing to reduce volume and to stabilize the waste to the extent possible (the incinerator, which was shut down for modifications, is in startup and is expected to resume operations in 1996). Some LLW does not meet criteria for onsite disposal. This waste is stored temporarily until treatment and disposal options are developed. Liquid LLW is either evaporated and processed to calcine, or solidified and disposed of. The volume of LLW disposed of at INEL's Radioactive Waste Management Complex is 189,660 yd3. As of 1991, the facility had a capacity for 235,345 yd3, with an additional 88,000 yd3 of expansion capacity available. Figure H.2.1-5 illustrates LLW management at INEL. Mixed Low-Level Waste. Mixed LLW is generated in small quantities at INEL and is stored in several areas onsite (Argonne National Laboratory-West, Idaho Chemical Processing Plant, Special Power Excursion Reactors Test). Although its volume is small, it poses significant disposal problems because it is difficult to treat and cannot be disposed of until adequate treatment is developed. In the future, the Waste Experimental Reduction Facility incinerator at the Power Burst Facility will process mixed low-level (organic) wastes. Argonne National Laboratory-West plans to complete a multipurpose waste management facility by 1996 which will include provisions for mixed waste. Additional facilities planned for operation by the year 2000 at other INEL locations will be able to treat mixed waste and render it acceptable for disposal. Figure H.2.1-5 illustrates mixed waste management at INEL. Although mixed wastes generated from past operations in liquid and solid form are stored in many locations at INEL, the bulk of that volume is solid waste stored at the Radioactive Waste Management Complex. Its volume is approximately 60 percent of the TRU waste volume also stored there and is 11percent of the total volume of waste stored or disposed of at that facility. INEL has listed 34 facilities where mixed wastes are or will be treated to remove, destroy, or stabilize their hazardous constituents in the future, and prepare them for permitted disposal (INEL 1993a:5). The inventory of mixed LLW and its treatment and storage facilities at INEL are listed in tables H.2.1-7, H.2.1-8, and H.2.1-9. Hazardous Waste. Hazardous waste is staged in a RCRA-permitted building at the Central Facilities Area prior to shipment to an offsite commercial RCRA-permitted facility. The Hazardous Waste Storage Facility is nearing capacity since hazardous waste shipments to offsite permitted facilities have been temporarily suspended pending completion of a review by DOE. However, shipments are expected to be resumed in the near future. The INEL waste minimization program is expected to significantly reduce the quantities of hazardous wastes generated at INEL over the next 5 years. By that time, the use of nonhaz- ardous chemicals and the recycle of those that cannot be substituted, should nearly eliminate the generation of hazardous waste. Nonhazardous Waste. Nonhazardous wastes are processed at each facility on the INEL site. A nonhazardous industrial commercial waste landfill is located at the Central Facilities Area. Wastes are segregated into sanitary, industrial, and asbestos wastes before being placed in the landfill. Increased recycling is expected to reduce nonhazardous waste generation by 50 percent by 1997. In the future, sanitary wastes may be sent offsite for disposal in a permitted facility, while industrial and asbestos wastes will continue to be disposed of at INEL. A new multipurpose facility is planned to be in operation at Argonne National Laboratory-West by 1996 to collect, monitor, and consolidate Argonne National Laboratory-West nonhazardous wastes before shipment to the Central Facilities Area. Figure (Page H-14) Figure H.2.1-1.-Spent Nuclear Fuel Management at Idaho National Engineering Laboratory. Figure (Page H-15) Figure H.2.1-2.-High-Level Waste Management at Idaho National Engineering Laboratory. Figure (Page H-16) Figure H.2.1-3.-Transuranic Waste Management at Idaho National Engineering Laboratory. Figure (Page H-17) Figure H.2.1-4.-Low-Level Waste Management at Idaho National Engineering Laboratory. Figure (Page H-18) Figure H.2.1-5.-Mixed Waste Management at Idaho National Engineering Laboratory. Table H.2.1-1.-High-Level Waste at Idaho National Engineering Laboratory Waste Matrix Number of Inventory as of Number of Waste Streams Total Generation Inventory Waste Streams August 31, 1994 Five-Year Projection Five-Year Projection (yd3) (yd3) Remote-handled Aqueous liquids/slurries 1 9,040 1 3,519 (1,830,000 gal) (711,000 gal) Inorganic process residues 1 4,860 1 829 (calcined solids) Total 2 13,900 2 4,350 Source: DOE 1993b; IN DOE 1994a. Table H.2.1-2.-High-Level Waste Treatment Capability at Idaho National Engineering Laboratory Treatment Unit Treatment Method Input Output Capability Total Comment Capability Capacity (yd3/yr) HEPA Filter Leach Chemical extraction HLW remote-handled - Concentrated liquid HLW 15 Under repair. Final Facility alpha, inorganic debris (to calcine), (2,990 GPY) RCRA 1990, interim LLW solid NESHAP 1999 Idaho Chemical Water washing, CO2 HLW remote-handled - HLW-RH - solid HLW- 297 Operational 1993 Processing decontamination debris remote-handled, Plant Decontamination LLW liquids Facility Idaho Waste Vitrification HLW remote-handled - HLW-RH - solid, 3,960 Unapproved, planned Immobilization Facility calcine solids stabilized New Waste Calcining Evaporation HLW remote-handled - HLW-RH - aqueous 183,329 Available 2000 interim Facility Evaporator aqueous liquids liquids (37,032,515 GPY) RCRA 1990 Table H.2.1-3.-High-Level Waste Storage at Idaho National Engineering Laboratory Storage Unit Input Capability Total Capacity Comment Facility aqueous liquid, toxic (yd3) (1,348,030 GPY) Idaho Chemical Processing Plant Tank Farm HLW remote-handled - liquid, corrosive, toxic, listed 17,500 In operation; interim RCRA 1990; to be closed (3,530,000 gal) New Waste Calcine Facility Tanks HLW remote-handled - liquid, corrosive, toxic, listed 337 In operation; staging tanks for calcined feed; (68,074 gal) interim RCRA 1990 Calcine Solid Storage Facility HLW remote-handled - solid, toxic, listed (calcine) 9,305 In operation; State final permit 1992; RCRA Part B submitted 1994. Permit applications Calcination organic, metals for new storage bins (#8 and #9) to be w/mercury submitted. FAST Reactor and New Waste Calcine Facility HLW remote-handled - solid, toxic 217 In operation; RCRA Part B submitted 1993 HEPA Filter Storage Facilities Table H.2.1-4.-Mixed Transuranic Waste at Idaho National Engineering Laboratory Waste Matrix Number of Inventory as of Number of Waste Streams Total Generation Waste Streams August 31, 1994 Five-Year Projection Five-Year Projection (yd3) (yd3) Contact-Handled Inorganic process residues 31 8,511 0 0 Contaminated soils/debris 1 50 0 0 Contaminated debris 10 1,611 0 0 Contaminated metal debris 6 9,839 0 0 Inorganic, non-metal debris 5 719 0 0 Combustible debris 10 728 0 0 Heterogeneous debris 25 17,699 0 Unknown solids 9 11,502 0 0 Uncategorized/unknown 3 Inorganic process residue 2 15 0 0 Contaminated debris 1 7 0 0 Heterogeneous debris 2 29 1 44 Unknown solid 3 9 0 0 Total 108 51,205 1 44 Source: DOE 1994k. Table H.2.1-5.-Transuranic and Mixed Transuranic Waste Treatment Capability at Idaho National Engineering Laboratory Treatment Unit Treatment Method Input Capability Output Capability Total Capacity Comment (yd3/yr) Idaho Chemical Processing Water washing HLW, TRU, LLW, mixed HLW, TRU, LLW, mixed 149 Operational Plant LLW, alpha LLW - HEPA filter leach HLW, TRU, LLW, Mixed HLW, TRU, LLW, Mixed 15 Existing, plan to use LLW LLW Idaho Waste Processing Amalgamate, decontaminate, TRU, Mixed TRU, LLW, Mixed TRU, LLW 15,810 Unapproved, planned Facility incinerate, encapsulate, mixed LLW, alpha, liquid, size, stabilize, desorb, and solid vitrify Liquid Effluent Treatment Fractionate, evaporate TRU, LLW, mixed LLW, TRU, LLW 14,376 Operational; RCRA final and Disposal alpha (2,903,420 GPY) 1990; NESHAP final and State PSD 1988 New Waste Calcining Calcify HLW, TRU, LLW, mixed HLW, TRU, LLW, mixed 6,556 Operational; RCRA interim Facility LLW, alpha, liquid LLW (1,324,250 GPY) 1990 Remote Mixed Waste Melt, drain, evaporate TRU, LLW, alpha TRU, LLW 37 Unapproved, planned Treatment Waste Characterization Characterize, stabilize, Alpha mixed TRU, mixed Mixed TRU, 392 Planned, approved, available and Storage Facility amalgamate, neutralize, LLW, liquid, and solid mixed LLW, LLW 1999 adsorb Waste Immobilization Vitrify or stabilize in ceramic HLW, TRU, LLW, mixed HLW, TRU, LLW 3,960 Planned, unapproved Facility LLW, alpha Table H.2.1-6.-Transuranic and Mixed Transuranic Waste Storage at Idaho National Engineering Laboratory Storage Unit Input Capability Total Capacity Comment (yd3) Argonne National Laboratory-West Sodium Storage Mixed TRU solid 25 RCRA Part B submitted 1994 Argonne National Laboratory-West Scrap Mixed TRU solid 252 RCRA Part B submitted 1994 Idaho Chemical Processing Plant HEPA Filters Mixed TRU solid 185 RCRA Part B submitted 1993 Radioactive Waste Management Complex TSA-3 Mixed TRU solid 141 Partial Closure, RCRA Part B submitted 1994 Radioactive Waste Management Complex Waste Storage Mixed TRU solid 147,019 RCRA Part B submitted 1991 Radioactive Waste Management Complex Intermediate-level TRU Storage Mixed TRU solid 131 RCRA Part B submitted 1991 TSA-RE Retrieval Modification Facility Mixed TRU solid 122,179 RCRA Part B submitted 1994 Table H.2.1-7.-Mixed Low-Level Waste Streams at Idaho National Engineering Laboratory Waste Matrix Number of Inventory as of Number of Waste Streams Total Generation Waste Streams August 31, 1994 Five-Year Projection Five-Year Projection (yd3) (yd3) Contact-handled Aqueous liquids 12 156 5 10 (31,500 gal) Organic liquids 17 40 3 5 (8,080 gal) Inorganic process residues 39 4,615 8 117 Organic process residues 3 <1 1 3 Contaminated soils/debris 6 286 1 8 Contaminated debris 11 1,990 1 8 Contaminated metal debris 12 9,353 2 16 Inorganic non-metal debris 6 459 0 0 Combustible debris 13 934 3 8 Heterogeneous debris 33 10,183 10 183 Labpacks 8 6 1 1 Reactive metals 1 <1 0 0 Elemental lead 5 544 4 62 Unknown solids 6 4,191 1 8 Uncategorized/unknown 2 397 0 0 Cement forms 0 0 1 4 Remote-handled Inorganic process residue 1 1 0 0 Contaminated debris 1 1 0 0 Heterogeneous debris 2 101 1 2,616 Reactive metals 1 1 0 0 Elemental lead 1 71 1 165 Total 180 33,327 45 3,215 Source: DOE 1994k. Table H.2.1-8.-Mixed Low-Level Waste and Low-Level Waste Treatment Capability at Idaho National Engineering Laboratory [Page 1 of 2] Treatment Unit Treatment Method Input Capability Output Capability Total Capacity Comment (yd3/yr) HEPA Filter Leach Acid leach HLW, TRU, mixed LLW solid to RWMC, 15 Under modification; RCRA (CPP-659) LLW-contact-handled, concentrated liquid to tank final 1990; interim -remote-handled, farm, nonhazardous to NESHAP to 1999 alpha, solid, debris sanitary landfill Idaho Chemical Processing Water wash, CO2, HLW, TRU, mixed Mixed LLW, HLW, TRU 297 Water wash operational, CO2 Plant Debris Treatment abrasion LLW-contact-handled, solid, liquid planned, available 1994 and Containment -remote-handled alpha, solid, debris Idaho Waste Processing Amalgamation, incineration, Mixed TRU, mixed Mixed TRU, mixed LLW, 20,677 Unapproved, planned Facility macroencapsulation, LLW, contact-handled, LLW solid sizing, stabilization, remote-handled thermal desorption alpha INEL Waste Treatment, Absorption, neutralization, Mixed LLW-contact- Mixed LLW, LLW Planned Operational 40 CFR 262.34 solidification handled, aqueous liquid, solid, debris Liquid Effluent Fractionation, Mixed LLW-contact- Mixed LLW-contact- 15,993 Operational; RCRA final Treatment and Disposal evaporation handled, remote-handled handled, remote-handled (3,230,569 GPY) 1990; NESHAP final and liquid liquid to acid recycle for State PSD 1988 (PEW evaporator) NWCF, or tank farm Mixed LLW Treatment Amalgamation, Mixed LLW-contact- Mixed LLW-contact-handled 525 Approved, planned Facility decontamination, handled liquid, solid incineration macroencapsulation, neutralization, precipitation, sizing, stabilization New Waste Calcining Calcification Mixed LLW, HLW, HLW-remote-handled solid 6,560 Operational; RCRA interim Facility (CPP 659) mixed TRU-remote- (1,320,000 GPY) 1990 handled liquid Portable Water Treatment Adsorption, filtration, Mixed LLW-contact- Mixed LLW 2,860 Operational; interim RCRA System neutralization handled, aqueous (577,000 GPY) 1990; renewal 1995 liquid Radioactive Sodium Waste Steam oxidation Mixed LLW- Mixed LLW-contact- 911 Existing, needs modification Processing Facility contact-handled handled, decontaminated sodium Remote Mixed Waste Melt, drain, evaporate Mixed LLW-remote-handled, Mixed LLW, remote- 37 Unapproved, planned Treatment alpha handled, alpha Test Area North 726A Ion exchange Mixed LLW-contact- LLW, mixed LLW, 249 Operational Treatment Unit handled, aqueous liquid nonhazardous liquid (50,200 GPY) Tan Cask Dismantlement Disassembly, recovery Mixed LLW- Mixed LLW-contact-handled 16 Operational contact-handled Waste Characterization Neutralization, stabilization, Mixed LLW, MTRU, Mixed LLW, mixed TRU, Planned Planned, approved Facility amalgamation, adsorption liquid, solid certified, pre-treated repackaged Waste Engineering Amalgamation Mixed LLW- LLW solid 0.04 Planned, approved Development Facility contact-handled, solid Waste Engineering Debris sizing Mixed LLW, LLW-contact- Mixed LLW, LLW solid 44 Planned, approved Development Facility handled, solid Waste Engineering Neutralization Mixed LLW- LLW 3 Planned, approved Development Facility contact-handled Waste Engineering Stabilization Mixed LLW- LLW 110 Existing, plan to use Development Facility contact-handled 2,407 solid Waste Experimental Incineration, stabilization, Mixed LLW-contact- LLW, mixed LLW solid to Input 64,910 Operational; interim Reduction Facility macroencapsulation handled, liquid, RWMC (stabilized solids (13,111,719 GPY); output NESHAP 1987, 1992; solid and grout) 309 grout and 3,617 RCRA interim 1987, 1992; stabilized solids to RWMC State final 1992 Table H.2.1-9.-Low-Level Waste and Mixed Low-Level Waste Storage at Idaho National Engineering Laboratory Storage Unit Input Capability Total Capacity Comment Vitrification or ceramic LLW solid (yd3) Argonne National Laboratory-West Sodium Storage Mixed LLW-TRU 421 RCRA Part B submitted 1994 Argonne National Laboratory-West Scrap Storage Mixed LLW-TRU 252 RCRA Part B submitted 1994 Idaho Chemical Processing Plant Fast HEPA Filter Mixed LLW 33 RCRA Part B submitted 1993 Storage Idaho Chemical Processing Plant CPP-1619 Storage Mixed LLW 59 RCRA Part B to be submitted 1995 Idaho Chemical Processing Plant CPP-1617 Staging Mixed LLW 667 RCRA Part B to be submitted 1995 Idaho Chemical Processing Plant New Waste Calcining Mixed LLW, TRU 184 RCRA Part B submitted 1993 Facility HEPA Filter Storage Power Burst Facility Waste Engineering Development Mixed LLW 5 RCRA Part B to be submitted 1995 Facility Storage Power Burst Facility MLLW Storage Mixed LLW 59 RCRA Part B submitted 1993 Power Burst Facility Waste Engineering Development Mixed LLW 594 RCRA Part B to be submitted 1995 Facility Containment Portable Storage at SPERT IV Mixed LLW 310 RCRA Part B submitted 1993 Power Burst Facility Waste Experimental Reduction Mixed LLW 361 RCRA Part B submitted 1993 Facility Storage Radioactive Waste Management Complex Mixed LLW, alpha LLW, TRU 147,019 RCRA Part B submitted 1990, Interim TRU Modules TSCA 1992 Radioactive Waste Management Complex Mixed LLW, alpha LLW, TRU 131 RCRA Part B submitted 1991 Intermediate-level Storage Radioactive Waste Management Complex Alpha LLW, TRU 122,000 RCRA Part B submitted 1994 TSA-RE Retrieval Modification Facility Test Area North 647 Waste Storage Mixed LLW 136 RCRA Part B to be submitted 1995 Test Area North 628 SMC Container Storage Mixed LLW 164 RCRA Part B submitted 1993 H.2.2 Nevada Test Site Radioactive and hazardous materials have been extracted and analyzed after underground tests. These activities have resulted in the accumulation of low-level, hazardous, and mixed wastes which must be treated, stored, and disposed. No reactors or reprocessing facilities have operated at NTS. No inventory of spent fuel or HLW has been created, shipped to, or stored at NTS. The Environmental Restoration and Waste Management Site Specific Plan Fiscal Years 1994-1998 (DOE/NV-336 UC-900) discusses the activities at NTS to achieve full compliance with environmental laws and regulations. The report addresses remediation activities, and the treatment, storage and disposal of current waste generation. The Site Book for Waste Management (May 1994) and The Draft Site Treatment Plan (August 1994) detail waste management activities at NTS. Radioactive and hazardous wastes generated from past nuclear testing activities were disposed of at Areas 2, 3, 5, 6, 8, 9, 12, and 23. These were mixed wastes and LLW composed of debris, drilling mud, decontamination wastes, laboratory, and classified wastes. Areas 3 and 5 are still currently active for waste treatment, storage, and disposal. Area 3 receives offsite and onsite bulk waste for disposal in subsidence craters. A RCRA closure plan has been submitted to the Nevada Division of Environmental Protection for this facility. The Radioactive Waste Management Complex in the north of Area 5 contains the LLW management unit and receives packaged classified and unclassified low-level and mixed wastes. It also has TRU wastes from Lawrence Livermore National Laboratory in storage, and a hazardous waste accumulation site. In the past waste disposal was accomplished through landfills, underground injection, and leachfields on NTS and through offsite disposal. NTS has a goal to achieve compliance with environmental laws and regulations and to remove or immobilize hazardous substances, pollutants, and contaminants. These activities are expected to result in an acceptable level of environmental restoration for all sites by 2007 (NTDOE 1993d:82). The Remedial Investigation/Feasibility Study that will guide this restoration is expected to be completed in 1996. Pollution Prevention. The Nevada Operations Office is an active participant in DOE's national waste minimization and pollution prevention program. A comprehensive waste minimization plan for NTS was completed in 1991, which defines specific goals, methods, responsibility, and achievements for organizations. A Waste Minimization Coordinator has been identified to provide a point of contact for NTS waste minimization activities, and a Waste Minimization Task Force has been formed from NTS contractors and users. The management and operations contractor has three full-time employees in its Waste Minimization Project Office, dedicated to promoting waste minimization and pollution prevention, and assuring compliance with DOE Executive orders throughout the site. Since the initiation of the waste minimization program, several steam-cleaning operations have been eliminated, and one-half of the hazardous solvents used at NTS have been replaced with nonhazardous solvents. Recycling and reclamation activities have been established to reuse lead, silver, lubricating oil, and trichlorotrifluoroethane. Automatic decontamination equipment, recycling fabrication tool coolant systems, and continuous oil change and reburn systems have been placed in service to reduce hazardous waste generation. Closed loop effluent recycling for steam cleaning has eliminated the production of 4.7 million gallons of wastewater annually, and has reduced hazardous wastes generation by 90 percent. Two solvent waste stills recycle 85 percent of all solvents and thinners used. Nonhazardous aqueous solution parts cleaners have eliminated the need for parts cleaning solvents (NT DOE 1993a:1). The procurement of all materials is also reviewed for the opportunity to reduce the purchase of hazardous materials for NTS operations. For the future, planning for remediation (i.e.plutonium-contaminated soil cleanup) includes research and development for best available technology consistent with waste minimization goals. In addition, an education and training program for all site personnel and for the surrounding community is helping to increase awareness of best practices and lessons learned in waste reduction. Transuranic Waste. TRU waste is stored on the TRU Pad Waste Storage in Area 5. This waste was generated at Lawrence Livermore National Laboratory and shipped to NTS between 1974 and 1990. All NTS mixed TRU waste is expected to be certified for disposal at WIPP in Carlsbad, NM, or another suitable repository should WIPP prove to be unsatisfactory. The Nevada Operations Office is planning to construct a TRU Waste Certification Building for breaching, sampling, and certifying containers of TRU waste to meet the WIPP Waste Acceptance Criteria. However, delays are expected, because the WIPP Waste Acceptance Criteria cannot be finalized until the conditions imposed by EPA (after testing is complete) are known. This waste inventory consists of 800 yd3 of heterogeneous debris (NTDOE1993f:37). NTS has areas of plutonium-contaminated soil as the result of nuclear weapons tests. The technology for the treatment of these soils is presently being developed. Table H.2.2-1 lists the mixed TRU waste storage units at NTS. Low-Level Waste. LLW was generated from underground testing of nuclear weapons as contaminated soil surrounding the test cavity. Although the debris from a weapons test remains underground by design, samples of this debris are brought to the surface for analysis and then must be disposed. The majority of LLW generated at NTS is disposed of in subsidence craters in Area 3. This area also receives substantial quantities of containerized bulk waste from other offsite DOE facilities. Some waste disposal units are being closed in this area, while others are being readied for future use. Area 5 receives low-level radioactive waste from both onsite and offsite generators. New disposal capacity is planned for this area, and the onsite/offsite generators will be required to meet the NTS waste acceptance criteria (which includes periodic reviews by the Nevada Operations Office) to allow them to ship LLW for disposal at NTS. Historically, the volume of waste received from offsite is approximately equal to or slightly greater than the volume of waste generated onsite. Onsite waste generation will decline due to cessation of nuclear testing. Remediation activities at NTS will produce waste streams that will have to be treated, stored, and disposed. Any onsite/offsite waste shipments must meet NTS waste acceptance criteria which require that the waste be ready for disposal at NTS. The planning for and progress of remediation activities is described in detail in the Environmental Restoration and Waste Management Site Specific Plan Fiscal Years 1994-1998. The LLW disposal capacity in use or planned is listed in table H.1.5-1. Mixed Low-Level Waste. Mixed LLW is generated by defense program-related support activities, environmental restoration activities, and activities supporting TRU waste disposal at WIPP or another suitable repository should the WIPP prove to be unacceptable. Wastes were generated by the analytical activities supporting weapons tests and consisted of drilling muds and debris generated from tunnel reentry and rehabilitation. Additional wastes result from radiochemical analysis, and from the decontamination of equipment and facilities used in sample extraction and analysis. NTS has received mixed wastes from other DOE sites and may receive additional waste pending the completion of the Site Treatment Plans for all DOE sites and once proper permits are obtained. Mixed LLW streams are being characterized to fully determine what technologies and capabilities are required for safe, environmentally sound and compliant disposal. Nine waste streams at NTS require additional characterization before a formal determination of whether the waste is mixed can be made. Currently, the Nevada Operations Office is planning to build the Liquid Waste Treatment System, a central facility for treating contaminated effluents from environmental restoration and defense programs activities. The Liquid Waste Treatment System would be comprised of double-lined receiving/holding tanks, evaporation reservoirs, process equipment for chemical separation of solids, and a batch plant to provide sludge/sediment stabilization through cementation. Receiving/holding and evaporation reservoirs and associated mixed waste processes will be RCRA-permitted. Table H.2.2-2 lists mixed LLW storage and disposal facilities at NTS. Table H.2.2-3 lists the mixed LLW streams inventory and 5-year projected generation at NTS. Table H.2.2-3 does not include the nine potential mixed waste streams which are awaiting further characterization and evaluation. The total volume is 350 yd3 including a 45,000-pound empty spent shipping cask. The 7,500 yd3 of projected mixed wastes from environmental activities are also not included due to lack of characterization. Table H.2.2-4 lists mixed LLW treatment facilities at NTS. Hazardous Waste. Hazardous wastes are generated from ongoing operations at NTS. Wastes consist of solvents, lubricants, fuel, lead, metals, and acids. Hazardous wastes are accumulated at various sites around NTS while they await shipment offsite to a RCRA-permitted facility. Over the next 5 years, additional satellite storage locations are planned. A separate accumulation site across the road from Area 5 is provided to avoid potential cross-contamination with radioactive waste. The generation of hazardous wastes at NTS is expected to decrease significantly because of the cessation of nuclear testing, the completion of environmental restoration activities, and because of the impact of waste minimization activities. Hazardous waste accumulation capacity in Area 5 is approximately 1,500 yd3 (NT REECO 1994a:11). Nonhazardous Waste. Nonhazardous sanitary wastes are expected to be generated at the current rate for the next several years, then decline due to the cessation of nuclear weapons testing. Recycling of paper, metals, glass, plastics, and cardboard has already resulted in some decreases in waste quantities. Table H.2.2-1.-Mixed Transuranic Waste Storage at Nevada Test Site Storage Unit Input Capability Total Capacity Comment (yd3) Asphalt Storage Pad Mixed TRU solid 1,485 Available storage capacity on the TRU Pad to be used for storage of (covered building) future, onsite generated mixed LLW that does not meet RCRA Land fusion Disposal Restriction standards. Table H.2.2-2.-Low-Level and Mixed Low-Level Waste Storage and Disposal Capacity at Nevada Test Site Disposal Unit Input Capability Total Capacity Comment (yd3) Mixed Waste, P03U Management Unit Mixed LLW solid 155,532 Nonoperational. RCRA Part A 1988. EA published, withdrawn. Will be considered in site-specific EIS. LLW Disposal, P04U LLW solid, wood, metal, 87,565 Operational. Additional 801,300 yd3 capacity available for rubble, debris expansion LLW Disposal, P06U LLW solid 35, 318 Operational, reserved for future use Classified Shallow Land Burial, T02C LLW solid, metal, solidified 2,220 Operational-No remaining capacity liquid in approved containers Shallow Land Burial, T03U LLW solid, metal, debris, 9,268 Reserved for LLW disposal unclassified, solidified liquid Classified Shallow Land Burial, T04C LLW solid, metal, solidified 1,985 Operational liquid in approved containers Mixed Waste Storage Pad Mixed LLW solid Planned Planned. RCRA Part B submitted in 1992 Bulk LLW Disposal, U3AHAT LLW solid, wood, metal, 558,869 Operational solidified liquid, soil, biological Table H.2.2-3.-Mixed Low-Level Waste Streams at Nevada Test Site Waste Matrix Number of Waste Streams Inventory as of Number of Waste Streams August 31, 1994 Five-Year Projection (yd3) Total Generation Five-Year Projection (yd3) Aqueous liquids 0 0 1 5,440 Organic process residues 2 340 0 0 Contaminated soil 1 3.4 0 0 Uncategorized soil 2 1 3 2,040 Debris 4 7 1 10 Lab packs 2 0.3 0 0 Lead acid batteries 1 0.1 0 0 Total 12 351.8 5 7,490 Source: NT DOE 1994a. Table H.2.2-4.-Mixed Low-Level Waste and Low-Level Waste Treatment Capability at Nevada Test Site Treatment Unit Treatment Method Input Capability Output Capability Total Capacity Comment (yd3 per year) Liquid Waste Treatment Separation, evaporation, Mixed LLW liquids and LLW solid 29,700 Now in Title I design; in the System stabilization slurries (6,000,000 GPY) current design, RCRA organics cannot be accepted Source: NT DOE 1994a. H.2.3 Oak Ridge Reservation ORR consists of three operating industrial complexes in and around the city of Oak Ridge. The Energy Systems Waste Management Organization provides the waste management oversight for ORR. It also provides guidance to each of the operating facility waste management divisions which are responsible for operating and managing their respective waste management facilities and activities. Y-12 Plant. Laboratory, maintenance, construction, demolition, and cleanup activities; machining operations; and waste produced in the purification of uranium for recycle are the primary waste generation activities at the Y-12 Plant (Y-12). In addition, metal- plating operations generate plating waste solutions while various laboratory activities generate reactive wastes and waste laboratory chemicals. Liquid process waste and the sludge resulting from the treatment of these process wastes are generated throughout the plant. Waste oils and solvents are generated from machining and cleaning operations. Daily operations such as janitorial services and floor sweepings generate both noncontaminated and uranium-contaminated industrial trash. Pollution Prevention. The Y-12 Pollution Prevention Awareness Program Plan describes the overall program in detail. The program is designed to maintain the flow of information pertaining to waste minimization and pollution prevention and to facilitate activities to implement real reductions in waste generation. A summary description of the four key elements of the Waste Minimization and Pollution Prevention Program includes a promotional campaign, information exchange, a waste tracking system, and waste assessment performance. One goal of the program is to sustain an effective pollution prevention effort by improving the awareness of the employees of waste minimization opportunities and activities. Improved awareness is accomplished in many ways including training, posters, publications, seminars, promotional campaigns, and recognition of individuals and teams for activities that reduce waste generation. Waste minimization activities at other ORR sites and other weapons sites provide useful input to the program. Using ideas developed by others is an important aspect that can save time and resources. Tracking waste generation in a manner that lends itself to waste minimization reporting is a prerequisite to documenting successes or failures in waste minimization efforts. Y-12 is improving its ability to record and track waste shipments. Process waste assessments are being conducted as part of the ongoing program to identify, screen, and analyze options to reduce the generation of waste. This determines the amount of material in a workplace that is disposed of as waste during work operations. The assessment provides a summary of hazardous materials usage and waste production and identifies those processes and operations that need to be improved or replaced to promote waste minimization. Spent Nuclear Fuel. Y-12 does not generate any spent nuclear fuel; however, it does store and safeguard a small amount of reactor-irradiated nuclear material in Building 9720-5. It is a large warehouse facility containing numerous vaults for storage. Some features of the facility are classified and it is distinguished by its high level of security. Operations consist of transfers, storage, and inventory of highly enriched uranium (HEU) in con- tainers of various types. High-Level Radioactive Waste. Y-12 does not generate or manage HLW. Transuranic Waste. Y-12 does not generate or manage TRU waste. Low-Level Waste. Machining operations which use stock materials including steel, stainless steel, aluminum, depleted uranium, and other materials produce machine turnings and fines as waste products. Waste treatment provides controlled conversion of waste streams generated from operations to an environmentally acceptable, or to a more efficiently handled or stored, form. This activity includes continuing operation and maintenance of facilities that treat wastewaters and solid waste generated from production and production support activities. Waste minimization and planned treatment facilities are expected to reduce the magnitude of these wastes. In 1992, Y-12 treated approximately 128,000 gallons of liquid LLW and 170 yd3 of solid LLW (ORDOE1993b:9-3). Table H.2.3-1 summarizes the LLW treatment facilities at Y-12 of which the major facilities are described below. The Uranium Chip Oxidation Facility thermally oxidizes depleted and natural uranium (less than 1percent enrichment) machine chips under controlled conditions to a stable uranium oxide. Upon arrival, chips are weighed, placed into an oxidation chamber, and ignited. The oxide is transferred into drums and transported to the Uranium Oxide Storage Vaults. The Uranium Chip Oxidation Facility is not designed to treat uranium sawfines. Hence, sawfines are currently blended with uranium oxide and placed in the Oxide Vaults as a short-term treatment method. The Waste Feed Preparation Facility processes and prepares solid LLW for volume reduction by an outside contractor or storage at Y-12. The facility utilizes a 200-ton capacity baler to reduce the waste volume to one-eighth of its original size. Waste comes to the facility from areas known to generate contaminated material, or from dumpsters that were analyzed at the Trash Monitoring Station and deemed to be above the radioactive acceptability limits for the sanitary landfill. The compacted bales are placed in DOT-approved metal boxes and staged in an adjacent warehouse prior to offsite shipment for incineration or storage at Y-12. The Uranium Treatment Unit is located near Building 9206 and is used to treat uranium-contaminated nitrate waste solutions which are generated in enriched uranium recovery operations in buildings 9212 and 9206. After the waste is processed through the Uranium Treatment Unit, it is transferred to the Y-12 Waste Management Division for storage, further treatment, and/or final disposal. The Waste Coolant Processing Facility is a biodegradation and storage facility for waste coolants that may be LLW and utilizes the following equipment for coolant treatment: Three storage tanks; Feed tank; Waste processing reactor/clarifier; Sludge holding tank; Two sludge blenders/dryers; Effluent holding tank; and Transfer pumps. Microorganisms biodegrade approximately 30,000gallons of waste coolant per month into harmless products. Each batch of coolant takes approximately 30 days to treat. After treatment, the clarifier separates the wastes into three process streams: floating oily solids, liquid effluent, and settled biological solids. Floating solids are dewatered in the dryer/ribbon blender and are transferred to drums. Liquid effluent is sent to the Central Pollution Control Facility or West End Treatment Facility/West Tank Farm for final treatment prior to NPDES discharge. Biological solids are further treated in the aeration tank and are then recycled or sent through the blender for dewatering. Nonrecycled solids are currently pumped into tankers for storage. This practice will continue until adequate treatment and disposal methods are established. Long-term storage options include storage in warehouses, tanks, and vaults, as well as storage of Y-12 wastes in buildings at K-25. The major Y-12 LLW storage facilities, described below, are summarized in table H.2.3-2. In 1992, approximately 600 yd3 of LLW and 1,330 yd3 of uranium-contaminated scrap metal was stored at Y-12 (ORDOE1993b:9-6). The Classified Waste Storage Facility will provide storage for Y-12 classified wastes contaminated with radionuclides. These wastes are currently being stored by the waste generators. The facility will meet plant security requirements for classified waste man- agement and guidelines for the management of LLW and mixed LLW. The Classified Waste Storage Facility is equipped with a baler for volume reduction and shape-changing capabilities, but the baler will not become operational until the ventilation and fire- suppression systems are upgraded to meet health, safety, and fire protection requirements. Funding for this facility upgrade has not yet been made available. Wastes will be monitored by Health Physics personnel. The facility is located in Building 9720-25. Buildings 9206 and 9212 containerized waste storage units provide for the storage of cans of ash resulting from the combustion of uranium-contaminated solid wastes. Combustible solid wastes contaminated with enriched uranium are ashed during the uranium recovery process. The resulting cans of ash are stored in buildings 9206 and 9212 containerized storage units until uranium accountability results have been obtained and the material can be returned to the uranium recovery process for further processing to recover the enriched uranium. The Building 9720-25 classified containerized waste storage unit provides for the permitted storage of RCRA hazardous waste and mixed LLW, which is classified for national security purposes under provisions of the Atomic Energy Act. Waste is stored in this unit awaiting further processing, treatment, or ultimate disposal. The Depleted Uranium Oxide Storage Vaults I and II are located on Chestnut Ridge northeast of Building 9213. The vaults are constructed of reinforced concrete and provide a retrievable storage repository for uranium oxide, uranium metal, and a blended mixture of uranium sawfines and oxide. The vaults contain a negative pressure exhaust system that operates during material entry. The exhaust is filtered and monitored prior to its release to the atmosphere. The facility utilizes forklift trucks, electric hoists, and a motorized drum dumper during operation. Depleted uranium oxide and blended sawfines are delivered in sealed 30- and 55-gallon drums. The containers have a weight limit of 850 pounds. The Old Salvage Yard contains both low-level uranium-contaminated and nonradioactive scrap metal. However, most scrap currently sent to this facility is contaminated. The Contaminated Scrap Metal Storage is an area within the Old Salvage Yard that is used to store uranium-contaminated scrap metal. Contaminated scrap is being placed in B-25 boxes and eventually will be transferred to the above-grade storage pads. Noncontaminated scrap is sold when offsite shipments are allowed. This facility is located at the west end of Y-12. Y-12 has no current onsite LLW disposal capability. All disposal activities at the Bear Creek Burial Ground were terminated on June 30, 1991. This landfill was used to dispose of radiologically-contaminated solid waste. These wastes are currently containerized and stored at Y-12 in above-grade storage pads or are shipped offsite for incineration. In 1992, approximately 220 yd3 of solid nonmetallic LLW were sent offsite to be incinerated with the ash returned to Y-12 for storage (ORDOE1993b:9-5). The Low-Level Waste Disposal Facilities project will provide new disposal facilities at a new centralized location of the ORR. The Low-Level Waste Disposal Facilities will utilize state-of-the-art disposal technologies, including lined trenches with leachate collection treatment capabilities and tumulus confinement disposal units. The Class-II facility, for wastes contaminated with very low concentrations of long half-life radionuclides, is expected to be opera- tional in 1998. DOE has indefinitely postponed construction of the Class-I facility, for wastes contaminated with low concentrations of predominantly short half-life radionuclides. Mixed Low-Level Waste. Mixed LLW is generated from the development, metal preparation, fabrication, and assembly/industrial engineering functions at Y-12. Mixed LLW are hazardous wastes such as solvents, degreasers, biodegradable coolants, organic and inorganic acids, biodenitrification sludge, and wastewater that are contaminated with enriched and/or depleted uranium. There is no disposal of mixed waste at Y-12; however, future plans include disposal of mixed wastes at a permitted offsite commercial facility. Mixed wastes are put in storage awaiting treatment, treated at Y-12, or sent to another ORR facility for treatment. Table H.2.3-3 presents the inventory of mixed LLW at Y-12 as of December 31, 1992 along with a 5-year projection. In 1992, approximately 354,000 gallons of liquid mixed LLW was treated at Y-12 (ORDOE1993b:9-3). The Y-12 Waste Management Division operates several mixed LLW treatment facilities which are described below and were previously summarized in table H.2.3-1. The Groundwater Treatment Facility treats wastewater from the Liquid Storage Facility and seepwater collected at K-25 to remove volatile and nonvolatile organic compounds and iron. It is part of the Disposal Area Remedial Action program to collect and treat contaminated groundwater from the Bear Creek Burial Grounds. The Groundwater Treatment Facility is located at the far west end of Y-12, adjacent to the West End Treatment Facility. This facility utilizes an air stripping operation to remove volatile organics. In addition, carbon adsorption eliminates nonvolatile organics and PCBs. Iron removal equipment is also operational. After treatment, wastewater is sampled and recycled if additional processing is required. Wastewater that meets discharge specifications is pumped into East Fork Poplar Creek through an NPDES monitoring station. The Groundwater Treatment Facility treated and discharged approximately 501,000 gallons during 1992 (OR DOE 1993b:9-3). The West End Treatment Facility/West Tank Farm treats the following nitrate-bearing wastes generated by Y-12 production operations: nitric acid wastes; nitrate-bearing rinsewaters; mixed acid wastes; waste coolants; mop water; caustic wastes; and biodenitrification sludges. Treatment operations consist of biological denitrification, biological oxidation, metals precipitation, coagulation, flocculation, clarification, filtration, pH adjustment, degassification, and carbon adsorption. Wastes are received at the West End Treatment Facility/West Tank Farm in 5,000-gallon tankers, 600-gallon polytanks, and in smaller, approved waste transportation containers such as drums, bottles, and carboys. Detailed waste analysis documentation is used to determine the treatment scheme and temporary storage location of each shipment. The West End Treatment Facility Effluent Polishing System facilitates the removal of uranium, trace metals, and suspended solids. The treated wastewater is then discharged to East Fork Poplar Creek through an NPDES monitoring station. Sludges, spent carbon, and spent filter material generated during the treatment processes are currently stored in 500,000-gallon tanks. A major modification to the West End Treatment Facility/West Tank Farm is currently in the design phase. This modification will remove all heavy metals up front, thus separating the hazardous sludge from the nonhazardous sludge. Approximately two-thirds of the current sludge volume generated can then be disposed of as nonhazardous wastes. The Y-12 Cyanide Treatment Unit provides storage and treatment of waste solutions containing metallic cyanide compounds from spent plating baths and precious metal recovery operations. The cyanide reduction process performed within the unit is currently performed in 55-gallon containers, although plans are under way to discontinue this method of treatment and initiate use of fixed tanks for use in the treatment process. After waste is treated at the Cyanide Treatment Unit, it is transferred to the West End Treatment Facility for further treatment and discharged to the East Fork Poplar Creek. In 1992, approximately 450 yd3 of mixed LLW including PCB and uranium waste were stored at Y-12 (ORDOE1993b:9-6). Table H.2.3-2 summarized the mixed LLW storage facilities at Y-12 which are described below. The Containerized Waste Storage Area consists of three concrete pads covering approximately 25,000ft2. These pads provide storage for LLW, RCRA hazardous, and mixed LLW. An impermeable dike surrounds each pad to provide one foot of spill containment. Fire protection at this facility is currently being upgraded. The Building 9811-1 RCRA Storage Facility (OD7and OD8) contains a diked storage area for tanks (OD7) and an enclosed storage area for containers (OD8) with a capacity of 1,000 drums. The OD7 contains four 30,000-gallon tanks, one 10,000- gallon tank, two 3,000-gallon tanks, associated piping and pumps, and an oil/water separator. RCRA waste oil/solvent mixtures containing various concentrations of chlorinated and nonchlorinated hydro-carbon solvents, uranium, trace PCBs, and water for specific chemical constituents are stored at OD8 in 55-gallon drums and 300-gallon Tuff-tanks to await sampling and analytical results. Wastes deemed compatible with OD7 materials are pumped into those tanks. Noncompatible wastes are transported to different facilities. The Waste Oil/Solvent Storage Facility (OD9) is a permitted RCRA/TSCA hazardous waste storage facility. It consists of a diked area supporting five 40,000-gallon tanks, a tanker transfer station with five centrifugal transfer pumps, and a drum storage area. Three tanks house PCB wastes contaminated with uranium, one tank contains non-radioactive PCB wastes, and one tank holds RCRA hazardous wastes. Likewise, a diked and covered pad furnishes space for 35 drums. Wastes assigned to this facility are first stored at OD8 (Building 9811-1 RCRA Storage Facility) to await laboratory results. The diked area contains additional space for a sixth 40,000-gallon tank. This facility is projected to be used until 2010, due to the anticipated lack of disposal outlets for uranium-contaminated organic liquids. The Liquid Organic Waste Solvent Storage Facility (OD10) contains four 6,500-gallon and two 3,000-gallon stainless steel tanks for storage of ignitable nonreactive liquids, including those contaminated with PCBs and uranium. In addition, a diked and covered storage area provides space for 1,000 drums of material. The facility is capable of segregating various spent solvents for collection and storage. Major solvent waste streams are transferred to tanks until commercial resale, disposal, or incineration at K-25 takes place. Building 9720-9 Storage Area supplies a drum storage area for mixed and/or PCB wastes, including an area designed to contain flammable wastes. The western half, which contains space for approximately 1,500 drums, stores both PCB and RCRA hazardous waste. However a diking upgrade is planned to allow for the handling of RCRA materials. The facility's eastern half is not currently in use. Upgrades to the ventilation, diking, and fire-suppression systems will comply with RCRA, TSCA, and DOE standards and will allow for mixed and PCB waste storage. The design of these modifications is complete, and con- struction will begin when NEPA documentation has been submitted and approved. The RCRA Staging and Storage Facility (Building 9720-31) prepares solid, liquid, and sludge wastes for offsite shipment. The facility consists of seven storage rooms and seven staging rooms, each with a separate ventilation system. The staging rooms house small containers that are packed with compatible materials and shipped. The storage rooms hold larger containers, such as 55-gallon drums. Each room, which can hold up to 90 drums, accommodates a different class of hazardous waste. The RCRA and PCB Container Storage Area (Building 9720-58) is a warehouse facility utilized for staging prior to treatment of PCB-contaminated equipment (transformers, capacitors, and electrical switchgear) and nonreactive, nonignitable RCRA waste contaminated with uranium. Waste containers received at Building 9720-58 include 30- and 55-gallon drums, 330- and 660-gallon portable tanks, B-25 boxes, and self-contained PCB equipment. The Solid Storage Facility provides 17,500 ft2 of storage space for PCB- and uranium-contaminated soil. The facility also contains a synthetic liner for leachate collection and a leak detection system. Collected leachate is transferred to the Liquid Storage Facility for pretreatment. The Solid Storage Facility is currently undergoing the RCRA Part B permitting process. No additional wastes are being added to the facility. Hazardous Waste. Plating rinsewaters; waste oil and solvents from machining and cleaning operations; contaminated soil, soil solutions, and soil materials from RCRA closure activities; and waste contaminated with hazardous constituents from construc- tion/demolition activities are the major sources of hazardous waste. In 1992, approximately 150,300gallons of hazardous liquid were treated (OR DOE 1993b:9-3). In addition 419,900 gallons of liquid leachate from the Bear Creek Burial Ground were processed. The Y-12 Waste Management Division operates several hazardous treatment facili- ties that are described below and are summarized in table H.2.3-4. The Plating Rinsewater Treatment Facility treats dilute plating rinsewaters contaminated primarily with chromium, copper, nickel, and zinc. In addition, the facility can treat cyanide-bearing wastes and remove chlorinated hydrocarbons. In 1991, the Plating Rinsewater Treatment Facility treated 283,504 gallons of plating rinsewater. The facility is located across the street from the Building 9401-2 Plating Shop, which produces most of Y-12's rinse-waters. The facility neutralization, equalization, and cyanide destruction equipment is located outdoors in a diked basin. The remainder of the facility process is located in Building 9623. Rinsewaters are received via a direct pipeline from the Plating Shop. In addition, rinsewaters may be received in tankers, polytanks, or in any acceptable waste shipping container. The Plating Rinsewater Treatment Facility performs the following treatment operations: pH adjustment; flow equalization; heavy metal removal by electrochemical precipitation; flocculation; clarification; carbon adsorption; and filtration. After the clarification operation, the rinsewater is transferred to the Central Pollution Control Facility. The Central Pollution Control Facility provides the carbon adsorption operation, final filtration, and discharge to East Fork Poplar Creek through an NPDES monitoring station. Treated rinsewater is sometimes recycled for use as make-up water for Central Pollution Control Facility processes. Sludge from the clarifica- tion process is transferred to the Central Pollution Control Facility and then taken to the West Tank Farm for interim storage. Hazardous waste is being stored until Martin Marietta Energy Systems and DOE approve shipment for offsite disposal under the DOE "NoRadAdded" performance objective (ORDOE1993a:9-11). In 1992, approximately 260yd3 of hazardous waste and 60 yd3 of PCB wastes were placed in storage at Y-12 (ORDOE1993b:9-6). Table H.2.3-5 summarizes the major existing Y-12 hazardous waste storage facilities described below. The Oil Landfarm Soil Storage Facility contains approximately 550 yd3 of soil contaminated with PCBs and volatile organics (OR DOE 1993a:9-21). The soil was excavated from the Oil Landfarm and Tributary 7 in 1989. The soil is contained in a covered, double-lined concrete dike with a leak-detection system. The leak-detection system will soon be modified to enhance detection capabilities. The Liquid Storage Facility of the Disposal Area Remedial Actions Liquid Storage Treatment Unit is a hazardous waste storage facility built during the Bear Creek Burial Ground closure activities. It is located in Bear Creek Valley approximately two miles west of Y-12. It collects and stores groundwater and other wastewaters received from the Seep Collection Lift Station, the Solid Storage Facility, tankers, poly-tanks, and the diked area rainfall accumulation. Feed streams may contain oil contaminated with PCBs, volatile and nonvolatile organic compounds, and heavy metals. Processing and storage equipment include: Two 75,000-gallon bulk storage tanks; 6,000-gallon oil storage tank; Gravity separator; Filtering unit; Composite sampling station; and Tanker transfer station. The wastewater travels through the gravity separator, cartridge filters, and composite sampling station prior to storage in the bulk tanks. A reinforced concrete dike surrounds all equipment to provide spill containment. After sufficient wastewater accumulates in the bulk storage tanks, it is processed at the Groundwater Treatment Facility. A new leachate collection system collects and pumps hazardous waste seepage from the burial ground to the Liquid Storage Facility. In 1992, approximately 7,900 gallons of liquid hazardous waste from Y-12 was incinerated offsite (ORDOE1993b:9-5). Other hazardous waste is sent offsite to commercial vendors or other ORR sites. The Y-12 Waste Management Division operates the Sanitary and Industrial Landfill II which provides special waste disposal including asbestos materials, aerosol cans, materials contaminated with beryllium oxide, glass, fly ash, coal pile runoff sludge, empty pesticide containers, and Steam Plant Wastewater Treatment Facility sludge. The landfill area is located on Chestnut Ridge near the eastern end of the plant and serves Y-12, Oak Ridge National Laboratory, K-25, and other DOE prime contractors in Oak Ridge. The landfill utilizes shallow land burial by the large trench method and is permitted by the State of Tennessee. Requests are filed with the state to provide disposal for additional materials as needed. The Chestnut Ridge Borrow Area Waste Pile (Industrial Waste Landfill III) consists of mercury-contaminated soil removed from the Oak Ridge Civic Center area and deposited at Y-12 Chestnut Ridge. No further disposal at this site has been made. Closure of this waste pile was initiated after a complete soil analysis following state sampling regulations was completed. Nonhazardous Waste. Major waste-generating activities include construction and demolition activities that produce large volumes of noncontaminated wastes, including lumber, concrete, metal objects, soil, and roofing materials. Industrial trash is generated by daily operations throughout the plant. These operations include janitorial services, floor sweepings in production areas, and production activities. In 1992, about 375,700 gallons of wastewaters from the Central Pollution Control Facility and the Plating Rinsewater Treatment Facility and 37,860,000 gallons of wastewaters from the Steam Plant were processed. In addition, approximately 280,700 gallons of other liquid nonhazardous waste was treated. The Waste Storage Facility in Building 9720-25 has solid waste baler with an 8:1 compaction ratio (DOE 1994n). Approximately 1,970 yd3 of solid nonhazardous waste was compacted during 1992 (ORDOE1993b:9-3). The Steam Plant Wastewater Treatment Facility treats approximately 40 million gallons per year of wastewater from steam plant operations, demineralizers, and coal pile runoff. Treatment processes include wastewater collection/sedimentation, neutralization, clarification, pH adjustment, and dewatering. The treatment facility utilizes automated processes for continuous operation. All solids generated during treatment are nonhazardous and are disposed of in the sanitary landfill. The treated effluent is monitored prior to NPDES discharge to the East Fork Poplar Creek. The Y-12 Utilities Department manages this facility. Lake Reality is a lined containment basin with a surface area of about 2acres. The pond serves to enhance the water quality of East Fork Poplar Creek downstream of Y-12. The Sludge Handling Facility (T-118) was designed and constructed to provide water filtration and sludge dewatering in support of a storm sewer cleaning and relining project. Filtered water was reused by the sewer-cleaning contractor, and the dewatered sludge was stored in specially constructed containers for future disposal. The facility is currently being used to store containers of LLW. The Steam Plant Ash Disposal Facility is used to collect, dewater, and dispose of sluiced bottom ash generated during operation of the coal-fired steam plant. An additional trench was constructed for the disposal of sanitary and industrial wastes generated by Oak Ridge National Laboratory, K-25, and Y-12. In order to comply with environmental regulations for landfill operations, the Steam Plant Ash Disposal Facility includes a leachate collection system, a transfer system to discharge the collected leachate into the Oak Ridge public sewage system, groundwater monitoring wells, and a gas migration/ventilation system. The landfill, Industrial Landfill V, is permitted to dispose of approximately 4 million ft3 per year of industrial waste. The facility was designed and is operated in accordance with Tennessee solid waste disposal regulations and became operational in March 1994. In 1992, approximately 1,100 yd3 of clean scrap metal was stored at Y-12 (OR DOE 1993b:9-6). The salvage yard is used for the staging and public sale of nonradioactive, nonhazardous scrap metal. Sales have been suspended, however, until procedures to meet the DOE "No Rad Added" performance objective have been approved. The New Salvage Yard provides accumulation and sorting activities for nonradiologically contaminated scrap metal. Plans are in place to provide an automotive lead cell battery repository for used batteries until recycling options are initiated. This facility is located near the Bear Creek Burial Ground. Construction debris is buried at Landfill VI and VII on Y-12. Oak Ridge National Laboratory. Because Oak Ridge National Laboratory is a research facility, it has many diverse waste-generating activities, each of which may produce only a small quantity of waste. Isotope production, utilities, and support functions such as photography are additional sources of waste. The radioactive wastes produced by each activity at Oak Ridge National Laboratory reflect the nature of its operation. A large number of radioisotopes are handled, in isotope production and packaging, in reactor and accelerator operations, in reprocessing studies on nuclear fuel, and in investigations into the interactions of radioactivity with living systems. The radioactive wastes generated by these activities can be classified as follows: Concentrates generated by the treatment of intermediate-level wastes, which are disposed of by hydrofracture; LLW contaminated with beta/gamma emitting radioactivity. These wastes, which have a low surface dose rate, are compacted if possible and disposed of in earthen trenches; those wastes which exhibit a high surface dose rate are disposed of in augered holes; TRU wastes, which are retrievably stored; and Low-level alpha-emitting wastes, which are evaluated for criticality hazards before disposal in augered holes. Pollution Prevention. Waste segregation is used to minimize the generation of solid LLW. By providing collection barrels for both radioactive and nonradioactive wastes, the volume of wastes that requires handling as radioactive waste has been reduced. Before these procedures were implemented, radioactive and nonradioactive wastes were discarded in the same barrel. This contaminated the nonradioactive portion and required special disposal of an inflated amount of waste. Spent Nuclear Fuel. Oak Ridge National Laboratory generates small quantities of spent nuclear fuel. Several facilities described below are used to house spent nuclear fuel (DOE 1993r:28-29). The interim management of spent nuclear fuel (pending availability of a geologic repository) will be in accordance with the ROD from the Department of Energy Pro- grammatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Final Environmental Impact Statement (DOE/EIS- 0203-P). Irradiated Fuels Examination Laboratory (Building 3525). The Irradiated Fuels Examination Laboratory only contains hot cells. Disassembly and examination of irradiated fuel and components continue to be the mission of the facility. High Level Radiochemical Laboratory (Building 4501). The High Level Radiochemical Laboratory contains centrally located hot cells supported by various laboratories capable of handling radioactive material. It has been used in performing work on fission gas release in light water reactor fuel rods. The spent nuclear fuel is in dry storage. Radiochemical Engineering Development Center (Building 7920). The Radiochemical Engineering Development Center is a multipurpose hot cell facility with the appropriate equipment, shielding, and containment provisions to safely process and store large quantities of highly radioactive fuel elements. It was specifically built to prepare and process targets for the High Flux Isotope Reactor. Bulk Shielding Reactor. This pool-type research reactor is currently shut down with the core stored in racks. Fuel assemblies from the Oak Ridge Research Reactor are also stored in the pool. High Flux Isotope Reactor. The High Flux Isotope Reactor is an 85 megawatt (MW), beryllium-reflected, light-water-moderated, flux-trap-type research reactor with associated support equipment and a storage pool. Missions include production of isotopes for medical and industrial applications, neutron-scattering experiments, and various material irradiation experiments. This is the only reactor that is still generating fuel elements that will need storage in the future. Molten Salt Reactor Experiment. The Molten Salt Reactor Experiment is an 8 MW, homogeneous reactor consisting of uranium fluoride fuel in molten lithium salt. Its purpose was to test the practicality of a molten-salt reactor concept for central power station applications. The fuel is being stored in the salt storage tanks beneath the reactor. Tower Shielding Reactor. The Tower Shielding Reactor is a reactor facility where experiments were conducted outdoors on a remote hilltop. It is a spherically symmetric 1 MW plate-type reactor. The purpose of the facility was to conduct large-scale experiments to test shielding design methods and obtain associated data. The original core is located in the reactor. Four fuel plates are stored in the underground site, and 1,200 low-enriched fuel pins are stored in DOT shipping containers. 7823A/7827/7829 Wells. These shielded, retrievable storage facilities are stainless-steel dry wells placed in the ground but are currently closed to further storage. The wells were used to store irradiated fuel and associated fission products from 1972 to 1989. Waste Area Grouping 7 (Homogeneous Reactor Experiment Wells). In 1964, seven augered holes were drilled to store 135 gallons of a 40-molar fuel solution. Each well was filled with soil to ground level and marked by a concrete plug and brass plaque. Classified Burial Ground. In the past, fuel materials were buried here. The exact quantity and location of this material is not known. This area is now closed to operations. Solid Waste Area 6. This facility houses the Suspension Test Reactor fuel. Seven of the underground dry-storage units are empty although one unit has been found to contain water and another contains moist sand. These units are therefore not available for additional storage. A summary table of the inventory of reactor-irradiated nuclear material is shown in table H.2.3-6. High-Level Radioactive Waste. Oak Ridge National Laboratory does not generate or manage HLW. Transuranic Waste. Table H.2.3-7 presents the inventory of mixed TRU wastes at Oak Ridge National Laboratory as of December 31, 1992 along with a five-year projection. The bulk of Oak Ridge National Laboratory's mixed TRU waste is in three liquid/sludge waste streams that are stored in tanks at the present time. Each of these tank's wastes must be remotely-handled because of the high radioactivity. Oak Ridge National Laboratory's Underground Storage Tank management program includes implementation of leak detection, corrosion protection, spill and overflow protection, annual tightness testing, operational controls, record keeping, reporting, and replacement of those systems that cannot be upgraded by 1998. The program also addresses the immediate removal from service and remediation of sites with tanks found to be leaking, and it implements any required closures, corrective actions, and any upgrading and/or replacement of affected tanks in accordance with the regulatory requirements. Status of the tanks managed under the Underground Storage Tank Program through 1991 is as follows: Twenty-six tanks have been excavated or permanently taken out of service (twenty approved by Tennessee as closed while six require additional investigation and/or corrective action before final closure approval). Twenty-four tanks are deferred from 40 CFR 280 regulations. These will be taken out of service or upgraded. Two tanks were upgraded in 1990 to meet the current leak detection requirements. Two tanks contain heating oil and are excluded from regulation under 40 CFR 280. Five tanks contain waste oil contaminated with radionuclides and are excluded under 40 CFR 280. Solid TRU waste consisting of filters, paper, metals, and other items is generated at Oak Ridge National Laboratory through laboratory, pilot plant, and reactor operations. This includes both contact-handled and remote-handled TRU waste contaminated with lead and, in some cases, mercury. There is no treatment of TRU wastes at Oak Ridge National Laboratory. TRU wastes generated at Oak Ridge National Laboratory are being placed in retrievable storage. Contact-handled TRU waste is packaged predominantly in drums, while remote-handled TRU waste is packaged in concrete casks. In 1992, approximately 3 yd3 of contact-handled and 2 yd3 of remote-handled TRU waste were placed in storage (OR DOE 1993b:9-7). Current activities center around certification of contact-handled waste, planning and designing of a repackaging and certification facility for remote-handled wastes, and planning for shipment of wastes to WIPP or another suitable repository should WIPP prove to be unsatisfactory. The repackaging facility, which is in Building 7880, is called the Waste Handling and Packaging Plant and is planned for 2001. Table H.2.3-8 summarizes the storage capability for TRU and mixed TRU wastes at Oak Ridge National Labo- ratory. Low-Level Waste. Isotope production and research activities generate a variety of low-level radioactive wastes to include low-level wastewater. Sources of solid LLW include contaminated equipment, filters, paper, rags, plastic, and glass, and sludge from the Process Waste Treatment Plant. Table H.2.3-9 shows the LLW treatment facilities that are operating. Solid LLW to include radioactive scrap metal is placed in storage prior to disposal. In 1992, approximately 884yd3 of solid LLW, 27 yd3 of radioactive scrap metal, and 24 yd3 of PCB-contaminated LLW were placed in storage awaiting disposal (ORDOE1993b:9-7). Table H.2.3-10 lists the LLW and mixed LLW storage facilities currently operating at Oak Ridge National Laboratory. The area designated as SWSA 6 is the only onsite disposal unit at Oak Ridge National Laboratory. It receives solid LLW, including radioactively-contaminated asbestos. In 1992, approximately 131 yd3 of radioactive sanitary waste, 56 yd3 of radioactive scrap metal, and 39 yd3 of radioactively-contaminated asbestos was buried at SWSA 6 (ORDOE1993b:9-4). Table H.2.3-11 lists the LLW disposal units at SWSA-6. Mixed Low-Level Waste. Because Oak Ridge National Laboratory is a research facility, it has many diverse waste-generating activities, each of which may produce only a small quantity of waste. Isotope production, utilities, and support functions such as photography are additional sources of waste. Mixed wastes are generated by research projects and some facility operations. Isotope production and research activities generate a variety of mixed low-level and mixed TRU wastes. Table H.2.3-12 presents the inventory of mixed LLW at Oak Ridge National Laboratory as of December 31, 1992, along with a five-year projection. As shown in table H.2.3-9 three facilities are currently treating mixed waste at Oak Ridge National Laboratory: the Process Waste Treatment Plant, the Liquid Low-Level Waste Evaporation Facility, and the Melton Valley Low-Level Waste Immobilization Facility (OR DOE 1993a:9-21). One other treatment facility at Oak Ridge National Laboratory, the Non- radiological Wastewater Treatment Plant, is operating and could be used to treat mixed waste. The Process Waste Treatment Plant is designed to treat process wastewaters, groundwater, and evaporator condensate wastewaters that contain low levels of radioactivity. Small concentrations of radioactive materials have occasionally been processed. Process wastewaters may contain small quantities of radionuclides, metals, anions, and organic chemicals. Under normal operating conditions, the Process Waste Treatment Plant can process wastewater at a rate of 130 gallons per minute (gpm). The design capacity is 200 gpm. Wastewaters can contain organic materials and low levels of radioactivity. The facility can treat waste streams with some heavy metals but not streams containing PCBs. The Liquid Low-Level Waste Evaporation Facility treats liquid LLW using evaporation. It operates in a semicontinuous mode; waste is accumulated in collection tanks and transferred through underground piping to an evaporator system. The design capacity is 28,000 gallons per day (GPD). The facility processes an average of 300 GPD of liquid wastes under normal operating conditions. The facility can treat waste streams containing organic contaminants. The Melton Valley Low-Level Waste Immobilization Facility is used to solidify liquid mixed LLW that has a pH greater than 12.5 and that contains some heavy metals. This liquid mixed LLW is transferred from tanks by interconnecting pipelines. Batches of waste are pumped from a liquid decantation system to a solidification system as required to provide adequate storage-tank capacity. The facility operates only on a campaign basis to provide adequate storage capacity. Solidification is currently performed using cementation. Design capacity is 16,500 gallons per month of liquid waste. Under normal operating conditions, the facility can process 2,000 gallons per month as required to provide adequate storage-tank capacity. The facility cannot treat HLW, alpha-contaminated waste with TRU activity levels greater than 100nanocuries per gram (nCi/g), organic wastes, or PCBs. A summary of the mixed LLW storage facilities at Oak Ridge National Laboratory is shown in table H.2.3-10. An estimate of the capacity of these facilities is also given. In 1992, approximately 11 yd3 of mixed waste were placed in storage at Oak Ridge National Laboratory (OR DOE 1993b:9-7). The only disposal of mixed waste done at Oak Ridge National Laboratory is the burial of radioactive asbestos at SWSA-6. Asbestos contaminated with low-levels of radioactivity is placed in silos. In 1992, approximately 39yd3 of contaminated asbestos were buried (OR DOE 1993b:9-4). Low-level contaminated biological waste has also been buried at SWSA-6. Hazardous Waste. Hazardous wastes are generated in laboratory research, electroplating operations, painting and maintenance operations, descaling, demineralizer regeneration, and photographic processes. Few hazardous wastes are treated in onsite facilities. Onsite treatment at Oak Ridge National Laboratory includes elementary neutralization and detonation facilities. A summary of the hazardous waste treatment facilities at ORNL is shown in table H.2.3-13. In 1992, approximately 1,720 gallons of liquid hazardous wastes were treated at the Nonradiological Wastewater Treatment Plant and about 130gallons of hazardous waste were evaporated (OR DOE 1993b:9-3). The Nonradiological Wastewater Treatment Plant is designed to reduce pollutant concentrations in nonradiological wastewaters including hazardous wastes to levels acceptable for effluent discharge. The plant operates in a continuous mode and involves physical and chemical processing steps. The facility contains a heavy-metal removal system, where the pH of the wastewater is raised to 10.5 in a clarifier. Polymers are added to induce flocculation and settling of the metal precipitates. The wastewater is passed through a filtration system to remove particulates. An air stripper then removes volatile organics and activated carbon columns remove mercury. The Chemical Detonation Facility treats small amounts of wastes that would be dangerous to transport offsite. Explosives such as aged picric acid are detonated in the detonation facility. Certain other wastes (e.g., spent photographic processing solutions) are processed onsite into a nonhazardous state. Those wastes that are safe to transport are shipped to offsite RCRA-permitted commercial treatment/disposal facilities. In 1992, approximately 58 yd3 of hazardous waste and 31 yd3 of PCB waste were stored at Oak Ridge National Laboratory (ORDOE1993b:9-7). PCB wastes are managed in storage facilities until they can be shipped offsite for treatment and/or disposal. PCB-contaminated and/or hazardous wastes are temporarily stored at Building 7507, and PCB-contaminated wastes are stored on the 7507W Storage Pad. Due to the "No Rad Added" policy, hazardous wastes are being stored as mixed waste. A listing of the hazardous waste storage facilities at Oak Ridge National Laboratory is shown in table H.2.3-14. Approximately 17 yd3 of asbestos wastes were sent offsite to the Y-12 Sanitary and Industrial Landfill II. About 20 yd3 of hazardous and PCB wastes were sent to K-25 for storage and incineration in the TSCA Incinerator (OR DOE 1993b:9-5). Nonhazardous Waste. Nonhazardous wastes result from Oak Ridge National Laboratory maintenance and utilities. The steam plant and the sanitary waste treatment plant produce a sludge that is sampled to demonstrate that it is nonhazardous and meets the Y-12 Industrial and Sanitary Landfill II waste acceptance criteria. Scrap metals are discarded from maintenance and renovation activities and are recycled when appropriate. Construction and demolition projects also produce nonhazardous industrial wastes. All solid nonhazardous wastes and medical wastes after they are autoclaved to render them non- infectious except scrap metal are sent to the Y-12 Industrial and Sanitary Landfill II. Approximately 27yd3 of scrap metal were placed in storage at Oak Ridge National Laboratory in 1992 until it is definitely characterized as nonradioactive per the "No-Rad Added" policy (OR DOE 1993b:9-7). K-25 Site. Enrichment, maintenance, decontamination, and research and development activities have generated a wide variety of waste at K-25. Because of its past uranium enrichment mission, uranium is the predominant radionuclide found in K-25 waste streams. Waste management activities are increasing. Low-level radioactive wastes from other DOE sites are being placed in building vaults until a final disposition strategy is identified. Also, PCB wastes and RCRA wastes contaminated with uranium began arriving from other DOE sites in 1987 for incineration in the K-1435 TSCA Incinerator. Tables H.2.3-16 and H.2.3-15 summarize the storage and treatment facilities at K-25 that are capable of storing and treating multiple categories of waste. Pollution Prevention. K-25 policy mandates minimization of waste generated while achieving compliance with applicable environmental regulations. Five waste reduction options are used at K-25: segregation, material substitution, process innovation, mechanical volume reduction, and recycling/reuse. In recent years, some aluminum cans, worker clothing, and office furniture have been recycled for use at K-25. Such recycling has saved approximately 2,500,00 lb of materials as of 1991. K-25 management supports the waste reduction program. An example of this program is the conversion to gas-fired boilers to reduce opacity excursions and, in effect, reduce or eliminate fly ash production. Spent Nuclear Fuel. K-25 does not generate or manage spent nuclear fuel. High-Level Radioactive Waste. K-25 does not generate or manage HLW. Transuranic Waste. K-25 does not generate or manage TRU waste. Low-Level Waste. Solid LLW is generated by discarding radioactively-contaminated construction debris, wood, paper, asbestos, trapping media, and process equipment and by removing radionuclides from liquid and airborne discharges. Currently, solid LLW is being stored for future disposal. Table H.2.3-17 shows the storage facilities that deal only with LLW. Specifics on some of the storage facilities are described below. Treatment of the current inventory of contaminated scrap metal at K-25 (as well as at Portsmouth, Paducah, and Fernald facilities) is expected to occur over the next 3 to 5 years as part of a comprehensive DOE Scrap Metal Program to be managed through K-25. All contaminated scrap metal is stored aboveground at the K-770 scrap metal facility until further disposal methods are evaluated. The Uranium Hexafluoride Cylinder Program is directed toward improving the safety and reliability of long-term storage for 7,000 cylinders currently at K-25. These cylinders remain from the now-terminated gaseous diffusion mission. In storage at the site are approximately 5,000 10-ton and 14-ton cylinders of depleted uranium hexafluoride; 1,000 cylinders of normal-assay feed uranium hexafluoride; 400cylinders containing more than 50 pounds of "enriched" material; and 600 miscellaneous empty cylinders. The Uranium Hexafluoride Cylinder Program is being designed to develop a clear understanding of the current conditions of the cylinders and define any near-term and long-term actions for safe storage of the cylinders pending decisions on ultimate disposition of the uranium hexafluoride material. Some of the initial actions in the program are a baseline inspection, a corrosion coupon program, and an ultrasonic thickness measurement program. The baseline inspection identified a variety of cylinder defects which will require special attention and also identified four breached cylinders. Immediate corrective actions have been taken to handle the breached cylinders and a schedule of activities has been developed for moving and repairing the cylinders. The cylinders containing normal-assay feed uranium hexafluoride are currently being shipped to the Paducah Gaseous Diffusion Plant. The current DOE direction for the 5,000 cylinders with depleted uranium hexafluoride is to store them until at least the year 2020, at which time conversion to oxide will be performed if no other uses have been determined. A plan for cleaning the cylinders containing more than 50 lb of enriched material and empties has not yet been approved (this may be performed at K-25 or at one of the operating gaseous diffusion plants). Currently, there are no onsite disposal facilities being operated at K-25. Energy Systems Waste Management Organization has been established and assigned the responsibility to design, construct, and operate all new LLW disposal facilities for the ORR. This orga- nization is physically located at K-25. Mixed Low-Level Waste. Mixed LLW primarily consists of contaminated waste oils, solvents, sludges, soils, and acid wastes. Table H.2.3-18 presents the inventory of mixed LLW as of December 31, 1992 along with a 5-year projection. Sludges contaminated with low-level radioactivity were generated by settling and scrubbing operations and were stored in K-1407B and K-1407C ponds. Sludges have been removed from these ponds, and a portion have been fixed in concrete at the K-1419 Sludge Treatment Facility and stored above ground at the K-1417 Drum Storage Yard. These materials are considered mixed LLW; however, a delisting petition has been submitted to EPA. Disposition of this waste is pending a determination of this petition. Most of the treatment of mixed waste is at the TSCA Incinerator and the Central Neutralization Facility. The majority of waste treated at the TSCA Incinerator cannot be treated by commercial incinerators because of radioactive contamination. All waste sent to this facility must be fully characterized and identified. DOE has an approved chain-of- custody system for all waste received from offsite. The K-1435 TSCA Incinerator is capable of incinerating waste that is mixed or that contains PCBs. In 1990, a limited amount of waste was incinerated as a part of the startup testing. The incinerator began full operations in early 1991 and met all regulatory requirements in processing 1,310 yd3 of mixed waste. Mixed TSCA waste is being generated in the ash residue at the TSCA Incinerator. Compliance issues regarding the management of the mixed PCB and radioactive waste generated in the ash are being pursued with EPA by DOE. Most of the radioactively-contaminated wastewater treated at the Central Neutralization Facility is generated at the TSCA Incinerator from the wet scrubber blowdown. Treated effluents are discharged through a designated release point. The contaminated sludges that precipitate in the sludge-thickener tank are stored in an approved above-ground storage area at K-25. RCRA mixed, radioactive land disposal restricted waste (including some nonradiological classified land disposal restricted waste) has been stored in some areas for longer than 1 year (OR DOE 1993a:9-26). These wastes are currently subject to the land disposal restriction that permits storage only for accumulation of sufficient quantities to facilitate proper treatment, recycling, or disposal. This waste is being stored because of the nationwide shortage of treatment and disposal facilities for these types of waste. Private-sector technology demonstrations are being conducted that involve uranium extractions from sludge. Uranium-contaminated PCB wastes (i.e., mixed wastes) are being stored in excess of the 1-year limit imposed by TSCA because of the lack of treatment and disposal capacities. DOE and EPA have signed a Federal Facility Compliance Agreement, effective February 20, 1992, to bring the facility into compliance with TSCA regulations for use, storage, and disposal of PCBs. It also addressed the approximately 10,000 pieces of nonradioactive PCB-containing dielectric equipment associated with the shutdown of diffusion plant operations. In 1989, during routine inspections of the drums of stabilized K-1407 Pond sludge at the K-1417 Storage Facility, it was discovered that many of the drums had begun to corrode. Free liquid (waste with a pHof 12) on top of the concrete in the drums was found to be causing the corrosion (OR DOE 1993a:9-16). An action plan has been implemented to decant and/or dewater the mixed waste contained in the drums. A total of 45,000 drums of stabilized material and 32,000 drums of raw sludge must be processed and moved to storage facilities that meet regulations governing mixed wastes. Of these 77,000 drums, 10,000 are currently stored in K-25 vaults and 67,000 are located at the K-1417A and K-1417B Drum Storage yards. It is planned that all containers will be transferred to and stored in new and existing facilities, the K-1065 site and K-31 and K-33 buildings, respectively. Hazardous Waste. Hazardous wastes generated at K-25 include PCB articles and items, waste oils and items, and uncontaminated asbestos waste. All hazardous wastes are managed according to applicable state and Federal regulations and DOE orders. Several waste management facilities are already in place. Changing laws and regulations have made it necessary to upgrade several facilities and to design and construct new facilities that reflect the most recent environmental technology. The Central Neutralization Facility and the TSCA Incinerator are the two major facilities that treat hazardous waste. The Central Neutralization Facility provides pH adjustment and chemical precipitation for several aqueous streams throughout K-25. The main purpose of the Central Neutralization Facility is to treat wastewater to ensure compliance with the requirements of NPDES discharge limits on pH, heavy metal concentrations, and suspended solids. The treatment system consists of two 25,000-gallon reaction tanks and a 60,000-gallon sludge-thickener tank. Acidic wastes are neutralized with a hydrated-lime slurry, and basic wastes are neutralized with sulfuric or hydrochloric acid. The hydrated lime bin and acid tanks are located at the facility. The treatment facility is physically divided into two distinct sections for treating both hazardous and nonhazardous waste streams. The TSCA Incinerator consists of storage tanks, dikes, and the incinerator. The incinerator system consists of a liquid, solid, and sludge feed system; a rotary kiln incinerator; and a secondary combustion chamber. The wastes treated at this facility include oils, solvents, chemicals, sludges, and aqueous waste. In general, most of the waste stored at K-25 is designated as hazardous waste which has been contaminated with PCBs. Recyclable materials such as mercury and silver-bearing photographic wastes are stored before recycling, while other hazardous wastes are stored until sufficient quantity is accumulated for an offsite shipment. All offsite disposals of hazardous wastes were halted in 1991 until procedures addressing a DOE performance objective of "No Rad Added" were developed by the sites and approved by DOE Headquarters. Incineration is the preferred method for offsite treatment or disposal of wastes, particularly PCB wastes; however, landfills and other types of disposal are used as needed. In 1992, 290 yd3 of asbestos were placed in the Y-12 landfill. Nonhazardous Waste. Computer paper is being recycled from the K-25 Computer Technology Center. The program for recycling paper is being reviewed for expansion into nonradiological areas. Product substitutions at the paint shop and photography lab have resulted in a decrease of waste generation. No percentage of reduction has been calculated due to the lack of baseline data. Waste assay monitors have been purchased and are being used to screen solid, potentially radioactive waste to determine the potential to manage it as a nonhazardous waste. The K-770 clean scrap yard provides storage for nonradioactive scrap metal. The scrap metal is stockpiled before being sold to the public. The solid nonhazardous waste from K-25 is sent to the Y-12 Industrial and Sanitary Landfill II. Some materials such as furniture, file cabinets, and paper are sold through property sales. The only nonhazardous treatment facility at K-25 is the sanitary waste treatment plant. The sanitary sludge is disposed of in the Y-12 landfill. Table H.2.3-1.-Low-Level and Mixed Low-Level Waste Treatment Capability at Y-12 [Page 1 of 2] Treatment Unit Treatment Method(s) Input Capability Output Capability Total Capacity Change (yd3 per year) Biodenitrification Neutralization pH Liquid mixed LLW (nitrate Biosludge to West End Treatment 1,500 RCRA permit-by-rule Unit (Bldg. adjustment nitrate solutions from enriched Facility (300,000 GPY) 9818) removal uranium recovery - Buildings 9212 and 9206) Central Pollution Filtration carbon Liquid LLW, mixed LLW, Treated wastewater discharged 9,900 Final NPDES permit May 1, 1990. Permit Control Facility adsorption, oil/water and hazardous waste through NPDES outfall and (2,000,000 GPY) only allows 28,000 gallons in three days. separation, and sludge (nonnitrate liquid wastes) solids to West Tank Farm Includes 4,930 yd3 of hazardous waste dewatering treated. Included in hazardous waste treatment table. Cyanide Chemical oxidation, pH Liquid mixed LLW and Wastewater to West End Treatment 33 Interim RCRA status September 29, 1992. Treatment adjustment hazardous waste (cyanide Facility (6,600 GPY) Facility spent plating batches) (Bldg. 9201-SN) Liquid Storage Oil/water separation by Liquid mixed LLW (leachate Stored liquids to Groundwater 12,400 Also a storage unit. Amount of mixed Facility (Bldg. filter cartridges from certain capped burial Treatment Facility and PCB- (2,500,000 GPY) LLW treated is approximately 4,300 yd3 9416-35) grounds in Bear Creek laden oil to TSCA incinerator per year. Valley) Depleted Calcination Solid mixed LLW (uranium Uranium oxide to depleted Design feedrate is Scheduled construction startup in 1996. Uranium fines) uranium oxide storage vaults classified. Oxidation Facility Groundwater Carbon absorption and air Liquid mixed LLW (Liquid Groundwater air stripper effluent, 12,400d Final NPDES permit May 23, 1990, and Treatment stripping Storage Facility spent carbon, and sludge to (2,500,000 gal/hr) RCRA permit submitted January 31, Facility groundwater) depleted uranium oxide storage 1990. Amount of mixed LLW treated is (Bldg. 9616-7) vaults and liquid effluent through approximately 4,300 yd3 per year. NPDES outfall Interim Reactive Open burning Solid LLW (sodium- Treated residue waste to depleted Campaign 2 times per State air permit submitted September 29, Waste Treatment potassium waste) uranium oxide storage vaults and year, 8 hours per 1992, and RCRA permit submitted Area treated waste to K-25 campaign, 15 GPD January 31, 1990. Interim facility awaiting completion of Reactive Waste Treatment Facility. Design feedrates 0.9 yd3 per year. Mercury Metal precipitation, Mercury contaminates from Wastewater effluent discharged via 130,000 Planned, but unapproved. Anticipated that Treatment filtration, carbon wastewater treatment NPDES. Solids require further (26,300,000 GPY) treatment rate limited to-50 gpm. Facility absorption stream treatment at another facility Capacity is maximum design value. Oak Ridge Thermal desorption, Liquid and solid mixed LLW - Planned Scheduled for 2004. Reservation decontamination, Mixed Waste stabilization, and sorting Treatment Facility Production Waste Decontamination, Solid mixed LLW - 8,650 Planned and available October 1, 2000. Treatment incineration, and (demolition waste, Design feedrate is 1.4 yd3/hr. Hours in Facility neutralization noncombustible LLW, and operation is estimated to be 6,000 hours. Phase II incinerator ash, mixed waste sludges, and mixed waste soils) Uranium Chip Incineration Solid LLW (depleted and Uranium oxide to depleted Classified yearly Final state air permit expires January 1, Oxidation normal uranium chips) uranium oxide storage vaults treatment 1994 and final NPDES permit approved Facility January 22, 1987. Design feedrate is 2,200 lbs/hr. Uranium Leaching, filtration, Metal and organic removal All waste diverted to 1,500b System is exempt from permitting Recovery dissolution, oxidation, from aqueous stream, Bioidentification Unit (300,000 GPY) requirements under agreement with the Operation evaporation, extraction aqueous neutralization, State Same capacity as (Bldg. 9206, purification for recycle Biodenitrification Unit. 9272) Uranium Filtration and precipitation Liquid mixed LLW Organic waste to TSCA 2 yd3/day Unit has been decommissioned and is in Treatment Unit (uranium-contaminated Incinerator at K-25 (500 GPD) standby mode. (Portable) organic solvents) Waste Coolant Extended activated sludge Liquid mixed LLW Oily solids to dewatering and 990 Also a storage unit. May be capable of Processing treatment, sludge drying (contaminated waste drums, biological solids to (200,000 GPY) treating of mixed LLW. Facility coolants) dewatering, and liquid to Central (Bldg. 9983-78) Pollution Control Facility or West End Treatment Facility/West Tank Farm Waste Feed Compaction Compactible solid LLW Compacted solid LLW to Y-12 24,800 An exemption for the state air permit has Preparation Sludge Handling Pad been granted. Design feedrate is 30 Facility yd3/hr. Intermittent operation at 8 (Bldg. 9401-4) hours/day and 2 days/week West End Absorption, anaerobic Liquid mixed LLW and Liquid effluent through NPDES 10,900 Final NPDES permit September 30, 1990 Treatment digestion, clarification, hazardous waste outfall (2,200,000 GPY) and interim RCRA status January 31, Facility coagulation, filtration, (radioactive-contaminated 1990. Design capacity is 2,700,000 (Bldg. 9616-7) flocculation, and and nonradioactive nitrate GPY). precipitation waste) Table H.2.3-2.-Low-Level and Mixed Low-Level Waste Storage Capability at Y-12 [Page 1 of 2] Storage Unit Input Capability Total Capacity Comment (yd3) 9811-1 Tank Storage Unit Liquid and solid hazardous (beryllium)- mixed LLW 671 RCRA permit submitted January 23, 1992 (OD-7) (135,000 gal) Above Grade Storage Pads Solid LLW 9,300 Above ground storage of low-level until Low-Level Waste Disposal Facility Alpha-4 Container Storage Area Solid mixed LLW (Old shutdown process waste) 1,970 RCRA permit submitted January 31, 1990. One area of building being modified for 95 yd3 of storage. (Bldg. 9404-7) Solid PCB and uranium contaminated waste 52 Storage of liquid and/or hazardous waste not permitted except for PCB waste. Capacity for 496 drums. As of August, 1994, 10 yd3 is available for storage. Buildings 9206 and 9212 Liquid/solid LLW and mixed LLW 26 Part B permit Building 9720-9 Storage Area Liquid/solid LLW and mixed LLW 1,290 Part B permit. As of August 1994 approximately 520 yd3 (260,000 gal) of LLW and mixed LLW stored. Hazardous waste in table H.2.3-5. Buildings 9825-1 and -2 oxide vault Solid LLW (depleted uranium oxide and metal) 1,340 Two vaults of reinforced concrete. Classified Waste Storage Area Solid LLW and mixed LLW 825 Part B permit. Estimated that inventory is approximately (Bldg 9720-25) 670 yd3 as of August 1994. Container Storage Facility Solid mixed LLW 133 RCRA permit submitted January 31, 1990 (Bldg. 9720-12) Contaminated Scrap Metal Storage Yard Solid mixed LLW (uranium-contaminated scrap). 3600 Estimated that inventory is approximately 240 yd3 as of August 1994. Cyanide Treatment Facility Cyanide spent plating batches, mixed LLW 11 Interim RCRA status September 27, 1992. Also (2,240 gal) treatment facility for hazardous and mixed wastes. DARA Solid Storage Facility Solid mixed LLW 6,620 Facility full as of August 1994 East Chestnut Ridge Waste Pile Solid mixed LLW (contaminated soil and spoil from 1,200 RCRA permit submitted January 31, 1990. Facility is full closure of RCRA units) as of August 1994. Kerr Hollow Quarry Liquid mixed LLW 802 Part B permit (162,000 gal) Liquid Organic Waste Storage Liquid and solid mixed LLW. Ignitable nonreactive and 52 RCRA permit submitted December 1, 1991. A diked and (Bldg. 9720-45, OD-10) radioactive waste. Can also include hazardous waste (10,600 gal) covered storage area for 120 drums of material. Also, included in hazardous waste storage table. Liquid Organic Waste Storage Tank 600A Liquid hazardous (corrosive) waste and mixed LLW 15 RCRA permit submitted January 31, 1990 (Bldg. 9720-45, OD-10) (3,000 gal) Liquid Organic Waste Storage Tank 600B Liquid hazardous (corrosive) waste and mixed LLW 15 RCRA permit submitted January 31, 1990 (Bldg. 9720-45, OD-10) (3,000 gal) Liquid Organic Waste Storage Tank 700A Liquid mixed LLW (uranium-contaminated gasoline and 32 RCRA permit submitted December 1, 1990 (Bldg. 9720-45, OD-10) diesel) (6,500 gal) Liquid Organic Waste Storage Tank 700B Liquid mixed LLW (uranium-contaminated rinsewaters) 32 RCRA permit submitted December 1, 1990 (Bldg. 9720-45, OD-10) (6,500 gal) Liquid Organic Waste Storage Tank 900A Radioactive rinsewater. 32 RCRA permit submitted December 1, 1990 (Bldg. 9720-45, OD-10) (6,500 gal) Liquid Organic Waste Storage Tank 900B Radioactive liquid solvents and organics 32 RCRA permit submitted December 1, 1990 (Bldg. 9720-45) (6,500 gal) OD-8/Container Warehouse Liquid and solid hazardous - mixed LLW 530 RCRA permit submitted January 23, 1992. Waste is (Bldg. 9811-1) (106,000 gal) eventually taken to OD-9 or OD-10. Oil Land Farm Storage Contaminated scrap metal 6,200 Facility is full as of August 1994 PCB, Shed Solid LLW and mixed LLW (PCB-contaminated waste 250 Part B permit (Bldg. 9720-58) included) RCRA and PCB Container Storage Area Solid mixed LLW 630 RCRA permit submitted January 23, 1992 (Bldg. 9720-58) RCRA Staging Area (Bldg. 9720-31) Liquid and solid mixed LLW and hazardous waste 220 RCRA permit submitted January 31, 1990 (45,000 gal) Solid Storage Facility Solid mixed LLW and hazardous waste to include PCB- 4,000 yd2 RCRA permit submitted January 31, 1990. Contains contaminated waste 4,000 yd3 waste pile contaminated with radioactivity. Waste Oil/Solvent Storage Facility I Liquid mixed LLW (including PCBs) and hazardous 17 RCRA permit submitted December 1, 1991. No reactives (Bldg. 9811-8) waste (3,400 gal) or ignitables. Interim storage until containers can be emptied into tanks. Waste Oil/Solvent Storage Facility II Liquid mixed LLW (including PCBs) and hazardous 200 RCRA permit submitted December 31, 1991. No (Bldg. 9811-8) waste (40,000 gal) reactives or ignitables. Material has been shipped to TSCA incinerator. Waste Oil/Solvent Storage Facility IV Liquid and solid mixed LLW (including PCBs) and 200 RCRA permit submitted December 1, 1991. No reactives (Bldg. 9811-8) hazardous waste (40,000 gal) or ignitables. Material has been shipped to K-25 TSCA incinerator. Waste Oil/Solvent Storage Facility V Liquid mixed LLW (including PCBs) and hazardous 200 RCRA permit submitted January 31, 1990. No reactives (Bldg. 9811-8) waste (40,000 gal) or ignitables. Material has been shipped to K-25 TSCA incinerator. West End Tank Farm Mixed LLW (sludge) 12,400 Permit by rule Table H.2.3-3.-Mixed Low-Level Waste at Y-12 Waste Matrix Number of Inventory as of Number of Waste Streams Total Generation Waste Streams December 31, 1992 Five-Year Projection Five-Year Projection (yd3) (yd3) Contact-Handled Aqueous liquids 10 (880 gal) 6 6 (1,200 gal) Organic liquids 42 450 35 870 (90,000 gal) (176,000 gal) Inorganic solids 25 6,500 15 800 Organic solids 23 55 14 90 Soils 8 8,400 4 40 Metal and inorganic debris 1 60 1 0.4 Combustible debris 41 120 29 310 Reactive metals 5 1 4 5 Beryllium waste 1 <0.1 None None Batteries 1 2 1 10 Other 22 20 10 12 Total 179 15,612 119 2,143 Source: DOE 1994k; OR DOE 1994a. Table H.2.3-4.-Hazardous Waste Treatment Capability at Y-12 Treatment Unit Treatment Input Output Total Comment Method(s) Capability Capability Capacity (yd3/yr) Central Pollution Control Facility Filtration, carbon adsorption, Liquid hazardous Rinsewater sludge to 9,900 Final NPDES, May 1, 1990. oil/water separation, and (concentrated plating waste, West Tank Farm and (2,000,000 GPY) Permit only mows 28,000 sludge dewatering cyanide rinsewater waste, liquid effluent to mixed gallons in three days. and plating rinsewater) and waste storage Total includes 4,970 yd3 liquid low-level (West Tank 9616-8) of mixed waste treatment. Also, included in mixed waste treatment table. Cyanide Treatment Unit Oxidation Cyanide spent plating batches Plating Solution to West End 33 Interim RCRA status (Bldg. 9201-5N) Treatment Facility (6,600 GPY) September 19,1992. Also, has 11 yd3 of mixed waste storage. Included in mixed waste treatment table. Plating Rinsewater Treatment Cyanide destruction, ph Liquid hazardous (plating Treated wastewater 40,000 Final NPDES and RCRA Facility (Bldg. 9409-11 adjustment electrochemical rinsewater) and mixed LLW discharged through Central (8,000,000 GPY) permit January 1, 1990. and 9623) chrome reduction, carbon Pollution Control Facility Also, included in mixed adsorption, and filtration NPDES outfall and solids waste treatment table. to West Tank Farm Table H.2.3-5.-Hazardous Waste Storage Capability at Y-12 Storage Unit Input Capability Total Capacity Comment (yd3) Building 9418-9 PCB-contaminated mineral oil 70 Below-grade, diked tank. (14,000 gal) Building 9720-9 Storage Area Liquid and solid hazardous wastes to 1,290 RCRA permit submitted September 24, 1991 and TSCA permit include PCBs (260,000 gal) approved September 24, 1991. Part of building included in mixed waste storage table. Disposal Area Remedial Liquid hazardous wastes 823 bulk Interim status November 1, 1988. Also, a treatment unit. Provides Actions Liquid Storage (166,000 gal) temporary storage prior to treatment. Includes two 75,000-gal bulk Facility (Bldg. 9416-35) storage tanks, a 6,000-gal oil storage tank, and a 10,000 gal tank for seep water. Oil Drum Storage Area PCB-contaminated oils 59 Site is closed except for tankers. (OD-3) (11,900 gal) Oil Landfarm Soils Solid hazardous waste contaminated 550 Final RCRA permit June 30, 1989. No new wastes are being stored. Storage Facility with PCBs and volatile organics (111,000 gal) (excavated soil from the closure of the Oil Landfarm) RCRA Staging/Area Liquid and solid hazardous waste to 221 RCRA permit submitted January 31, 1990. include PCB-contaminated waste (44,600 gal) Waste Oil/Solvent Storage Liquid hazardous waste including 200 RCRA permit submitted January 31, 1990. No radioactive Facility III (Bldg. 9811-6) PCBs (40,000 gal) contaminated waste, reactives, or ignitables. Waste Oil/Solvent Storage Liquid hazardous waste 200 RCRA permit submitted January 31, 1990. No radioactive waste, Facility IV (Bldg. 9811-6, (40,000 gal) PCB waste, reactives, or corrosives. OD-9) Table H.2.3-6.-Inventory of Reactor-Irradiated Nuclear Material at Oak Ridge Reservation Site Facility Type Number and Form Estimated Heavy Metal (yd3) Oak Ridge National Building 3019 SRS production fuel 176 cans 0.006 Laboratory - Building 3019 Hanford production fuel 42 cans 0.006 - Building 3019 Commercial fuel (Canada ConEd) 401 cans 0.08 - Building 4501 Commercial fuel 40 sections 0.0005 - Buildings 3525 and 7920, Dry Wells Research reactor fuel Fuel samples and targets 0.007 7823A, 7827, and 7829 - Bulk Shielding Reactor Research reactor fuel 41 BSR elements and 32 ORR 0.004 elements (pool 80 percent full) - Classified Burial Ground Unknown Unknown Unknown - High Flux Isotope Reactor Research reactor fuel 43 assemblies (pool 40 percent full) 0.04 - Homogeneous Reactor Experiment Wells Research reactor fuel 135 gallons of uranyl sulphate 0.0003 - Molten Salt Reactor Experiment Research reactor fuel LiF and BeF2 salt mixture 0.003 - Tower Shield Reactor Research reactor fuel 1 assembly (pool full) 0.0007 Y-12 Plant Building 9720-5 Space Nuclear Auxiliary Power-10 Fuel 36 rods in NaK 0.0004 - Building 9720-5 Health Physics Research Reactor Fuel 31 HPRR fuel pieces 0.01 Table H.2.3-7.-Mixed Transuranic Waste at Oak Ridge National Laboratory Waste Matrix Number of Inventory as of Number of Waste Streams Total Generation Waste Streams December 31, 1992 Five-Year Projection Five-Year Projection (yd3) (yd3) Contact-Handled Multiple, alpha 4 1,020 1 60 Remote-Handled Multiple, alpha 2 1,400 2 83 Total 6 2,420 3 143 Source: DOE 1994k; OR DOE 1994a. Table H.2.3-8.-Transuranic and Mixed Transuranic Waste Storage Capability at Oak Ridge National Laboratory Storage Unit Input Capability Total Comment Capacity (yd3) TRU Retrievable Concrete Cask Storage Contact-handled solid mixed TRU 961 Interim Part A permit (included in Part B application) Facility (Bldg. 7842) waste and LLW TRU Retrievable Concrete Cask Storage Remote-handled solid mixed TRU 182 RCRA Part B submitted March 1992. May contain lead and Facility (Bldg. 7855) waste mercury RCRA constituents. TRU Retrievable Drum Storage Facility Contact-handled solid mixed TRU 459 RCRA permit submitted May 21, 1984. Mainly 55-gallon (Bldg. 7826) waste drums. May contain lead. Only contact-handled TRU, less than 200 mrem per hour. RCRA closure is underway. TRU Retrievable Drum Storage Facility Contact-handled solid mixed TRU 534 RCRA permit submitted January 14, 1993. Mainly 55- (Bldg. 7834) waste gallon drums. May contain lead. Only contact-handled TRU, less than 200 mrem per hour. RCRA closure is underway. TRU Retrievable Drum Storage Facility Contact-handled and remote-handled 939 Under CERCLA closure (Bldg. 7802N Trenches) solid mixed TRU waste TRU Retrievable Concrete Cask Storage Contact-handled solid mixed TRU 961 Interim Part A permit (included in Part B application) Facility (Bldg. 7878) waste TRU Retrievable Drum Storage Facility Contact-handled solid mixed TRU 401 Interim RCRA Part A permit (included on RCRA Part B (Bldg. 7879) waste application). TRU Retrievable Drum Storage Facility Contact-handled solid mixed TRU 108 Interim Part A (Bldg. 7934) waste Table H.2.3-9.-Low-Level and Mixed Low-Level Waste Treatment Capability at Oak Ridge National Laboratory Treatment Unit Treatment Method(s) Input Capability Output Capability Total Capacity Comment (yd3 per year) Compactor (Bldg. 7831) Compaction Compactible solid Compacted solid LLW in B-25 14,800 Design capacity LLW (4x4x6 ft) boxes to K-25 Liquid Low-Level Waste Evaporation and ion exchange Liquid LLW and Evaporator condensates to 540 Normal operating capacity. Evaporation Facility mixed LLW Process Waste Treatment (109,360 GPY) Maximum capacity is 1,200 Plant. Some evaporator gal/hr for 20 hours per bottoms are stored at Melton month. Valley Facility. Melton Valley Low-Level Decantation and stabilization Remote-handled, Solid LLW concrete block to 248 Design capacity of 982 m3/yr. Waste Immobilization alpha liquid mixed storage (49,900 GPY) System is limited to 50,000 Facility LLW gallons per campaign. Nonradiological Clarification, dual media pressure Liquid and mixed Dewatered waste, carbon 977,000 Normal generating capacity. Wastewater Treatment filter, air stripper carbon adsorption, LLW liquid discharge (197,100,000 GPY) Design capacity is Plant (Bldg. 3608) neutralization filter press 1,980,000 yd3/yr. dewatering, ion exchange Process Waste Treatment Ion exchange, neutralization, Liquid LLW and Solid LLW 347,000 Normal operating capacity. Plant (Bldg. 3544) clarification, and filter presses mixed LLW (filter cake) to storage at K- (70,000,000 GPY) Design capacity is 25. Wastewater is sent to 521,000 yd3/yr. nonradiological Wastewater Treatment Plant. Waste Handling and Evaporation, microwave solidification, Solid mixed LLW Drums and boxes Planned Remote handling capability for Packaging Plant solid segregation and packaging packaging Source: DOE 1993h; DOE 1994k; DOE 1994n; OR DOE 1993a. Table H.2.3-10.-Low-Level and Mixed Low-Level Waste Storage Capability at Oak Ridge National Laboratory Storage Unit Input Capability Total Capacity Comment (yd3) Eight Melton Valley Storage Tanks W-24 Solid mixed TRU (sludge) and 1,980 RCRA permit submitted January 17, 1982. Solidified waste through W-31 (248 yd3 each) - Bldg. 783B LLW from LLW Evaporation Facility. Building 7823B, 7823E, 7827, 7829, LLW 2,750 No permit necessary 7831C, 7878A, B7823C, B7823D Buildings 7075, 7830A, 7934 Mixed waste 156 Interim RCRA Part A (included in RCRA Part B application) Bulk Contaminated Soil Facility Low-level contaminated soil 1,230 Planned and funded (Bldg. 7576) Class III/IV Waste Storage Class III and IV solid LLW 741 Planned and funded. RCRA Part B permit submitted March 30, 1992 Facility 7841 LLW (contaminated scrap metal) 578 No permit necessary Five Evaporator Service Tanks - Solid mixed LLW 1,240 Final RCRA permit submitted January 17, 1992 C-1 and C-2, W-21, W-23 (248 yd3 each) Mixed Waste Drum Storage Pad Solid and liquid mixed LLW 96 Interim Part B RCRA submitted May 21, 1992 (Bldg. 7507W) (19,400 gal) SWSA-6 Staging Facility (Bldg. B7878) Solid LLW and mixed waste 196 RCRA interim permit submitted January 14, 1993 Staging Facility-Semi Underground Mixed waste oils, solvents, and 144 RCRA interim permit submitted January 14, 1993 (Bldg. 7823) other process wastes (29,100 gal) Table H.2.3-11.-Low-Level Waste Disposal Units at Oak Ridge National Laboratory Disposal Unit Input Capability Capacity Comment (yd3) Asbestos Silos (SWSA-6) Low-level contaminated asbestos 614 Unit accepts only Y-12 asbestos, if contaminated with other than uranium contamination, other than that no offsite waste accepted Biological Trenches (SWSA-6) Low-level contaminated biological waste 3,310 Landfill operation High Range Silos (SWSA-6) Solid LLW (200 mrem/hr to 1 rem/hr) 2,740 Concrete silos inside diameter (15 ft x 8 ft) Interim Waste Management Solid LLW B-25 boxes encased in concrete 7,050 Planned - 6 Tumulus facilities (60 ft x 90 ft) Facility Low Range Silos (SWSA-6) Solid LLW (<200 mrem/hr) 5,030 Concrete silos inside diameter (15 ft x 8 ft) Tumulus Pad II (SWSA-6) Noncompactible contact handled (<200 mrem/hr) 783 Pad is 60 ft x 90 ft. Non-operational due to pending closure. solid LLW in B-25 boxes encased in concrete Table H.2.3-12.-Mixed Low-Level Waste at Oak Ridge National Laboratory Waste Matrix Number of Inventory as of Number of Waste Streams Total Generation Waste Streams December 31, 1992 Five-Year Projection Five-Year Projection (yd3) (yd3) Contact-handled Aqueous liquid 7 70 6 127 (14,100 gal) (33,400 gal) Organic liquids 9 150 6 130 (30,200 gal) (26,700 gal) Inorganic liquids 8 100 4 70 Solids 1 5 None None Debris 6 4 2 0.3 Lab packs 5 90 5 15 Elemental mercury 1 2 1 0.2 (320 gal) (30 gal) Batteries 1 2 1 1 Others 1 80 1 50 Remote-handled Aqueous liquid, alpha 2 3,040 1 459 (613,000 gal) (121,000 gal) Total 41 3,543 27 852 Source: DOE 1994k; OR DOE 1994a. Table H.2.3-13.-Hazardous Waste Treatment Capability at Oak Ridge National Laboratory Treatment Unit Treatment Method(s) Input Capability Output Capability Total Capacity Comment (yd3/yr) Chemical Detonation Open burning Solid and liquid explosive Residue (ash) to Sludge Campaign RCRA interim permit submitted Facility (Bldg. 7667) wastes (lab pack Fixation Facility for January 14, 1993 flammables) treatment Neutralization Facility Neutralization Liquid acids Liquid effluent through 58,800 Final RCRA permit submitted (Bldg. 3518) NPDES and storage to (11,900,000 GPY) January 17, 1992. Design Nonradiation Waste feedrate is 30 yd3/yr. Treatment Plant Nonradiological Wastewater Clarification, filtering, Liquid corrosive waste in Dewatered waste, carbon, 977,000 Normal operating capacity. Treatment Plant air stripping, absorption, storage. liquid discharge (197,100,000 GPY) Design capacity is 1,980,000 (Bldg. 3608) neutralization, yd3/yr. Also included in mixed dewatering, and ion waste treatment table. exchange Table H.2.3-14.-Hazardous Waste Storage Capability at Oak Ridge National Laboratory Storage Unit Input Capability Total Capacity Comment (yd3) Chemical Waste Storage Facility (Bldg. 7653) Solid explosives, lab pack chemicals, and 33 RCRA interim permit application submitted January 14, waste reactive metals (6,720 gal) 1993. Clean Oil Storage Pad (Bldg. 7651) Clean oil 37 RCRA interim permit submitted January 14, 1993. Can (7,470 gal) be used for mixed wastes. Hazardous Waste (PCB) Storage Facility Liquid PCB 41 RCRA interim permit submitted January 14, 1993. Can (Bldg. 7507) (8,220 gal) be used for mixed wastes. Hazardous Waste Storage Facility (Bldg. 7652) Hazardous bulk liquids and solids 74 Final RCRA Part B September 1, 1986. Can be used for (14,900 gal) mixed wastes. Long-term Hazardous Waste Storage Facility Liquid solid hazardous wastes 81 RCRA interim permit submitted January 14, 1993. (Bldg. 7654) (16,400 gal) Can be used for mixed wastes. Table H.2.3-15.-Low-Level, Mixed Low-Level, and Hazardous Waste Treatment Capability at K-25 Site [Page 1 of 2] Treatment Unit Treatment Method(s) Input Capability Output Capability Total Capacity Comment Central Neutralization Clarification, thickening, Liquid LLW, mixed LLW, and Liquid effluent through NPDES 189,000 yd3/yr Final NPDES permit October 1, Facility (K-1407H) and neutralization hazardous waste outfall and sludge to (38,000,000 GPY) 1992. Normal operating Hazardous Waste Storage Unit capacity. Permitted capacity is 58,400 GPY. Combustible Mixed Thermal destruction Combustible debris, Ash, Wastewater, Ash-flyash 635 yd3/yr Planned and unapproved. Waste Treatment heterogeneous debris Feasibility study estimated Facility treatment capacity at 800 tons per year. K-1420 Decon Facility Decontamination Solid LLW and mixed LLW Decon solution to Sludge Campaign Configured for LLW only. Can metal debris, inorganic non- Fixation Facility, degrease be modified to handle mixed metal debris, contaminated sludge and inorganic sludge to waste. equipment storage and rinsewater to Central Neutralization Facility TSCA Incinerator Incineration (rotary kiln) Liquid and solid - mixed LLW, Ash (solid mixed LLW and 2,440 yd3/yr (liquids) Final state air permit expires (K-1435) LLW and mixed LLW hazardous) to Hazardous (491,000 GPY) October 2, 1993; state RCRA contaminated with PCBs Waste Storage Unit, WSU- permit expires September 27, 012, ash water and blowdown 1997 and TSCA permit expires water (mixed LLW and March 20, 1992. Normal hazardous) to Central operating capacity. Max. Neutralization Facility, and capacity is 20,600 yd3/yr. sludge (solid mixed LLW) to Sludge Fixation Facility Waste Incinerator Incineration Type "O" waste contaminated Ash (solid LLW) to Hazardous 0.1 yd3/hr The facility is non-operational (K-1421) trash Waste Storage Unit, WSU-013 due to upgrades. Design feedrate. Wastewater Treatment Centrifugation, Liquid mixed LLW Leachate (liquid LLW) to 1 yd3/hr RCRA permit submitted Facility (K-1232) neutralization, and Central Neutralization Facility May 18, 1989. Design feedrate. precipitation and sludge (solid mixed LLW) Facility not currently being to Sludge Fixation Facility utilized. Metal and Debris Waste Surface decontamination Metal debris inorganic non- Wastewater treated debris, Planned and Plan to treat mixed waste. Treatment Facility metal debris, heterogeneous sludges unapproved Mixed Sludge Treatment Radioactivity Wastewater, treatment sludges, Stabilized sludges, stabilized Planned and Technologies and processes are Infrastructure concentration, ash, plating waste sludges solids-rad, wastewater unapproved still being determined. Plan to stabilization treat mixed waste. precipitation, filtration, off-gas treatment sampling analysis Staging and Processing Repackaging/bulking/cons Aqueous/halogenated organic Wastewaters, drums, organic Planned and Plan to treat mixed waste. Facility olidation, rinsing PCB liquids, absorbed organic rinsate unapproved drum, pH adjustment liquids, paint chip/solids, activated carbon, biological materials, organic chemicals, contaminated soils Waste Soils Treatment Thermal desorption Contaminated soils LDR soils, debris, scrubber Planned and Plan to treat mixed waste. Facility (primary), possible soil residues unapproved Available December 2004. watering Source: DOE 1994k; DOE 1994n; OR MMES 1993e. Table H.2.3-16.-Low Level, Mixed Low-Level, and Hazardous Waste Storage Capability at K-25 Site [Page 1 of 3] Storage Unit Input Capability Total Capacity Comment (yd3) Dewatered Raw Sludge Storage Solid mixed LLW, hazardous, and LLW 19,700 RCRA permit expires 2023. Design capacity. Includes 1,670 yd3 of mixed (Bldg. K-1065C) LLW. Dewatered Raw Sludge Storage Solid mixed LLW, hazardous, and LLW 10,500 RCRA permit expires 2002. Design capacity. Includes 8,660 yd3 of mixed (Bldg. K-31) LLW. Flammable Liquid Storage Tanks Liquid and mixed LLW, and hazardous 140 RCRA permit expires September 1, 2002. Two bulk storage tanks. (K-1202) waste (28,500 gal) Flammable Liquid Storage Unit Liquid and mixed LLW, and hazardous 140 RCRA permit expires September 1, 2002. Two bulk storage tanks. (K-1420A) waste (28,500 gal) Hazardous Waste Storage Unit, Solid mixed LLW and hazardous waste 601 RCRA permit expires September 1, 2002. Vault for radiogenic lead waste. WSU-002 (K-311-1) Includes 11 m3 of LLW as of June 1994. Hazardous Waste Storage Unit, Liquid and solid LLW, mixed LLW, 582 RCRA permit expires September 1, 2002. RCRA sludges and ash from WSU-005 (K-310-1) hazardous, and non-RCRA waste (117,000 gal) operation of K-1035 incinerator. Hazardous Waste Storage Unit, Liquid and solid LLW, mixed LLW, 576 RCRA permit expires September 1, 2002. Mixed waste capacity in 200 WSU-006 (Vault 2A) hazardous, and non-RCRA waste (116,000 gal) yd3. Hazardous Waste Storage Unit, Liquid and solid LLW, mixed LLW, 545 RCRA permit expires September 1, 2002. Has been used for RCRA, PCB, WSU-007 (K-309-3) hazardous, and non-RCRA waste (110,000 gal) and mixed wastes from all sites at ORR. As of August 1994, 463 yd3 of mixed LLW may be stored. Hazardous Waste Storage Unit, Liquid and solid LLW, mixed LLW, 563 RCRA permit expires September 1, 2002. Storage of laboratory wastes, Vault 4, WSU-011 (K-301-1) hazardous, and non-RCRA waste to (114,000 gal) acids, bases, and organics. include PCBs Hazardous Waste Storage Unit, Liquid and solid LLW, mixed LLW, 796 RCRA permit expires September 1, 2002. Waste consists of sludges and WSU-012 (K-301-1, Vault 4A) hazardous, and non-RCRA waste to (161,000 gal) incinerator ash. As of August, 1994, 564 yd3 of mixed LLW may be include PCBs stored. Hazardous Waste Storage Unit, Liquid and solid LLW, mixed LLW, 496 RCRA permit expires September 1, 2002. Waste consists primarily of WSU-013 (K-301-2, Vault 4B) hazardous, and non-RCRA waste to (100,000 gal) photographic waste and incinerator ash. include PCBs Hazardous Waste Storage Unit, Liquid and solid LLW, mixed LLW, 659 RCRA permit expires September 1, 2002. Storage of PCB organics and WSU-023 (K-302-4) hazardous, and non-RCRA waste to (33,000 gal) mercury-contaminated organics. As of August 1994, 500 yd3 of mixed include PCBs LLW can be stored. Hazardous Waste Storage Unit, Liquid and solid LLW, mixed LLW, 711 RCRA permit expires September 1, 2002. Storage of hazardous wastes WSU-024 (Vault 8A) hazardous, and non-RCRA waste to (143,000 gal) from K-25 and Y-12. include PCBs Hazardous Waste Storage Unit, Liquid and solid LLW, mixed LLW, 519 RCRA permit expires September 1, 2002. Storage of RCRA and mixed WSU-025 (K-302-5) hazardous, and non-RCRA waste to (37,000 gal) wastes from K-25 and Y-12. As of August 1994, 500 yd3 of mixed LLW include PCBs can be stored. Hazardous Waste Storage Unit, Liquid/solid mixed LLW, LLW and 775 RCRA permit expires September 1, 2002 WSU-026 (K-303-1) hazardous waste (156,000 gal) Hazardous Waste Storage Unit, Liquid/solid mixed LLW 648 RCRA permit expires September 1, 2002 WSU-028 (K-303-2) (131,000 gal) Buildings K-1232, K303-3, Liquid and solid mixed waste 904 Permitted K-305-12, K306-4 (182,000 gal) Building K-306-IT, WSU-067 vault, Liquid and solid hazardous waste 204 Permit not necessary (K-25) (41,200 gal) Buildings K-1417 and K-1419 Solid mixed waste (sludge) 11,600 Under RCRA closure Hazardous Waste Storage Unit, Liquid/solid mixed LLW, mixed LLW and 774 RCRA permit expires September 1, 2002. WSU-056 (Vault 19A) hazardous (156,000 gal) Hazardous Waste Storage Unit, Liquid/solid LLW, mixed LLW, and 463 RCRA permit expires September 1, 2002. Part of former K-305-6 vaults 19 WSU-057 (K-305-6) hazardous (93,400 gal) and 19B. Storage of K-25 pond waste sludge from closure of K-1407B pond. Hazardous Waste Storage Unit, Liquid/solid mixed LLW, LLW and 1,030 RCRA permit expires September 1, 2002. As of August 1994, 476 yd3 of WSU-066 (K-305-12) hazardous (208,000 gal) mixed LLW can be stored. Hazardous Waste Storage Unit, Liquid/solid LLW, mixed LLW, and 293 RCRA permit expires September 1, 2002. Sludges generated during WSU-067 (K-306-1) hazardous waste (59,200 gal) treatment of Y-12 wastewaters. As of August 1994, 130 yd3 of mixed LLW may be stored. Hazardous Waste Storage Unit, Liquid/solid LLW, mixed LLW, and 562 RCRA permit expires September 1, 2002. Sludges generated during WSU-068 (Vault 23A) hazardous waste (113,000 gal) treatment of Y-12 wastewaters at either K-1232 or Y-12 facilities. As of August 1994, 427 yd3 of mixed LLW may be stored. Hazardous Waste Storage Unit, Liquid/solid LLW, mixed LLW, and 483 RCRA permit expires September 1, 2002. Storage of RCRA, PCB, and WSU-070 (K-306-3) hazardous waste (97,500 gal) mixed wastes from K-25, Y-12, and ORNL. As of August 1994, 375 yd3 of mixed LLW may be stored. Hazardous Waste Storage Unit, Liquid/solid mixed LLW, LLW and 374 RCRA permit expires September 1, 2002. WSU-072 (K-306-4) hazardous waste (75,400 gal) Hazardous Waste Storage Unit, Liquid/solid mixed LLW, LLW and 1,350 RCRA permit expires September 1, 2002. Design capacity. As of August WSU-074 (Vault 25A) hazardous waste (271,000 gal) 1994, 375 yd3 of mixed LLW can be stored. Hazardous Waste Storage Unit, Liquid/solid LLW, mixed LLW, hazardous 174 RCRA permit expires September 1, 2002. Used for solvents and waste oil WSU-1000 (K-1036-A) (35,100 gal) storage. Oil may be contaminated. Maximum capacity is 2,000 55-gal drums. Hazardous Waste Storage Unit, Liquid/solid LLW, mixed LLW, hazardous, 409 RCRA permit expires September 1, 2002. No reactives or incompatibles. WSU-1003 (K-711) and non-RCRA waste to include PCBs (82,400 gal) Waste oils and solvents generated at Fernald, Ohio and other DOE facilities. Max. capacity of 1,800 55-gal drums. As of August 1994, 304 yd3 of mixed LLW may be stored. Hazardous Waste Storage Unit, Liquid/solid LLW, mixed LLW, and 11 RCRA permit expires September 1, 2002. No incompatibles. Used for out- WSU-1004 (K-1025C) hazardous wastes (2,250 gal) of-date or off-specification laboratory chemicals - disposed through offsite commercial facilities. As of August 1994, 7 yd3 of mixed LLW may be stored. Hazardous Waste Storage Unit, Liquid/solid LLW, mixed LLW, hazardous, 4 RCRA permit expires September 1, 2002. Gases are commercial products WSU-1005 (K-1302) and non-RCRA compressed gas (747 gal) that are to be discarded or treated. K-31 WP (Dewatered Raw Sludge Hazardous/mixed waste 10,500 RCRA permit expires September 1, 2002. Storage of solidified pond waste Storage) sludge from closure of K-1407-B and -C ponds. As of August 1994, 8,680 yd3 of mixed LLW can be stored. K-33 WP Mixed waste 15,700 RCRA permit expires September 1, 2002. Storage of solidified pond waste sludge from closure of K-1407-B and -C ponds. As of August 1994, 11,100 yd3 of mixed LLW can be stored. K-306-IT (Bldg K-25, Hazardous TSCA waste 204 RCRA final permit expires September 1, 2002. Will be used for RCRA and WSU-067 vault) (53,900 gal) mixed wastes from K-25, Y-12, and ORNL. Currently, empty PCB- contaminated containers from K-25 and Y-12 being stored in vault. RCRA Storage Unit (WSU-009), Liquid and solid LLW and hazardous 381 RCRA final permit expires September 1, 2002. Vault 3A wastes (76,900 gal) TSCA Container and Tank Storage Non-PCB contaminated flammable liquid 689 TSCA incinerator has three storage areas. The tank farm has 3 10,000-gal (K-1435) and mixed low-level that is also PCB- (139,000 gal) and 12 5,000-gal tanks for liquid only. Area B (TSCA waste) can store contaminated 352 55-gal drums and Area C (RCRA waste) can store 496 55-gal drums. Final state air permit expires October 1, 1993 and state RCRA permit submitted August 1, 1991. TSCA Storage Unit (K-33) Liquid and solid hazardous waste 1,260 No permit required (254,000 gal) TSCA Storage Unit (K-726) Liquid and solid non-RCRA, 124 No permit required. As of August 1994, 111 yd3 of hazardous waste is nonradioactive waste contaminated with (124,900 gal) stored. PCBs TSCA Storage Unit, WSU-031 Liquid and solid LLW and non-RCRA, 764 RCRA permit submitted October 1, 1991. (K-303-4) nonradioactive waste contaminated with (154,000 gal) PCBs Waste Oil/Hazardous Wastes Storage I Liquid and solid LLW and mixed LLW 244 RCRA state permit submitted March 1, 1991. Wastes stored include oils, (K-1425 container) (49,000 gal) solvents, water, and organics. Maximum capacity is 480 55-gal drums. Waste Oil/Hazardous Wastes Storage Liquid LLW and mixed LLW 450 Final air permit expires October 1, 1995 and RCRA state permit submitted II (K-1425 tanks) (90,000 gal) August 1, 1991. Wastes stored include oils, solvents, water, and organics. Four 22,500-gal tanks. Waste Staging Facility (K-1423) Liquid and solid non-RCRA, 371 Planned and funded for April 1, 1999 nonradioactive; hazardous; LLW; and (74,800 gal) mixed LLW Vault 6 LLW 222 No permit necessary K 303-3/Vault 6A, Vault 11A Solid LLW and mixed LLW 10,400 Permitted. As of August 1994, 774 yd3 of mixed LLW can be stored. Table H.2.3-17.-Low-Level Waste Storage Capability at K-25 Site Storage Unit Input Capability Total Capacity Comment (yd3) LLW Drum and Container Liquid and solid LLW 4,450 No permit necessary Facilities (897,000 gal) Contaminated Scrap Metal Solid LLW (uranium-contaminated scrap 265,000 6.9 acres of contaminated scrap metal. As of August 1994, 29,600 yd3 of LLW Yard (K-770) metal, ferrous and nonferrous) can be stored. LLW Storage Unit, Solid LLW 753 Used for nonhazardous radioactively contaminated waste generated at ORNL. WSU-004 (K-310-2) LLW Storage Unit, Solid LLW 867 Used for nonhazardous radioactively contaminated waste from K-25. WSU-008 (K-309-2) LLW Storage Unit, Liquid and solid LLW 616 RCRA permit expires September 1, 2002. Construction upgrades required before WSU-032 (K-303-5) (124,000 gal) storage of mixed waste. Used for nonhazardous radioactively contaminated waste from K-25. LLW Storage Unit, Solid LLW 737 RCRA interim status September 1, 1990. Construction upgrades required before WSU-044 (Vault 15A) storage of mixed waste. Used for nonhazardous radioactively contaminated waste from K-25, Y-12, and ORNL. LLW Storage Unit Solid LLW 519 Used for nonhazardous radioactively contaminated soil from Y-12. As of August (K-306-2) 1994, 246 yd3 of LLW can be stored. LLW Storage Unit, Solid LLW 449 Used for nonhazardous radioactively contaminated soil from Y-12. As of August WSU-076 (K-306-7) 1994, 412 yd3 of LLW can be stored. LLW Storage Unit, Solid LLW 5,010 Outdoor storage area (K 1066-H) RUBB-2 Tent (K-1313A) Solid LLW 178 Permit not necessary Vault 6 (K-25) Solid LLW 170 No permit necessary Table H.2.3-18.-Mixed Low-Level Waste at K-25 Site Waste Matrix Number of Inventory as of Number of Total Generation Waste Streams December 31, 1992 Waste Streams Five-Year Projection (yd3) Five-Year Projection (yd3) Contact-handled Aqueous liquids 15 359 4 204 (72,400 gal) (41,200 gal) Organic liquids 27 1,300 9 6,070 (263,000 gal) (1,220,000 gal) Inorganic residues 8 12,400 6 979 Organic residues 22 676 None None Uncategorized soils 1 5 1 12 Metal and inorganic debris 15 236 10 638 Reactive metals 1 <0.1 None None Labpacks 18 4 10 8 Compressed gases 5 3 2 9 Elemental mercury 3 221 1 10 Elemental lead 1 28 1 7 Batteries 2 8 1 37 Uncategorized 4 17 None None Cement forms 1 20,700 None None Total 123 36,000 45 7,770 Source: DOE 1994k. H.2.4 Pantex Plant This section describes the baseline conditions and specific waste management operations at Pantex. As part of its normal operations, Pantex generates low-level, mixed low-level, hazardous, and nonhazardous wastes. Tables H.2.4-1 and H.2.4-2 present a detailed description of treatment and storage facilities with estimated capacities. Pantex's goals regarding the management of LLW, mixed LLW, and hazardous wastes are to: Minimize the volumes of low-level radioactive and hazardous wastes generated to the extent technologically and economically practicable. Recycle those wastes applicable to the best available technology. Minimize contamination of existing or proposed real property and facilities. Ensure safe and efficient long-term management of all wastes. Pollution Prevention. Pantex has a waste minimization program that was formed to define an effective waste minimization system for the site. A committee provides awareness of the program, identifies tasks, and provides liaison between the site and outside entities. Some of the accomplishments of this program are as follows (PX MH 1991a:8-11): Compaction of 1,200 drums to approximately 250 drums. Disposal cost savings of approximately $300,000 was achieved. Separation of radioactive and hazardous waste materials when shearing weapons components. Reclamation of gold from this process netted $243,000. Reclamation of oil, antifreeze, and refrigerant. Substitution of scintillation solution that is nonhazardous. Reuse of explosives and solvents. Repackaging of paint into smaller containers. Substitution of naphtha with nonhazardous biodegradable cleaning solution. Transuranic Waste. No TRU waste or mixed TRU wastes are currently generated at Pantex during normal operation. However, there is a potential for an off-normal event to generate small amounts of contact-handled TRU waste during a weapon dismantlement activity. Three drums of TRU waste were generated several years ago from an incident during weapon dismantlement. Ultimately, Pantex plans to ship its TRU waste to a DOE-approved storage site when available. Low-Level Waste. The waste streams for LLW have the following options available for management consideration (PX MH 1990b:13): Continue to ship to a DOE-approved disposal site such as NTS. Compact solid waste, if possible. Computerize tracking of radioactive waste. Implement improved segregation program. Solid LLW generated consists of contaminated parts from weapons assembly and disassembly functions and waste materials associated with these functions, such as protective clothing, cleaning materials, filters, and other similar materials. The compactible components of this waste are processed at the Pantex Solid Waste Compaction Facility and staged along with the noncompactible components for shipment to a DOE-approved disposal site. Table H.2.4-3 lists Pantex's primary LLW streams, how they are generated, primary radioactive constituents, and method of storage or disposal. Table H.2.4-4 provides an inventory of LLW at Pantex as of December 2, 1994, and a 5-year generation projection. Mixed Low-Level Waste. The waste streams for mixed LLW have the following options available for management consideration: Treat to satisfy Land Disposal Restrictions requirements and ship to a DOE-approved facility for storage or disposal. Treat to satisfy Land Disposal Restriction requirements and ship to a commercial-approved facility for storage or disposal. Ship offsite for treatment and disposal. Pantex generates solid mixed LLW during weapons component testing functions. These wastes consist primarily of depleted uranium and beryllium residue and fragments from explosive components tests, contaminated gravel, cleaning materials, and protective clothing associated with these operations (PXMH1990b:35). Other mixed LLW streams include cleaning materials from weapons assembly and disassembly operations. Table H.2.4-5 lists Pantex's primary mixed waste streams, how they are generated, primary constituents, materials, and method of treatment. Table H.2.4-6 lists the mixed waste storage inventory as of April 15, 1994. Projections for the following 5 years are also included. The FS-23 facility has a containment test fire chamber where oxides of depleted uranium and beryllium are generated from testing. The chamber and equipment are cleaned after each test and the residue (solid waste) is placed into shipping containers. The containers are monitored for contamination and then forwarded to a staging area for shipment offsite. Mixed LLW (HE-contaminates only) is currently treated at the Burning Ground which has an operating capacity of 38 yd3 per year (DOE 1994k). The Hazardous Waste Treatment and Processing Facility is being planned to treat mixed LLW in the future. Hazardous Waste. The waste streams for hazardous waste have the following options available for management consideration: Continue to ship to approved hazardous waste disposal facilities. Encapsulate solid waste and ship to a DOE-approved disposal site. Treat onsite for neutralization of corrosive wastes. Table H.2.4-7 lists Pantex's primary hazardous waste streams, how they are generated, primary constituents, and method of storage or disposal. Table H.2.4-8 presents the inventory and a 5-year projections for hazardous waste as of December 2, 1994. The treatment of hazardous waste is done at the following facilities: The Burning Ground is an open-burning area where explosives, explosive-contaminated waste, and explosive-contaminated spent solvents are burned. A large volume reduction is attained using this method. The Hazardous Waste Treatment and Processing Facility will be involved in the processing of liquid/solid hazardous waste and classified materials made from hazardous materials. The facility has been planned and approved and should be available in 1998. Hazardous waste is also shipped offsite to commercial RCRA-permitted facilities. There are several separate storage facilities for hazardous wastes. Hazardous Waste Drum Storage Area- All liquid drums are placed in spill-containment pans. The facility is inspected weekly for leakers. Small lab samples of hazardous waste are stored in two chemical storage containers in this area. The materials stored there are as follows: - Asbestos; - Mercury-contaminated wastes; - Burning Ground ash; and - Electroplating sludge. At Building 16-1, used crank case oil is stored underground until sufficient quantities are generated for offsite processing. Nonhazardous Waste. The Sewage Community Treatment Quality Upgrade is a fiscal year 1996 EM project at Pantex. This project would upgrade the Pantex sanitary system to ensure that wastewater standards are met through secondary/tertiary treatment. Included in this project is the upgrade of the existing treatment lagoon to treat sewage, repair and replace existing deteriorated sewer lines, construct a closed system to eliminate the use of open ditches for conveyance of industrial wastewater discharges, and implement a plant stormwater management system. Table H.2.4-1.-Waste Treatment Capability at Pantex Plant Treatment Unit Treatment Method(s) Input Capability Output Capability Total Capacity Comment Batch Master Hazardous Filtration, neutralization, Bldg. 12-5C metal cleaning bath, Batch master metal Process as needed Nonoperational due to Waste Tank System and precipitation plating process waste, sodium precipitates to pending closure (Bldg. 12-68) hydroxide radiator cleaner, and Hazardous Waste spent electrolyte solutions Storage Pad and effluent to Wastewater Treatment Plant Building 11-15A Immobilization Mixed LLW To be determined 240 yd3/yr Planned Building 11-9 Immobilization Mixed LLW To be determined 240 yd3/yr Planned Burning Cages (2) Open burning HE-contaminated trash Ash 164 yd3/batch Interim permit until December 31, 1999. Nonoperational due to upgrades/major repairs Burning Pads (3) Open burning HE and wet HE Ash to 11-7N Storage Process as needed Interim permit until -Burning Ground Pad December 31, 1999 Burning Trays (9) Open burning Bulk explosives Ash to 11-7N Storage 0.7 yd3/batch No two adjacent trays are -Burning Ground Pad allowed to burn at the same time. Closed-Loop Decon Reduction Contaminated lead (solid mixed Acid Bath (liquid mixed Campaign One process per year. System LLW) LLW) to NSSI Standby mode. Compactor (Bldg. 12-42) Hydraulic ram compactor Solid LLW (gloves, kim wipes, Compacted LLW in Process as needed No TRU waste, Greater- - in-drum compaction paper) 17H 55-gallon drums than-Class C, mixed to Storage Igloo 4-56 waste, free liquids, or gases Flashing Pits (3) -Burning Open burning Encased explosives, Flashed scrap to sale as Process as needed Interim permit until Ground demilitarization, and scrap December 31, 1999 sanitization, HE-contaminated equipment, and HE Hazardous Waste Immobilization Liquid and solid mixed LLW and To be determined 655 yd3/yr Available for treating Treatment & Processing repackaging, hazardous waste mixed waste by 1999 Facility neutralization compaction, shredding, sorting, and solidification Table H.2.4-2.-Waste Storage Capability at Pantex Plant Storage Unit Input Capability Total Capacity Comment (yd3) Buildings 11-7A and 11-7B Liquid and solid mixed LLW 527 Permitted and operating storage capacity. (106,000 gal) Buildings 4-46, 4-72, and 4-74 Liquid and solid mixed LLW 245 Permitted capacity pending permit modification. (49,500 gal) Operating capacity is 157 yd3. Conex Containers WM-1 to WM-8 Containerized solid mixed low-level and 750 Permit dated April 1, 1991. Permitted capacity. silver photo wastes Operating capacity is 157 yd3. Conex Container WM-1A, WM-1B, WM-3A, Containerized liquid and solid LLW 494 No plans to receive offsite waste. Permitted capacity WM-5A, and WM-5B. (99,700 gal) pending permit modification. Operating capacity is 98 yd3. Hazardous Waste Storage Pad (Bldg. 11-7N) Various liquid and solid hazardous wastes 164 Interim permit dated April 19, 1990. Permitted and (33,000 gal) operating capacity. Hazardous Waste Storage Pad (Bldg. 11-9N) Various liquid and solid hazardous wastes 496 Permit dated March 1994. Permitted capacity. (100,000 gal) Operating capacity is 329 yd3. Igloo 4-50 Liquid and solid mixed LLW 552 Final permit dated April 24, 1992. Permitted capacity. (111,000 gal)) Operating capacity is 52 yd3. Igloo 4-56 Liquid and solid LLW 56 No plans to receive offsite waste (11,400 gal) RCRA Hazardous Waste Storage Staging Containerized liquid and solid mixed LLW 1,370 RCRA permit submitted April 1, 1990. Permitted Facility (Bldg. 16-16) (276,000 gal) capacity. Operating capacity is 426 yd3. Expected to be operation in 1997. Warehouse (Bldg. 12-42) Solid LLW 21,900 Short-term storage for drums that go to Bldg. 4-56. Amount stored as of December 1993. Table H.2.4-3.-Low-Level Waste Streams at Pantex Plant Source Waste Description Radioactive Constituents Primary Materials Disposal Assembly/ Debris from demilitarization and Thorium, U-238, tritium General noncompactible Disposal at DOE-approved dismantlement sanitization operations crushed/granulated plastic and metal offsite facility. operations debris Assembly/ Compactible material from normal U-238, tritium, thorium, Lab wipes and other support materials Disposal at DOE-approved dismantlement/ assembly/dismantlement/stockpile and plutonium offsite facility. stockpile surveillance. surveillance operations Assembly/ Radiological materials from normal U-238, tritium, thorium, Protective clothing, wipes, swipes, tape, Disposal at DOE-approved dismantlement and operation associated with weapons and plutonium plastic, and other material in the offsite facility. stockpile assembly, dismantlement, facility radiation protection program. surveillance surveillance, container monitoring, operations and routine sample counting operations. Weapon component Debris generated during past testing of Depleted U-238 residue Contaminated soil and gravel, additional Stored onsite pending testing and mock devices associated with any miscellaneous materials. eventual shipment to DOE- evaluation known waste stream. approved disposal site. Decontamination Materials generated during the Tritium Protective clothing, concrete rubble, Stored onsite pending products decontamination of a concrete solidified liquids, tools, equipment, and eventual shipment to DOE- assembly work cell (one time plastic and paper products containing approved disposal site. generation). tritium. Source: PX Battelle 1995a. Table H.2.4-4.-Low-Level Waste Inventory at Pantex Plant Waste Stream Name Inventory as of December 2, 1994 Total Generation Five-Year Projection (yd3) (yd3) Beryllium solid waste 140 931 Tritium contaminated waste (solid/liquid) 72 234 (14,500 gal) (47,300 gal) Labpacks, nonregulated radioactive (solid) 1 1 Contaminated soil 10 10 Waste water 9 12 (1,760 gal) (2,370 gal) Contaminated metal 0.03 0.03 Desiccant 0.3 29 Plant refuse (paper, foam, rags, cardboard) 138 932 Total 370 2,150 Source: PX Battelle 1995a. Table H.2.4-5.-Mixed Low-Level Waste Streams at Pantex Plant [Page 1 of 2] Treatability Group Waste Stream Name Composition Process Description Treatment Alternatives Organic liquids Paint waste and organic Paint and solvent Stripping, surface preparation, and Encapsulation, incineration, molten salt liquid repainting. destruction, filtration, centrifugation, oxidation, reduction, and amalgamation (Hg only) - Spent solvents Freon, methyl ethyl ketone, Cleaning dissolution of HE - HE, and dimethyl sulfoxide - Mercury contaminated Mercury contaminated oil Vacuum pump oil change - liquid - Organics, miscellaneous Halogenated and non- Paint, solvent and special product - halogenated solvents material storage - Scintillation fluids Scintillation fluids packaged Radioactivity testing - with vermiculite Aqueous liquids Wastewater Water, HE, chromium, lead Water-jet and thermal shock activities Incineration, wastewater treatment - Alodine solution Chromic acid, fluoride salts, Surface preparation before paint - and iron cyanide removal - Rinse water, equipment Water, metals, and solvents Rinsing equipment - wash - Metal cleaning waste Water, alodine, nitric acid, Etching and cleaning of metals - uranium, thorium cadmium, Cr, lead and Hg Inorganic solids Lead waste Portion of lead drum liner Removal of lead liner from drum Plasma melting, chemical leaching, and encapsulation - Ash, Burning Ground Inorganic ash residue Burning of HE - Soils ER Program potential mixed Spill cleanup, drill cuttings, ER Program site contaminated soils Encapsulation, thermal, physical, chemical, and waste (soils) sample waste containment Debris Organic debris: solvent- Alcohol, kimwipes, filters, Weapon dismantlement and Encapsulation, incineration, metal melting, contaminated solids rags, leads, solvents maintenance slagging, plasma melting, molten salt, aqueous washing, chemical leaching, sonification, and amalgamation (mercury only) - Inorganic debris: Contaminated scrap metal Demilitarization activities - contaminated scrap metal from demilitarized and sanitized weapons parts - Inorganic debris: lead- Seals and tape intermixed Demilitarization sanitation activities - contaminated waste with glass and paper - Inorganic debris: mercury- Glass bulbs, mercury- Maintenance of lighting - contaminated solids contaminated solids - Heterogeneous debris; metal Metals, solvents, lead, Maintenance and special activities - contaminated waste tritium, beryllium - Solvent contaminated solid Solvents and heavy metals Painting, paint removal, maintenance, - waste and heterogenous testing, and dismantlement activities debris Explosives Wastewater sludge from Explosive contaminated Filtering of wastewater with HE Open Burning (non-Plutonium contaminated) explosives solids, DMSO Aqueous washing, base hydrolysis, and chemical leaching - Explosive contaminated High-explosive residue, Assembly/disassembly processes - support material mercury Batteries (demilitarized and Batteries (demilitarized and Nickel cadmium, lead, Dismantlement activities Encapsulation, metal melting, and slagging sanitized) sanitized) nickel Compressed gases (aerosol Aerosol containers Discarded paint cans General maintenance Decontamination and disposal containers) Table H.2.4-6.-Mixed Low-Level Waste Inventory at Pantex Plant Treatability Group Number of Inventory as of Total Generation Waste Streams April 15, 1994 Five-Year Projection (yd3) (yd3) Aqueous liquids 3 7 32 (1,470 gal) (6,450 gal) Organic liquids 5 11 3 (2,310 gal) (505 gal) Inorganic solids 2 30 0.2 Soils 1 0.2 None Debris 6 95 123 Lab packs 1 2 2 Explosives 2 11 76 Liquid mercury 1 1 liter None Batteries 1 0.1 2 Compressed gases 1 0.3 None Total 23 153 238 Source: 69 Table H.2.4-7.-Hazardous Waste Streams at Pantex Plant Process Generation Constituents Materials Disposal/Storage Method High explosives Materials generated during manufacture High explosives HE machining coolant fluid, Filtration, settlement, Burning machining and retirement. HE waste scrap, retired HE Ground treatment, monitor and components bury burn residue Spent solvents-explosive, Materials generated from chemicals used in High explosives, Explosives contaminated Evaporate solvents and ignite contaminated synthesis and solvents used in formation solvents spent solvents residue at Burning Ground, of HE. disposal offsite at EPA- and state-approved site Mercury contaminated Materials generated in lab glassware during Mercury, vacuum pump Mercury, vacuum pump oil, Held for recycle or disposal at waste vacuum pull down and in following clean- oil pump filter, paper waste, rags, offsite EPA- and State- up. gloves, other miscellaneous approved site clean-up materials Explosive contaminated, Materials generated during explosive High explosives Explosives, contaminated Burn at Burning Ground, monitor solid waste processing. mops, rags, wipes, boxes, and bury in landfill and paper. Chrome plating waste Materials generated during chrome Chromium Chromium-contaminated Filter chromium, monitor liquid electroplating process in machine shop spent chemicals and discharge to sanitary sewer, plating room. drum CrOH cakes for disposal at authorized site Cleaning liquid Materials generated during parts cleaning Petroleum naphtha/ Cleaning liquid compound Offsite-approved disposal compounds operations at vehicle maintenance facility. mineral spirits Immersion carburetor Materials generated during vehicle Waste compound Carburetor cleaning liquid Offsite reclamation cleaner carburetor cleaning. cleaning liquid Miscellaneous discarded Materials generated during lab operations, Miscellaneous lab Miscellaneous lab chemicals Offsite-approved disposal lab chemicals collected through a periodic sweep of labs. chemicals Silver contaminated Materials generated during photograph Photo chemicals Silver contaminated photo Reclamation of silver photo waste silver activities. chemicals, photo paper, recovery canisters Lead shields Materials generated during removal of lead Lead Lead shields Sold as scrap lead shields. Radiator cleaner Materials generated during vehicle radiator Sodium hydroxide Radiator cleaner Offsite-approved disposal site cleaning operations. Paint waste Materials generated during vehicle product Paint and paint sludge Paint and paint sludge Offsite-approved recycler and industrial maintenance. Spent carbon Materials generated during filtering High explosives Contaminated carbon filters Burned at burning ground, ash to explosives contaminated wastewater. offsite approved disposal site Source: PX MH 1988a; PX MH 1990b. Table H.2.4-8.-Hazardous Waste Inventory at Pantex Plant Waste Stream Name Inventory as of Total Generation December 2, 1994 Five-Year Projection (yd3) (yd3) Explosive-contaminated solid waste 5 30 Burning Ground waste from thermal treatment 2 10 Labpacks (solid) 0.6 7 Photographic film 0 1 Lead waste 0 0.1 Spent halogenated and nonhalogenated solvents 2 45 and mixtures (462 gal) (9,090 gal) Heavy metal contaminated parts 0 1 Sodium hydroxide waste (solid) 0 10 Paint sludge 3 4 (610 gal) (832 gal) Wastewater from operations and monitoring 0.6 15 (116 gal) (2,970 gal) Metal cleaner and photographic waste 0.1 17 (13 gal) (3,420 gal) Recyclable and nonrecyclable used batteries 0.5 258 Solvent-contaminated solids 4 39 Mercury (solid/liquid) 0 <0.1 (3 gal) Sandblasting waste 0.8 2 Lead-contaminated waste 0 0.9 Miscellaneous organics (solid/liquid) 0.6 20 (111 gal) (4,040 gal) Contaminated engine oil 0 3 (568 gal) Oil filter waste <0.1 0.6 Miscellaneous discards contaminated with heavy metals 30 932 Empty organic compressed gas cylinders 0.4 31 Recyclable scrap metal with precious metals 0.2 2 Total 50 1,430 Source: PX Battelle 1995a. H.2.5 Savannah River Site The process of manufacturing useful nuclear materials has produced radioactive, mixed, and hazardous wastes that are treated, stored, or disposed of on SRS. The Savannah River Site Waste Management Draft Environmental Impact Statement (DOE/EIS-0217D), addresses the tasks of cleaning up existing waste units and bringing current operations into compliance with applicable regulations. It deals in detail with the current conditions and plans for remediation. It also addresses the development and funding of processes to minimize waste generation and to safely process and dispose of future waste generation. Pollution Prevention. Pollution prevention, previously driven by best management practices and economics, is now mandated by statutes, regulations, and agency directives. The SRS Waste Minimization and Pollution Prevention Program is designed to achieve continuous reduction of wastes and pollutant releases to the maximum extent feasible and in accordance with regulatory requirements while fulfilling national security missions. The SRS Waste Minimization and Pollution Prevention Awareness Plan addresses wastes and potential pollutants of all types and establishes priorities for accomplishing waste minimization and pollution prevention through source reduction, recycling, treatment, and environmentally safe disposal. Spent Nuclear Fuel. Spent nuclear fuel is not designated as a waste and is not included in the waste inventory since, during processing, separation of useful isotopes from the spent nuclear fuel is accomplished, and only the remaining waste is classified as HLW, TRU, or LLW. DOE discontinued reprocessing spent nuclear fuel in 1992. DOE published the ROD in the Federal Register (60 FR 28680) on June 1, 1995, for the Programmatic Spent Nuclear Fuel and Idaho National Laboratory Environmental Restoration and Waste Management Programs EIS documenting its decisions for the treatment and stabilization of the current inventory of spent nuclear fuel after the completion of programmatic and site- specific reviews pursuant to the National Environmental Policy Act. SRS has been one of the receiving sites for returned domestic and foreign research reactor spent fuel. The preparation of production, commercial, and research reactor fuel for long-term storage and the receipt of fuel from offsite is addressed in the ROD and in the EIS on the proposed policy for the acceptance of U.S.-origin foreign research reactor spent fuel. There are 184 metric tons of production reactor spent fuel and targets and 17metric tons of commercial, experimental, and research reactor spent fuel in storage at SRS (DOE1994g:2-9). High-Level Waste. Liquid HLW containing actinides and hazardous chemicals were generated from recovery and purification of TRU products and from spent fuel processing, and retreivably stored in 51 underground tanks. (One of these tanks is out of service.) The waste is segregated by heat generation rate, neutralized to excess alkalinity, and stored to permit the decay of short-lived radionuclides before its volume is reduced by evaporation. Of the 51tanks, 29 are located in the H-Area Tank Farm, and 22 are located in the F-Area Tank Farm. The tanks are of four different designs, but all are of carbon steel. Wastes are transferred to and processed in the newer tanks which have full height secondary containment and forced water cooling. Some older tanks contain old salt and sludge awaiting waste removal. Other old tanks have had waste removed except for residue, and are used to store low activity waste. The older tanks will be taken out of service when space in other tanks becomes available due to transfer to the Defense Waste Processing Facility. High-heat liquid waste is stored for 1- to 2-years to allow decay of radionuclides before being processed through evaporators. Low-heat waste is sent directly to the evaporator feed tanks. Each tank farm has one evaporator that is used to reduce the volume of the water and concentrate the solids. A replacement higher capacity evaporator is planned which may be used in conjunction with the current evaporators. Liquids can be reduced to 25 to 33 percent of original volume and stored as salts or sludges. Cesium removal columns can operate in conjunction with the evaporators. The evaporators obtain decontamination factors of 10,000 to 100,000 and the cesium removal columns can obtain another 10 to 200 decontamination factors. Decontaminated liquids (overheads) are sent to the Effluent Treatment Facility for processing before being released to Upper Three Runs Creek. The concentrated salt solution is processed to remove radionuclides and the decontaminated solution is sent to the Defense Waste Processing Facility: Saltstone Facility for solidification and storage onsite in the Saltstone Vaults. The remaining sludges and salts contain the majority of the radionuclides, and are stored separately, awaiting vitrification. Prior to vitrification, salt would be precipitated in the In Tank Precipitation process. The precipitate and sludge would be fed into the vitrification process in the Defense Waste Processing Facility. The waste will be mixed with borosilicate glass and immobilized by melting and pouring the mixture into stainless steel cylinders. These cylinders will be stored in a shielded facility at the Defense Waste Processing Facility until a repository is available. Figure H.2.5-1 illustrates HLW management at SRS. Tables H.2.5-1, H.2.5-2 and H.2.5-3 list HLW inventories and treatment and storage facilities at SRS. Transuranic Waste. All TRU waste currently being generated is stored in containers on above ground storage pads. Older TRU wastes (prior to 1965) were buried in plastic bags and cardboard boxes in earthen trenches. Wastes containing more than 0.1 Ci per package were placed in concrete containers and buried. Wastes containing less than 0.1 Ci per package were buried unencapsulated in earthen trenches. Since 1974, TRU wastes containing more than 10 nCi/g have been stored in retrievable containers free of external contamination. Polyethylene lined galvanized drums containing more than 0.5 Ci are additionally protected by closure in concrete culverts. Currently, approximately 85 percent of the TRU waste in storage is suspected of being contaminated with hazardous constituents. Presently, waste is characterized by onsite generators and is being stored prior to final disposal. TRU waste containing less than 100 nCi/g may be disposed of as LLW at SRS. Waste containing greater than 100 nCi/g and meeting the final WIPP waste acceptance criteria will be sent to WIPP, if WIPP is determined to be a suitable repository pursuant to the requirements of 40 CFR 191 and 40 CFR 268. Waste not meeting the acceptance criteria as currently packaged will be repack- aged as necessary to meet the WIPP waste acceptance criteria. If additional treatment is necessary for disposal at WIPP, SRS would develop the appropriate treatment technology, or ship this waste to another facility for treatment. Studies are underway to solve the problem of high heat TRU waste which is unique to SRS. Wastes with high Pu238 fractions generate too much heat to be shipped in the TRUPACT-II. TRU waste is currently stored on 17 pads at the Solid Waste Disposal Facility in the E- Area. The TRU waste management plan is illustrated in figure H.2.5-2. Table H.2.5-4 lists the mixed TRU waste inventories. Tables H.2.5-5 and H.2.5-6 present the TRU and mixed TRU waste treatment and storage facilities. Low-Level Waste. Both liquid and solid LLW are treated at SRS. Liquids are processed to remove and solidify the radioactive constituents and to release the balance of the liquids to permitted discharge points. The bulk of liquid waste is aqueous process waste including effluent cooling water, purge water from storage basins for irradiated reactor fuel or target elements, distillate from the evaporation of process waste streams, and surface water runoff from areas where there is a potential for radioactive contamination. Aqueous LLW streams are sent to the Effluent Treatment Facility where they are treated by filtration, reverse osmosis and ion exchange to remove the radionuclide contaminants. After treatment, the effluent is discharged to Upper Three Runs Creek. The resultant wastes are concentrated by evaporation and stored in the H-Area Tank Farm for eventual treatment in the Defense Waste Processing Facility: Saltstone Facility. In that facility, they will be processed with grout for onsite disposal. Figure H.2.5-3 illustrates the liquid LLW processing at SRS. Processing and disposal of solidified liquids is illustrated in figures H.2.5-4 and H.2.5-5. Inventory, treatment, and storage facilities for LLW and mixed LLW are listed in tables H.2.5-7, H.2.5-8, and H.2.5-9. Disposal of solid LLW at the SRS traditionally has been accomplished using engineered trenches in accordance with the guidelines and technology existing at the time of disposal. The E-Area Vault project is a comprehensive effort for upgrading LLW disposal at SRS based on meeting the requirements of the current DOE orders, incorporating technological advances, and addressing more stringent Federal regulation and heightened environmental awareness. Four basic types of vaults/buildings are being constructed for the different waste categories: low-activity waste vault, intermediate-level nontritium vault, intermediate-level tritium vault, and long-lived waste storage building. The vaults are below-grade concrete structures and the storage building is a metal building on a concrete pad. Long-lived waste is being stored until a final disposition can be determined. Additional information on these facilities is given in table H.2.5-10. Solid LLW is segregated into several categories to facilitate proper treatment, storage, and disposal. Solid LLW that radiates less than 200 mrem per hour at 5 cm from the unshielded container is considered low-activity waste. If it radiates greater than 200mrem per hour at 5 cm, it is considered intermediate-activity waste. This waste is typically contaminated equipment from separations, reactors, or waste management facilities. Intermediate activity tritium waste is intermediate-activity waste with greater than 10 Ci of tritium per container. Spent lithium-aluminum targets from tritium operations equipment is included in this waste. Long-lived waste is contaminated with long-lived isotopes that exceed the waste acceptance criteria for disposal. Resin contaminated with carbon-14 from reactor operations is an example. Excavated soil from radiological materials areas that is potentially contaminated soil and cannot be economically demonstrated to be uncontaminated is managed as suspect soil. Figure H.2.5-5 illustrates LLW management at SRS. Solid LLW typically consists of protective clothing, contaminated equipment, irradiated hardware that does contain spent fuel, spent lithium-aluminum targets (from tritium extraction), and spent deionizer resins. All LLW is disposed of in the Solid Waste Disposal Facility in the E-Area between the F- and H-Areas. Wastes are compacted and packaged for burial. The primary method of disposal of low-activity waste is burial in engineered low-level earthen trenches. Trenches are located above the water table in soil containing enough clay to maintain its integrity, in an area where surface runoff can be controlled. The trench floors are sloped to a sump to eliminate standing water. After emplacement, the waste containers are covered with a soil cap, planted with selected grasses, and graded to direct runoff away from the trench. Intermediate-level wastes are disposed of in poured-in-place, top loading below-grade facilities to achieve as close to a zero release criteria as possible. Monitoring wells are located near each disposed waste area to verify performance and to monitor groundwater in the vicinity of the vaults. The existing 195-acre burial ground is filled and new concrete lined facili- ties are under construction to meet future SRS requirements. As of June 1994, the total inventory of LLW disposed of at SRS is 980,000 yd3 (DOE 1994n:SRS). Mixed Low-Level Waste. Mixed LLW is in interim storage in the E- and G-Areas in various buildings in drums, concrete culverts, and metal boxes. These South Carolina Department of Health and Environmental Control-permitted facilities will remain in use until appropriate treatment and disposal is performed on the waste. The planned and funded Hazardous/Mixed Waste Treatment and Disposal Facility will process both mixed and hazardous wastes. The mixed waste management plan for SRS, illustrated in figure H.2.5-6, is being reevaluated through the development of a Site Treatment Plan in accordance with the Federal Facility Compliance Act of 1992. Mixed waste inventories are listed in table H.2.5-7. Treatment facilities and processes are listed in table H.2.5-8. Storage facilities capacity and status are listed in tables H.2.5-9 and H.2.5-10. Hazardous Waste. Typical hazardous wastes at SRS are lead, mercury, cadmium, 1,1,1-trichloro-ethane, leaded oil, trichlorotrifluoroethane, benzene, and paint solvents. Figure H.2.5-7 illustrates the processing of hazardous wastes at SRS. This waste is stored in three South Carolina Department of Health and Environmental Control-permitted buildings and facilities in the 700 area. One of these buildings is covered under a RCRA final permit. RCRA permits have been submitted for the other facilities. The buildings are constructed with sloped floors, dikes, and sumps to provide adequate containment in the event of a spill. Waste is stored in DOT- approved containers. Some of the waste is shipped to an offsite vendor for processing and disposal, thus allowing the site to maintain its current storage capabilities. Nonhazardous (Sanitary) Waste. SRS operates its own sanitary waste landfill near road C, between C-3 and E. The first section of this landfill is at capacity, the second section reached capacity in 1993, and the third (interim) section is expected to provide capacity until 1997. Waste minimization and disposal method improvements are being employed to more efficiently utilize the landfill. The open pit method is used, and wastes are weighed and recorded before being disposed of in the facility. This facility has been found to be a source of groundwater contamination in the past, and is operating under a South Carolina Department of Health and Environmental Control permit which was valid through 1994. It will be modified, if necessary, to adequately assess the impact of continued use of this landfill. In the future, SRS is planning to contract with offsite facilities for the disposal of its sanitary waste. Other Nonhazardous Waste. SRS disposes of other nonhazardous wastes in addition to the nonhazardous wastes disposed of in the sanitary landfill. These wastes consist of scrap metal, powerhouse ash, domestic sewage, scrap wood, construction debris, and used railroad ties. Scrap metal is sold to salvage vendors for reclamation. Powerhouse ash and domestic sewage sludge is used for land reclamation. Scrap wood is burned in the open. Construction debris is used for erosion control. Railroad ties have been processed into a bio- degradable state. Nonhazardous waste management is illustrated in figure H.2.5-8. Figure (Page H-78) Figure H.2.5-1.-High-Level Waste Management Plan at Savannah River Site. Figure (Page H-79) Figure H.2.5-2.-Transuranic Waste Management Plan at Savannah River Site. Figure (Page H-80) Figure H.2.5-3.-F- and H-Areas Effluent Treatment Facility Waste Management Plan at Savannah River Site. Figure (Page H-81) Figure H.2.5-4.-Saltstone (Low-Level Waste) Disposal Plan at Savannah River Site. Figure (Page H-82) Figure H.2.5-5.-Low-Level Waste Management Plan at Savannah River Site. Figure (Page H-83) Figure H.2.5-6.-Mixed Waste Management Plan at Savannah River Site. Figure (Page H-84) Figure H.2.5-7.-Hazardous Waste Management Plan at Savannah River Site. Figure (Page H-85) Figure H.2.5-8.-Nonhazardous Solid Waste Management Plan at Savannah River Site. Table H.2.5-1.-High-Level Wastes at Savannah River Site Waste Matrix Number of Inventory as of Number of Waste Streams Total Generation Waste Streams September 30, 1993 Five-Year Projection Five-Year Projection (yd3) (yd3) Remote-handled Aqueous liquids, slurries 3 167,900 3 17,800 (33,900,000 gal) (3,600,000 gal) Inorganic non-metal Debris 1 42 0 0 Total 4 167,900 3 17,800 Source: DOE 1994k; WSRC 1994a. Table H.2.5-2.-High-Level Waste Treatment Capability at Savannah River Site Treatment Unit Treatment Method Input Capability Output Capability Total Capacity Comment (yd3 per year) F- and H-Tank Farms Neutralization HLW aqueous liquid HLW aqueous liquid, b Operational dissolution, chemical solutions and slurries sludge, solutions reaction Savannah River Ion exchange HLW aqueous liquid Mixed LLW liquid, HLW 16,934 Operational Technology Center high sludge (457,229 GPY) activity treatment probe F- and Evaporation, ion HLW aqueous liquid HLW sludge, salt, slurry, 83,333 Operational H-Evaporators exchange (cesium organic solid (2,250,000 GPY) removal) Replacement Evaporator Evaporation, ion HLW aqueous liquid HLW sludge, salt, slurry, 120,000 Planned for 1997 exchange (cesium organic solid (3,240,000 GPY) removal) Extended Sludge Decontamination HLW sludge HLW sludge Dependent on tank Operational Processing inventory In-Tank Precipitation Precipitation, adsorption, HLW salt solution HLW, LLW precipitate 190,000c Startup December 1994 filtration slurry (5,130,000 GPY) Defense Waste Processing Vitrification HLW precipitate, sludge HLW solid borosilicate 8,570 Planned available March Facility Vitrification glass (1,731,000 GPY) 1996 Plant Table H.2.5-3.-High-Level Waste Storage at Savannah River Site Storage Unit Input Capability Total Capacity Comment (yd3) F-Area Tank Farm HLW, corrosive, toxic aqueous liquids, 64,400 Operational salt, sludge (13,000,000 gal) H-Area Tank Farmb HLW, corrosive, toxic aqueous liquids, 109,000 Operational salt, sludge (22,100,000 gal) Total - 173,400 - (35,100,000 gal) Defense Waste Processing Facility HLW solid borosilicate glass in stainless 2,826 First unit available December 31, Vitrification Plant steel cylinders 1995 Defense Waste Processing Facility HLW solid borosilicate glass in stainless 2,826 Second unit planned Vitrification Plant steel cylinders Total Solid - 5,652 - Table H.2.5-4.-Mixed Transuranic Waste at Savannah River Site Waste Matrix Number of Inventory as of Number of Waste Streams Total Generation Waste Streams September 30, 1993 Five-Year Projection Five-Year Projection (yd3) (yd3) Contact-Handled Organic liquids 2 1.7 0 0 (343 gal) Combustible debris 2 6,570 1 267 Ash 1 0.1 0 0 Total 5 6,572 1 267 Source: DOE 1994k; WSRC 1994a. Table H.2.5-5.-Transuranic and Mixed Transuranic Waste Treatment Capability at Savannah River Site Treatment Unit Treatment Method Input Capability Output Capability Total Capacity Comment Transuranic Waste Facility Sorting, shredding, grouting, Miscellaneous TRU, extraction Solid TRU in drums Proposed facility Proposed facility sampling, venting, repackaging procedure toxic, listed Table H.2.5-6.-Transuranic and Mixed Transuranic Waste Storage at Savannah River Site Storage Unit Input Capability Total Capacity Comment (yd3) TRU Storage Pads Miscellaneous solid TRU waste, 22,900 Operational RCRA Part A. No offsite waste planned. Buried waste extraction procedure toxic, listed to be exhumed, processed at TRU Waste Facility, and shipped to WIPP Source: DOE 1993g; SR MMES 1993a; WSRC 1994a. Table H.2.5-7.-Low-Level and Mixed Low-Level Wastes at Savannah River Site Waste Matrix Number of Inventory as of Number of Waste Streams Total Generation Waste Streams September 30, 1993 Five-Year Projection Five-Year Projection (yd3) (yd3) Contact-Handled Aqueous liquids/slurries 6 130 3 1,504 (26,300 gal) (304,000 gal) Organic liquids 8 171 4 506 (34,500 gal) (102,000 gal) Inorganic process residues 10 2,931 4 654 Debris 2 1,584 0 0 Metal debris 4 147 1 4 Combustible debris 2 8 2 4 Homogeneous debris 4 3,662 2 36 Lab packs 1 0.2 0 0 Reactive metals 1 1 0 0 Elemental mercury 1 0.3 0 0 Elemental lead 1 226 1 78 Vitrified forms 0 0 1 654 Ash, alpha 0 0 1 81 Uncategorized soils, alpha 1 24 0 0 Remote-Handled Inorganic process residues 1 13 0 0 Metal debris 1 0.3 2 26 Total 42 8,358 21 3,551 Source: DOE 1994k; WSRC 1994a. Table H.2.5-8.-Low-Level and Mixed Low-Level Waste Treatment Capability at Savannah River Site Treatment Unit Treatment Method Input Capability Output Capability Total Capacity comment (yd3 per year) Consolidated Incineration Incineration Mixed LLW, liquid, solid Ash, slurry 71,555 Planned, approved, RCRA Facility (14,455,000 GPY) final, available 1996 Consolidated Incineration Stabilization Mixed LLW, ash, slurry Stabilized LLW, mixed 30 Planned, approved, RCRA Facility Ashcrete LLW, solid final, available 1996 F- and H-Areas Effluent Neutralization, Mixed LLW, aqueous Corrosive LLW liquid 311,882 Operational, NPDES: Treatment Facility chemical precipitation, liquids (F&H Area concentrate, treated (63,000,000 GPY) Operating filtration, carbon wastewater, evaporator water effluent; used adsorption, reverse overheads and condensate, activated carbon, used osmosis, ion ex- cesium removal column ion exchange resins change, evaporation, effluent, etc.) (solid LLW) mercury adsorption H-Area Compactor Compaction Solid LLW job waste Compacted LLW 36,624 Operational Hazardous/Mixed Waste Distillation, Liquids and solids, mixed Wastewater, solid 1,163 Planned, approved, Treatment/ electrochemical, LLW, toxic, corrosive, stabilized LLW (234,926 GPY) availability unknown Disposal Facility encapsulation, reactive, metal, sludge solidification, precipitation, size reduction, amalgamation, stabilization M-Area Compactor Compaction Solid LLW job waste Compacted LLW 36,624 Operational M-Area Dilute Effluent Filtration, Liquid mixed LLW Wastewater, solid mixed 130,080 Operational, NPDES: Treatment Facility neutralization, LLW (26,000,000 GPY) operating precipitation M-Area Vendor Treatment Vitrification Aqueous liquids and Wastewater, solid mixed 1,960 Planned, approved, NPDES: Facility slurries, mixed LLW LLW (396,000 GPY) construction, available 1995 Savannah River Technology Ion exchange Mixed LLW, aqueous Aqueous liquid, solid, 1,960 Operational, RCRA: interim Center Ion Exchange liquids mixed LLW (396,000 GPY) Treatment Probe Low Activity Z-Area Saltstone Facility Stabilization Liquids, mixed LLW, Solid LLW, nonhazardous 12,400 Operational, permitted (solidification with sludges, toxic, corrosive (2,500,000 GPY) disposal, CWA, RCRA: final radio-nuclide binders) Table H.2.5-9.-Low-Level and Mixed Low-Level Waste Storage at Savannah River Site Storage Unit Input Capability Total Capacity Comment (yd3) Burial Ground Solvent Tanks (523-31) Liquid mixed LLW 990 To be closed, RCRA Part A (200,000 gal) Defense Waste Processing Facility Organic Waste Liquid mixed LLW, ignitable, toxic 743 Operational, RCRA Part A Storage Tank (430-3) (150,000 gal) Liquid Waste Solvent Tanks (533-36) Liquid mixed LLW 990 Proposed facility (200,000 gal) M-Area Process Waste Interim Treatment/Storage Liquid mixed LLW, listed, (electroplate sludge) 10,900 Operational, RCRA Part A Facility (2,200,000 gal) Mixed Waste Storage Buildings Liquid mixed LLW solid, toxic, listed, ignitable, 1,690 Operational, RCRA Part A (643-29E and 643-43E) metal, sludge, soil (341,000 gal) Mixed Waste Storage Shed (316-M) Liquid and solid mixed LLW 153 Operational, RCRA Part A (30,800 gal) Savannah River Laboratory High Activity Liquid mixed LLW, toxic, Toxicity Characteristic 259 Operational, RCRA Part A Storage Tanks (772-2A) Leaching Procedure (52,300 gal) Hazardous Waste Storage Facility (645-2N) Mixed LLW 761 Operational, RCRA Part B (154,000 gal) Total - 16,486 - (3,328,100 gal) Table H.2.5-10.-Waste Disposal at Savannah River Site Disposal Unit Input Capability Capacity Comment (yd3) Hazardous/Mixed Waste Disposal Vaults Solid mixed LLW, listed (CIF, Ashcrete and 3,920 Planned and funded, RCRA blowdown) submitted 1990, available 2000. Intermediate-Level Waste Vaults Solid LLW 8,060 Under construction Low- and Intermediate-Level Disposal Area Solid LLW 994,000 Operational Low Activity Waste Vaults Solid LLW, compacted waste, contaminated 44,000 Under construction equipment, filters, sediment, job control waste, process beds, soils, resins, lithium-aluminum melted forms Z-Area Saltstone Vaults Solid LLW 1,491,000 15 vaults operational, additional 27 vaults planned
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