The process of manufacturing useful nuclear materials has produced radioactive, mixed, and hazardous wastes that are treated, stored, or disposed of at SRS. The Savannah River Site Waste Management Final Environmental Impact Statement (DOE/EIS-0217, July 1995) addressed the tasks to be completed in the next 10 years to clean up existing waste units and bring current operations into compliance with applicable regulations. The EIS discusses the current conditions and provides DOE's preferred alternatives for processing current and future waste streams. It also addresses the development and funding of processes to minimize waste generation and to safely process and dispose of future waste generation. Because there is no spent nuclear fuel associated with the fabrication of primaries, there will be no further discussion of spent nuclear fuel at SRS.
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 a continuous reduction of wastes and pollutant releases to the maximum extent feasible 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.
High-Level Waste. Liquid HLW containing actinides and hazardous chemicals was generated from recovery and purification of TRU products and from spent fuel processing, and is retrievably stored in 51 underground tanks. One of these tanks is out of service. The tanks are managed in compliance with Federal laws, State of South Carolina regulations, and DOE orders. 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 51 tanks, 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. Newer tanks which have full height secondary containment and forced water cooling are used for waste processing. Some older tanks contain salt and sludge awaiting waste removal. Old tanks that have had waste removed except for residue 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 that may be used in conjunction with the current evaporators. Liquids can be reduced to 25 to 33 percent of their 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 onsite storage 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 would be mixed with borosilicate glass and immobilized by melting and then pouring the mixture into stainless steel cylinders. These cylinders would be stored in a shielded facility at the Defense Waste Processing Facility until a repository is available. Figure H.2.2-1 illustrates HLW management at SRS. Tables H.2.2-1, H.2.2-2, and H.2.2-3 list HLW inventories and treatment and storage facilities at SRS.
| Waste Matrix | Number of Waste Streams | Inventory as of September 30, 1994 (m3) | Number ofWaste Streams Five-Year Projection | Total Generation Five-Year Projection(m3) |
|---|---|---|---|---|
| Remote-Handled | ||||
| Aqueous liquids, slurries | 2 | 127,040 | 2 | 15,430 |
| SR DOE 1995c; WSRC 1995a. | ||||
| Treatment Unit | Treatment Method | Input Capability | Output Capability | Total Capacity 1 (m 3 per year) | Comment |
|---|---|---|---|---|---|
| F- and H-Tank Farms | Neutralization dissolution and chemical reaction | HLW aqueous liquid solutions and slurries | HLW aqueous liquid, sludge, and solutions | 2 | Operational |
| Savannah River Technology Center high activity treatment probe | Ion exchange | HLW aqueous liquid | Mixed LLW liquid and HLW sludge | 1,725 | Operational |
| F- and H-evaporators | Evaporation and ion exchange (cesium removal) | HLW aqueous liquid | HLW sludge, salt, slurry, and organic solid | 26,9003 | Operational |
| Replacement evaporator | Evaporation and ion exchange (cesium removal) | HLW aqueous liquid | HLW sludge, salt, slurry, and organic solid | 13,800 | Design and construction phase planned for 1999 |
| Defense Waste Processing Facility | Vitrification | HLW and precipitate slurry | HLW borosilicate | 18,800 | Operational |
| Extended sludge processing | Soil washing to remove soluble salts, precipitation | HLW sludge | HLW sludge | 834 | Operational |
| In-tank precipitation | Soil washing to remove soluble salts, precipitation | HLW salt solution | LLW salt solution and HLW precipitate slurry | Would produce 22,700 m 3 salt solution and 1,900 m 3 precipitate | Operational |
| Late wash | Washing to remove sodium nitrate | HLW precipitate slurry | HLW precipitate | 24,600 | Undergoing design and construction |
| Storage Unit | Input Capability | Total Capacity4 | Comment |
|---|---|---|---|
| F- and H-Area Tank Farms5 | HLW, corrosive, toxic aqueous liquids, salt, and sludge | 145,000 m 3 | Operational |
| Defense Waste Processing Facility vitrification plant, glass waste storage buildings | HLW solid borosilicate glass in stainless steel cylinders | 2,286 canisters (3.8 t glass) | First unit available December 31, 1995, one building constructed, one more planned |
| Defense Waste Processing Facility vitrification plant, failed equipment storage | Failed melters | 3,720 m 3 |
Transuranic Waste. All TRU waste currently being generated is stored in containers on aboveground storage pads in compliance with state regulations and DOE orders. Older TRU wastes (prior to 1965) were buried in plastic bags and cardboard boxes in earthen trenches. Wastes containing more than 0.1 curies (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 it 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 repackaged 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 plutonium-238 fractions generate too much heat to be shipped in the Transuranic Package Transporter (TRUPACT)-II container. TRU waste is currently stored on 17 pads at the Solid Waste Disposal Facility in E-Area. The TRU waste management plan is illustrated in figure H.2.2-2. Table H.2.2-4 lists the mixed TRU waste inventories. Tables H.2.2-5 and H.2.2-6 present the TRU and mixed TRU waste treatment and storage facilities.
| Waste Matrix | Number of Waste Streams | Inventory as ofSeptember 30, 1994 (m 3) | Number of Waste StreamsFive-Year Projection | Total GenerationFive-Year Projection(m 3) |
|---|---|---|---|---|
| Contact-Handled | ||||
| Organic liquids | 1 | <1 | 0 | 0 |
| Combustible debris | 3 | 7,693 | 1 | 240 |
| Debris | 2 | 199 | 2 | 2,613 |
| Ash | 1 | <1 | 0 | 0 |
| Total | 5 | 8,162 | 1 | 2,853 |
| DOE 1995gg; WSRC 1995a. | ||||
| Treatment Unit | Treatment Method | Input Capability | Output Capability | Total Capacity6 | Comment |
|---|---|---|---|---|---|
| TRU Waste Characterization/ Certification Facility | Assaying, sorting, decontamination, size reduction, welding, venting, and encapsulation | Mixed and nonmixed TRU wastes | Certified forms for disposal | 1,720 m3/yr | Begin operations in 2007 |
| Alpha vitrification | Vitrification | TRU and mixed TRU waste | Certified and stabilized forms for disposal | 559 m3/yr liquid or 2,280 m3/yr solid | Planned |
| Storage Unit | Input Capability | Total Capacity (m 3) | Comment |
|---|---|---|---|
| TRU storage pads | Miscellaneous solid TRU waste, extraction procedure toxic, listed | 34,400 | Operational RCRA Part A. No offsite waste planned. Buried waste to be exhumed, processed at TRU Waste Facility, and shipped to WIPP. Nineteen pads in use, 10 additional pads planned. |
| SR DOE 1995c; WSRC 1995a; WSRC 1995b. | |||
Low-Level Waste. Both liquid and solid LLW are treated at SRS. Liquids are managed and processed to remove and solidify the radioactive constituents and to release the balance of the liquids to permitted discharge points in compliance with state regulations. 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 prior to treatment in the Defense Waste Processing Facility Saltstone Facility. In that facility, they are processed with grout for onsite disposal. Figure H.2.2-3 illustrates the LLW processing at SRS. Treatment and storage facilities for LLW are listed in tables H.2.2-7 and H.2.2-8.
Disposal of solid LLW at SRS traditionally has been accomplished using engineered trenches in accordance with the guidelines and technology existing at the time of disposal. Currently, packaged LLW is deposited in the E-Area vaults, which are concrete structures that meet the requirements of DOE orders, incorporate technological advances, and address more stringent Federal regulations and heightened environmental awareness. Four basic types of vaults/buildings are utilized 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.2.2-9.
| Treatment Unit | Treatment Method | Input Capability | Output Capability | Total Capacity7 (m 3 per year) | Comment |
|---|---|---|---|---|---|
| Consolidated Incineration Facility and Ashcrete Stabilization Facility | Incineration/stabilization | LLW, mixed LLW, liquid, solid, ash, and slurry | Stabilized LLW, mixed LLW, and solid waste | 4,630 (liquid)17,830 (solid) | Planned, approved, RCRA final, available 1996 |
| F- and H-Areas Effluent Treatment Facility | Neutralization, chemical precipitation, filtration, carbon adsorption, reverse osmosis, ion exchange, evaporation, and mercury adsorption | Mixed LLW, aqueous liquids (F- and H- area wastewater, evaporator overheads and condensate, and cesium removal column effluent) | Corrosive LLW liquid concentrate, treated water effluent used activated carbon, and used ion exchange resins (solid LLW) | 1,930,000 | Operational, NPDES operating |
| M-, L-, and H-Area compactors | Compaction | Solid LLW job waste | Compacted LLW | 3,983 | Operational |
| Hazardous/Mixed Waste Containment Building | Physical and chemical decontamination, wet chemical oxidation, encapsulation, and amalgamation | Liquids and solids, mixed LLW, toxic, corrosive, reactive, metal, sludge, and debris | Containment facility | 703 | Planned, approved, begin operation in 2006 |
| Low-level waste smelter | Offsite decontamination | LLW and equipment | Recovered metal | 600 | Offsite facility |
| Non-alpha vitrificationfacility | Sorting and vitrification | LLW, mixed LLW, and hazardous wastes | Mixed LLW | 3,090 | Proposed facility |
| Offsite mixed wastetreatments | Amalgamation, PCB destruction, acid bath, and smelting | Mixed LLW | Solid LLW | 124 | Offsite facilities |
| M-area Liquid Effluent Treatment Facility | Filtration, flocculation neutralization, and precipitation | Liquid mixed LLW | Wastewater, solid mixed LLW, and sludge | 999,000 | Operational, NPDES: operating |
| M-Area Vendor Treatment Facility | Vitrification | Aqueous liquids and slurries, mixed LLW, and sludges | Wastewater, solid mixed LLW, and borosilicate glass | 2,470 | Planned, approved, contract awarded for construction NPDES |
| Savannah River Technology Center ion exchange treatment probe low activity | Ion exchange | Mixed LLW and aqueous liquids | Aqueous liquid, solid, and mixed LLW | 11,200 | Operational, RCRA: interim |
| Soil Sort Facility | Sorting and separating contaminated soils | LLW soil | Low-level contaminated and uncontaminated soil | 2,540 | Proposed facility |
| Offsite supercompactor | Compaction | Solid LLW | Compacted solid LLW | 42,400 | Commercial facilities |
| Onsite supercompactor | Compaction | Solid LLW | Compacted solid LLW | 5,700 | Proposed facility |
| Z-Area Saltstone Facility | Stabilization (solidification with radionuclide binders) | Liquids, mixed LLW, sludges, toxic, corrosive | Solid LLW, nonhazardous | 28,400 | Operational, permitted disposal, CWA, RCRA: final |
| Storage Unit | Input Capability | Total Capacity8 (m 3) | Comment |
|---|---|---|---|
| Burial ground solvent tanks (S23-30) | Liquid mixed LLW | 727 | To be closed, RCRA Part A |
| Defense Waste Processing Facility organic waste storage tank (430-S) | Liquid mixed LLW, ignitable, toxic | 568 | Operational, RCRA Part A |
| Liquid waste solvent tanks (S33-36) | Liquid mixed LLW | 454 | Planned facility |
| M-Area Process Waste Interim Treatment/Storage Facility | Liquid mixed LLW, listed, (electroplate sludge) | 8,300 | Operational, RCRA Part A |
| Mixed waste storage buildings (643-29E and 643-43E) | Liquid mixed LLW solid, toxic, listed, ignitable, metal, sludge, soil | 1,300 | Operational, RCRA Part A |
| Mixed waste storage shed (316-M) | Liquid and solid mixed LLW | 120 | Operational, RCRA Part A |
| Savannah River Laboratory high activity storage tanks (772-2A) | Liquid mixed LLW, toxic, toxicity characteristic teaching procedure | 198 | Operational, RCRA Part A |
| Hazardous Waste Storage Facility (645-2N) | Mixed LLW | 580 | Operational, RCRA Part B |
| Process waste interim treatment | Liquid mixed LLW | 8,300 | Operational, RCRA Part A |
| Long-lived waste storage buildings | Process water deionizers containing carbon 14 | 3,330 | Planned facility |
| Disposal Unit | Input Capability | Capacity 9,10 (m 3) | Comment |
|---|---|---|---|
| Hazardous/mixed waste disposal vaults | Solid mixed LLW and listed (CIF, Ashcrete, blowdown, and vitrified) | 45,600 | 10 vaults are planned and funded, RCRA submitted 1990, available 2002. |
| Intermediate-level waste vaults | Solid LLW | 27,000 | 2 vaults operational, additional 5 planned |
| Low activity waste vaults | Solid LLW, compacted waste, contaminated equipment, filters, sediment, job control waste, process beds, soils, resins, and lithium-aluminum melted forms | 61,500 | 1 vault constructed additional 12 planned. |
| LLW disposal facility, slit trenches | Solid LLW | 407,000 | 58 trenches planned |
| Z-area saltstone vaults | Solid LLW | 1,110,000 | 2 vaults operational, additional 12 vaults planned |
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 centimeters (cm) (1.97 inch [in]) from the unshielded container is considered low-activity waste. If it radiates greater than 200 mrem per hour at 5 cm (1.97 in), 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 and cannot be economically demonstrated to be uncontaminated is managed as suspect soil. Solid LLW typically consists of protective clothing, contaminated equipment, irradiated hardware, spent lithium-aluminum targets (from tritium extraction), and spent deionizer resins. All LLW is disposed of in the Solid Waste Disposal Facility in E-Area between F- and H-Areas. Wastes are compacted and packaged for burial. Monitoring wells are located near each disposed waste area to verify performance and to monitor groundwater in the vicinity of the vaults. As of December 1994, the total inventory of LLW disposed of at SRS was 676,400 m3(884,700 yd 3) (DOE 1995gg).
Mixed Low-Level Waste . Management of mixed wastes includes safe storage until treatment is available. Mixed LLW is stored in A-, E-, M-, N-, and S-Areas in various tanks and buildings. These facilities include burial ground solvent tanks, the M-Area process waste interim treatment/storage facility, Savannah River Technology Center mixed waste storage tanks, and the organic waste storage tanks. 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 Hazardous/Mixed Waste Treatment and Disposal Facility and the Consolidated Incineration Facility will process both mixed and hazardous wastes. The mixed waste management plan for SRS, illustrated in figure H.2.2-4, has been 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.2.2-10. Treatment facilities and processes are listed in table H.2.2-7. The capacities and status of the different storage facilities are listed in table H.2.2-8.
| Waste Matrix | Number of Waste Streams | Inventory as of September 30, 1994 (m3) | Number of Waste Streams Five-Year Projection | Total Generation Five-Year Projection (m3) |
|---|---|---|---|---|
| Aqueous liquids/slurries | 6 | 158 | 8 | 4,692 |
| Debris | 12 | 4,069 | 13 | 3,840 |
| Special waste | 4 | 83 | 4 | 32 |
| Homogeneous solids | 12 | 2,726 | 5 | 155 |
| Lab packs | 1 | 8 | 1 | 5 |
| Organic liquids | 3 | 139 | 4 | 587 |
| Soil/gravel | 2 | 17 | 0 | 0 |
| Total | 40 | 7,200 | 35 | 9,311 |
| DOE 1995gg; WSRC 1995a; WSRC 1995b. | ||||
Hazardous Waste. Typical hazardous wastes at SRS include lead, mercury, cadmium, 1,1,1-trichloro-ethane, leaded oil, trichlorotrifluoroethane, benzene, and paint solvents. Figure H.2.2-5 illustrates the processing of hazardous wastes at SRS. Table H.2.2-11 lists hazardous waste storage facilities at SRS. This waste is stored in RCRA-permitted buildings in B-, M-, and N-Areas, and open storage areas located on the asphalt pads within the fenced area of N-Area. DOE started to send hazardous waste offsite for treatment and disposal, but in 1990 imposed a moratorium on shipments of hazardous materials from radiological areas. Waste that is not subject to the moratorium is shipped to an offsite vendor for processing and disposal. SRS annually publishes the SRS Tier Two Emergency and Hazardous Chemical Inventory Report, which lists hazardous chemicals that are present above their minimum threshold level or that are categorized as extremely hazardous substances by the emergency planning Community Right-to-Know Act of 1986. The annual reports filed under the Superfund Amendments and Reauthorization Act for the SRS facilities include year-to-year inventories of these chemicals.
| Storage Unit | Input Capability | Capacity (m 3) | Comment |
|---|---|---|---|
| Solid Waste Storage Pads | Containerized solid hazardous wastes only | 1,758 | |
| Building 316-M | Containerized hazardous wastes | 117 | RCRA-permitted interim status |
| Building 710-B | Containerized hazardous wastes | 146 | RCRA-permitted interim status |
| Building 645-N | Containerized hazardous wastes | 171 | RCRA-permitted interim status |
| Building 645-4N | Containerized hazardous wastes | 426 | RCRA-permitted interim status |
| SR DOE 1995c. | |||
Nonhazardous Waste. Municipal solid waste generated at SRS is currently being sent to a permitted offsite disposal facility. DOE is evaluating a proposal to participate in an interagency effort to establish a regional solid waste management center at SRS (DOE/EA-0989, DOE/EA-1079).
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 are used for land reclamation. Scrap wood is burned onsite or chipped for mulch. Construction debris is used for erosion control. Railroad ties are shipped offsite for disposal. Nonhazardous waste management is illustrated in figure H.2.2-6.
2 Batch process; depends on available tanks and process used.
3 Based on net tank space gained. Input volume. SR DOE 1994b; SR DOE 1995b; SR DOE 1995c; WSRC 1995a; WSRC 1995b.
4 Schedules and capacities for facilities under design or construction are subject to changes such as availability of funds and permit issuance.
5 Tanks that do not meet secondary containment criteria as described in the Federal Facility Compliance Agreement are not included. SR DOE 1994b; SR DOE 1995c.
6 For facilities under design or construction this is a design capacity. Schedules and capacities for facilities under design or construction are subject to changes such as availability of funds, results of treatability studies, and permit issuance. SR DOE 1995c; WSRC 1995a; WSRC 1995b.
7 For those facilities already in use, this is a normal operating capacity; whereas, for facilities under design or construction, this is a design capacity. Schedules and capacities for facilities under design or construction are subject to changes such as availability of funds, results of treatability studies, and permit issuance. SR DOE 1995c; WSRC 1995a.
8 Schedules and capacities for facilities under design or construction are subject to changes such as availability of funds and permit issuance. WSRC 1995a.
9 Schedules and capacities for the facilities under design or construction are subject to changes such as availability of funds and permit issuance.
10 Includes current capacity and projections through 2024. SR DOE 1994b; SR DOE 1995c; WSRC 1995a; WSRC 1995b.
