ML15258A413

Shine Medical Technologies V. 0 - Section 19.02 - Proposed Action

ML15258A413
Person / Time
Site:	SHINE Medical Technologies
Issue date:	08/27/2015
From:	Bynum R Shine Medical Technologies
To:	Office of Nuclear Reactor Regulation
Lynch S
References
SHINE, SHINE.SUBMISSION.22, SHN.PSAR.P, SHN.PSAR.P.10
Download: ML15258A413 (28)

Text

Chapter 19 - Environmental Review Table of Contents SECTION 19.2 PROPOSED ACTION Table of Contents Section Title Page 19.2 PROPOSED ACTION .....................................................................................19.2-1 19.2.1 SITE LOCATION AND LAYOUT ..................................................................19.2-6 19.2.2 RADIOISOTOPE FACILITY DESCRIPTION................................................19.2-11 19.2.3 WATER CONSUMPTION AND TREATMENT .............................................19.2-12 19.2.4 COOLING AND HEATING DISSIPATION SYSTEMS ..................................19.2-13 19.2.5 WASTE SYSTEMS ......................................................................................19.2-14 19.2.6 STORAGE, TREATMENT, AND TRANSPORTATION OF RADIOACTIVE AND NONRADIOACTIVE MATERIALS, INCLUDING LEU, WASTE, RADIOISOTOPES, AND ANY OTHER MATERIALS ...................................19.2-21 SHINE Medical Technologies 19.2-i Rev. 0

Chapter 19 - Environmental Review List of Tables List of Tables Number Title 19.2.0-1 Estimated Materials Consumed During Construction Phase 19.2.0-2 Proposed Construction/Demolition Equipment Used in the Construction, Preoperational, and Decommissioning Phases 19.2.1-1 Sensitive Populations, Nearest Resident, and Landmarks within 5 Miles (8 km) of the Site 19.2.5-1 Estimated Type and Quantity of Radioactive Wastes Associated with the SHINE Facility SHINE Medical Technologies 19.2-ii Rev. 0

Chapter 19 - Environmental Review List of Figures List of Figures Number Title 19.2.1-1 SHINE Facility Site Layout 19.2.2-1 Isotope Production System High-Level Flow Diagram 19.2.3-1 Water Balance Diagram SHINE Medical Technologies 19.2-iii Rev. 0

[Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]

Chapter 19 - Environmental Review Acronyms and Abbreviations Acronyms and Abbreviations Acronym/Abbreviation Definition

°F degrees Fahrenheit

°C degrees Celsius

µS/cm micro-Siemens per centimeter AEA Atomic Energy Act of 1954 ac. acre AHA acetohydroxamic acid

[ Proprietary Information ] [ Proprietary Information ]

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Btu/hr british thermal units per hour Btu/scf british thermal units per standard cubic feet Ce Cerium cfm cubic feet per minute CFR Code of Federal Regulations Ci curies CO2 carbon dioxide CP Construction Permit Cs-137 cesium-137 d or D deuterium D-T deuterium-tritium DSSI Diversified Scientific Services, Inc.

EPA U.S. Environmental Protection Agency ER Environmental Report ES EnergySolutions FDA U.S. Food and Drug Administration ft. feet SHINE Medical Technologies 19.2-iv Rev. 2

Chapter 19 - Environmental Review Acronyms and Abbreviations Acronyms and Abbreviations (contd)

Acronym/Abbreviation Definition ft3 cubic feet FP fission product g/L grams/liter gpm gallons per minute GTCC greater than Class C gU/L grams of uranium per liter H2 hydrogen 4He helium ha hectare HNO3 nitric acid hr hour HVAC heating, ventilation, and air conditioning I iodine I-129 iodine-129 I-131 iodine-131 IU irradiation unit keff effective multiplication factor kg kilograms km kilometer kV kilovolts lbs pounds LEL lower explosive limit LEU low enriched uranium SHINE Medical Technologies 19.2-v Rev. 0

[Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]

Chapter 19 - Environmental Review Acronyms and Abbreviations Acronyms and Abbreviations (contd)

Acronym/Abbreviation Definition LSA low specific activity m meters M molar MBtu/hr million british thermal units per hour MeV million electron volts mi. mile MLLW mixed low level waste Mo molybdenum Mo-99 or 99Mo molybdenum-99 n neutron NOx nitrogen oxides NRC U.S. Nuclear Regulatory Commission O2 oxygen OL Operating License PPE personal protective equipment PSAR Preliminary Safety Analysis Report psig pound-force per square inch gauge Pu plutonium RCA radiologically controlled area RCRA Resource Conservation and Recovery Act scf standard cubic feet SHINE SHINE Medical Technologies, Inc.

soln solution

[ Proprietary Information ] [ Proprietary Information ]

t or T tritium SHINE Medical Technologies 19.2-vi Rev. 0

Chapter 19 - Environmental Review Acronyms and Abbreviations Acronyms and Abbreviations (contd)

Acronym/Abbreviation Definition TBP tri-butyl phosphate Tc technetium Tc-99m technetium-99m TCLP Toxicity Characteristic Leaching Procedure TDN thermal denitration TRCS TSV Reactivity Control System TRPS TSV Reactivity Protection System TS target solution TSV target solution vessel U uranium U-235 uranium-235 U3O8 triuranium octoxide (yellowcake)

UO3 uranium trioxide (yellowcake)

UREX uranium extraction USGS United States Geological Survey WCS Waste Control Specialists WI Wisconsin Xe-133 xenon-133 yr year SHINE Medical Technologies 19.2-vii Rev. 0

Chapter 19 - Environmental Review Proposed Action CHAPTER 19 19.2 PROPOSED ACTION The proposed federal action is issuance of a Construction Permit (CP) and Operating License (OL) to SHINE Medical Technologies, Inc. (SHINE) for a radioisotope production facility to produce molybdenum-99 (Mo-99), iodine 131 (I-131), and xenon-133 (Xe-133). The decay product of Mo-99, technetium-99m (Tc-99m), is used for diagnostic medical isotope procedures.

The applicant for this CP and the OL and owner of the radioisotope facility is SHINE Medical Technologies, Inc., a Wisconsin corporation.

SHINE has the necessary authority, control, and rights related to the construction and operation of the isotope production facility once the CP and the OL are approved.

The projected schedule for the SHINE facility is as follows:

• Start date of construction: January 2015.

• End date of construction: December 2015.

• Date of commercial operation: June 2016.

• Date of decommissioning: June 2046.

SHINE plans on performing activities in accordance with 10 CFR 50.10(a)(2) prior to receiving the CP.

The construction phase of this project requires an average of 248 workers (421 at peak times) and a monthly average of 303 truck deliveries and 9 off-site waste shipments. Materials consumed are shown in Table 19.2.0-1 and also include approximately 24,587 gallons of diesel fuel (as a bounding assumption fuel is assumed to be diesel) on an average monthly basis. The different types of construction equipment used during the construction phase are shown in Table 19.2.0-2. These construction activities affect 51.0 acres (ac.) (20.6 hectares [ha]) of land of which approximately 25.1 ac. (10.2 ha) of land are only temporarily affected.

Prior to full commercial operation, the SHINE facility equipment undergoes a thorough commissioning phase involving a series of test operations designed to ensure the facility is functioning as designed. Once the equipment has been commissioned, it is used to produce and ship quantities of Mo-99, I-131, and Xe-133 for customer qualification and input to the U.S. Food and Drug Administration (FDA) approval process. This preoperational phase requires an average of 390 workers (451 at peak times) and a monthly average of 190 truck deliveries and 9 off-site waste shipments. Materials consumed include approximately 11,721 gallons of diesel fuel (as a bounding assumption fuel is assumed to be diesel) on a monthly basis. The different types of construction equipment used during the preoperational phase are shown in Table 19.2.0-2.

After the FDA approves SHINEs customers final products for commercial use, the facility produces and ships several batches of Mo-99, I-131, and Xe-133 per week. Production devices are normally operated on a weekly basis and the operation schedules for the devices are normally staggered to accommodate customer requirements. Operational activities require an SHINE Medical Technologies 19.2-1 Rev. 0

Chapter 19 - Environmental Review Proposed Action average of 150 workers and a monthly average of 36 truck deliveries and 1 off-site waste shipment. Materials to be stored on-site in small quantities include 55 gallon drums of lubricating oil and grease for fans, pumps, hoists, trolleys and rotating equipment and hydraulic oil for heating, ventilation, and air conditioning (HVAC) dampers and hydraulically operated equipment.

Limited on-site storage of acid and caustic chemicals for regeneration of the water treatment demineralizer beds and processes are required. A bounding value of approximately 30,000 gallons (113,562 liters) of diesel fuel for the standby diesel generator are contained in an outside, underground storage tank. Approximately 25.9 acres (10.5 hectares) of land are permanently affected due to operational activities.

Once the facility reaches the end of its useful life, it will be decommissioned. Any radioactive equipment and materials will be disposed of according to local and federal laws and regulations.

Post-operational decommissioning activities require an average of 205 workers (257 at peak times) and a monthly average of 72 truck deliveries and 191 off-site waste shipments. Materials consumed include approximately 28,607 gallons (108,290 liters) of diesel fuel (as a bounding assumption fuel is assumed to be diesel) on a monthly basis. The different types of construction equipment used during the decommissioning phase are shown in Table 19.2.0-2.

SHINE Medical Technologies 19.2-2 Rev. 0

Chapter 19 - Environmental Review Proposed Action Table 19.2.0-1 Estimated Materials Consumed During Construction Phase Material Amount Concrete 27,700 cubic yards Structural Steel 140 tons Misc. Steel 30 tons Steel Liner 100 tons Asphalt 2200 cubic yards Stone Granular Material 16,000 cubic yards Roofing 150 tons SHINE Medical Technologies 19.2-3 Rev. 0

Chapter 19 - Environmental Review Proposed Action Table 19.2.0-2 Proposed Construction/Demolition Equipment Used in the Construction, Preoperational, and Decommissioning Phases (Sheet 1 of 2)

Present During Present During Present During Construction Preoperation Decommissioning Equipment (Y or N) (Y or N) (Y or N)

Asphalt Compactor, Cat Y Y N CB434C, 107 Hp Asphalt Paver, Barber Y Y N Greene AP-1000, 174 Hp Backhoe/Loader, Cat Y Y Y 430, 105 Hp Boom Lift, JLG 800AJ, Y Y Y 65 Hp Concrete Pump, Y N N Putzmeister 47Z-Meter, 300 Hp Crane, Lattice Boom, Y N Y Manitowoc 8000, 80t, 205 Hp Crane, Picker, Grove Y N Y RT530E-2 30t, 160 Hp Crane, Picker, Grove Y N Y RT600E-2 50t, 173 Hp Dump, Duel Axel (15 cy) Y Y Y Mack, 350 Hp Excavator, Large, Cat Y N Y 345D L, 380 Hp Excavator, Medium, Cat Y N Y 321D LCR,148 Hp Extended Forklift, Lull Y Y Y 1044C-54, 115 Hp Fuel Truck, Mack MP6, Y N Y 150 Hp Material Truck, 21/2 ton, Y Y Y F-650, 270 Hp Mechanics Truck, 21/2 Y Y Y ton, F-650, 270 Hp SHINE Medical Technologies 19.2-4 Rev. 0

Chapter 19 - Environmental Review Proposed Action Table 19.2.0-2 Proposed Construction/Demolition Equipment Used in the Construction, Preoperational, and Decommissioning Phases (Sheet 2 of 2)

Present During Present During Present During Construction Preoperation Decommissioning Equipment (Y or N) (Y or N) (Y or N)

Motor Grader, Cat Y Y Y 140M, 183 Hp Pickup Truck, F-250, Y Y Y 300 Hp Semi Tractor & Trailer Y N Y (20 cy), Mack MP8, 450 Hp Skidsteer Loader, Case Y Y Y SR200, 75 Hp Tracked Dozer, Cat D6, Y Y Y 150 Hp Tracked Dozer, Cat D7, Y Y Y 235 Hp Tracked Dozer, Cat D8, Y N Y 310 Hp Tracked Loader, Cat Y Y Y 973C, 242 Hp Vibratory Soil Y Y Y Compactor, Cat CS74, 156 Hp Water Truck, Mack MP6, Y Y Y 150 Hp Portable Air Y Y Y Compressors, <50 Hp Portable Generators, Y Y Y

<50 Hp Portable Welders, <50 Y Y Y Hp Walk Behind Compactor, Y Y Y

<50 Hp SHINE Medical Technologies 19.2-5 Rev. 0

Chapter 19 - Environmental Review Proposed Action 19.2.1 SITE LOCATION AND LAYOUT 19.2.1.1 Site Location The SHINE site is located approximately 4 miles (mi.) (6.4 kilometers [km]) south of Janesville, Rock County, Wisconsin. The SHINE facility is centered at approximately 42° 37 26.9 N latitude, and 89° 1 29.5 W longitude.

The sensitive populations (e.g., schools, daycare facilities, hospitals), nearest resident, and landmarks (including highways, transportation facilities, rivers and other bodies of water) within 5 mi. (8 km) of the site are provided in Table 19.2.1-1. There are no daycare centers or retirement homes located within 5 mi. (8 km) of the SHINE facility.

19.2.1.2 Site Layout Figure 19.2.1-1 shows the layout of major structures and the site boundary. The site boundaries cover approximately 91 ac. (36.8 ha). The following structures shown in Figure 19.2.1-1 are located on the site:

• Production facility building

• Support facility building

• Waste staging and shipping building

• Diesel generator building

• Administration building

• Security station 19.2.1.2.1 Chemical, Diesel Fuel, and Hazardous and Radioactive Material Receipt, Holding, and Storage Areas The following buildings and areas receive, store, hold, retain or process chemicals used in the facility and support buildings on the site:

• Production facility building

- Rejected material

- Receiving area

- Receipt inspection

- Target solution preparation

- Materials lab

- Caustics room

- Acids room

- Hot cell

- CO2-compressed gases room

- Mechanical room

- Boiler room

- HVAC chiller room

- Trade spaces

- General storage SHINE Medical Technologies 19.2-6 Rev. 0

Chapter 19 - Environmental Review Proposed Action

- Fire brigade

- Health physics (hot)

- Health physics (cold)

- Ion exchange assembly

- FDA lab

- Hot lab

- Isolation pack room

- Radioactive waste packaging

- Product packing

- Material shipping

- High voltage breakers

- Diesel generator room

- Day tank room

- Janitorial closet

• Diesel generator building

- Diesel room

- Underground storage tank

• Waste staging and shipping facility building

• Support facility building

- Receiving area

- Chemicals room

- General storage

- Janitorial closet

- Propane canister storage (for fork lifts) 19.2.1.2.2 Underground, Stormwater, and Sewage Features An underground storage tank near the diesel generator building provides storage for the diesel generator.

A sanitary sewer pipeline carries wastewater from the SHINE facility to the city main sewage pipeline. A natural gas pipeline provides commercial natural gas to the SHINE facility. An underground electrical distribution line connecting to the electric transformers provides electricity to the SHINE site. A municipal water line lateral is accessed to provide the SHINE facility with water supply. Infrastructure improvements are discussed in Subsection 19.4.13.7.1.

Per Figure 19.2.1-1, the SHINE facility buildings, storage, and miscellaneous structures/areas are surrounded by an exterior stormwater runon diversion berm with an interior and exterior ditch. The exterior ditch directs stormwater and farm field runoff to flow spreaders, which direct the excess water to the surrounding fields. The interior ditch directs excess water to the stormwater vegetated swale, which slopes towards an existing road side drainage. A stormwater overflow storage area is provided for beyond-design events. The stormwater systems are SHINE Medical Technologies 19.2-7 Rev. 0

Chapter 19 - Environmental Review Proposed Action designed to address 1-year, 2-year, 24-hour storm events per state regulations, and are also designed to address 10-year and 100-year events, as required by the City of Janesville.

19.2.1.2.3 Monitoring Stations Refer to Figure 19.4.8-1 for environmental monitoring station locations. The need for monitoring stations is discussed in the following subsections:

• Air monitoring - Subsection 19.4.2

• Groundwater monitoring - Subsection 19.4.4

• Surface water monitoring - Subsection 19.4.4

• Meteorological monitoring - Subsection 19.4.2

• Ecological monitoring - Subsection 19.4.5

• Radiological monitoring - Subsection 19.4.8.3 SHINE Medical Technologies 19.2-8 Rev. 0

Chapter 19 - Environmental Review Proposed Action Table 19.2.1-1 Sensitive Populations, Nearest Resident, and Landmarks within 5 Miles (8 km) of the Site (Sheet 1 of 2)

Facility Type Location of Interest Distance to Project Site Boundary Residential Nearest Full-Time Resident 0.33 mi. (0.53 km) northwest Airport Park 0.30 mi. (0.48 km) northwest Park Paw Print Park 1.16 mi. (1.87 km) northwest First Choice Womens Health Center 1.37 mi. (2.20 km) north Medical Mercy Clinic South 1.58 mi. (2.54 km) north Mercy Hospital 4.21 mi. (6.78 km) north Blackhawk Technical College Aviation Center 0.89 mi. (1.43 km) southwest Educational Rock County Christian School 1.14 mi. (1.83 km) south Jackson Elementary School 1.28 mi. (2.06 km) south Community Center Caravilla Education and Rehabilitation Comm Center 1.62 mi. (2.61 km) south Dairy Production 0.51 mi. (0.82 km) east Horse Pasture 0.52 mi. (0.84 km) east Animal Production Goat Production 0.69 mi. (1.11 km) northwest MacFarland Pheasants, Inc. 0.86 mi. (1.38 km) north Beef Production Area 0.97 mi. (1.56 km) southwest SHINE Medical Technologies 19.2-9 Rev. 0

Chapter 19 - Environmental Review Proposed Action Table 19.2.1-1 Sensitive Populations, Nearest Resident, and Landmarks within 5 Miles (8 km) of the Site (Sheet 2 of 2)

Facility Type Location of Interest Distance to Project Site Boundary Rock River 1.9 mi. (3.1 km) west Spring Brook 3 mi. (4.8 km) north Rivers/Creeks Turtle Creek 4.5 mi. (7.2 km) southeast Fisher Creek 3 mi. (4.8 km) northwest Markham Creek 2.5 mi. (4.0 km) northwest Airports Southern Wisconsin Regional Airport 0.4 mi. (0.6 km) west Railroad Union Pacific Railroad 1.7 mi. (2.7 km) northwest U.S. Highway 51 Adjacent to the site boundary Highways U.S. Highway 14 3.75 mi. (6.0 km) northeast Interstate 39/90 2.1 mi. (3.4 km) east SHINE Medical Technologies 19.2-10 Rev. 0

[Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]

Chapter 19 - Environmental Review Proposed Action 19.2.2 RADIOISOTOPE FACILITY DESCRIPTION SHINE proposes to build a radioisotope facility. This facility produces Mo-99, I-131, and Xe-133.

The SHINE facility consists of eight irradiation units (IUs) capable of producing up to 8200 6-day curies per week of Mo-99. Figure 19.2.2-1 provides a flow diagram of the isotope production process.

[ Proprietary Information ]

19.2.2.1 General Description of the Isotope Production Process The SHINE facility produces Mo-99, I-131, and Xe-133 as fission products of uranium-235 (U-235) in a subcritical, low enriched uranium (LEU) target solution. The subcritical solution is located in an annular target solution vessel (TSV) and driven by an accelerator-based neutron source located on the center axis of the TSV annulus. The neutron source consists of a deuterium (d or D) beam impacting a tritium (t or T) gas target which produces energetic neutrons via the d(t,4He)n reaction. The neutron source is supplied with tritium gas from a tritium purification system.

The neutron population from the driver is increased as it travels through a neutron multiplier on its way to the TSV, and then further multiplied in the target solution itself via subcritical fission reactions. As the target solution is irradiated, radiolysis and fission will create off-gases that are handled by a system designed to recombine hydrogen and oxygen and trap certain volatile fission products.

During normal operation, the IUs are operated on a weekly basis. At the end of each irradiation cycle, the target solution is removed from the TSV and transferred to a hot cell where isotopes are selectively extracted. Purified Mo-99, I-131, and Xe-133 are tested by quality control, packaged, and shipped to customers.

After the target solution passes through the extraction column, it is evaluated for re-use. In most cases, the solution is returned to the TSV with minimal adjustment. At some point, however, certain fission products that have built up over time may need to be removed from the solution, in which case the solution undergoes a clean-up process.

Target solution preparation and clean-up, isotope extraction and purification, and any tanks containing target solution (besides the TSV) generate radioactive off-gases that are captured by a radioactive gas treatment system. The neutron generator, target solution preparation, tritium purification, TSV off-gas handling, radioactive gas treatment, target solution clean-up, isotope extraction, and isotope purification generate radioactive waste in various forms that is processed, packaged, (in some cases) staged, and disposed of according to its classification. Subsection 19.2.5 provides additional information on the radioactive waste treatment systems. Refer to Figure 19.2.2-1 for a flow diagram of the radioisotope production process.

SHINE Medical Technologies 19.2-11 Rev. 0

Chapter 19 - Environmental Review Proposed Action 19.2.3 WATER CONSUMPTION AND TREATMENT 19.2.3.1 Water Consumption The Janesville municipal water system will supply the water needs of the SHINE facility. A water use diagram for the facility is provided in Figure 19.2.3-1. Water uses for the facility include the following:

• Isotope production

• Isotope processing

• Potable water

• Fire protection

• Facility heating and cooling For isotope production, water is required for the preparation of the target solution. Water required for isotope production amounts to 175 gallons/day (gpd) (662 liters/day [lpd]). Processing including isotope extraction and purification, target solution clean-up, and waste processing requires 1051 gpd (3979 lpd) of water. There will be no liquid discharges from the radiologically controlled area (RCA) to the Janesville municipal sanitary system.

Wastewater from outside the RCA will be discharged to the Janesville municipal sanitary system.

Potable water demand is 3270 gpd (12,378 lpd) and blowdown and makeup to the facility heating water system is 2580 gpd (9766 lpd). The makeup requirement to the fire protection system is 5 gallons per minute (gpm) (19 liters per minute [lpm]). The largest automatic fire suppression system demand in the event of a fire is 390 gpm (1476 lpm). The automatic fire suppression demand will be supplied by a fire water tank. The makeup water requirement for the facility chilled water supply and distribution system is 5 gpm (19 lpm). The makeup water requirement for the facility heating water system is 5 gpm (19 lpm).

19.2.3.2 Water Treatment The SHINE facility includes the following water treatment processes:

• Demineralization (i.e., deionization).

• Cooling water treatment.

• Facility heating water system treatment.

19.2.3.2.1 Water Demineralization Within the SHINE facility, most of the water used within the process is demineralized in order to control the addition of chemicals within the water to process streams. This is particularly important given the radiological nature of some parts of the process (and the resultant potential for the formation of activation products), and the necessity of a highly pure Mo-99 product.

SHINE Medical Technologies 19.2-12 Rev. 0

Chapter 19 - Environmental Review Proposed Action 19.2.3.2.2 Cooling Water Treatment Water for use in the closed-loop cooling water system is typically treated prior to addition to the loop, and then dosed periodically. The dosing is determined by testing. The types of chemicals added to the water are:

• Biocides - added to inhibit microbial growth in the water, which can lead to fouling.

• Corrosion inhibitors - added to inhibit corrosion of piping and components the cooling water flows through. Often corrosion is inhibited by halogen-based biocides.

• Scale inhibitors - added to reduce scale formation, particularly within heat exchangers.

The specific inhibitor(s) is selected based on the chemistry of the makeup water for the cooling water system.

19.2.3.2.3 Facility Heating Water System Treatment The SHINE facility uses a closed-circuit heated water system for building heating. This is referred to as a boiler by HVAC engineers, but the water does not change phases. The feedwater for this system is treated to reduce corrosion and to reduce scaling.

The magnitude of corrosion and scaling in any specific application is a function of the feedwater chemistry and the operating conditions of the boiler system. In some instances, feedwater is demineralized prior to being fed to the boiler.

The boiler capacity is calculated based on 100 pound-force per square inch gauge (psig) steam, and using a combined 5 percent blowdown and losses (i.e., make-up water is 5 percent of steam flow). The peak annual facility HVAC heat load (Btu/hr) is used as the sizing criteria for the required steam flow rate with a 50 percent margin included for other facility heating usage.

19.2.4 COOLING AND HEATING DISSIPATION SYSTEMS 19.2.4.1 Cooling Systems Water used for SHINE facility cooling is produced at a central location by multiple air-cooled chillers. The chilled water is circulated in primary-secondary fashion, utilizing heat exchangers (shell and tube type) to isolate the process and HVAC loops from the central chilled water loop.

This allows for temperature regulation of the water loops. Chillers have N+1 redundancy (i.e., there will be one redundant unit). They shut down upon a loss of power event.

• Cooling water is used in the SHINE facility for process cooling. A water supply temperature of 85 degrees Fahrenheit (°F) (29 degrees Celsius [°C]) with a return average temperature of 100°F (38°C) is assumed.

• Chilled water may be used in the facility for process cooling and is used for HVAC cooling. A chilled water supply temperature of 40°F (4°C) with a 50°F (10°C) return temperature is assumed.

SHINE Medical Technologies 19.2-13 Rev. 0

Chapter 19 - Environmental Review Proposed Action The air-cooled chillers operate year-round, rejecting heat directly to the atmosphere through a sensible heat transfer process (forced air blowing over coils). No water is consumed or lost by evaporation in this arrangement. The total estimated heat of rejection witnessed by the chillers:

• Estimated peak process load: 2.64 x 106 british thermal units per hour (Btu/hr) (2.79 x 106 kilojoules per hr [kJ/hr]).

• Estimated peak HVAC load: 4.66 x 106 Btu/hr (4.92 x 106 kJ/hr).

• Estimated heat of compression: 1.83 x 106 Btu/hr (1.93 x 106 kJ/hr).

• Estimated total heat rejection load: 9.13 x 107 Btu/hr (9.63 x 106 kJ/hr).

For bounding purposes, the units are considered to run continuously (i.e., 24 hrs per day, 7 days per week).

Being a closed-loop system, makeup water is periodic and minimal (less than 10 percent of the system capacity per year). Makeup water is treated. Water treatment is standard chemical treatment.

The chillers contain non-chlorofluorocarbon refrigerant and are located outdoors. The SHINE facility does not use cooling towers.

19.2.4.2 Heating System Multiple natural gas fired boilers provide heating water to the HVAC air handlers. The peak boiler load is 6.6 MBtu/hr (6.3 kJ/hr), with a total annual natural gas consumption of 7.67 x 107 standard cubic feet (scf) (2.17 x 106 cubic meters [m3]). Ultimately, all of this heat ends up in the environment.

This assumes a natural gas heat content of 900 Btu/scf, an 80 percent efficient boiler, no recirculation, operation 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day and 7 days per week, supply air volume of 156,000 cubic feet per minute (4417 cubic meters per minute) at site altitude and a reheat capability up to 75°F (24°C).

19.2.5 WASTE SYSTEMS 19.2.5.1 Sources of Radioactive Liquid, Solid, and Gaseous Waste Material 19.2.5.1.1 Facility The sources of radioactive liquid, solid, gaseous waste generated by the operation of the SHINE facility are as follows:

• Neutron generators.

• Waste generated by the TSV solution preparation process includes used cans in which new uranium metal is received, personnel protective equipment (PPE), and spent filters.

• Waste generated by the operation of the TSV off-gas system includes spent zeolite beds.

SHINE Medical Technologies 19.2-14 Rev. 0

[Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]

Chapter 19 - Environmental Review Proposed Action

• Waste generated by operation of the Mo-99 recovery system includes the spent extraction columns, spent wash solution, and rotovap condensate.

• Waste generated by the target vessel solution cleanup process includes [ Proprietary Information ] UREX raffinate, non-RCRA (Resource Conservation and Recovery Act) spent solvent when replaced infrequently, spent resin columns, and spent caustic scrubber solution.

• Routine waste from maintenance activities.

• The Mo-99 purification process produces waste consisting of glassware and liquid waste.

19.2.5.1.2 Nearby Operating Facilities Facilities that handle and store radioactive materials in the area of the SHINE facility are discussed in Subsection 19.3.8.5.

19.2.5.2 Type and Quantity of Radionuclides and Hazardous Materials The type and quantity of radionuclides and hazardous materials is provided in Table 19.2.5-1.

19.2.5.3 Description of Waste Systems 19.2.5.3.1 Solid Radioactive Waste Handling System Class A solid waste consists of Class A trash (e.g., personal protective equipment [PPE], Mo-99 purification glassware, filters), extraction columns, and the neutron generators. The Class A trash is consolidated for low specific activity (LSA) shipment. Extraction columns are replaced after each TSV processing batch. After a two week decay period in the Mo extraction cell, the columns are stored within the facility for further decay and consolidated for LSA shipment. The neutron generators are planned to be replaced on an approximately yearly basis. After replacement, the neutron generators are size-reduced and consolidated for shipment as LSA. The Class A trash, extraction columns, and the neutron generators are shipped approximately yearly to EnergySolutions (ES) disposal site.

The zeolite beds are associated with the TSV off-gas system. The toxicity characteristic leaching procedure (TCLP) may or may not result in the classification of zeolite beds as Resource Conservation and Recovery Act (RCRA) waste; however, testing of untreated silver mordenite at Hanford indicated the material exceeds TCLP limits prior to solidification. The waste is also radioactive and would be a mixed low level waste (MLLW). Tritium, iodine, xenon, and krypton enters these beds. Only iodine is adsorbed in the zeolite beds. The waste classification for this material is a function of both the efficiency of the zeolite beds and the change out frequency of the beds. It is likely the beds, in terms of operational lifetime, could build up enough iodine-129 to be greater than Class C (GTCC) waste. The zeolite is shipped to an off-site processor. The shipment is a Type B shipment and occurs infrequently. The processor for the zeolite beds is Waste Control Specialists (WCS) in Andrews, Texas.

SHINE Medical Technologies 19.2-15 Rev. 0

[Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]

Chapter 19 - Environmental Review Proposed Action The ion exchange resin used for removal of cesium-137 (Cs-137) and cerium (Ce) has a high capacity for Cs-137 capture and will be changed out based on curie limits at the receiving facility and also based on shipping limits. The spent resins are solidified in a shielded waste processing hot cell. The used resin is classified as GTCC waste and is shipped as Type B to an off-site location for long-term storage at WCS.

As discussed above, the target solution cleanup system uses an anion exchange column to remove technetium and iodine. When the anion exchange resin is replaced, the spent resin is solidified on-site and sent off-site for disposal (WCS in Andrews, Texas).

There will be no solid waste disposal at the SHINE site.

19.2.5.3.2 Liquid Radioactive Waste System Liquid waste discharged from the various processes at the SHINE facility (other than spent solvent) are combined into one of two tanks. Two tanks are needed to allow liquid waste to decay and also so that a somewhat consistent radiological environment exists for waste processing.

Once the first tank is filled the other tank will begin to fill. At this point the pH is adjusted so that the waste can be passed through an ion exchange resin for removal of Cs-137 and Ce-144/

Pr-144. This allows the majority of the liquid stream to become Class A waste. This cleaned-up material is then sent to an evaporator for volume reduction. The evaporator overheads are reused and the bottoms are solidified and shipped to ES for final disposal. The spent resin treatment is discussed in the section above. No liquid radioactive waste is discharged from the SHINE facility.

The spent solvent is not a RCRA waste and is replaced once per year. The solvent is sent to a processor (Diversified Scientific Services, Inc [DSSI], in Kingston, Tennessee) for thermal treatment.

[ Proprietary Information ] This waste is classified as Class B waste and is shipped as Type B to WCS in Andrews, Texas.

[ Proprietary Information ] The waste is solidified in a hot cell using Portland cement. Some additives may be required based on the final chemistry of incoming resin and precipitate. These shipments are Type B shipments.

There will be no liquid waste disposal at the SHINE site.

19.2.5.4 Proposed Hazardous Material Disposal Activity The only hazardous (or potentially hazardous) materials are [ Proprietary Information ] and the zeolite beds. Although small quantities of [ Proprietary Information ] is expected to pass TCLP, and is not considered hazardous waste. Waste streams with a hazardous component are mixed low-level waste such as the zeolite beds and are handled as described in Subsection 19.2.5.3.1.

SHINE Medical Technologies 19.2-16 Rev. 2

Chapter 19 - Environmental Review Proposed Action 19.2.5.5 Direct Radiation Sources Stored On-Site or near the SHINE Facility 19.2.5.5.1 Direct Radiation Sources Stored On-Site The wastes listed in Table 19.2.5-1 are stored on-site for a period of time before they are shipped off-site. The frequency of shipment of each type of waste is provided in Table 19.2.5-1.

LEU metal is stored in the target solution preparation area. Medical isotopes will not be stored for any significant time period as they must be shipped to clients as quickly as possible.

19.2.5.5.2 Direct Radiation Sources Stored near the SHINE Facility There are no direct radiation sources stored near the SHINE facility. Facilities that handle and store radioactive materials in the area of the SHINE facility are discussed in Subsection 19.3.8.5.

19.2.5.6 Pollution Prevention and Waste Minimization Pollution prevention and waste minimization planning provides the framework for promoting environmental stewardship and educating employees in the environmental aspects of activities occurring in the workplace, the community, and homes. The SHINE facility will have a program for pollution prevention and waste minimization that includes the following:

• Waste minimization and recycling for the various phases of the SHINE facility construction and operation.

• Employee training and education on general environmental activities and hazards regarding the facility, operations and the pollution prevention program, as well as waste minimization requirements, goals, and accomplishments.

• Employee training and education on specific environmental requirements and issues.

• Responsibilities for pollution prevention and waste minimization.

• Recognition of employees for efforts to improve environmental conditions.

• Requirements for employees to consider pollution prevention and waste minimization in day-to-day activities and engineering.

SHINE Medical Technologies 19.2-17 Rev. 0

[Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]

Chapter 19 - Environmental Review Proposed Action Table 19.2.5-1 Estimated Type and Quantity of Radioactive Wastes Associated with the SHINE Facility (Sheet 1 of 3) 55-gallon drum Number of Class as Volume as equivalent Shipment Shipments/

Description Matrix Generated Contents Volume shipped (ft3) as shipped Type yr Destination Neutron Generator Solid A Activated metal parts Extraction Columns Solid A Stainless resin columns 4338 4338 590 LSA 3.00 ES ft3/yr Class A Trash Solid A PPE, Mo-99 purification glassware, filters, etc Spent Solvent Liquid(a) A n-dodecane, 22 gallons/ -- 0.4 LSA 1.00 DSSI tributyl yr phosphate Tc/I columns Resin C Resin 16 gallons/ 23 3.1 Type B 0.3 WCS yr Zeolite Beds Solid GTCC Silver coated 0.4 ft3/yr 0.4 0.05 Type B 1.00 WCS beds Cs/Ce Media Resin GTCC Resin 16 gallons/ 23 3.1 Type B 0.3 WCS yr

[ Proprietary [ Proprietary B [ Proprietary 295 79 11 Type B 1.00 WCS Information ] Information ] Information ] gallons/yr SHINE Medical Technologies 19.2-18 Rev. 2

[Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]

Chapter 19 - Environmental Review Proposed Action Table 19.2.5-1 Estimated Type and Quantity of Radioactive Wastes Associated with the SHINE Facility (Sheet 2 of 3) 55-gallon drum Number of Class as Volume as equivalent Shipment Shipments/

Description Matrix Generated Contents Volume shipped (ft3) as shipped Type yr Destination Spent Washes Liquid(a) A [ Proprietary Information ]

Rotvap Condensate Liquid(a) A [ Proprietary Information ]

UREX Raffinate Liquid(a) B [ Proprietary Information ]

59,708 9738 1324 LSA 18 ES Decontamination (a) A Decon fluid gallons/yr Liquid Waste unknown Spent Eluate Liquid(a) A [ Proprietary Solution Information ]

NOx Scrubber Liquid(a) A [ Proprietary Solution Information ]

SHINE Medical Technologies 19.2-19 Rev. 0

Chapter 19 - Environmental Review Proposed Action Table 19.2.5-1 Estimated Type and Quantity of Radioactive Wastes Associated with the SHINE Facility (Sheet 3 of 3) a) Liquid waste discharged from the various processes at the SHINE facility is either solidified and then shipped to a waste depository or reused.

SHINE Medical Technologies 19.2-20 Rev. 0

Chapter 19 - Environmental Review Proposed Action 19.2.6 STORAGE, TREATMENT, AND TRANSPORTATION OF RADIOACTIVE AND NONRADIOACTIVE MATERIALS, INCLUDING LEU, WASTE, RADIOISOTOPES, AND ANY OTHER MATERIALS There are no storage needs for enriched uranium fuel, irradiated enriched uranium, or medical isotope product. LEU metal (not fuel) is stored in the target solution preparation area. Medical isotopes will not be stored for any significant time period as these items will be transported to clients as quickly as possible. Irradiated enriched uranium is not stored, as the facility cleans up and recycles this material.

The radiological wastes listed in Table 19.2.5-1 are stored on-site for a period of time before they are shipped off-site. The frequency of shipment of each type of waste is provided in Table 19.2.5-1. Enough storage capacity is provided on-site to accommodate the amount of waste between shipments to the off-site repositories. Subsections 19.2.5.3.1 and 19.2.5.3.2 discuss solid and liquid radioactive waste handling. Radioactive waste gases are discussed in Subsection 19.4.8.2.

The treatment and packaging for shipment of radioactive and nonradioactive wastes and medical isotopes are controlled with SHINE facility procedures.

The packaging systems used to transport enriched uranium, radioactive wastes, and medical isotopes are licensed for the class and type of material that is being transported.

The target solution for the SHINE irradiation unit is made on-site at the SHINE facility from LEU metal purchased from Y-12, located in Oak Ridge, Tennessee. Y-12 is approximately 650 miles by road from Janesville, Wisconsin.

The radioactive wastes will be transported to the destinations listed on Table 19.2.5-1. The distances from the SHINE facility to these facilities are provided in Subsection 19.4.10.1.1.

The medical isotopes produced by SHINE are shipped to three processing facilities, as discussed in Subsection 19.4.10.1.1. The distances from the SHINE facility to these facilities are provided in Subsection 19.4.10.1.1.

SHINE Medical Technologies 19.2-21 Rev. 0