ML22042A098

Kairos Power LLC, Chapter 2, Environmental Report

ML22042A098
Person / Time
Site:	Hermes
Issue date:	02/10/2022
From:	Kairos Power
To:	Office of Nuclear Reactor Regulation
Shared Package
ML22042A095	List: ML22042A096 ML22042A097 ML22042A098
References
KP-NRC-2202-005
Download: ML22042A098 (18)

Text

Environmental Report Proposed Action CHAPTER 2 PROPOSED ACTION 2.1 PROPOSED ACTION The Proposed Federal Action is issuance of a Construction Permit (CP) and subsequent Operating License (OL) for a nonpower reactor facility (Hermes) to test and demonstrate the key technologies, design features, and safety functions of the Kairos Power Fluoride SaltCooled High Temperature Reactor (KP FHR) technology. The facility would also provide data that may be used for the validation of safety analysis tools and computational methodologies used for the designing and licensing future KPFHR reactors.

The applicant for this CP and the OL and owner of the facility is Kairos Power LLC, (Kairos Power).

Information about Kairos Power is provided with the Preliminary Safety Analysis Report (PSAR). As the owner and licensee, Kairos Power has the necessary authority and control related to the construction and operation of the facility once the CP and the OL are approved.

Kairos Power is requesting NRC review and approval of the CP application to support construction of safetyrelated structures, systems, and components anticipated to begin as early as mid2023. Kairos Power is a recipient of a U.S. Department of Energy (DOE) Advanced Reactor Demonstration Program (ARDP) award for Risk Reduction funding for the KPFHR technology with initial operations proposed to begin by mid2026. To support this objective, the earliest start date for construction is expected to be April 2023 and the earliest projected date for completion of construction is mid2025. The latest projected date for completion of construction is anticipated to be December 2026. The facility is expected to have a 410year operational license. Therefore, decommissioning activities would be expected to be initiated after the operational phase ends and is anticipated to begin in 20306.

The construction phase of this project is estimated to require an estimated average of 212 onsite workers (425 at peak times) and a monthly average of 213 truck deliveries and four offsite shipments of construction debris. Table 2.11 shows estimates for materials that would be consumed. Additionally, approximately 31,800 gallons of diesel fuel (as a bounding assumption, fuel is assumed to be diesel) is assumed to be consumed on an average monthly basis. Table 2.12 shows the different types of construction equipment that would be used during the construction phase. These construction activities are estimated to affect an estimated 138 acres of land, of which an estimated 30 acres would be permanently disturbed for operation of the facility.

A lowpressure, molten salt coolant, i.e., Li2BeF4 (Flibe) and the intermediate coolant (nitrate salt) would be shipped to the site prior to startup. Flibe is estimated to be delivered in 20 shipments of 1 ton each. Nitrate salt is estimated to be delivered in 28 shipments of approximately 7 tons each.

During operations, an estimated average of 38 workers per weekday (68 fulltime positions) are required for staffing. An estimated monthly average of 15 truck deliveries and four offsite waste shipments. An additional 20 shipments of Flibe (approximately one ton each) is estimated to be delivered to the facility before the end of the first two years of operation and 28 shipments per year of nitrate salt (7 tons each) for the duration of operations. Hazardous materials that would be stored onsite in small quantities include new Flibe and nitrate salt lubricating oil for rotating equipment and cleaning materials and consumables used for cleaning and maintenance. A bounding value of approximately 21,555 gallons of diesel fuel for the standby diesel generator would be contained in an onsite storage tank.

Once the facility reaches the end of its licensed life, the Operating License would be amended by the NRC and decommissioning activities would be commenced. Radioactive equipment and materials will be disposed according to local and federal laws and regulations. It is estimated that postoperational Kairos Power Hermes Reactor 21 Revision 0

Environmental Report Proposed Action 2.3 NONPOWER REACTOR The facility would house one Hermes reactor. The Hermes reactor is a KPFHR with the core configuration made up of a pebble bed core, graphite moderator/reflector, and Flibe molten salt coolant. This will be a nonpower test reactor with approximate dimensions of the reactor vessel being 3.4 meters in diameter and 4.7 meters in height. The facility will contain only one unit with a maximum thermal power of 35 megawatts (MW) thermal (MWth). The purpose of the reactor will be to demonstrate and test the design features and safety functions of the technology. It will be a nonpower test reactor, whereby the heat generated in the core will not be used for the production of electric power. Instead, heat will be transported out of the core via the primary heat transport system (PHTS) and then dissipated into the atmosphere via the primary heat rejection system (PHRS). Figure 2.31 shows the process flow diagram for the reactor and heat dissipation .

The reactor vessel and internal structures will be constructed of stainless steel that conforms to the 2019 composition specification requirements of American Society of Mechanical EngineersSection III, Division 5, with a targeted service life of 410 years. The moderator/reflector will be constructed of a nuclear grade graphite selected for its compatibility with the chemistry environment of the reactor core and would also have a targeted service life of 410 years.

The reactor core will use 4centimeter (cm)diameter graphite pebbles with embedded coated TRI structural ISOtropic (TRISO) particle fuel. The particles will be comprised of a uranium fuel kernel and three layers of carbon and ceramic based materials that prevent the release of radioactive fission products. The maximum enrichment of the uranium fuel will be 19.55 weight percent, and the required startup fissile inventory is estimated to be no greater than 25 kilograms (kg) 235U. A fraction of the pebbles in the core are moderator (graphiteonly) pebbles. Fuel pebbles are extracted from the reactor while online using the pebble extraction machine, the burnup is measured, and the fuel is either returned to the reactor or removed to storage. The estimated residence time for pebbles in Hermes is about 315 days.

Kairos Power Hermes Reactor 214 Revision 0

Environmental Report Proposed Action 2.6.1.2.2 Wet Solid Wastes Wet solid wastes would include filters and or sieves from the inert gas system (IGS), chemistry control system, and IGS oxygen and moisture absorbers. Like dry solid wastes, wet solid wastes would be packaged and prepared for onsite storage and then eventual shipment offsite.

2.6.1.2.3 Tritium Management System The tritium management system (TMS) would provide capture of tritium (H3) from gas streams in various plant locations to reduce environmental releases. Figure 2.61 identifies the tritium management system components and indicates the approximate distribution of tritium throughout the reactor system. H3 is produced primarily by neutron irradiation of lithium in the salt coolant, such as from lithium7 (Li7), lithium6 (Li6) remaining after initial enrichment, and Li6 produced from transmutation of beryllium9 (Be9). The primary system functions of the TMS include:

H3 separation from argon in the IGS H3 separation from dry air in the PHRS cover gas H3 separation from dry air in Reactor Building cells Final collection and disposition of H3 The TMS would produce three solid radioactive waste streams:

High specific activity H3 stored as metal hydride High specific activity H3 on molecular sieve Low specific activity tritium on molecular sieve 2.6.1.2.4 Fuel Pebble Handling and Storage System Operation of the facility is estimated to be 410 years and would generate approximately 38,800 spent pebbles per year. Therefore, over this duration, it is estimated that 388,000155,200 used pebbles would be produced. The Hermes reactor fuel and moderator pebbles are continually cycled through the pebble handling and storage system (PHSS) which removes pebbles from the reactor for inspection. A fuel pebble is removed permanently from circulation and placed in a storage canister if it meets preset standards for burnup and integrity. Fuel and moderator pebbles that are removed are replaced with new pebbles. This system requires a constant supply of new fuel pebbles. The storage canisters would be transferred to an onsite canister storage system with an estimated conservativesufficient storage capacity of 192 canisters for 4 years of licensed reactor operation. Section 2.7.1 provides a description of spent fuel storage.

2.6.1.3 Gaseous Radioactive Waste System The facility is not expected to need a gaseous radioactive waste system. Gaseous radioactive wastes generated would be primarily discharged to the Reactor Building exhaust system, in which they pass through a high efficiency particulate air filter. Releases to the atmosphere would be controlled such that the total radiation exposure to persons outside the controlled area is as low as reasonably achievable and does not exceed applicable regulations.

2.6.2 Nonradioactive and Hazardous Waste Systems The facility would generate general types and quantities of nonradioactive and nonhazardous solid waste. No specific systems are planned other than waste management plans and policies that would control nonradioactive and nonhazardous solid wastes. Solid waste management and control measures for the facility would include waste reduction, recycling, and waste minimization practices that would be Kairos Power Hermes Reactor 222 Revision 0

Environmental Report Proposed Action 2.7 STORAGE, TREATMENT, AND TRANSPORTATION OF RADIOACTIVE AND NONRADIOACTIVE MATERIALS 2.7.1 New and Irradiated Fuel The Hermes reactor will use spherical fuel pebbles containing embedded TRISO particles. The fuel design is described in PSAR Section 4.2. A manufacturer has not been decided for the Hermes reactor. New fuel is anticipated to either be shipped to the facility in U.S. Department of Transportation (DOT) certified shipping containers or manufactured at a nearby manufacturing facility using highassay lowenriched uranium (HALEU) supplied from external sources. The fuel would also be stored onsite in the shipping containers until loaded into the PHSS.

During reactor operations, the facility would receive an initial shipment of fuel and periodic shipments of fuel to support continued operations over an estimated 410year license period. When removed from the reactor, used TRISO fuel pebbles would be stored in canisters in a spent fuel storage area within the Reactor Building. Each canister would hold approximately 2,100 fuel pebbles. Once a canister is filled, the canister would be initially stored in a watercooled storage pool. During this time the decay heat generation drops rapidly. The pool would also accommodate a full core offload for temporary storage.

After the initial cooling period in the pool, fuel canisters would be transferred to the larger aircooled storage cavity. The storage capacity of the aircooled cavity would have an estimated conservative storage capacity of 192 canisters, which is sufficient for 410 years of licensed reactor operation.

If necessary, spent fuel canisters would be loaded into dry storage casks suitable for onsite storage on an exterior spent fuel storage pad. Such storage canisters have not been specifically designed for the Hermes fuel but the individual canisters are compatible with conventional dry cask overpacks. Spent fuel would ultimately be transferred from onsite storage casks to spent fuel shipping containers certified by the NRC and DOT. While a large number of transportation packages are certified by the NRC for shipping unirradiated light water reactor (LWR) fuel, irradiated LWR fuel, and radioactive waste, transportation packages would need to be certified for shipping nonLWR fuel. Without a certified design, the number of spent fuel shipments cannot be calculated, but would be bounded by the 60 annual shipments of spent fuel provided for an 880 MWelectric (MWe) reference reactor described in NRC guidance (Reference 1).

Spent fuel would eventually be transported by truck or rail to a final spent fuel repository or a regional spent fuel storage facility. Neither facility currently exists in the United States. However, the transportation distance is likely bounded by the approximate 2,100 miles from Oak Ridge, Tennessee to Beatty, Nevada. Beatty, Nevada is located just west of Yucca Mountain, the site in the United States most studied for suitability as a spent fuel repository.

2.7.2 Lowlevel Radioactive Waste Operations and decommissioning would generate solid LLRW. Generally, LLRW would be stored in strong, tight industrial packages approved for transportation. Common waste containers include B12 and B25 steel boxes, and 55gallon steel drums. LLRW would be transported by truck to disposal sites west of Andrews, Texas (Waste Control Specialists) or near Clive, Utah (EnergySolutions). The Waste Control Specialists disposal site accepts Class A, B, and C waste and is approximately 1,300 miles from Oak Ridge. The EnergySolutions disposal site accepts only Class A waste and is approximately 2,000 miles from Oak Ridge. Some wastes could be managed through EnergySolutions Bear Creek LLRW processing facility located less than 4 miles south of the site. While the ultimate disposal route for waste processed through the Bear Creek facility is dependent on the waste type, it often ultimately gets shipped to Utah for final disposal.

Kairos Power Hermes Reactor 226 Revision 0

Environmental Report Proposed Action Flibe is utilized in the IMS, the PHTS, and the reactor, all of which are located in the Reactor Building.

Used radioactive Flibe that is removed from the IMS in liquid form during normal operations would be filled into containers where it would be allowed to cool and solidify. It is estimated that the Flibes specific activity in curies per ton (Ci/ton) after a cooling period of 1 year would be 380 Ci/ton. No other treatment would be required. The solid Flibe is anticipated to be stored onsite until decommissioning when it would be shipped to Waste Control Specialists for Class B or C LLRW disposal. Storage areas for solidified Flibe waste would require additional radiation shielding to keep occupation radiation doses below regulatory limits an as low as reasonably achievable.

An estimated 120 drums of Flibe waste would be generated over the assumed 410 year licensed life of the facility. The waste would require a Type B shipping cask. The capacity of a Type B cask is dependent on the shielding necessary. Assuming a minimum of six drums per cask, 120 drums would require 20 cask shipments. Alternatively, Type B drums could be used likely resulting in more drums per shipment and fewer shipments.

During operations, nitrate salts used to transfer heat from the reactor to the heat dissipation system would be pumped through the PHRS. The nitrate salts would be approximately 60 percent sodium nitrate and 40 percent potassium nitrate by weight. Used radioactive nitrate salt would be pumped into storage containers and allowed to cool prior to being shipped to Waste Control Specialists for Class B LLRW disposal or to EnergySolutions for Class A LLRW disposal. No other treatment would be required.

Based on an estimated 200 tons of nitrate salt shipped to the site annually, an average of 10 truck shipments per year would be required to ship an equivalent amount of salt waste. Waste containers would not require radiation shielding.

The IGS would transport radioactive materials (fission products, tritium, and other radionuclides) for downstream treatment. The TMS would capture tritium from gas streams in various plant location in order to reduce environmental releases. The TMS would separate tritium from argon in the IGS, from dry air in the PHRS cover gas, and from dry air in the Reactor Building cells and collect the tritium in solid materials for final disposition as a solid LLRW. These wastes are expected to be Class B LLRW that would be stored on site in approved shipping containers until transported to Waste Control Specialist for disposal.

Tritium would not ultimately be stored in a liquid or gaseous form in the TMS. A modest amount of water may be used for analytical purposes such as tritium trapping in water bubblers and liquid scintillation counting (estimated 1 ft3/year with dissolved tritium activity of 10 Ci [10 Ci/year total liquid water waste]). There would be a small amount of tritium ingress into other water systems, but it is not expected that water from these systems would be released as effluent from the Reactor Building.

The total number of LLRW shipments has not been calculated. However, including the number of waste nitrate slat shipments, the total number of LLRW shipments would be expected to be bounded by the 46 annual shipments of LLRW provided for an 880 MWe reference reactor described in NRC guidance (Reference 1).

2.7.3 Nonradioactive Materials Nonradioactive Flibe is anticipated to be shipped to the site in approximately 20 initial 1ton shipments with an additional 20 tons estimated to be shipped before the end of the first two years of operation.

The Flibe would be stored in the Reactor Building. Nitrate salt would be shipped to the facility at an estimated rate of 200 tons per year in approximately 28 shipments (7 tons per shipment) and stored in the intermediate salt vessel located in the Reactor Building. As discussed in Section 2.4, the facility would also receive twelve 4,000gallon shipments of demineralized water each month.

Kairos Power Hermes Reactor 227 Revision 0

Environmental Report Chapter 4 - Impacts CHAPTER 4 IMPACTS OF PROPOSED CONSTRUCTION, OPERATIONS, AND DECOMMISSIONING This chapter provides an analysis of the impacts of construction, operation, and decommissioning of the facility. Overall impact rankings are given to each environmental resource evaluated. Unless otherwise defined, criteria followed the guidance given in NRC Impact Rankings in 10 CFR 51 Subpart A, Appendix B, Table B1, Footnote 3 as follows:

SMALL (S) - Environmental effects are not detectable or are so minor that they would neither destabilize nor noticeably alter any important attribute of the resource.

MODERATE (M) - Environmental effects are sufficient to alter noticeably, but not to destabilize, important attributes of the resource.

LARGE (L) - Environmental effects are clearly noticeable and are sufficient to destabilize important attributes of the resource.

4.1 LAND USE AND VISUAL RESOURCES This section assesses the impacts of construction and operation on land use and visual resources for the site and region. As described in Section 3.1, the land use for the site and region is analyzed using the National Land Cover Database 2016. Impacts include effects from activities associated with construction and operation, including excavation, grading, placement of fill material, temporary staging and construction laydown, construction of permanent features, and potential operational disturbances.

4.1.1 Land Use This section discusses the land use impacts from construction and operation of the facility.

4.1.1.1 Site and Region As described in Section 3.1, the site consists of an approximate 185 acre parcel located within the Department of Energy (DOE) East Tennessee Technology Park (ETTP) in Oak Ridge, Tennessee. The site is located on a parcel that previously housed Buildings K31 and K33, which were part of the K25 complex and operated as the Oak Ridge gaseous diffusion plant (ORGDP). The region surrounding the site is defined in Subsection 3.1.1.2 as the area within a 5mile radius of the site center point. The entire region is located within Roane, Loudon, and Morgan Counties, Tennessee.

The land use impacts to the site and near offsite areas are based on the conversion of the site from a Brownfield to an active industrial area. As described in Section 3.1, the entire site is classified as a Brownfield due to the previous disturbances associated with use of the site for the K33 Building as part of the K25 Gaseous Diffusion Plant for the Manhattan Project. Therefore, the site has been historically industrial in nature. While the site is currently vegetated and unused, it remains part of the ETTP which is an industrial park. As such, impacts to land use from construction and operations would be SMALL.

The source of uranium for the TRISO fuel has not been finalized. For the purposes of evaluating potential impact, this report assumes it would be sourced from an insitu leach mine within the U.S., converted to gaseous uranium hexafluoride, and enriched to a maximum of 19.55 weight percent using commercially available centrifuge technology at an existing facility located within the U.S. While the uranium requirements, and thus land use requirements, for highassay, lowenriched fuel could be greater than for standard lowenriched fuel, Hermes will use significantly less uranium over its lifetime than a light water power reactor. Approximately 2.330.93 metric tons of uranium (MTU) would be needed over the 410year licensed operating life compared to an average of 20 to 33 MTU per year for lightwater power reactors. Therefore, the impacts on land use would be SMALL and bounded by impacts described in Kairos Power Hermes Reactor 41 Revision 0

Environmental Report Chapter 4 - Impacts Table S3 of 10 CFR 51.51 which considers the impacts from a generic reactor requiring an average of 33 MTU per year. Optionally, enriched uranium could be sourced from international supplies, or from existing stores in the U.S., either of which option would reduce the overall environmental impacts within the U.S. compared to the assumed option.

4.1.1.2 Special Land Uses As discussed in Subsection 3.5.4, there are two special land use areas in the region (Oak Ridge Wildlife Management Area [WMA] and Black Oak Ridge Conservation Easement [BORCE]), with neither area located onsite. Permanent and temporary impacts from construction and operation of the facility occur onsite and in near offsite areas, but not within either of these special land use areas. No direct or indirect impacts occur to special land use classification areas. Therefore, impacts to special land use classification areas would be SMALL.

4.1.1.3 Agricultural Resources and Facilities As described in Subsection 3.3.3.2, no prime farmland or farmland of statewide importance occurs within the site boundaries as the site is classified as a Brownfield. No other significant agricultural resources within the region of the site are located offsite in the region, as discussed in Subsection 3.1.1.2, and therefore, would not be impacted by construction and operationsrelated impacts. As such, direct and indirect impacts to agricultural resources and facilities from construction and operations would be SMALL.

4.1.1.4 Major Population Centers and Infrastructure Section 3.1 summarizes the major population centers and infrastructure located within Roane, Loudon, and Morgan Counties, which include the population center of Oak Ridge. The nearest major population center is the City of Knoxville located approximately 25 miles east of the site in Knox County. Permanent and temporary impacts from construction and operations of the facility occur onsite and immediately adjacent to the boundary of the site. Therefore, construction and operationsrelated direct and indirect impacts on major population centers and infrastructure would be SMALL.

4.1.1.5 Impacts from Decommissioning The facility is expected to begin operational activities in 2025 or 2026. The licensed life of the facility is expected to be 410 years. As a result, decommissioning activities would be expected to commence in 20306. Decommissioning activities, however, are similar to construction activities and involve heavy equipment to dismantle buildings and remove roadway and parking facilities. Resultant land uses following decommissioning are undetermined but may consist of returning the site to a Brownfield or open space. As such, direct and indirect impacts from decommissioning are anticipated to be similar to the impacts associated with construction and would be SMALL.

4.1.2 Visual Resources The visual setting of the area affected by the construction and operation of the site is described in Subsection 3.1.2. A design simulation of the proposed facility is shown in Figure 4.11. The existing site is composed entirely of land used for industrial purposes. Although the site has been previously disturbed, it is currently a Brownfield and there are no existing architectural features, established structures, or natural or built barriers, screens, or buffers. Consequently, the facility would alter the onsite condition and would partially obstruct views of the existing landscape. However, the aesthetic and scenic quality of the site is already low because of the historic activities at the site and surrounding industrial areas (see Subsection 3.1.2). Approximate dimensions of the Reactor Building complex for the visual impact Kairos Power Hermes Reactor 42 Revision 0

Environmental Report Chapter 4 - Impacts below 25 tpy for all HAPs combined. As a result, the project is subject to nonTitle V requirements. No air quality modeling is required for nonTitle V permitting.

4.2.1.2.1 Gaseous Effluents Air emissions of nonradiological gaseous criteria pollutants and HAPs would be emitted during the operations phase from: (1) intermittent use of dieselpowered or natural gas powered standby power generation sources such as generators or combustion gas turbines, (2) intermittent use of propanefired heaters for the intermediate coolant located in the primary heat rejection system (PHRS) during maintenance activities, (3) dieselpowered trucks that deliver material and haul off wastes, and (4) worker commuter vehicles. Radiological air emissions would be produced in the operations phase from the primary heat rejection stack, decay heat removal system vents, Reactor Building ventilation stack, and spent fuel cooling stack.

4.2.1.2.2 Evaluation of Emission Impacts on Air Quality Vehicle and Other Emissions During the operations phase, vehicular air emissions occur from the commuting workforce and from routine deliveries to/from the facility. The volume of traffic generated during operations is considerably lower than that expected during construction. Additionally, the lands on the developed site are either developed surfaces (buildings, paved parking/access road) or have been landscaped. Limitation of routine vehicle usage to paved areas reduces the emissions of fugitive dust. Impacts from vehicular air emissions and fugitive dust are far less than during the construction phase. Therefore, impacts during the operations phase would be SMALL.

Release Point Characteristics There would also be intermittent emissions from standby power generation sources such as generators or combustion gas turbines. These generators would operate less than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year. If used exclusively for replacement or standby service and at or less than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year, these generator units would not require a construction or operating permit, as outlined in Chapter 12003904 (Construction and Operating Permits) of the Tennessee Air Pollution Control Regulations. In addition, the potential to emit for the generator units based on 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> of operation would produce insignificant emissions (less than 5 tons per year for criteria pollutants and less than 1,000 pounds per year for an individual hazardous air pollutant [HAP]), as defined in Chapter 12000309 of the Tennessee Air Pollution Control Regulations; therefore, impacts would be SMALL.

Uranium Fuel Cycle Hermes will use significantly less uranium over its lifetime than a lightwater power reactor.

Approximately 2.330.93 MTU would be needed over the 410year licensed operating life compared to an average of 20 to 33 MTU per year for lightwater power reactors. Therefore, the environmental impacts from air emissions generated during mining, enrichment, and fuel fabrication activities would be SMALL and bounded by impacts described in Table S3 of 10 CFR 51.51 which considers the impacts from a generic LWR requiring an average of 33 MTU per year.

4.2.1.2.3 Greenhouse Gas (GHG) Emissions Greenhouse gases trap heat in the atmosphere, absorbing and emitting radiation in the thermal infrared range. The most important of these gases are carbon dioxide (CO2), methane, nitrous oxide, and Kairos Power Hermes Reactor 415 Revision 0

Environmental Report Chapter 4 - Impacts 4.7 SOCIOECONOMICS This subsection describes potential impacts to the socioeconomic environment, including transportation system impacts associated with the construction, operation and decommissioning of the facility. The evaluation of potential socioeconomics impacts addresses potential changes in the regional population, economy, housing availability, and public services. The evaluation of transportation system impacts addresses routes and modes that are involved with transporting materials, workers, and equipment to the site.

4.7.1 Socioeconomics Impacts This section evaluates impacts to the population, housing, public services (e.g., water supply), public education, and taxrevenues in the region of influence (ROI), that result from constructing, operating, and decommissioning the facility. The ROI is identified as the fivecounty region nearest the site (Anderson, Knox, Loudon, Morgan, and Roane) as illustrated in Figure 3.71 (Reference 1). Potential impacts of constructing the facility are attributable to the size of the construction workforce, the expenditures needed to support the construction program, and the tax payments made to political jurisdictions.

Because direct impacts are those that occur onsite, the only direct impacts are associated with the presence of the workforce at the site. All other socioeconomic impacts are considered to be indirect, as they occur offsite. The analysis presented in this subsection is based on the bounding parameters for the projected workforces for construction, operation, and decommissioning. As noted in Table 4.71, the peak onsite construction phase (contractor) workforce is 425 (212 offpeak) workers, and the maximum onsite operational phase workforce is 68 workers. This analysis assumes a 24month schedule of constructionrelated activities. Decommissioning is estimated to start in 20306 and would involve a peak month onsite workforce of 340 (168 average) workers.

4.7.1.1 Population Impacts In 2019, population in the ROI was 664,125 (Reference 2). Growth projections show that the population in the ROI in 2026 would be approximately 710,778, and the population in the ROI in 2031 would be approximately 732,719 (see Table 3.72) (Reference 3). The analysis of population impacts considers the population growth potential due to the workforce requirements for construction, operational and decommissioning phases. Workforce estimates are based on 2016 data from the U.S. Census Bureau (USCB) County Business Patterns and Bureau of Labor Statistics (BLS) (Reference 4, Reference 5), the latest year for which this information is available.

As shown in Table 3.75, in 2019 the total ROI labor force was 331,121 (Reference 6). Table 4.71 shows the estimated number of construction workers for the major labor categories in the ROI was 24,238 in 2016. As a conservative measure, Table 4.71 delineates 20 percent of the construction workforce as labor available to Kairos, for an available labor pool of 4,848 workforce (Reference 5). These estimates show that substantially all of the peak requirement (425 construction workers) are present within the ROI labor. There are no estimated labor force deficiencies by occupation. Thus, the estimated ROI labor force in the construction trades is demonstrated to be abundant relative to construction workforce requirements, which greatly reduces the potential for large numbers of trade workers to relocate in the ROI. It is possible that some workforce may commute or temporarily relocate to the site from nonROI counties, but these numbers would not be significant or cause a perceptible increase in the ROIs 2019 population of 664,125 (Reference 3). Therefore, the impact of the construction of the facility on population would be SMALL.

Table 4.71 shows the estimated number of operations workers for the major labor categories in the ROI was 22,358 in 2016. As a conservative measure, Table 4.71 delineates 10 percent of the construction Kairos Power Hermes Reactor 441 Revision 0

Environmental Report Chapter 4 - Impacts workforce as labor available to Kairos, for an available labor pool of 2,236 workforce (Reference 5).

These estimates show that substantially all of the required 68 permanent operations workers are available in the ROI. It is possible that some workforce may commute or relocate to the site from non ROI counties to pursue job opportunities, but these numbers would not be significant or cause a perceptible increase in the ROIs population of 710,778 in 2026, the year operations is expected to commence (Reference 3). Therefore, the impact of the construction of the facility on population would be SMALL.

As shown in Table 4.71, the estimated number of decommissioning workers for the major labor categories in the ROI was 7,531 in 2016. As a conservative measure, Table 4.71 delineates 20 percent of the decommissioning workforce as labor available to Kairos, for a total of 1,506 (Reference 5). These estimates show that substantially all of the required 340 decommissioning workers are available in the ROI. It is possible that some workforce may commute or relocate to the site from nonROI counties to pursue job opportunities, but these numbers would not be significant or cause a perceptible increase in the ROIs projected population of 732,719 in 2031, which is five years before the estimated decommissioning in 2036 (Reference 3). Therefore, the impact of the construction of the facility on population would be SMALL.

4.7.1.2 Housing Impacts Section 3.7.2.2 and Table 3.79 provide a summary of housing utilization sourced from 20152019 American Community Survey 5Year Estimates. This data is used to evaluate the number of housing units that may be available to accommodate housing demands resulting from construction, operations and decommissioning.

In 2019, there were 31,317 vacant housing units in the ROI (see Table 3.79) (Reference 2). The amount of housing availability within the ROI is substantially greater than the total estimated demand for housing due to construction of the facility, which is negligible because Table 4.71 shows that substantially all of the peak requirement for construction, operations and decommissioning are available in the ROI labor force. Thus, workers do not need to relocate to the ROI to support construction phase peak needs, operational workforce needs or decommissioning. There is clearly an adequate supply of vacant housing to accommodate the requirements of new workers or families who may choose to relocate to the site for temporary or permanent housing (Reference 5).

The potential impacts on housing would be SMALL due to the large number of available vacant housing units in the ROI and the lack of demand related to the construction, operations and decommissioning workforce.

4.7.1.3 Public Services Impacts Construction of the facility requires potable water to support the needs of the construction work force.

During construction and operations, the City of Oak Ridge Public Works would supply water to the site, including potable water uses, fire protection uses, and typical construction uses (e.g., dust suppression and concrete mixing). The average per capita water usage in the United States is 82 gallons per day (gpd) per person including personal use, bathing, laundry and other household uses (Reference 7). At a conservatively assumed 41 gpd for each construction worker who is onsite for 8 to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per day, an average onsite workforce of 212 needs 8,692 gpd for potable and sanitary use. During peak usage, an estimated 426 construction workers would be onsite, and would need 17,425 gpd for potable and sanitary use. As discussed in Section 3.7.2.5, the City of Oak Ridge Public Works has excess water capacity of 46 MGD. Therefore, impacts on public water supply by the onsite construction workforce would be SMALL.

Kairos Power Hermes Reactor 442 Revision 0

Environmental Report Chapter 4 - Impacts perceptible change in school enrollment. Therefore, the level of impact to the local public education system would be SMALL.

4.7.1.5 Tax Revenue Related Impacts Tax revenues associated with the construction, operation, and decommissioning of the facility include payroll taxes on wages and salaries of the construction and operations work forces, sales and use taxes on purchases made by Kairos Power and the construction, operations and decommissioning workforces, and property taxes on owned real property and improvements. Increased tax collections are a benefit to the state, county, and municipallevel jurisdictions as well as school districts.

4.7.1.6 Personal and Corporate Income Taxes Workforce payroll taxes (federal and state) are generated by construction, operations and decommissioning activities and purchases as well as taxes generated by workforce expenditures. State tax payments are distributed throughout the ROI and extend beyond the ROI, based on the expectation that some construction, operations and decommissioning employees reside outside of the ROI. The relocation of workers to the ROI and surrounding counties, including some expected to relocate to Tennessee from other states, results in an increase in payroll taxes paid to Tennessee.

4.7.1.7 Sales Taxes Workers commuting to the site from within and outside of the ROI contribute sales tax revenues to the State of Tennessee and to Roane County and any other counties where they live. The vast majority of sales tax revenues from the ROI are collected by the State, as Roane sales tax rate is very low. But the ROI does experience an increase in the amount of sales taxes collected, reflecting the concentration of relocated workers. Sales tax revenues also result from direct purchases by Kairos Power for materials, equipment and services supporting the construction project, long term operations, and decommissioning. The distribution of these tax revenues is determined by the business locations of the material and service providers and likely reflects a broad area including the ROI and beyond to multiple states. The amount of sales taxes collected over a potential 410year licensed operating period that are attributable to the facility is significant but is relatively minor when compared to the total amount of taxes collected in the ROI.

4.7.1.8 Property Taxes The facility would be located in Roane County. As such, property taxes are paid to Roane County. These jurisdictions all provide public services that benefit Kairos Powers business and employees.

4.7.1.9 Summary of Tax Impacts Overall tax revenues generated by construction, operation and decommissioning of the facility would be significant in absolute dollars across the lifetime of the facility. However, the overall tax revenues are relatively small in comparison to the established tax base of Roane County. The maximum increase in property tax revenues after expiration of the tax increment financing agreement is expected to be substantially less than 10 percent of the total tax revenue at the city and county levels. Therefore, total tax revenues from Kairos Power would result in SMALL positive impacts at the community level.

4.7.1.10 Other Socioeconomics Related Impacts Socioeconomics related impacts in addition to those specifically described above include the potential for supportive business expansion and associated land use changes in Roane County as a result of the investments from Kairos Power. Land use changes due to housing needs are not expected due to the large number of existing vacant housing units. Potential land use changes include those to provide for Kairos Power Hermes Reactor 444 Revision 0

Environmental Report Chapter 4 - Impacts 4.8.2.1 Layout and Location of Radioactive Material Figure 2.23 depicts the physical layout of the site indicating site features, structures, and designated areas. Radioactive materials would be within the Reactor Building and the Auxiliary Systems Building with the high radiation materials limited to the Reactor Building. The Reactor Building would contain spent fuel storage facilities with a capacity sufficient for 410 years of reactor operation. Access to the Reactor Building and the Auxiliary Systems Building would be strictly controlled and personnel entering these buildings would be participants in the occupational dose monitoring program.

4.8.2.2 Characteristics of Radiation Sources and Expected Radioactive Effluents 4.8.2.2.1 Gaseous Sources of Radiation Gaseous radioactive effluents would be discharged primarily through the Reactor Building exhaust system. However, as stated in Subsection 2.6.1.3, there is no anticipated need for a gaseous radioactive waste system. Discharges from the Reactor Building exhaust system would pass through a HEPA filter and would be monitored prior to release. Tritium is expected to be the dominant routine gaseous radionuclide. No significant gaseous radioactive effluents are expected to be discharged through the spent fuel cooling system (SFCS), the DHRS, or the PHRS. All releases would be within the limits of 10 CFR 20 with consideration of the guidance provided in Regulatory Guide 4.20; therefore, the impacts from gaseous sources of radiation would be SMALL.

4.8.2.2.2 Liquid Sources of Radiation The major liquid sources of radiation during operations would include the Flibe reactor coolant and the liquid nitrate salt intermediate coolant. However, when these materials have reached the end of their useful life, they are allowed to cool and solidify. Therefore, they would be managed as solid lowlevel radioactive waste (LLRW) during operations and decommissioning. Shielding materials, such as thick concrete walls, would be used to shield staff from large radiation exposures. Where necessary, piping used to circulate radioactive liquids would also be shielded to reduce radiation exposure rates.

Exposures to these materials would be controlled to limit occupational doses with below regulatory limits provided in 10 CFR 20, Subpart C, Occupational Dose Limits. There would be small volumes of liquid wastes containing primarily tritium. These wastes would only be disposed of within the limits of 10 CFR 20 Table 3 (limits for releases to sewers); therefore, the impacts from liquid sources of radiation would be SMALL.

4.8.2.2.3 Fixed Sources of Radiation During operations, solid sources of radiation that contribute to the direct dose would include fresh, circulating, and spent nuclear fuel, radioactive solid Flibe and nitrate salts, and other LLRWs, such as used moderator pebbles. During decommissioning, sources of radiation would also include the Hermes reactor and activated reactor system components and structural materials surrounding the reactor.

These sources would be within the Reactor Building until they are removed for routine waste shipments or as part of facility decommissioning. Shielding materials, such as thick concrete walls, would be used to shield staff from large radiation exposures and control radiation doses to below the occupational limits provided in 10 CFR 20, Subpart C; therefore, the impacts from solid sources of radiation would be SMALL.

4.8.2.3 Baseline Radiation Levels Background radiation levels and radiation levels in the vicinity of the site is discussed in Section 3.8. The site was once home the DOEs K31 and K33 gaseous diffusion plants and supporting facilities. Prior to transferring the properties for industrial development, the DOE conducted environmental baseline Kairos Power Hermes Reactor 454 Revision 0

Environmental Report Chapter 4 - Impacts Systems designed to support the safe and efficient management of these waste streams are described in Section 2.6. These waste systems would be operated in accordance with written procedures such that the final waste form would be acceptable for transportation in U.S. Department of Transportation (DOT) and/or NRC certified shipping containers. The quantities of radioactive wastes are also discussed in Section 2.6. There would be no onsite disposal of radioactive wastes during operations.

Each Hermes TRISO fuel pebble is estimated at 6 grams of uranium. At 35 MWth and 6 percent fissions per initial (heavy) metal atom (FIMA), an estimated 38,800 pebbles, or approximately 233 kilograms of uranium, will be consumed by the Hermes Reactor each year. Since the life of the Hermes Reactor is estimated to be 410 years, a total of 388,000155,200 pebbles, or approximately 2,330931 kilograms of uranium (2.330.93 metric tons of uranium [MTU] over 410 years), would be consumed (this is a conservative estimate that assumes Hermes operates at full power). In contrast, the amount of spent fuel discharged from a typical light water reactor operating at low burnups is about 20 MTU per year.

Reprocessing is currently unlikely in the U.S., and an open fuel cycle is anticipated. Used TRISO fuel is assumed to be stored onsite until ultimate disposal. Management of used nuclear fuel is addressed in 10 CFR 51.23 and the associated NUREG-2157, Generic Environmental Impact Statement for Continued Storage of Spent Nuclear Fuel (Reference 1). NUREG-2157 concluded that the impact for atreactor storage for each resource most of the resource areas would be small for shortterm, longterm, and indefinite storage. NUREG2157 did not address nonLWRs; to provide additional guidance to nonLWR license applications, the NRC, through Pacific Northwest National Laboratory, prepared NonLRW Reactor Fuel Environmental Data (PNNL29367) (Reference 2). Given degradation rates for storage systems associated with continued storage of TRISO fuel would not be significantly different than those considered for LWR storage systems, the environmental impacts for continued storage of LWRs described in NUREG-2157 are considered to bound any impacts of the Hermes fuel storage.

Furthermore, the anticipated low mass of spent fuel generated during Hermes operations, approximately 0.932.33 MTU over 410 years, would be significantly lower than the 20 MTU per year generated from the power reactor evaluated in NUREG-2157.

Based on the quantities of waste, systems designed to manage radioactive waste streams, and waste management, impacts from all types of waste generated during operations, including impacts on the capacity of waste management facilities, would be SMALL. Impacts from waste transportation are discussed in Section 4.10.

4.9.1.3 Decommissioning Prior to decommissioning the facility, Kairos Power would provide the NRC with a license termination plan (LTP) as described in NUREG 1757, Consolidated Decommissioning Guidance, Volumes 1 through 4.

The LTP is defined in NUREG 1757 as a detailed description of the activities a reactor licensee intends to use to assess the radiological status of its facility, to remove radioactivity attributable to licensed operations at its facility to levels that permit release of the site in accordance with NRCs regulations and termination of the license, and to demonstrate that the facility meets NRCs requirements for release.

An LTP consists of several interrelated components including: (1) a site characterization; (2) identification of remaining dismantlement activities; (3) plans for site remediation; (4) detailed plans for the final radiation survey; (5) a description of the end use of the facility, if restricted; (6) an updated site specific estimate of remaining decommissioning costs; and (7) a supplement to the environmental report, pursuant to 10 CFR 51.33, describing any new information or significant environmental change associated with the licensees proposed termination activities (see 10 CFR 50.82).

Kairos Power Hermes Reactor 494 Revision 0

Environmental Report Chapter 4 - Impacts other sections of this ER and the direct and indirect impacts from the constructionrelated traffic would be SMALL.

4.10.2 Impacts from Operation During the operation period, which includes startup activities, the facility would receive shipments of new nuclear fuel and coolant salts. When shipped to the site, the coolant salts would be nonradioactive; however, both the primary salt coolant Flibe and the intermediate (for heat transfer) nitrate salt coolant would become radioactive. There is sufficient storage capacity onsite for storage of the radioactive Flibe wastes, which would be allowed to cool, solidify, and likely held until decommissioning. As such, transportation of Flibe waste is described in Section 4.10.3. If Flibe wastes were shipped prior to decommissioning, impacts would be bound by those described in Section 4.10.2.3. Similarly, there would be sufficient onsite storage capacity for spent TRISO fuel and spent fuel transportation is also discussed in Section 4.10.3.

The following sections describe the impacts from transportation of materials to and from the facility during operations. Collectively, these impacts would be SMALL.

4.10.2.1 Transportation of Unirradiated Fuel In the United States, lowenriched nuclear fuel for commercial lightwater nuclear power plants is manufactured at either one of three facilities located in South Carolina, North Carolina, and Richland, Washington. A decision on the sourcing of fuel has not been made at this time. Fuel may be provided from either existing manufacturers or manufactured by Kairos Power at a nearby facility. For evaluation purposes it is assumed new TRISO fuel would be shipped by truck from Richland, WA. Richland, WA is the location of the furthest nuclear fuel manufacturer in the U.S. from the Kairos site.

Before startup, the facility would receive an initial shipment of fuel and then periodic shipments thereafter of fuel over the reactors estimated 410year licensed operating life. The fuel loading for each 4.0 centimeterdiameter fuel pebble is estimated at 6 grams of uranium (6gU/pebble). For Hermes, at 35 MWth and 6 percent fissions per initial (heavy) metal atom (FIMA), 38,800 pebbles will be consumed by the Hermes Reactor each year. Since the life of the Hermes Reactor is estimated to be 410 years, a total of 388,000155,200 pebbles would be consumed.

Fresh fuel would likely be shipped from the manufacturer in appropriately certified containers such as VersaPac (VP) containers manufactured by DAHER Group, Transport Logistics International, Inc.

(Reference 2). There are two VP sizes available which are certified by the DOT and configured for shipment of uranium oxides, uranium metal, uranyl nitrate crystals, and other uranium compounds such as TRISO fuel, which is specifically mentioned in the certification (Reference 3). The VP110 is a 110 gallon drumlike package and the VP55 is a smaller 55gallon drumlike package. Both packages meet the specifications provided in 49 CFR 173.417 for fissile material package. If the VP55 is used, each would contain approximately 350 fuel pebbles (Reference 2). The VP55 has an outer diameter for approximately 23.2 inches and a height of 34.8 inches and has maximum gross weight limit of 750 pounds (Reference 3).

Fuel would be transported to the facility either periodically or once per year given the relatively small quantity involved. Approximately 111 containers of new fuel would be shipped each year consisting of 350 fuel pebbles per VP55 (Reference 2). A standard highway shipping weight limit of 80,000 pounds gross weight and approximately 40,000 pounds cargo weight for a 40foot container is maintained.

Therefore, at 750 pounds per fuel container containing 350 fuel pebbles, approximately three trucks would be needed to transport a years supply of fuel when operating at 35 MWth.

Kairos Power Hermes Reactor 497 Revision 0

Environmental Report Chapter 4 - Impacts Unlike a conventional reactor which places new fuel into its core upon receipt, fuel pebbles would be continually fed into the reactor as spent fuel pebbles are being removed. Therefore, once containers of new fuel are received at the reactor facility, they would be placed into the fresh fuel storage area. There is sufficient onsite storage capacity for new fuel awaiting loading into the reactor at the facility.

Unirradiated fuel would be shipped on exclusiveuse vehicles and fuel packages. Conveyances transporting unirradiated fuel packages must satisfy the radiation level restrictions in 49 CFR 173.441.

For exclusive use shipments, the dose on contact with the package would not exceed 1 rem per hour (rem/hr) for a closed transport vehicle, 0.2 rem/hr at any point on the outer surface of the vehicle, and 0.01 rem/hr at 2 meters from the outer surface of the vehicle provided the conditions in 49 CFR 173.441(b)(1) are met. However, as evaluated in Environmental Survey of Transportation of Radioactive Materials to and from Nuclear Power Plants, WASH1238, external dose rate associated with traditional unirradiated fuel shipments containing between 0.5 and 2.0 curies of uranium in fuel casks would average about 4.0E04 rem/hr at about 1 meter from the surface of the package and 5.0E05 rem/hr at about 3 meters, well below the regulatory limits (Reference 4).

Transportation dose modeling of traditional LWR fuel using RADTRAN has demonstrated that the impacts from incident free transportation and transportation accidents is SMALL (Reference 5, Reference 6, Reference 7). The U.S. Department of Defense (DOD), acting through the Strategic Capabilities Office, has analyzed the transportation of highactivity lowenriched uranium TRISO fuels in VP110 packages from Lynchburg, Virginia to Idaho using RADTRAN and also determined that the radiological risk measured as a risk of latent cancer fatality is less than 1 in 10,000 (Reference 8).

Therefore, the impacts from the transportation of TRISO new fuel to the facility would be SMALL. Given uncertainty in the specific shipping modes and routes for transporting TRISO fuel to the facility, the shorter transportation distance than evaluated by DOD, the likely avoidance of major population centers, and the significant amount of past analysis of incidentfree transportation of unirradiated nuclear fuel, a casespecific RADTRAN analysis was not performed for this Environmental Report.

4.10.2.2 Transportation of Spent Fuel Spent fuel pebbles would be stored in long cylindrical storage canisters that are compatible with conventional dry cask storage overpacks. Individual canisters are 12 inches in outer diameter and over 7 feet in height. Each container would hold approximately 1,900 to 2,100 fuel pebbles. Canisters would be stored in a water pool for 30 to 50 days for initial cooling and then transferred to an aircooled spent fuel storage bay.

Shipments of spent fuel during normal operations are not anticipated. Spent fuel would remain on site in the spent fuel storage facility which would be designed to accommodate all of the spent fuel generated during the expected 410year licensed life of the reactor. Therefore, transportation of spent fuel is addressed as a decommissioning activity in Section 4.10.3.1 of this Environmental Report.

4.10.2.3 Transportation of Radioactive Waste Routine LLRW would be transported offsite for disposal via truck. As provided in Table 2.61, radioactive waste volumes would be bounded by the estimates in WASH1238 (Reference 4) and Kairos Power would not ship more than 3,800 ft3 of Class B solid LLRW, primarily waste generated from tritium removal systems, and less than 400 ft3 of Class A lowlevel dry active waste. These volumes would result in approximately 46 truck shipments per year. While some dry active waste may be compacted in waste drums, Kairos Power would not treat any other LLRW on site prior to transportation.

Kairos Power Hermes Reactor 498 Revision 0

Environmental Report Chapter 4 - Impacts 4.10.3 Impacts from Decommissioning At the time of final reactor shutdown, the facility would initiate decommissioning and transportation of equipment, material, and waste. As noted previously, the facility would not ship spent fuel during the reactors expected 410year licensed operating life and would hold all spent fuel shipments until decommissioning. Therefore, the transportation of spent fuel is analyzed below.

4.10.3.1 Transportation of Spent Fuel While there are currently no available sites to receive spent fuel, such as would be generated from operating the Hermes reactor at the facility, it is assumed that spent fuel shipments would be transported as follows:

By truck over commercial highways To a facility not more than 2,100 miles away, which is the approximate distance from Oak Ridge, Tennessee to Beatty, Nevada (west of Yucca Mountain)

In a transportation cask that is certified by the NRC and the DOT for transportation of spent TRISO fuel Radiation doses to members of the public and workers from incidentfree transportation are bounded by the DOT conveyance dose rate limits evaluated in Section 4.10.2.5 Not more than 60 spent fuel shipments by truck in a single year (bound by the 880 MWe reference reactor in WASH1238)

Impacts from transportation accidents is not requested in Part 1 of ISG for NUREG1537. However, NRC has evaluated the risks from spent fuel transport conducted in compliance with 10 CFR Part 71 regulations, Packaging and Transportation of Radioactive Material, in NUREG2125, Spent Fuel Transportation Risk Assessment. NUREG2125 considered radiological and nonradiological risks from routine incidentfree transportation and transportation accidents. The findings and conclusions reported by the NRC are that the radiological impacts from spent fuel transportation conducted in compliance with NRC regulations are low.

In NUREG2125, the NRC provided general insights on expected changes resulting from transporting higher burnup spent LWR fuel. The NRC stated that for incidentfree transportation, there would be no effect, as the external dose rates will need to meet the same DOT requirements. The NRC also concluded that impacts to the public will be bounding for accident scenarios even considering changes in the radionuclide inventory and increases in release factors.

Therefore, the impacts from transporting spent fuel from the facility are in compliance with DOT and NRC regulations and would be SMALL.

4.10.3.2 Transportation of Radioactive Waste The environmental impacts from the decommissioning of nuclear power plants, including the impacts from the transportation of decommissioning waste, have been analyzed by the NRC as described in NUREG0586, Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities, Supplement 1, Volume 1. The NRC made the generic conclusion that for all plants, the potential transportation impacts would be SMALL, with the factor determining the magnitude of transportation impacts of decommissioning including:

Changes in waste production due to decontamination and dismantlement activities that increase the amount of waste shipped offsite Changes in transportation methods (rail, truck, or barge) related either to the increased amount to be shipped offsite or the type of material to be shipped Kairos Power Hermes Reactor 4102 Revision 0

Environmental Report Alternatives The environmental impacts associated with inwater retrofit activities, potential dredging requirements, and impingement and entrainment would be greater than using the existing municipal system.

The site has an expected limited licensed operational life of 410 years and does not support the costs associated with retrofitting the existing structure.

Per conversations with the Oak Ridge Utility Services Department, the wastewater plant receiving the flows from the industrial parks on the west end of the city is currently rated for 0.6 MGD with an average flow between 0.05 and 0.07 MGD; however, peak flows have occasionally exceeded the 0.6 MGD plant capacity. The city is currently working towards reducing inflow and infiltration coming to the plant. The city is evaluating an expansion to this plant which would double the capacity; however, no specific plans are currently in place.

Since the municipal waste system currently has sufficient capacity to service the needs of the site (0.07 MGD), it has been selected as the proposed wastewater discharge option. Wastewater discharge to Poplar Creek was considered as a potential alternative, but was eliminated from further consideration due to the following:

Existing oil water separators and discharge structures currently exist near the proposed site.

However, additional upgrades may be required to include additional permitting, water treatment, and monitoring.

The environmental impacts associated with inwater retrofit activities and added discharges to the environment would be greater than utilizing the existing municipal system.

The facilitys operational life of 410 years does not support the costs associated with retrofitting existing structures.

5.3 REASONABLE ALTERNATIVES This section describes how the site was developed, and potential alternatives to the proposed project, based on the guidance in Section 19.5 of the Final ISG Augmenting NUREG1537, Part 1 and Section 19.5 of the Final ISG Augmenting NUREG1537, Part 2. Based on the guidance in these ISG documents, this section:

Describes the process used to develop, identify, and evaluate reasonable alternatives Describes reasonable alternatives considered Identifies the alternatives that were eliminated from further evaluation Considers whether alternatives may avoid or reduce adverse effects According to the two ISG documents, reasonable alternatives may include, but are not limited to, alternative sites, alternative siting within a proposed site, modification of existing facilities, alternative technologies, and/or alternative transportation methods. The proposed project involves the demonstration and testing of new technology. Therefore, alternative technologies are not considered, and modification of an existing facility to house the proposed project is not feasible. With respect to alternative transportation methods, the proposed location of the site on a specific site within the East Tennessee Technology Park (ETTP) limits transportation options to vehicle transport using the existing road network, or rail transport using the existing onsite rail network. Based on the scope/size of components, extensive use of rail transport is not expected to be necessary, but the existing rail infrastructure would be expected to be sufficient without significant modification. Alternative routes, types of vehicles, carpooling of workers, or other transportationrelated features may be considered as mitigation measures, but do not merit full analysis as alternatives. Similarly, the proposed project has been specifically sited within the former K33 site on the ETTP to minimize potential impacts. The Kairos Power Hermes Reactor 52 Revision 0

Environmental Report Alternatives Noise from construction and operational activities, including lighting, would result in some temporary and some permanent displacement of wildlife. Some temporarily displaced wildlife species would return to any remaining suitable habitat.

During operation, there would be the potential for birds to collide with buildings and stacks.

However, collisions are unlikely, and the impact is expected to be minor.

5.5.1.1.5 Historical and Cultural Resources Facility construction has the potential to impact archeological sites previously identified at the site.

An Archaeological Monitoring and Discovery Plan would be developed to minimize these impacts.

5.5.1.1.6 Socioeconomics Facility construction would result in a temporary increase in demand for housing, public education resources, police, fire, medical and social services, and parks and recreation facilities.

Facility operation would result in a minor increase in demand for housing, public education resources, police, fire, medical and social services, parks and recreation facilities, and other public services.

Facility construction would result in a temporary increase in local traffic due to construction workforce traffic in early morning and late afternoon and periodic construction vehicle traffic throughout the workday.

Facility operation would result in minor increase in local traffic due to vehicle movements associated with employees and deliveries/shipments of supplies and products.

5.5.1.1.7 Environmental Justice No environmental justice impacts would be anticipated.

5.5.1.1.8 Human Health During facility operation, the public would be exposed to minor doses of radiation due to transportation of radioactive materials to and from the site, as well as direct radiation and releases of gaseous effluents from the project. Radioactive materials would be strictly controlled, and all radiological doses would comply with regulatory limits.

5.5.1.2 Other Costs No other environmental costs, such as lost tax revenues or decreased recreational values, have been identified.

5.5.1.3 Environmental Benefits The construction phase of this project is expected to create approximately 212 onsite workers (425 at peak times) and 68 fulltime positions during the 410year operating period. Another 168 positions are expected during decommissioning. The wages earned and money spent by these workers would also stimulate the local economy.

5.5.1.3.1 Increase in Tax Payments The tax basis of unimproved land is determined by land value alone. Once buildings or other improvements are made, those improvements would be assessed, and both the land and the improvements would be taxed. The taxes for the site would increase substantially after project construction, benefitting Bonneville County.

Kairos Power Hermes Reactor 553 Revision 0