Tennessee Valley Authority; Watts Bar Nuclear Plant, Units 1 and 2, 3259-3263 [2019-01859]

Download as PDF Federal Register / Vol. 84, No. 28 / Monday, February 11, 2019 / Notices 03:45 p.m ............................................. Adjourn. Reason for Closing: The work being reviewed during closed portions of the site visit include information of a proprietary or confidential nature, including technical information; financial data, such as salaries and personal information concerning individuals associated with the project. These matters are exempt under 5 U.S.C. 552b(c), (4) and (6) of the Government in the Sunshine Act. Dated: February 6, 2019. Crystal Robinson, Committee Management Officer. [FR Doc. 2019–01868 Filed 2–8–19; 8:45 am] BILLING CODE 7555–01–P NUCLEAR REGULATORY COMMISSION [Docket Nos. 50–390 and 50–391; NRC– 2019–0046] Tennessee Valley Authority; Watts Bar Nuclear Plant, Units 1 and 2 Nuclear Regulatory Commission. ACTION: Environmental assessment and finding of no significant impact; issuance. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of amendments to licenses held by Tennessee Valley Authority (TVA, the licensee) for the operation of Watts Bar Nuclear Power Plant (WBN), Units 1 and 2. The proposed amendments would revise the WBN, Unit 2 Technical Specification (TS) 4.2.1, Fuel Assemblies, to add a limit on the number of tritium producing burnable absorber rods (TPBARs) that can be irradiated. This license amendment request also provides proposed changes to the WBN, Units 1 and 2 TSs related to the new criticality analyses performed for the spent fuel storage racks. The NRC is issuing an environmental assessment (EA) and finding of no significant impact (FONSI) associated with the proposed license amendments. SUMMARY: The EA and FONSI referenced in this document is available on February 11, 2019. ADDRESSES: Please refer to Docket ID NRC–2019–0046 when contacting the NRC about the availability of information regarding this document. You may obtain publicly-available information related to this document using any of the following methods: DATES: VerDate Sep<11>2014 18:05 Feb 08, 2019 Jkt 247001 3259 • Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC–2019–0046. Address questions about NRC Docket IDs in Regulations.gov to Krupskaya Castellon; telephone: 301–287–9221; email: Krupskaya.Castellon@nrc.gov. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may obtain publiclyavailable documents online in the ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/ adams.html. To begin the search, select ‘‘Begin Web-based ADAMS Search.’’ For problems with ADAMS, please contact the NRC’s Public Document Room (PDR) reference staff at 1–800–397–4209, 301– 415–4737, or by email to pdr.resource@ nrc.gov. The ADAMS accession number for each document referenced (if it is available in ADAMS) is provided the first time that it is mentioned in this document. In addition, for the convenience of the reader, the ADAMS accession numbers are provided in a table in the ‘‘Availability of Documents’’ section of this document. • NRC’s PDR: You may examine and purchase copies of public documents at the NRC’s PDR, Room O1–F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. John G. Lamb, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001; telephone: 301–415–3100; email: John.Lamb@nrc.gov. FOR FURTHER INFORMATION CONTACT: SUPPLEMENTARY INFORMATION: I. Introduction The NRC is considering issuance of amendments to Facility Operating License Nos. NFP–90 and NFP–96, issued to TVA for operation of the WBN, Units 1 and 2, located in Rhea County, Tennessee. In accordance with section 51.21 of title 10 of the Code of Federal Regulations (10 CFR), the NRC prepared the following EA that analyzes the environmental impacts of the proposed licensing action. Based on the results of this EA, and in accordance with 10 CFR 51.31(a), the NRC has determined not to prepare an environmental impact statement for the proposed licensing action, and is issuing a FONSI. PO 00000 Frm 00123 Fmt 4703 Sfmt 4703 II. Environmental Assessment Description of the Proposed Action The proposed action would revise the WBN, Unit 2 TS 4.2.1, Fuel Assemblies to allow up to 1,792 TPBARs to be irradiated in the reactor core. The proposed action would also revise the WBN, Units 1 and 2 TS 3.7.15, Spent Fuel Assembly Storage, to simplify the fuel storage limitations on fuel assemblies by eliminating the burnuprelated criteria; TS 3.9.9, Spent Fuel Pool Boron Concentration, to modify the minimum fuel storage pool boron concentration during refueling operations when fuel is stored in the pool; and TS 4.3, Fuel Storage, to replace the storage limitations on fuel assembly burnup and storage with a single requirement to maintain a specified boron concentration in the spent fuel pool. The proposed action would also add the WBN, Units 1 and 2 TS 3.7.18, Fuel Storage Pool Boron Concentration, to specify the minimum fuel storage pool boron concentration when fuel is stored in the pool, and TS 5.7.2.21, Spent Fuel Storage Rack Neutron Absorber Monitoring Program, to monitor the condition of the neutron absorber material used in the spent fuel pool storage racks to ensure it will continue to perform its assumed design functions. The proposed action is also described in the licensee’s application dated December 20, 2017 (ADAMS Accession No. ML17354B282), as supplemented by letters dated February 15, 2018 (ADAMS Accession No. ML18047A181), April 9, 2018 (ADAMS Accession No. ML18100A953) and October 4, 2018 (ADAMS Accession No. ML18283A107). Need for the Proposed Action The U.S. Department of Energy (DOE) and TVA are cooperating in a program to produce tritium for the National Security Stockpile by irradiating TPBARs at the WBN site. Tritium is produced when the neutrons produced by nuclear fission in the core are absorbed by the lithium target material of the TPBAR. A solid zirconium metal cladding covering the TPBAR (called a getter) captures the tritium produced. Most of the tritium is contained within the TPBAR, however, some tritium permeates through the TPBAR cladding and is released into the reactor coolant system. This proposed action is needed to support the DOE, National Nuclear Security Administration, national security stockpile needs in accordance E:\FR\FM\11FEN1.SGM 11FEN1 3260 Federal Register / Vol. 84, No. 28 / Monday, February 11, 2019 / Notices with Public Law (Pub. L.) 106–65. Section 3134 of Public Law 106–65 directs the Secretary of Energy to produce new tritium at TVA’s WBN site. By letter dated June 23, 2016 (ADAMS Accession No. ML18283A107), the NRC approved a similar amendment to irradiate 1,792 TPBARs in the WBN, Unit 1 reactor core. The EA and FONSI for that licensing action was completed June 23, 2016, and can be found in ADAMS (Accession No. ML16138A045). Environmental Impacts of the Proposed Action The proposed action consists of revising the WBN, Unit 2 TSs to allow and limit the number of TPBARs that can be irradiated in the reactor core. This license amendment request also provides proposed changes for both the WBN, Units 1 and 2 TSs related to the new criticality analyses performed for the spent fuel storage racks to allow the proper safe handling and storage of spent fuel, including TPBARs, at the WBN site. The radiological and nonradiological impacts on the environment that may result from the proposed action are summarized below. Non-Radiological Impacts The proposed changes would have no direct impacts on land use or water resources, including terrestrial and aquatic biota, as they involve no new construction or modification of plant operational systems. There would be no changes to the quality or quantity of nonradiological effluents and no need to change the plant’s National Pollutant Discharge Elimination System permit. There would be no changes in air pollutant emissions or ambient air quality from the proposed changes. In addition, there would be no noticeable effect on socioeconomic conditions in the region, no environment justice impacts, and no impacts to historic and cultural resources from the proposed TS changes. Therefore, there are no significant nonradiological environmental impacts associated with the proposed action. Radiological Impacts Radioactive Gaseous and Liquid Effluents and Solid Waste The WBN, Units 1 and 2, utilize waste treatment systems to collect, process, recycle, and dispose of gaseous and liquid effluents and solid wastes that contain radioactive material in a safe and controlled manner within NRC and U.S. Environmental Protection Agency’s radiation safety standards. Implementation of the proposed action would result in allowing the WBN, Unit VerDate Sep<11>2014 18:05 Feb 08, 2019 Jkt 247001 2, to irradiate up to 1,792 TPBARs, per cycle in the reactor core. This is the same number of TPBARs authorized by the NRC for the WBN, Unit 1 reactor core. This would also affect the quantities of radioactive material generated from WBN, Unit 2 as some tritium permeates through the TPBAR cladding and is released into the reactor coolant system. The average observed TPBAR tritium permeation rate for the WBN, Unit 1 tritium production is approximately 3 Curi per TPBAR per year (Ci/TPBAR/year), with the maximum observed permeation rate being approximately 4.8 Ci/TPBAR/ year. For the purposes of assessing the environmental impacts and regulatory compliance of this proposed action for the WBN, Unit 2 tritium production, TVA assumed a core load of 1,792 TPBARs with a permeation rate of 5.0 Ci/TPBAR/year of tritium, which is a conservative source term that bounds the observed and maximum TPBAR tritium permeation rate. While the quantity of tritium generated during plant operations will increase under the proposed action, current radioactive waste treatment systems will be able to handle that increase according to TVA. Radioactive Gaseous Effluents The WBN, Unit 2, maintains a gaseous waste management system (GWMS) that is designed to process and control the release of radioactive gaseous effluents into the environment in accordance with the requirements of 10 CFR 20.1301, Dose limits for individual members of the public, and to ensure consistency with the as low as reasonably achievable (ALARA) dose objectives set forth in appendix I to 10 CFR part 50. As stated above relative to TVA’s license amendment request, TVA assumed a core load of 1,792 TPBARs with a permeation rate of 5.0 Ci/TPBAR/ year of tritium, which is a conservative source term that bounds the observed and maximum TPBAR tritium permeation rate as seen from the WBN, Unit 1 tritium production. To determine whether the gaseous effluents would fall within the requirements of 10 CFR 20.1301, TVA calculated the sum of the ratios of each isotope concentration (C) to its corresponding gaseous Effluent Concentration Limit (ECL, as listed in 10 CFR part 20, appendix B, Table 2, Column 1). Consistent with the requirements of 10 CFR 20.1302(b)(2)(i), a C/ECL sum of less than 1.0 indicates that the annual average effluent release is within the limits of 10 CFR 20.1301. Tables 4.1–31 and 32 of the license amendment request demonstrate that PO 00000 Frm 00124 Fmt 4703 Sfmt 4703 TVA’s calculated C/ECL sums for gaseous effluent releases at the WBN, Unit 2 from an assumed core load of 1,792 TPBARs for containment purge without filtration would be 4.52×10¥1 and would be 4.01×10¥1 with continuous filtration. TVA’s calculated C/ECL sums for gaseous effluent releases for both of the WBN, Units 1 and 2 (dual operation) for containment purge without filtration would be 9.12×10¥1 and would be 8.02×10¥1 with continuous filtration. Both sets of numbers are within the maximum C/ ECL limit of 1.0 according to TVA. To determine whether the gaseous effluents are consistent with the ALARA dose objectives set forth in appendix I to 10 CFR part 50 (which are per-unit numbers) TVA calculated bounding public doses from the applicable plant effluent dose pathways with the tritium release attributable to TPBAR permeability. These doses were based on an assumed core load of 1,792 TPBARs and the methods and assumptions in the current WBN Offsite Dose Calculation Manual (ODCM), (documented in the Watts Bar Nuclear Plant 2017, Annual Radioactive Effluent Release Report (ADAMS Accession No. ML18120A138). TVA calculated that the Whole Body dose to a Maximally Exposed Individual from the WBN, Unit 2 would be 0.63 millirem (mrem) (0.0063 millisievert (mSv)), which is much less than the Whole Body dose objective in appendix I to 10 CFR part 50 of 5.00 mrem (0.05 mSv). TVA also calculated that the Organ Dose (Thyroid) to the Maximally Exposed Individual from the WBN, Unit 2 would be 8.30 mrem (0.083 mSv), which is less than the Organ dose objective in appendix I to 10 CFR part 50 of 15.00 mrem (0.15 mSv). Doses would be assumed to double (1.26 mrem or 0.0126 mSv Whole Body and 16.6 mrem or 0.166 mSv Organ Dose (Thyroid)) for dual reactor tritium production at both the WBN, Units 1 and 2, which would be within the appendix I to 10 CFR part 50 dose objective as they are per-unit numbers as stated above, and would also double according to TVA. Based on the above, the NRC staff finds that the TVA’s analyses have demonstrated that WBN, Unit 2, can be operated with the proposed maximum core loading of 1,792 TPBARs and that the current GWMS can maintain the gaseous effluents within the Effluent Concentration Limits listed in 10 CFR part 20, appendix B to meet the dose limit requirements to members of the public in 10 CFR 20.1301, as well as maintain doses to the public ALARA as per the dose objectives set forth in E:\FR\FM\11FEN1.SGM 11FEN1 Federal Register / Vol. 84, No. 28 / Monday, February 11, 2019 / Notices appendix I to 10 CFR part 50. Therefore, the NRC staff concludes that there would be no significant radiological impact from gaseous effluents under the proposed action. Radioactive Liquid Effluents The WBN, Unit 2 liquid radioactive waste system (LRWS) is used to collect and process radioactive liquid wastes to reduce radioactivity and chemical concentrations to levels acceptable for discharge to the environment according to TVA. The LRWS maintains sufficient processing capability so that liquid waste may be discharged to the environment below the regulatory limits of 10 CFR 20.1301 and consistent with the ALARA dose objectives in appendix I to 10 CFR part 50. The WBN, Units 1 and 2 share three large storage tanks in the LRWS, which includes a Tritiated Water Storage Tank with a capacity of 500,000 gallons. This storage tank supports managing large volume/high tritium concentrations in the reactor coolant system for both Units 1 and 2. These storage tanks can be used for liquid effluent holdup, dilution, and timing of releases to ensure that regulatory requirements are met. Release of radioactive liquids from the LRWS only occurs after laboratory analysis of the storage tank contents. If the activity is found to be above ODCM limits, the liquid waste streams are returned to the system for further processing by a mobile demineralizer. If the activity is found to be below the ODCM limits, the liquid waste stream is pumped to a discharge pipe where it is monitored for radiation levels and flowrate before it enters the Cooling Tower Blowdown line, where it can ultimately be discharged by permit into the Tennessee River. To determine whether the liquid effluents are within the requirements of 10 CFR 20.1301, TVA calculated the sum of the ratios of each isotope concentration (C) to its corresponding liquid Effluent Concentration Limit (ECL as listed in 10 CFR part 20, appendix B, Table 2, Column 2). Consistent with the requirements of 10 CFR 20.1302(b)(2)(i), a C/ECL sum of less than 1.0 indicates that the annual average effluent release is within the limits of 10 CFR 20.1301. Tables 4.1–28 through 30 of the license amendment request show TVA’s calculated C/ECL sums for liquid effluent releases from an assumed core load of 1,792 TPBARs. Table 4.1–28 indicates that extended effluent releases, without processing the liquid radioactive waste streams through the mobile demineralizer or allowing for sufficient dilution of the radioactive waste stream, would not VerDate Sep<11>2014 18:05 Feb 08, 2019 Jkt 247001 meet the regulatory requirements of 10 CFR 20.1301. The calculated C/ECL for the WBN, Unit 2 in this scenario is 5.23, which is greater than the maximum allowable C/ECL of 1.0. Dual operation of both the WBN, Units 1 and 2 in this scenario would yield a C/ECL of 10.5. To ensure that the effluent concentration limits of 10 CFR 20.1301 are met, Section 11.2.6.5 of the Final Safety Analysis Report states that ‘‘No untreated wastes are released unless they are below the Lower Limit of Detection.’’ Table 4.1–29 of the license amendment request demonstrates that TVA’s calculated C/ECL sum for liquid effluent releases for the WBN, Unit 2 processed through the mobile demineralizer would be 4.18×10¥1. Dual operation of both the WBN, Units 1 and 2 in this scenario would yield a C/ECL of 8.35×10¥1. Table 4.1–30 demonstrates that TVA’s calculated C/ECL for liquid effluents not processed through the mobile demineralizer, but sufficiently diluted before release, would be 4.23×10¥1. Dual operation of both the WBN, Units 1 and 2 in this scenario would yield a C/ECL of 8.47×10¥1. All numbers for both scenarios are within the maximum C/ECL limit of 1.0. To determine whether the liquid effluents are consistent with the ALARA dose objectives set forth in appendix I to 10 CFR part 50, TVA calculated bounding public doses from the applicable plant effluent dose pathways with the tritium release attributable to TPBAR permeability. These doses were based on an assumed core load of 1,792 TPBARs and the methods and assumptions in the current ODCM. TVA calculated that the Whole Body dose to a Maximally Exposed Individual from liquid effluents would be 0.37 mrem (0.0037 mSv), which is much less than the Whole Body dose objective in appendix I to 10 CFR part 50 of 3.00 mrem (0.03 mSv). TVA also calculated that the Organ Dose (Liver) to the Maximally Exposed Individual from liquid effluents would be 0.49 mrem (0.0049 mSv), which is much less than the Organ dose objective in appendix I to 10 CFR part 50 of 10.00 mrem (0.15 mSv). Doses would be assumed to double (0.74 mrem or 0.0074 mSv Whole Body and 0.98 mrem or 0.098 mSv Organ Dose (Liver)) for dual reactor tritium production at both the WBN, Units 1 and 2, which would be within the appendix I to 10 CFR part 50 dose objective as they are per-unit numbers as stated above, and would also double according to TVA. The NRC staff finds that TVA has demonstrated that WBN, Unit 2, can be PO 00000 Frm 00125 Fmt 4703 Sfmt 4703 3261 operated with the proposed maximum core loading of 1,792 TPBARs, and that with processing of the liquid radioactive waste streams through the demineralizer, or allowing for proper dilution of the liquid radioactive waste streams, the current LRWS can maintain the liquid effluents within the Effluent Concentration Limits listed in 10 CFR part 20, appendix B. Specifically, doses from liquid effluents would meet the requirements regarding members of the public in 10 CFR 20.1301 as well as maintain the public ALARA dose objectives set forth in appendix I to 10 CFR part 50. Therefore, the NRC staff concludes that there would be no significant radiological impact from gaseous effluents under the proposed action. Solid Radioactive Wastes Solid radioactive wastes generated by nuclear power plant operations at WBN, Units 1 and 2, are processed, packaged, and stored until they are shipped offsite to a vendor for further processing or to a licensed facility for permanent disposal, or both. The storage areas have restricted access and shielding to reduce radiation rates to plant workers. Solid radioactive wastes are packaged and transported in compliance with NRC’s regulations in 10 CFR parts 61, Licensing Requirements for Land Disposal of Radioactive Waste, and 71, Packaging and Transportation of Radioactive Material, and the U.S. Department of Transportation regulations in 49 CFR parts 170 through 179; and to maintain the dose limits of 10 CFR 20.1201, 10 CFR 20.1301, and design objectives in appendix I to 10 CFR part 50. Implementation of the proposed action would increase the activity and volume of solid radioactive waste due to the irradiation of the TPBAR base plates and thimble plugs, which remain after TPBAR consolidation activities. For the consolidation process, plant operators will remove the irradiated TPBAR assemblies from the spent fuel assemblies, disassemble all the irradiated TPBARs for consolidation, and place them into consolidation canisters. Operators will return the loaded consolidation canisters to the spent fuel racks, where they will remain until removed from the site. Offsite shipment and ultimate disposal would be conducted in accordance with agreements between TVA and DOE. The disposal volume of the TPBAR base plates and thimble plugs is estimated to be 33.3 cubic feet (0.942 cubic meters) per year. This additional volume represents a slight increase in the WBN, Units 1 and 2, annual estimated solid E:\FR\FM\11FEN1.SGM 11FEN1 3262 Federal Register / Vol. 84, No. 28 / Monday, February 11, 2019 / Notices waste generation from 65,640 cubic feet (1859 cubic meters) per year to 65,706 cubic feet (1861 cubic meters) per year. This projected increase in volume can be handled by the existing equipment and plant procedures that control radioactive solid waste handling without modification. The estimated increase in activity inventory attributable to the handling of the TPBAR base plates and thimble plugs ranges from approximately 3,600 Ci/yr (1.33×1014 Bq/yr) to 11,060 Ci/yr (4.09×1014 Bq/yr). While there would be increased activity associated with implementation of the proposed action, the existing equipment and plant procedures that control radioactive solid waste handling will continue to be used to maintain plant personnel exposures within the dose limits of 10 CFR 20.1201, 10 CFR 20.1301, and design objectives in 10 CFR part 50, appendix I. Based on the above, the NRC staff concludes that there would be no significant radiological impact from solid radioactive waste management under the proposed action. Spent Fuel Generation, Storage, and Handling The number of spent fuel bundles would increase by approximately four per cycle with implementation of the proposed action. WBN, Units 1 and 2, currently store spent fuel in spent fuel pools on site and in an independent spent fuel storage installation. There will be adequate spent fuel storage available on site, therefore, the NRC staff concludes that there would be no significant radiological impact from spent fuel generation and storage under the proposed action. As stated above in Section II of this document, the proposed action would also revise the WBN, Units 1 and 2 TS 3.7.15, Spent Fuel Assembly Storage, to simplify the fuel storage limitations on fuel assemblies by eliminating the burnup-related criteria; TS 3.9.9, Spent Fuel Pool Boron Concentration, to modify the minimum fuel storage pool boron concentration during refueling operations when fuel is stored in the pool; and TS 4.3, Fuel Storage, to replace the storage limitations on fuel assembly burnup and storage with a single requirement to maintain a specified boron concentration in the spent fuel pool. The proposed action would also add the WBN, Units 1 and 2 TS 3.7.18, Fuel Storage Pool Boron Concentration, to specify the minimum fuel storage pool boron concentration when fuel is stored in the pool, and TS 5.7.2.21, Spent Fuel Storage Rack Neutron Absorber Monitoring Program, to monitor the condition of the neutron VerDate Sep<11>2014 18:05 Feb 08, 2019 Jkt 247001 absorber material used in the spent fuel pool storage racks to ensure it will continue to perform its assumed design functions. These proposed changes would have no direct radiological environmental impacts. There would be no change to the types or amounts of radioactive effluents that may be released and, therefore, no change in occupational or public radiation exposure from the proposed changes. No changes would be made to plant buildings or the site property from these proposed changes. Therefore, there would be no significant radiological environmental impacts associated with these TS changes. Occupational Radiation Doses At WBN, Units 1 and 2, TVA maintains a radiation protection program to monitor radiation levels throughout the nuclear power plant to establish appropriate work controls, training, temporary shielding, and protective equipment requirements so that worker doses will remain within the dose limits of 10 CFR part 20, subpart C, Occupational Dose Limits. Implementation of the proposed action would affect the quantities of radioactive material generated during plant operations since some tritium permeates through the TPBAR cladding and is released into the reactor coolant system, as previously described. Separate from the environmental review for this EA, the NRC staff is evaluating the licensee’s technical and safety analyses provided in TVA’s license amendment request to ensure the licensee continues to meet NRC regulatory requirements for occupational dose. The results of the NRC staff’s safety review and conclusion will be documented in a safety evaluation that will be made publicly available following issuance of the EA. If the NRC staff concludes in the safety evaluation that the requested number of 1,792 TPBARs that can be irradiated, per cycle, in the WBN, Unit 2 core and the proposed changes related to the new criticality analyses performed for the spent fuel storage racks comply with NRC regulations for occupational dose, then granting the proposed license amendments will not have a significant radiological impact to workers. Design-Basis Accidents Design-basis accidents are evaluated by both TVA and the NRC staff to ensure that WBN, Units 1 and 2, can withstand the spectrum of postulated accidents without undue hazard to public health and safety and ensure the protection of the environment. PO 00000 Frm 00126 Fmt 4703 Sfmt 4703 The NRC staff is evaluating the licensee’s technical and safety analyses provided in the proposed license amendments to ensure the licensee continues to meet the NRC regulatory requirements for safe operation. The results of the NRC staff’s safety review and conclusion will be documented in a safety evaluation that will be made publicly available following issuance of the EA. If the NRC staff concludes in the safety evaluation that 1,792 TPBARs irradiated, per cycle, in the WBN, Unit 2 core and the proposed changes related to the new criticality analyses performed for the spent fuel storage racks comply with NRC regulations, and there is reasonable assurance that public health and safety will not be endangered, then granting the proposed license amendments will not have a significant environmental impact. Radiological Impacts Summary Based on the radiological evaluations presented in this EA, with the exception of the impacts associated with occupational dose and design-basis accidents, which the NRC staff are evaluating separately, implementation of the proposed action would not result in any significant radiological impacts. If the NRC staff concludes in the safety evaluation that 1,792 TPBARs irradiated, per cycle, in the WBN, Unit 2 core and the proposed changes related to the new criticality analyses performed for the spent fuel storage racks comply with NRC regulations, and there is reasonable assurance that public health and safety will not be endangered, then granting the proposed license amendments will not have a significant radiological impact to workers or the environment. Environmental Impacts of the Alternatives to the Proposed Action As an alternative to the proposed action, the NRC staff considered denial of the license amendment request (i.e., the no-action alternative). Denial of the license amendment request would result in no change in current environmental impacts. Accordingly, the environmental impacts of the proposed action and the no-action alternative are similar. Alternative Use of Resources There are no unresolved conflicts concerning alternative uses of available resources under the proposed action. Agencies and Persons Consulted An official of the State of the Tennessee was notified about the environmental assessment and the state official had no comments. E:\FR\FM\11FEN1.SGM 11FEN1 3263 Federal Register / Vol. 84, No. 28 / Monday, February 11, 2019 / Notices III. Finding of No Significant Impact The licensee has requested license amendments pursuant to 10 CFR 50.90, Application for amendment of license, construction permit, or early site permit, to revise the WBN, Unit 2 TSs to allow up to 1,792 TPBARs to be irradiated in the reactor core. The license amendments also provide proposed changes for both the WBN, Units 1 and 2 TSs related to the new criticality analyses performed for the spent fuel storage racks to allow the proper safe handling and storage of spent fuel, including TPBARs, at the WBN site. The NRC is considering issuing the requested amendments. The proposed action would not significantly affect plant safety, would not have a significant adverse effect on the probability of an accident occurring, and would not have any significant radiological or nonradiological impacts. The reason the environment would not be significantly affected is because while the proposed changes would result in increased radiological plant effluents and offsite doses, those numbers would still be within the regulatory limits as stated in 10 CFR part 20 and design objectives in appendix I to 10 CFR part 50. This FONSI incorporates by reference the EA in Section II of this notice. Therefore, the NRC concludes that the proposed action will not have a significant effect on the quality of the human environment. Accordingly, the NRC has determined there is no need to prepare an environmental impact statement for the proposed action. Previous considerations regarding the environmental impacts of operating Watts Bar, Units 1 and 2, in accordance with their operating licenses, are described in NUREG–0498, Final Environmental Statement Related to Operation of Watts Bar Nuclear Plant, Units 1 and 2, dated December 1978, and NUREG–0498, Supplement 1, dated April 1995, and NUREG–0498, Supplement 2, Final Environmental Statement Related to Operation of Watts Bar Nuclear Plant, Unit 2, dated May 2013 (ADAMS Package Accession Nos. ML082540803, ML081430592, and ML13144A092). This FONSI and other related environmental documents may be examined, and/or copied for a fee, at the NRC’s PDR, located at One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. Publicly-available records are also accessible online in the ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/ adams.html. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS should contact the NRC’s PDR reference staff by telephone at 1–800–397–4209 or 301–415–4737, or by email to pdr.resource@nrc.gov. IV. Availability of Documents The documents identified in the following table are available to interested persons through ADAMS. Document ADAMS accession No. NUREG–0498—Final Environmental Statement Related to Operation of Watts Bar Nuclear Plant, Units 1 and 2, dated December 1978. NUREG–0498—Final Environmental Statement Related to the Operation of Watts Bar Nuclear Plant, Units 1 and 2, Supplement 1, dated April 1995. NUREG–0498—Final Environmental Statement Related to the Operation of Watts Bar Nuclear Plant, Unit 2, Supplement 2, dated May 2013. Watts Bar Nuclear Plant, Unit 1: Environmental Assessment and Finding of No Significant Impact Related to License Amendment Request to Revise Technical Specification 4.2.1, Fuel Assemblies, dated June 23, 2016. TVA letter to NRC, Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN–TS–17–028), dated December 20, 2017. TVA letter to NRC, Correction to Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN–TS–17–028), dated April 9, 2018. TVA letter to NRC, Response to Request for Additional Information Regarding Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN– TS–17–028) (EPID L–2017–LLA–0427), dated October 4, 2018. WBN Offsite Dose Calculation Manual, as documented in the Watts Bar Nuclear Plant Annual Radioactive Effluent Release Report—2017, dated April 30, 2018. ML082540803 Dated at Rockville, Maryland, this 6th day of February 2019. For the Nuclear Regulatory Commission. John G. Lamb, Senior Project Manager, Special Projects and Process Branch, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. SECURITIES AND EXCHANGE COMMISSION [FR Doc. 2019–01859 Filed 2–8–19; 8:45 am] AGENCY: BILLING CODE 7590–01–P [Investment Company Act Release No. 33368; 812–14965] Yleana Advisors, LLC and Yleana Trust February 6, 2019. Securities and Exchange Commission (‘‘Commission’’). ACTION: Notice. Notice of an application for an order under section 6(c) of the Investment Company Act of 1940 (the ‘‘Act’’) for an exemption from sections 2(a)(32), 5(a)(1), 22(d), and 22(e) of the Act and rule 22c–1 under the Act, under sections 6(c) and 17(b) of the Act for an exemption from sections 17(a)(1) and 17(a)(2) of the Act, and under section VerDate Sep<11>2014 18:05 Feb 08, 2019 Jkt 247001 PO 00000 Frm 00127 Fmt 4703 Sfmt 4703 ML081430592 ML13144A092 ML16138A045 ML17354B282 ML18100A953 ML18283A107 ML18120A138 12(d)(1)(J) for an exemption from sections 12(d)(1)(A) and 12(d)(1)(B) of the Act. The requested order would permit (a) index-based series of certain open-end management investment companies (‘‘Funds’’) to issue shares redeemable in large aggregations (‘‘Creation Units’’); (b) secondary market transactions in Fund shares to occur at negotiated market prices rather than at net asset value (‘‘NAV’’); (c) certain Funds to pay redemption proceeds, under certain circumstances, more than seven days after the tender of shares for redemption; (d) certain affiliated persons of a Fund to deposit securities into, and receive securities from, the Fund in connection with the purchase and redemption of Creation Units; (e) certain registered management investment companies and unit E:\FR\FM\11FEN1.SGM 11FEN1

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[Federal Register Volume 84, Number 28 (Monday, February 11, 2019)]
[Notices]
[Pages 3259-3263]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-01859]


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NUCLEAR REGULATORY COMMISSION

[Docket Nos. 50-390 and 50-391; NRC-2019-0046]


Tennessee Valley Authority; Watts Bar Nuclear Plant, Units 1 and 
2

AGENCY: Nuclear Regulatory Commission.

ACTION: Environmental assessment and finding of no significant impact; 
issuance.

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is considering 
issuance of amendments to licenses held by Tennessee Valley Authority 
(TVA, the licensee) for the operation of Watts Bar Nuclear Power Plant 
(WBN), Units 1 and 2. The proposed amendments would revise the WBN, 
Unit 2 Technical Specification (TS) 4.2.1, Fuel Assemblies, to add a 
limit on the number of tritium producing burnable absorber rods 
(TPBARs) that can be irradiated. This license amendment request also 
provides proposed changes to the WBN, Units 1 and 2 TSs related to the 
new criticality analyses performed for the spent fuel storage racks. 
The NRC is issuing an environmental assessment (EA) and finding of no 
significant impact (FONSI) associated with the proposed license 
amendments.

DATES: The EA and FONSI referenced in this document is available on 
February 11, 2019.

ADDRESSES: Please refer to Docket ID NRC-2019-0046 when contacting the 
NRC about the availability of information regarding this document. You 
may obtain publicly-available information related to this document 
using any of the following methods:
     Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2019-0046. Address 
questions about NRC Docket IDs in Regulations.gov to Krupskaya 
Castellon; telephone: 301-287-9221; email: Krupskaya.Castellon@nrc.gov. 
For technical questions, contact the individual listed in the FOR 
FURTHER INFORMATION CONTACT section of this document.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly-available documents online in the 
ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``Begin Web-based ADAMS 
Search.'' For problems with ADAMS, please contact the NRC's Public 
Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or 
by email to pdr.resource@nrc.gov. The ADAMS accession number for each 
document referenced (if it is available in ADAMS) is provided the first 
time that it is mentioned in this document. In addition, for the 
convenience of the reader, the ADAMS accession numbers are provided in 
a table in the ``Availability of Documents'' section of this document.
     NRC's PDR: You may examine and purchase copies of public 
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 
Rockville Pike, Rockville, Maryland 20852.

FOR FURTHER INFORMATION CONTACT: John G. Lamb, Office of Nuclear 
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001; telephone: 301-415-3100; email: John.Lamb@nrc.gov.

SUPPLEMENTARY INFORMATION:

I. Introduction

    The NRC is considering issuance of amendments to Facility Operating 
License Nos. NFP-90 and NFP-96, issued to TVA for operation of the WBN, 
Units 1 and 2, located in Rhea County, Tennessee.
    In accordance with section 51.21 of title 10 of the Code of Federal 
Regulations (10 CFR), the NRC prepared the following EA that analyzes 
the environmental impacts of the proposed licensing action. Based on 
the results of this EA, and in accordance with 10 CFR 51.31(a), the NRC 
has determined not to prepare an environmental impact statement for the 
proposed licensing action, and is issuing a FONSI.

II. Environmental Assessment

Description of the Proposed Action

    The proposed action would revise the WBN, Unit 2 TS 4.2.1, Fuel 
Assemblies to allow up to 1,792 TPBARs to be irradiated in the reactor 
core. The proposed action would also revise the WBN, Units 1 and 2 TS 
3.7.15, Spent Fuel Assembly Storage, to simplify the fuel storage 
limitations on fuel assemblies by eliminating the burnup-related 
criteria; TS 3.9.9, Spent Fuel Pool Boron Concentration, to modify the 
minimum fuel storage pool boron concentration during refueling 
operations when fuel is stored in the pool; and TS 4.3, Fuel Storage, 
to replace the storage limitations on fuel assembly burnup and storage 
with a single requirement to maintain a specified boron concentration 
in the spent fuel pool. The proposed action would also add the WBN, 
Units 1 and 2 TS 3.7.18, Fuel Storage Pool Boron Concentration, to 
specify the minimum fuel storage pool boron concentration when fuel is 
stored in the pool, and TS 5.7.2.21, Spent Fuel Storage Rack Neutron 
Absorber Monitoring Program, to monitor the condition of the neutron 
absorber material used in the spent fuel pool storage racks to ensure 
it will continue to perform its assumed design functions.
    The proposed action is also described in the licensee's application 
dated December 20, 2017 (ADAMS Accession No. ML17354B282), as 
supplemented by letters dated February 15, 2018 (ADAMS Accession No. 
ML18047A181), April 9, 2018 (ADAMS Accession No. ML18100A953) and 
October 4, 2018 (ADAMS Accession No. ML18283A107).

Need for the Proposed Action

    The U.S. Department of Energy (DOE) and TVA are cooperating in a 
program to produce tritium for the National Security Stockpile by 
irradiating TPBARs at the WBN site. Tritium is produced when the 
neutrons produced by nuclear fission in the core are absorbed by the 
lithium target material of the TPBAR. A solid zirconium metal cladding 
covering the TPBAR (called a getter) captures the tritium produced. 
Most of the tritium is contained within the TPBAR, however, some 
tritium permeates through the TPBAR cladding and is released into the 
reactor coolant system.
    This proposed action is needed to support the DOE, National Nuclear 
Security Administration, national security stockpile needs in 
accordance

[[Page 3260]]

with Public Law (Pub. L.) 106-65. Section 3134 of Public Law 106-65 
directs the Secretary of Energy to produce new tritium at TVA's WBN 
site. By letter dated June 23, 2016 (ADAMS Accession No. ML18283A107), 
the NRC approved a similar amendment to irradiate 1,792 TPBARs in the 
WBN, Unit 1 reactor core. The EA and FONSI for that licensing action 
was completed June 23, 2016, and can be found in ADAMS (Accession No. 
ML16138A045).

Environmental Impacts of the Proposed Action

    The proposed action consists of revising the WBN, Unit 2 TSs to 
allow and limit the number of TPBARs that can be irradiated in the 
reactor core. This license amendment request also provides proposed 
changes for both the WBN, Units 1 and 2 TSs related to the new 
criticality analyses performed for the spent fuel storage racks to 
allow the proper safe handling and storage of spent fuel, including 
TPBARs, at the WBN site.
    The radiological and nonradiological impacts on the environment 
that may result from the proposed action are summarized below.
Non-Radiological Impacts
    The proposed changes would have no direct impacts on land use or 
water resources, including terrestrial and aquatic biota, as they 
involve no new construction or modification of plant operational 
systems. There would be no changes to the quality or quantity of 
nonradiological effluents and no need to change the plant's National 
Pollutant Discharge Elimination System permit. There would be no 
changes in air pollutant emissions or ambient air quality from the 
proposed changes. In addition, there would be no noticeable effect on 
socioeconomic conditions in the region, no environment justice impacts, 
and no impacts to historic and cultural resources from the proposed TS 
changes. Therefore, there are no significant nonradiological 
environmental impacts associated with the proposed action.
Radiological Impacts
Radioactive Gaseous and Liquid Effluents and Solid Waste
    The WBN, Units 1 and 2, utilize waste treatment systems to collect, 
process, recycle, and dispose of gaseous and liquid effluents and solid 
wastes that contain radioactive material in a safe and controlled 
manner within NRC and U.S. Environmental Protection Agency's radiation 
safety standards. Implementation of the proposed action would result in 
allowing the WBN, Unit 2, to irradiate up to 1,792 TPBARs, per cycle in 
the reactor core. This is the same number of TPBARs authorized by the 
NRC for the WBN, Unit 1 reactor core. This would also affect the 
quantities of radioactive material generated from WBN, Unit 2 as some 
tritium permeates through the TPBAR cladding and is released into the 
reactor coolant system. The average observed TPBAR tritium permeation 
rate for the WBN, Unit 1 tritium production is approximately 3 Curi per 
TPBAR per year (Ci/TPBAR/year), with the maximum observed permeation 
rate being approximately 4.8 Ci/TPBAR/year. For the purposes of 
assessing the environmental impacts and regulatory compliance of this 
proposed action for the WBN, Unit 2 tritium production, TVA assumed a 
core load of 1,792 TPBARs with a permeation rate of 5.0 Ci/TPBAR/year 
of tritium, which is a conservative source term that bounds the 
observed and maximum TPBAR tritium permeation rate. While the quantity 
of tritium generated during plant operations will increase under the 
proposed action, current radioactive waste treatment systems will be 
able to handle that increase according to TVA.
Radioactive Gaseous Effluents
    The WBN, Unit 2, maintains a gaseous waste management system (GWMS) 
that is designed to process and control the release of radioactive 
gaseous effluents into the environment in accordance with the 
requirements of 10 CFR 20.1301, Dose limits for individual members of 
the public, and to ensure consistency with the as low as reasonably 
achievable (ALARA) dose objectives set forth in appendix I to 10 CFR 
part 50.
    As stated above relative to TVA's license amendment request, TVA 
assumed a core load of 1,792 TPBARs with a permeation rate of 5.0 Ci/
TPBAR/year of tritium, which is a conservative source term that bounds 
the observed and maximum TPBAR tritium permeation rate as seen from the 
WBN, Unit 1 tritium production.
    To determine whether the gaseous effluents would fall within the 
requirements of 10 CFR 20.1301, TVA calculated the sum of the ratios of 
each isotope concentration (C) to its corresponding gaseous Effluent 
Concentration Limit (ECL, as listed in 10 CFR part 20, appendix B, 
Table 2, Column 1). Consistent with the requirements of 10 CFR 
20.1302(b)(2)(i), a C/ECL sum of less than 1.0 indicates that the 
annual average effluent release is within the limits of 10 CFR 20.1301. 
Tables 4.1-31 and 32 of the license amendment request demonstrate that 
TVA's calculated C/ECL sums for gaseous effluent releases at the WBN, 
Unit 2 from an assumed core load of 1,792 TPBARs for containment purge 
without filtration would be 4.52x10-1 and would be 
4.01x10-1 with continuous filtration. TVA's calculated C/ECL 
sums for gaseous effluent releases for both of the WBN, Units 1 and 2 
(dual operation) for containment purge without filtration would be 
9.12x10-1 and would be 8.02x10-1 with continuous 
filtration. Both sets of numbers are within the maximum C/ECL limit of 
1.0 according to TVA.
    To determine whether the gaseous effluents are consistent with the 
ALARA dose objectives set forth in appendix I to 10 CFR part 50 (which 
are per-unit numbers) TVA calculated bounding public doses from the 
applicable plant effluent dose pathways with the tritium release 
attributable to TPBAR permeability. These doses were based on an 
assumed core load of 1,792 TPBARs and the methods and assumptions in 
the current WBN Offsite Dose Calculation Manual (ODCM), (documented in 
the Watts Bar Nuclear Plant 2017, Annual Radioactive Effluent Release 
Report (ADAMS Accession No. ML18120A138). TVA calculated that the Whole 
Body dose to a Maximally Exposed Individual from the WBN, Unit 2 would 
be 0.63 millirem (mrem) (0.0063 millisievert (mSv)), which is much less 
than the Whole Body dose objective in appendix I to 10 CFR part 50 of 
5.00 mrem (0.05 mSv). TVA also calculated that the Organ Dose (Thyroid) 
to the Maximally Exposed Individual from the WBN, Unit 2 would be 8.30 
mrem (0.083 mSv), which is less than the Organ dose objective in 
appendix I to 10 CFR part 50 of 15.00 mrem (0.15 mSv).
    Doses would be assumed to double (1.26 mrem or 0.0126 mSv Whole 
Body and 16.6 mrem or 0.166 mSv Organ Dose (Thyroid)) for dual reactor 
tritium production at both the WBN, Units 1 and 2, which would be 
within the appendix I to 10 CFR part 50 dose objective as they are per-
unit numbers as stated above, and would also double according to TVA.
    Based on the above, the NRC staff finds that the TVA's analyses 
have demonstrated that WBN, Unit 2, can be operated with the proposed 
maximum core loading of 1,792 TPBARs and that the current GWMS can 
maintain the gaseous effluents within the Effluent Concentration Limits 
listed in 10 CFR part 20, appendix B to meet the dose limit 
requirements to members of the public in 10 CFR 20.1301, as well as 
maintain doses to the public ALARA as per the dose objectives set forth 
in

[[Page 3261]]

appendix I to 10 CFR part 50. Therefore, the NRC staff concludes that 
there would be no significant radiological impact from gaseous 
effluents under the proposed action.
Radioactive Liquid Effluents
    The WBN, Unit 2 liquid radioactive waste system (LRWS) is used to 
collect and process radioactive liquid wastes to reduce radioactivity 
and chemical concentrations to levels acceptable for discharge to the 
environment according to TVA. The LRWS maintains sufficient processing 
capability so that liquid waste may be discharged to the environment 
below the regulatory limits of 10 CFR 20.1301 and consistent with the 
ALARA dose objectives in appendix I to 10 CFR part 50. The WBN, Units 1 
and 2 share three large storage tanks in the LRWS, which includes a 
Tritiated Water Storage Tank with a capacity of 500,000 gallons. This 
storage tank supports managing large volume/high tritium concentrations 
in the reactor coolant system for both Units 1 and 2. These storage 
tanks can be used for liquid effluent holdup, dilution, and timing of 
releases to ensure that regulatory requirements are met. Release of 
radioactive liquids from the LRWS only occurs after laboratory analysis 
of the storage tank contents. If the activity is found to be above ODCM 
limits, the liquid waste streams are returned to the system for further 
processing by a mobile demineralizer. If the activity is found to be 
below the ODCM limits, the liquid waste stream is pumped to a discharge 
pipe where it is monitored for radiation levels and flowrate before it 
enters the Cooling Tower Blowdown line, where it can ultimately be 
discharged by permit into the Tennessee River.
    To determine whether the liquid effluents are within the 
requirements of 10 CFR 20.1301, TVA calculated the sum of the ratios of 
each isotope concentration (C) to its corresponding liquid Effluent 
Concentration Limit (ECL as listed in 10 CFR part 20, appendix B, Table 
2, Column 2). Consistent with the requirements of 10 CFR 
20.1302(b)(2)(i), a C/ECL sum of less than 1.0 indicates that the 
annual average effluent release is within the limits of 10 CFR 20.1301. 
Tables 4.1-28 through 30 of the license amendment request show TVA's 
calculated C/ECL sums for liquid effluent releases from an assumed core 
load of 1,792 TPBARs. Table 4.1-28 indicates that extended effluent 
releases, without processing the liquid radioactive waste streams 
through the mobile demineralizer or allowing for sufficient dilution of 
the radioactive waste stream, would not meet the regulatory 
requirements of 10 CFR 20.1301. The calculated C/ECL for the WBN, Unit 
2 in this scenario is 5.23, which is greater than the maximum allowable 
C/ECL of 1.0. Dual operation of both the WBN, Units 1 and 2 in this 
scenario would yield a C/ECL of 10.5.
    To ensure that the effluent concentration limits of 10 CFR 20.1301 
are met, Section 11.2.6.5 of the Final Safety Analysis Report states 
that ``No untreated wastes are released unless they are below the Lower 
Limit of Detection.'' Table 4.1-29 of the license amendment request 
demonstrates that TVA's calculated C/ECL sum for liquid effluent 
releases for the WBN, Unit 2 processed through the mobile demineralizer 
would be 4.18x10-\1\. Dual operation of both the WBN, Units 
1 and 2 in this scenario would yield a C/ECL of 8.35x10-\1\. 
Table 4.1-30 demonstrates that TVA's calculated C/ECL for liquid 
effluents not processed through the mobile demineralizer, but 
sufficiently diluted before release, would be 4.23x10-\1\. 
Dual operation of both the WBN, Units 1 and 2 in this scenario would 
yield a C/ECL of 8.47x10-\1\. All numbers for both scenarios 
are within the maximum C/ECL limit of 1.0.
    To determine whether the liquid effluents are consistent with the 
ALARA dose objectives set forth in appendix I to 10 CFR part 50, TVA 
calculated bounding public doses from the applicable plant effluent 
dose pathways with the tritium release attributable to TPBAR 
permeability. These doses were based on an assumed core load of 1,792 
TPBARs and the methods and assumptions in the current ODCM. TVA 
calculated that the Whole Body dose to a Maximally Exposed Individual 
from liquid effluents would be 0.37 mrem (0.0037 mSv), which is much 
less than the Whole Body dose objective in appendix I to 10 CFR part 50 
of 3.00 mrem (0.03 mSv). TVA also calculated that the Organ Dose 
(Liver) to the Maximally Exposed Individual from liquid effluents would 
be 0.49 mrem (0.0049 mSv), which is much less than the Organ dose 
objective in appendix I to 10 CFR part 50 of 10.00 mrem (0.15 mSv).
    Doses would be assumed to double (0.74 mrem or 0.0074 mSv Whole 
Body and 0.98 mrem or 0.098 mSv Organ Dose (Liver)) for dual reactor 
tritium production at both the WBN, Units 1 and 2, which would be 
within the appendix I to 10 CFR part 50 dose objective as they are per-
unit numbers as stated above, and would also double according to TVA.
    The NRC staff finds that TVA has demonstrated that WBN, Unit 2, can 
be operated with the proposed maximum core loading of 1,792 TPBARs, and 
that with processing of the liquid radioactive waste streams through 
the demineralizer, or allowing for proper dilution of the liquid 
radioactive waste streams, the current LRWS can maintain the liquid 
effluents within the Effluent Concentration Limits listed in 10 CFR 
part 20, appendix B. Specifically, doses from liquid effluents would 
meet the requirements regarding members of the public in 10 CFR 20.1301 
as well as maintain the public ALARA dose objectives set forth in 
appendix I to 10 CFR part 50. Therefore, the NRC staff concludes that 
there would be no significant radiological impact from gaseous 
effluents under the proposed action.
Solid Radioactive Wastes
    Solid radioactive wastes generated by nuclear power plant 
operations at WBN, Units 1 and 2, are processed, packaged, and stored 
until they are shipped offsite to a vendor for further processing or to 
a licensed facility for permanent disposal, or both. The storage areas 
have restricted access and shielding to reduce radiation rates to plant 
workers. Solid radioactive wastes are packaged and transported in 
compliance with NRC's regulations in 10 CFR parts 61, Licensing 
Requirements for Land Disposal of Radioactive Waste, and 71, Packaging 
and Transportation of Radioactive Material, and the U.S. Department of 
Transportation regulations in 49 CFR parts 170 through 179; and to 
maintain the dose limits of 10 CFR 20.1201, 10 CFR 20.1301, and design 
objectives in appendix I to 10 CFR part 50.
    Implementation of the proposed action would increase the activity 
and volume of solid radioactive waste due to the irradiation of the 
TPBAR base plates and thimble plugs, which remain after TPBAR 
consolidation activities. For the consolidation process, plant 
operators will remove the irradiated TPBAR assemblies from the spent 
fuel assemblies, disassemble all the irradiated TPBARs for 
consolidation, and place them into consolidation canisters. Operators 
will return the loaded consolidation canisters to the spent fuel racks, 
where they will remain until removed from the site. Offsite shipment 
and ultimate disposal would be conducted in accordance with agreements 
between TVA and DOE. The disposal volume of the TPBAR base plates and 
thimble plugs is estimated to be 33.3 cubic feet (0.942 cubic meters) 
per year. This additional volume represents a slight increase in the 
WBN, Units 1 and 2, annual estimated solid

[[Page 3262]]

waste generation from 65,640 cubic feet (1859 cubic meters) per year to 
65,706 cubic feet (1861 cubic meters) per year. This projected increase 
in volume can be handled by the existing equipment and plant procedures 
that control radioactive solid waste handling without modification. The 
estimated increase in activity inventory attributable to the handling 
of the TPBAR base plates and thimble plugs ranges from approximately 
3,600 Ci/yr (1.33x10\14\ Bq/yr) to 11,060 Ci/yr (4.09x10\14\ Bq/yr). 
While there would be increased activity associated with implementation 
of the proposed action, the existing equipment and plant procedures 
that control radioactive solid waste handling will continue to be used 
to maintain plant personnel exposures within the dose limits of 10 CFR 
20.1201, 10 CFR 20.1301, and design objectives in 10 CFR part 50, 
appendix I. Based on the above, the NRC staff concludes that there 
would be no significant radiological impact from solid radioactive 
waste management under the proposed action.
Spent Fuel Generation, Storage, and Handling
    The number of spent fuel bundles would increase by approximately 
four per cycle with implementation of the proposed action. WBN, Units 1 
and 2, currently store spent fuel in spent fuel pools on site and in an 
independent spent fuel storage installation. There will be adequate 
spent fuel storage available on site, therefore, the NRC staff 
concludes that there would be no significant radiological impact from 
spent fuel generation and storage under the proposed action.
    As stated above in Section II of this document, the proposed action 
would also revise the WBN, Units 1 and 2 TS 3.7.15, Spent Fuel Assembly 
Storage, to simplify the fuel storage limitations on fuel assemblies by 
eliminating the burnup-related criteria; TS 3.9.9, Spent Fuel Pool 
Boron Concentration, to modify the minimum fuel storage pool boron 
concentration during refueling operations when fuel is stored in the 
pool; and TS 4.3, Fuel Storage, to replace the storage limitations on 
fuel assembly burnup and storage with a single requirement to maintain 
a specified boron concentration in the spent fuel pool. The proposed 
action would also add the WBN, Units 1 and 2 TS 3.7.18, Fuel Storage 
Pool Boron Concentration, to specify the minimum fuel storage pool 
boron concentration when fuel is stored in the pool, and TS 5.7.2.21, 
Spent Fuel Storage Rack Neutron Absorber Monitoring Program, to monitor 
the condition of the neutron absorber material used in the spent fuel 
pool storage racks to ensure it will continue to perform its assumed 
design functions. These proposed changes would have no direct 
radiological environmental impacts. There would be no change to the 
types or amounts of radioactive effluents that may be released and, 
therefore, no change in occupational or public radiation exposure from 
the proposed changes. No changes would be made to plant buildings or 
the site property from these proposed changes. Therefore, there would 
be no significant radiological environmental impacts associated with 
these TS changes.
Occupational Radiation Doses
    At WBN, Units 1 and 2, TVA maintains a radiation protection program 
to monitor radiation levels throughout the nuclear power plant to 
establish appropriate work controls, training, temporary shielding, and 
protective equipment requirements so that worker doses will remain 
within the dose limits of 10 CFR part 20, subpart C, Occupational Dose 
Limits. Implementation of the proposed action would affect the 
quantities of radioactive material generated during plant operations 
since some tritium permeates through the TPBAR cladding and is released 
into the reactor coolant system, as previously described.
    Separate from the environmental review for this EA, the NRC staff 
is evaluating the licensee's technical and safety analyses provided in 
TVA's license amendment request to ensure the licensee continues to 
meet NRC regulatory requirements for occupational dose. The results of 
the NRC staff's safety review and conclusion will be documented in a 
safety evaluation that will be made publicly available following 
issuance of the EA. If the NRC staff concludes in the safety evaluation 
that the requested number of 1,792 TPBARs that can be irradiated, per 
cycle, in the WBN, Unit 2 core and the proposed changes related to the 
new criticality analyses performed for the spent fuel storage racks 
comply with NRC regulations for occupational dose, then granting the 
proposed license amendments will not have a significant radiological 
impact to workers.
Design-Basis Accidents
    Design-basis accidents are evaluated by both TVA and the NRC staff 
to ensure that WBN, Units 1 and 2, can withstand the spectrum of 
postulated accidents without undue hazard to public health and safety 
and ensure the protection of the environment.
    The NRC staff is evaluating the licensee's technical and safety 
analyses provided in the proposed license amendments to ensure the 
licensee continues to meet the NRC regulatory requirements for safe 
operation. The results of the NRC staff's safety review and conclusion 
will be documented in a safety evaluation that will be made publicly 
available following issuance of the EA. If the NRC staff concludes in 
the safety evaluation that 1,792 TPBARs irradiated, per cycle, in the 
WBN, Unit 2 core and the proposed changes related to the new 
criticality analyses performed for the spent fuel storage racks comply 
with NRC regulations, and there is reasonable assurance that public 
health and safety will not be endangered, then granting the proposed 
license amendments will not have a significant environmental impact.
Radiological Impacts Summary
    Based on the radiological evaluations presented in this EA, with 
the exception of the impacts associated with occupational dose and 
design-basis accidents, which the NRC staff are evaluating separately, 
implementation of the proposed action would not result in any 
significant radiological impacts. If the NRC staff concludes in the 
safety evaluation that 1,792 TPBARs irradiated, per cycle, in the WBN, 
Unit 2 core and the proposed changes related to the new criticality 
analyses performed for the spent fuel storage racks comply with NRC 
regulations, and there is reasonable assurance that public health and 
safety will not be endangered, then granting the proposed license 
amendments will not have a significant radiological impact to workers 
or the environment.

Environmental Impacts of the Alternatives to the Proposed Action

    As an alternative to the proposed action, the NRC staff considered 
denial of the license amendment request (i.e., the no-action 
alternative). Denial of the license amendment request would result in 
no change in current environmental impacts. Accordingly, the 
environmental impacts of the proposed action and the no-action 
alternative are similar.

Alternative Use of Resources

    There are no unresolved conflicts concerning alternative uses of 
available resources under the proposed action.

Agencies and Persons Consulted

    An official of the State of the Tennessee was notified about the 
environmental assessment and the state official had no comments.

[[Page 3263]]

III. Finding of No Significant Impact

    The licensee has requested license amendments pursuant to 10 CFR 
50.90, Application for amendment of license, construction permit, or 
early site permit, to revise the WBN, Unit 2 TSs to allow up to 1,792 
TPBARs to be irradiated in the reactor core. The license amendments 
also provide proposed changes for both the WBN, Units 1 and 2 TSs 
related to the new criticality analyses performed for the spent fuel 
storage racks to allow the proper safe handling and storage of spent 
fuel, including TPBARs, at the WBN site. The NRC is considering issuing 
the requested amendments. The proposed action would not significantly 
affect plant safety, would not have a significant adverse effect on the 
probability of an accident occurring, and would not have any 
significant radiological or nonradiological impacts. The reason the 
environment would not be significantly affected is because while the 
proposed changes would result in increased radiological plant effluents 
and offsite doses, those numbers would still be within the regulatory 
limits as stated in 10 CFR part 20 and design objectives in appendix I 
to 10 CFR part 50. This FONSI incorporates by reference the EA in 
Section II of this notice. Therefore, the NRC concludes that the 
proposed action will not have a significant effect on the quality of 
the human environment. Accordingly, the NRC has determined there is no 
need to prepare an environmental impact statement for the proposed 
action.
    Previous considerations regarding the environmental impacts of 
operating Watts Bar, Units 1 and 2, in accordance with their operating 
licenses, are described in NUREG-0498, Final Environmental Statement 
Related to Operation of Watts Bar Nuclear Plant, Units 1 and 2, dated 
December 1978, and NUREG-0498, Supplement 1, dated April 1995, and 
NUREG-0498, Supplement 2, Final Environmental Statement Related to 
Operation of Watts Bar Nuclear Plant, Unit 2, dated May 2013 (ADAMS 
Package Accession Nos. ML082540803, ML081430592, and ML13144A092).
    This FONSI and other related environmental documents may be 
examined, and/or copied for a fee, at the NRC's PDR, located at One 
White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. 
Publicly-available records are also accessible online in the ADAMS 
Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to ADAMS or who encounter 
problems in accessing the documents located in ADAMS should contact the 
NRC's PDR reference staff by telephone at 1-800-397-4209 or 301-415-
4737, or by email to pdr.resource@nrc.gov.

IV. Availability of Documents

    The documents identified in the following table are available to 
interested persons through ADAMS.

------------------------------------------------------------------------
                 Document                       ADAMS accession No.
------------------------------------------------------------------------
NUREG-0498--Final Environmental Statement  ML082540803
 Related to Operation of Watts Bar
 Nuclear Plant, Units 1 and 2, dated
 December 1978.
NUREG-0498--Final Environmental Statement  ML081430592
 Related to the Operation of Watts Bar
 Nuclear Plant, Units 1 and 2, Supplement
 1, dated April 1995.
NUREG-0498--Final Environmental Statement  ML13144A092
 Related to the Operation of Watts Bar
 Nuclear Plant, Unit 2, Supplement 2,
 dated May 2013.
Watts Bar Nuclear Plant, Unit 1:           ML16138A045
 Environmental Assessment and Finding of
 No Significant Impact Related to License
 Amendment Request to Revise Technical
 Specification 4.2.1, Fuel Assemblies,
 dated June 23, 2016.
TVA letter to NRC, Application to Revise   ML17354B282
 Watts Bar Unit 2 Technical Specification
 4.2.1, Fuel Assemblies, and Watts Bar
 Units 1 and 2 Technical Specifications
 Related to Fuel Storage (WBN-TS-17-028),
 dated December 20, 2017.
TVA letter to NRC, Correction to           ML18100A953
 Application to Revise Watts Bar Unit 2
 Technical Specification 4.2.1, Fuel
 Assemblies, and Watts Bar Units 1 and 2
 Technical Specifications Related to Fuel
 Storage (WBN-TS-17-028), dated April 9,
 2018.
TVA letter to NRC, Response to Request     ML18283A107
 for Additional Information Regarding
 Application to Revise Watts Bar Unit 2
 Technical Specification 4.2.1, Fuel
 Assemblies, and Watts Bar Units 1 and 2
 Technical Specifications Related to Fuel
 Storage (WBN-TS-17-028) (EPID L-2017-LLA-
 0427), dated October 4, 2018.
WBN Offsite Dose Calculation Manual, as    ML18120A138
 documented in the Watts Bar Nuclear
 Plant Annual Radioactive Effluent
 Release Report--2017, dated April 30,
 2018.
------------------------------------------------------------------------


    Dated at Rockville, Maryland, this 6th day of February 2019.
    For the Nuclear Regulatory Commission.
John G. Lamb,
Senior Project Manager, Special Projects and Process Branch, Division 
of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. 2019-01859 Filed 2-8-19; 8:45 am]
BILLING CODE 7590-01-P