Environmental Impact Statement - radioactive monticello

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Environmental Impacts of the Uranium Fuel Cycle and Solid Waste Management Onsite spent fuel. Based on information in the GELS, the Commission found that The expected increase in the volume of spent fuel from an additional 20 years of operation can be safely accommodated on site with small environmental effects through dry or pool storage at all plants if a permanent repository or monitored retrievable storage is not available. The staff has not identified any new and significant information during its independent review of the NMC ER, the.staff's site visit, the scoping process, its evaluation of other available information, or public comments on the draft SEIS. Therefore, the staff concludes that there are no impacts of onsite spent fuel associated with license renewal beyond those discussed in the GELS. * Nonradioloqical waste. Based on information in the GELS, the Commission found that No changes to generating systems are anticipated for license renewal. Facilities and procedures are in place to ensure continued proper handling and disposal at all plants. The staff has not identified any new and significant information during its independent review of the NMC ER, the staff's site visit, the scoping process,its evaluation of other available information, or. public comments on the draft SEIS. Therefore, the staff concludes that there are no nonradiological waste impacts during the renewal term beyond those discussed in the GELS. * Transportation. Based on information contained in the GELS, the Commission found that The impacts of transporting spent fuel enriched up to 5 percent uranium-235 with average burnup for the peak rod to current levels approved by NRC up to 62,000 MWd/MTU and the cumulative impacts of transporting HLW to a single repository, such as Yucca Mountain, Nevada, are found to be consistent with the impact values contained in 10 CFR 51.52(c), Summary Table S-4 - Environmental Impact of Transportation of Fuel and Waste to and from One Light- Water-Cooled Nuclear Power Reactor. If fuel enrichment or burnup conditions are not met, the applicant must submit an assessment of the implications for the environmental impact values reported in § 51.52. Monticello meets the fuel enrichment and burnup conditions set forth in Addendum 1 to the GELS. The staff has not identified any new and significant information during its independent review of the NMC ER, the staff's site visit, the scoping process, its evaluation of other available information, or public comments on the draft SEIS. Therefore, the staff concludes that there are no impacts of transportation associated with license renewal beyond those discussed in the GElS. NUREG-1437, Supplement 26 6-8 August 2006 1
6.2 References Environmental Impacts of the Uranium Fuel Cycle and Solid Waste Management 10 CFR Part 51. Code of Federal Regulations, Title 10, Energy, Part 51, "Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions." 10 CFR Part 54. Code of Federal Regulations, Title 10, Energy, Part 54, "Requirements for Renewal of Operating Licenses for Nuclear Power Plants." 10 CFR Part 63. Code of Federal Regulations, Title 10, Energy, Part 63, "Disposal of High- Level Radioactive Wastes in a Geologic Repository at Yucca Mountain, Nevada." 40 CFR Part 191. Code of Federal Regulations, Title 40, Protection of Environment, Part 191, "Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Waste." Energy Policy Act of 1992, Public Law No. 102-486, § 801, 1069 Stat. 2921. (codified at 42 USC 10101 note). National Academy of Sciences (NAS). 1995. Technical Bases for Yucca Mountain Standards. Washington, D.C. National Environmental Policy Act (NEPA) of 1969, as amended. 42 USC 4321, et seq. Nuclear Management Company (NMC). 2005. Applicant's Environmental Report-Operating License Renewal Stage, Monticello Nuclear Generating Plant. Docket No. 50-263, License No. DPR-22. Monticello, Minnesota. Nuclear Energy Institute, Inc. v. EPA, 373 F.3d 1251, 1273, 1299 (D.C. Cir. 2004). U.S. Department of Energy (DOE). 1980. Final Environmental Impact Statement: Management of Commercially Generated Radioactive Waste. DOE/EIS-0046F. Washington, D.C. U.S. Nuclear Regulatory Commission (NRC). 1996. Generic Environmental Impact Statement for License Renewal of Nuclear Plants. NUREG-1437, Volumes 1 and 2. Washington, D.C. U.S. Nuclear Regulatory Commission (NRC). 1999. Generic Environmental Impact Statement for License Renewal of Nuclear Plants, Main Report. Section 6.3 - Transportation, Table 9.1, Summary of findings on NEPA issues for license renewal of nuclear power plants, Final Report. NUREG-1437, Volume 1, Addendum 1, Washington, D.C. August 2006 6-9 NUREG-1437, Supplement 26 1
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NUREG-1437 Supplement 26 Generic En
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Generic Environmental Impact Statem
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Abstract The U.S. Nuclear Regulator
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Contents Abstract........... ......
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Contents 4.8.7 Conclusions Regardin
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Figures Figure 2-1. Figure 2-2. Fig
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Contents Table 5-1. Category 1 Issu
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Executive Summary The Commission ha
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Executive Summary NMC and the staff
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0 degree pCi microcurie(s) pCi/mL m
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Abbreviations/Acronyms IPE IPEEE J
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Abbreviations/Acronyms rem REMP RHR
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Introduction and (4) present the st
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Introduction (1) The environmental
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Introduction I assessment of the re
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Introduction This definition of pur
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2.0 Description of Nuclear Power Pl
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Description of Site and Environment
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Descfiption of Site and Environment
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Table 2-10. Land Use in Sherburne C
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Environmental Impacts of Refurbishm
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Environmental Impacts of Refurbishm
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Environmental Impacts of Operation
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Environmental Impacts of Alternativ
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9.0 Summary and Conclusions By lett
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Summary and Conclusions The GElS co
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Summary and Conclusions not reached
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z a :m G) CA, Table 9-1. Summary of
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Summary and Conclusions U.S. Nuclea
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Appendix A: Comments Received on th
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Appendix A Commenter ID Commenter A
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Appendix A A.1 Comments and Respons
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Monticello Nuclear Generating Plant
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3. General Comments Regarding Licen
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Appendix A nuclear power (I) and Mo
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Appendix A scoping process. If an i
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Appendix A Comment: The NRC does no
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Appendix A Comment: The EIS needs t
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Appendix A Comment: The EIS needs t
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Appendix A cognitive impairment. We
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Appendix A Despite available eviden
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Appendix A Comment: The Hospital Di
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Appendix A Comment: The NRC also fa
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Appendix A The NRC fails to acknowl
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the coal chain What about all the s
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gasification generation balanced ag
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Appendix A 14. Comments Concerning
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Appendix A Part II Comments Receive
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Appendix A Table A-2. (contd) Comme
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Appendix A Table A-2. (contd) Comme
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Appendix A A.2.4 General Comments i
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Appendix A Comment: Page 2-7, Line
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Appendix A turns out that we don't
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Appendix A A.2.12 Comments Concerni
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Appendix A Response: As described a
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information in the Final SEIS as pa
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Appendix A Response: The impacts to
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Appendix A Response: The text in Se
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aging management aspects of the lic
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Appendix A A-2 PURVES TODD: Just ba
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Appendix A PURVES TODD: Thank you v
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Appendix A So you don't look for wh
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Appendix A Yes CHUCK HOSTOVSKY: I t
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Appendix A information a little bit
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Appendix A Return-path: Received:
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Appendix A tAY-W8-2006 11! 07 'ENCL
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Appendix A ta W.Y United States Dep
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Appendix A MAY-17-206 13:11 P.04 U.
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Appendix A IMAY-17-20O6 13:12 P.06
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Appendix B Contributors to the Supp
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Appendix B Name Karen McWilliams Na
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Appendix C: Chronology of NRC Staff
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Appendix C May 27, 2005 May 27, 200
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Appendix C June 1,2005 June 2, 2005
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Appendix C January 23, 2006 Februar
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Appendix D Organizations Contacted
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Appendix D Wright County Assessor,
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Appendix E: Nuclear Management Comp
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Cn N0 Table E-2. (contd) Expiration
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Appendix E UNITED STATES -" NUCLEAR
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Appendix E N. Archabal -2- potentia
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Appendix E D. Stinnett -2- miles of
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Appendix E FIGURE 2.1-3 SITE BOUNDA
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Appendix E Common Name Scientific N
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Appendix E A. Stinnet : -2- ' !We a
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Appendix E 1.0 Introdution. The U.S
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Appendix E 6-M.LE SITE VICINITY Fig
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Appendix E agriculture and industri
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Appendix E -" .. " MWNTICELLO 345-K
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Appendix E Table 2. Terrestrial and
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Appendix E During the June 2005 sit
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Appendix E Vegetation management ma
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Appendix E Lehman, R.N. 2001. Rapto
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Appendix E MAY-31-206 15:31 P.02 MI
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Appendix F GElS Environmental Issue
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Appendix F References 10 CFR Part 5
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Appendix G: NRC Staff Evaluation of
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Appendix G Table G-1. Monticello Co
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Appendix G * The MACCS2 analyses pe
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Appendix G relative risk significan
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" Permanently posting an operator a
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Appendix G accident sequences to em
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Appendix G The staff noted that the
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Appendix G (testing of the boron in
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somewhat higher than what would act
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C Cn N, a) % Risk Reduction Total B
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Appendix G G.6 Cost-Benefit Compari
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Appendix G monetary equivalent of u
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Appendix G * SAMA 16- provide passi
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Appendix G several other SAMAs, res
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Appendix G Generating Plant, Docket
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NRC FORM 335 U.S. NUCLEAR REGULATOR
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