Environmental Impact Statement - radioactive monticello

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Environmental Impacts of Decommissioning are no impacts on ecological resources associated with decommissioning following the license renewal term beyond those discussed in the GELS. Socioeconomic impacts. Based on information found in the GELS, the Commission found that Decommissioning would have some short-term socioeconomic impacts. The impacts would not be increased by delaying decommissioning until the end of a 20-year relicense period, but they might be decreased by population and economic growth. 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 socioeconomic impacts associated with decommissioning following the license renewal term beyond those discussed in the GELS. 7.2 References 10 CFR Part 51. Code of Federal Regulations, Title 10, Energy, Part 51, "Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions." 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. U.S. Nuclear Regulatory Commission (NRC). 1996. Generic Environmental Impact Statement for License Renewal of Nuclear Plants. NUREG-1 437, Volumes 1 and 2, Waslhington, 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. U.S. Nuclear Regulatory Commission (NRC). 2002. Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities, Supplement 1, Regarding the Decommissioning of Nuclear Power Reactors. NUREG-0586, Supplement 1, Vols. 1 and 2, Washington, D.C. NUREG-1437, Supplement 26 7-4 August 2006 1
8.0 Environmental Impacts of Alternatives to License Renewal This chapter examines the potential environmental impacts associated with denying the renewal of an operating license (OL) for Monticello Nuclear Generating Plant (Monticello) (the no-action alternative); the potential environmental impacts from electric generating sources other than the Monticello site; the possibility of purchasing electric power from other sources to replace power generated by Monticello and the associated environmental impacts; the potential environmental impacts from a combination of generating and conservation measures; and other generation alternatives that were deemed unsuitable for replacement of power generated by Monticello. The environmental impacts are evaluated using the U.S. Nuclear Regulatory Commission's (NRC's) three-level standard of significance-SMALL, MODERATE, or LARGE-developed using the Council on Environmental Quality guidelines and set forth in the footnotes to Table B-1 of Title 10 of the Code of Federal Regulations (CFR) Part 51, Subpart A, Appendix B: SMALL-Environmental effects are not detectable or are so minor that they will neither destabilize nor noticeably alter any important attribute of the resource. MODERATE-Environmental effects are sufficient to alter noticeably, but not to destabilize important attributes of the resource. LARGE-Environmental effects are clearly noticeable and are sufficient to destabilize important attributes of the resource. The impact categories evaluated in this chapter are the same as those used in the Generic Environmental Impact Statement for License Renewal of Nuclear Plants (GELS), NUREG-1 437, Volumes 1 and 2 (NRC 1996, 1999)(a) with the additional impact category of environmental justice. 8.1 No-Action Alternative NRC's regulations implementing the National Environmental Policy Act (NEPA) of 1969 specify that the no-action alternative be discussed in an NRC environmental impact statement (EIS), (see 10 CFR Part 51, Subpart A, Appendix A[4]). For license renewal, the no-action alternative refers to a scenario in which the NRC would not renew the Monticello OL. The Northern States Power Company (NSP) would then cease plant operations when the current license expires and initiate the decommissioning of the plant. € The GElS was originally issued in 1996. Addendum 1 to the GElS was issued in 1999. Hereafter, all references to the "GEIS" include the GElS and its Addendum 1. August 2006 8-1 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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Page 122 and 123: 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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