Environmental Impact Statement - radioactive monticello

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Environmental Impacts of the Uranium Fuel Cycle and Solid Waste Management and significant information with respect to the offsite radiological impacts from license renewal related to disposal of spent nuclear fuel and high-level nuclear waste. - The EPA developed Yucca Mountain-specific repository standards, which were subsequently adopted by the NRC in 10 CFR Part 63. In an opinion, issued July 9, 2004, the U.S. Court of Appeals for the District of Columbia Circuit (the Court) vacated EPA's radiation protection standards for the candidate repository, which required compliance with certain dose limits over a 10,000 year period. The Court's decision also vacated the compliance period in NRC's licensing criteria for the candidate repository in 10 CFR Part 63. In response to the Court's decision, the EPA issued its proposed revised standards on August 22, 2005 (Federal Register, Volume 40, page 49014 [70 FR 49014]). In order to be consistent with the EPA's revised standards, the NRC proposed revisions to 10 CFR Part 63 on September 8, 2005 (70 FR 53313). Therefore, for the HLW and spent fuel disposal component of the fuel cycle, there is some uncertainty with respect to regulatory limits for offsite releases of radioactive nuclides for the current candidate repository site. However, prior to promulgation of the affected provisions of the Commission's regulations, the staff assumed that limits would be developed along the lines of the 1995 National Academy of Sciences report, Technical Bases for Yucca Mountain Standards, and that in accordance with the Commission's Waste Confidence Decision, 10 CFR 51.23, a repository that would comply with such limits could and likely would be developed at some site. Despite the current uncertainty with respect to these rules, some judgment as to the regulatory NEPA implications of offsite radiological impacts of spent fuel and HLW disposal should be made. The staff concludes that these impacts are acceptable in that the impacts would not be sufficiently large to require the NEPA conclusion that the option of extended operation under 10 CFR Part 54 should be eliminated. The staff has not identified any new and significant information during its independent review of I 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 offsite radiological impacts related to spent fuel and HLW disposal during the renewal term beyond those discussed in the GELS. Nonradiolopical impacts of the uranium fuel cycle. Based on information in the GELS, the Commission found that The nonradiological impacts of the uranium fuel cycle resulting from the renewal of an operating license for any plant are found to be small. 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 I information, or public comments on the draft SEIS. Therefore, the staff concludes that there NUREG-1 437, Supplement 26 6-6 August 2006 1
Environmental Impacts of the Uranium Fuel Cycle and Solid Waste Management are no nonradiological impacts of the uranium fuel cycle during the renewal term beyond those discussed in the GElS. Low-level waste storage and disposal. Based on information in the GELS, the Commission found that The comprehensive regulatory controls that are in place and the low public doses being achieved at reactors ensure that the radiological impacts to the environment will remain small during the term of a renewed license. The maximum additional on-site land that may be required for low-level waste storage during the term of a renewed license and associated impacts will be small. Nonradiological impacts on air and water will be negligible. The radiological and nonradiological environmental impacts of long-term disposal of low-level waste from any individual plant at licensed sites are small. In addition, the Commission concludes that there is reasonable assurance that sufficient lowlevel waste disposal capacity will be made available when needed for facilities to be decommissioned consistent with NRC decommissioning requirements. 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 low-level waste (LLW) storage and disposal associated with the renewal term beyond those discussed in the GElS. * Mixed waste stora-qe and disposal. Based on information in the GELS, the Commission found that The comprehensive regulatory controls and the facilities and procedures that are in place ensure proper handling and storage, as well as negligible doses and exposure to toxic materials for the public and the environment at all plants. License renewal will not increase the small, continuing risk to human health and the environment posed by mixed waste at all plants. The radiological and nonradiological environmental impacts of long-term disposal of mixed waste from any individual plant at licensed sites are small. In addition, the Commission concludes that there is reasonable assurance that sufficient mixed waste disposal capacity will be made available when needed for facilities to be decommissioned consistent with NRC decommissioning requirements. 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 mixed waste storage and disposal associated with the renewal term beyond those discussed in the GElS. August 2006 6-7 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 114 and 115: 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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Environmental Impact Statement - radioactive monticello

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