Environmental Impact Statement - radioactive monticello

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Environmental Impacts of Postulated Accidents Based on information in the GELS, the Commission found that: The probability weighted consequences of atmospheric releases, fallout onto open bodies of water, releases to groundwater, and societal and economic impacts from severe accidents are small for all plants. However, alternatives to mitigate severe accidents must be considered for all plants that have not considered such alternatives. Therefore, the Commission has designated mitigation of severe accidents as a Category 2 issue in 10 CFR Part 51, Subpart A, Appendix B, Table B-I. This issue, applicable to Monticello, is listed in Table 5-2. Table 5-2. Category 2 Issue Applicable to Postulated Accidents During the Renewal Term ISSUE-b10 CFR Part 51, Subpart 10 CFR 51.53(c)(3)(ii) SEIS A, Appendix B, Table B-1 GElS Sections Subparagraph Section POSTULATED ACCIDENTS Severe accidents 5.3.3; 5.3.3.2; 5.3.3.3; L 5.2 5.3.3.4; 5.3.3.5; 5.4; 5.5.2 The staff has not identified any new and significant information with regard to the consequences from severe accidents 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 severe accidents beyond those discussed in the GELS. However, in accordance with 10 CFR 51.53(c)(3)(ii)(L), the staff has reviewed severe accident mitigation alternatives (SAMAs) for Monticello. The results of its review are discussed in Section 5.2. 5.2 Severe Accident Mitigation Alternatives 10 CFR 51.53(c)(3)(ii)(L) requires that license renewal applicants consider alternatives to mitigate severe accidents if the staff has not previously evaluated SAMAs for the applicant's plant in an environmental impact statement (EIS) or related supplement or in an environmental assessment. The purpose of this consideration is to ensure that plant changes (i.e., hardware, procedures, and training) with the potential for improving severe accident safety performance are identified and evaluated. SAMAs have not been previously considered for Monticello; therefore, the remainder of Chapter 5 addresses those alternatives. NUREG-1437, Supplement 26 5-4 August 2006 1
Environmental Impacts of Postulated Accidents 5.2.1 Introduction This section presents a summary of the SAMA evaluation for Monticello conducted by NMC, and described in the ER, and the NRC's review of this evaluation. The details of the review are described in the NRC staff evaluation that was prepared with contract assistance from Information Systems Laboratories, Inc. The entire evaluation for Monticello is presented in Appendix G. The SAMA evaluation for Monticello was conducted with a four-step approach. In the first step NMC quantified the level of risk associated with potential reactor accidents using the plant-specific probabilistic safety assessment (PSA) and other risk models. In the second step NMC examined the major risk contributors and identified possible ways (SAMAs) of reducing that risk. Common ways of reducing risk are changes to components, systems, procedures, and training. NMC initially identified 40 potential SAMAs for Monticello. NMC screened out 24 SAMAs from further consideration because they are not applicable at Monticello due to design differences, require extensive changes that would involve implementation costs known to exceed any possible benefit, or exceed the dollar value associated with completely eliminating all internal and external event severe accident risk at Monticello. The remaining 16 SAMAs were subjected to further evaluation. During the second phase of the evaluation, NMC screened out one additional SAMA based on risk insights and other factors, leaving 15 SAMAs. In the third step NMC estimated the benefits and the costs associated with each of the remaining SAMAs. Estimates were made of how much each SAMA could reduce risk. Those estimates were developed in terms of dollars in accordance with NRC guidance for performing regulatory analyses (NRC 1997a,b). The cost of implementing the proposed SAMAs was also estimated. Finally, in the fourth step, the costs and benefits of each of the remaining SAMAs were compared to determine whether the SAMA was cost-beneficial, meaning the benefits of the SAMA were greater than the cost (a positive cost-benefit). NMC found seven SAMAs to be potentially cost-beneficial in the baseline analysis, and three additional SAMAs to be potentially cost-beneficial when alternative discount rates and analysis uncertainties are considered (NMC 2005a). NMC recognized that a combination of low-cost SAMAs can provide much of the risk reduction associated with higher-cost SAMAs, and may act synergistically to yield a combined risk reduction greater than the sum of the benefits for each SAMA if implemented individually. Since the ER was submitted, NMC has implemented six SAMAs, and reassessed the value of the remaining SAMAs. Implementation of the six SAMAs reduces the benefit of the remaining SAMAs such that only one SAMA remains potentially cost-beneficial. August 2006 5-5 NUREG-1437, Supplement 26 I
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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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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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