Environmental Impact Statement - radioactive monticello

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Environmental Impacts of Postulated Accidents SAR presents the design criteria and design information for the proposed reactor and comprehensive data on the proposed site. The SAR also discusses various hypothetical accident situations and the safety features that are provided to prevent and mitigate accidents. The NRC staff reviews the application to determine whether the plant design meets the Commission's regulations and requirements and includes, in part, the nuclear plant design and its anticipated response to an accident. DBAs are those accidents that both the licensee and the NRC staff evaluate to ensure that the plant can withstand normal and abnormal transients, and a broad spectrum of postulated accidents, without undue hazard to the health and safety of the public. A number of these postulated accidents are not expected to occur during the life of the plant, but are evaluated to establish the design basis for the preventive and mitigative safety systems of the facility. The acceptance criteria for DBAs are described in Title 10 of the Code of Federal Regulations (CFR) Part 50 and 10 CFR Part 100. The environmental impacts of DBAs are evaluated during the initial licensing process, and the ability of the plant to withstand these accidents is demonstrated to be acceptable before issuance of the operating license (OL). The results of these evaluations are found in license documentation such as the applicant's final safety analysis report (FSAR), the staff's safety evaluation report (SER), the final environmental statement (FES), and Section 5.1 of.this supplemental environmental impact statement (SEIS). A licensee is required to maintain the acceptable design and performance criteria throughout.the life of the plant, including any extended-life operation. The consequences for these events are evaluated for the hypothetical maximum exposed individual; as such, changes in the plant environment will not affect these evaluations. Because of the requirements that continuous acceptability of the consequences and aging management programs be in effect for license renewal, the environmental impacts as calculated for DBAs should not differ significantly from initial licensing assessments over the life of the plant, including the license renewal period. Accordingly, the design of the plant relative to DBAs during the extended period is considered to remain acceptable and the environmental impacts of those accidents were not examined further in the GELS. The Commission has determined that the environmental impacts of DBAs are of SMALL significance for all plants because the plants were designed to successfully withstand these accidents. Therefore, for the purposes of license renewal, DBAs are designated as a Category 1 issue in 10 CFR Part 51, Subpart A, Appendix B, Table B-1. The early resolution of the DBAs makes them a part of the current licensing basis of the plant; the current licensing basis of the plant is to be maintained by the licensee under its current license and, therefore, under the provisions of 10 CFR 54.30, is not subject to review under license renewal. This issue, applicable to Monticello, is listed in Table 5-1. NUREG-1437, Supplement 26 5-2 August 2006 1
Environmental Impacts of Postulated Accidents Table 5-1. Category I Issue Applicable to Postulated Accidents During the Renewal Term ISSUE-10 CFR Part 51, Subpart A, Appendix B, Table B-1 GElS Sections POSTULATED AccIDENTS Design basis accidents 5.3.2; 5.5.1 Based on information in the GELS, the Commission found that: The NRC staff has concluded that the environmental impacts of design basis accidents are of small significance for all plants. Nuclear Management Company (NMC) stated in its Environmental Report (ER) (NMC 2005a) that it is not aware of any new and significant information associated with the renewal of the Monticello OL. 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 related to design basis accidents beyond those discussed in the GElS. 5.1.2 Severe Accidents Severe nuclear accidents are those that are more severe than DBAs because they could result in substantial damage to the reactor core, whether or not there are serious offsite consequences. In the GELS, the staff assessed the impacts of severe accidents during the license renewal period, using the results of existing analyses and site-specific information to conservatively predict the environmental impacts of severe accidents for each plant during the renewal period. Severe accidents initiated by external phenomena, such as tornadoes, floods, earthquakes, fires, and sabotage have not traditionally been discussed in quantitative terms in FESs and were not specifically considered for the Monticello site in the GElS (NRC 1996). However, in the GElS, the NRC staff did evaluate existing impact assessments performed by the NRC and by the industry at 44 nuclear plants in the United States and concluded that the risk from beyond design-basis earthquakes at existing nuclear power plants is SMALL. Additionally, the NRC regulatory requirements under 10 CFR Part 73 provide reasonable assurance that the risk from sabotage is SMALL. Furthermore, the NRC staff concluded that the risks from other external events are adequately addressed by a generic consideration of internally initiated severe accidents. August 2006 5-3 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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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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