Environmental Impact Statement - radioactive monticello

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Appendix A Response: The text in Section 8.2.5 of the SEIS has been changed based on the information provided in this comment. Comment: Page E-2, Line 4: The US Fish and Wildlife Service Migratory Bird Treaty Act Permit was reissued on 04/01/2006. Authorization information is as follows: Number MB074020-0, Expiration Date: 03/31/09. (F-26) Comment: Page E-2, Line 10: The MNDNR Division of Fish and Wildlife Special Permit was reissued on 11/21/2005. Authorization information is as follows: Number 13315, Expiration Date: 12/31/06. (F-27) Comment: Page E-4, Line 24: Remove "NYDSEC: New York State Department of Environmental Conservation"--not relevant to discussion. (F-28) Comment: Page E-4, Line 3: The South Caroline Radioactive Waste Transport Permit was reissued for 2006. Authorization information is as follows: Number 0026-22-06-Y, Expiration Date: 12/31/06. (F-29) Comment: Page E-4, Line 8: The Tennessee Radioactive Shipment License was reissued for 2006. Authorization information is as follows: Number T-MN-002-L06, Expiration Date: 12/31/06. (F-30) Response: The text in Appendix E of the SEIS has been changed based on the information provided in these comments. Comment: Page G-23, Line 18: Replace "$1.1 x1 09" with "$1.1 x 109." (F-31) Response: The text in Appendix G of the SEIS has been changed based on the information provided in this comment. A.2.19 Comments Concerning Issues Outside the Scope of License Renewal: Aging Management and Independent Spent Fuel Storage Installation (ISFSI) Aginq Management Comment: The Monticello plant has been extremely well maintained over its lifetime, ensuring it can operate safely for at least an additional twenty years beyond the original operating license period. Approximately every two years, we perform a refueling and major maintenance outage in which we typically carry out over 2500 individual maintenance and inspection activities. This is in addition to the ongoing maintenance, inspection, and rigorous testing activities that are performed routinely during the period of plant operation. We have continued to invest in a wide range of equipment improvements to take advantage of technology and materials to ensure future reliable and safe operation, and this is relevant to the NUREG-1437, Supplement 26 A-58 August 2006 I
aging management aspects of the license renewal process. As we move forward, we will continue to upgrade and improve the equipment, the technology, and the training to the employees of the station. (C-3) Appendix A Response: Comments regarding aging management issues are outside the scope of license renewal and provide no new information; therefore, no changes were made to the SEIS. Independent Spent Fuel Storage Installation (ISFSI) Comment: Are you folks crazy, or do you think storing nuclear waste next to one of the largest freshwater rivers in the world is a good idea. (D-1) Comment: We are aware that there was a proposal before the Minnesota Environmental Quality Board for dry cask storage facility for spent nuclear fuel at Monticello. We note that the Environmental Impacts section of the Draft SEIS does not discuss the potential impacts associated with adding this type of spent fuel storage facility to the existing operation. We suggest that a new dry cask storage facility constitutes a new set of circumstances for this site and should be evaluated in greater detail for additional impacts to the environment. (H-3) Comment: The Federal Government's failure to site a nuclear waste repository should not be cause to close a functional, and large capital cost, generation plant before its' time. (E-2) Response: Onsite storage facilities are licensed separately from the reactor license renewal process. The NRC authorizes storage of spent nuclear fuel at an independent spent fuel storage installation (ISFSI) under two licensing options: a site-specific license or a general license. A general license authorizes a nuclear power plant licensee to store spent fuel in NRCapproved casks at an existing site that is licensed for operating of a power reactor under 10 CFR Part 50. An NRC-approved cask is one that has undergone a technical review of its safety aspects and been found to meet all of the NRC's requirements in 10 CFR Part 72. The NRC issues a Certificate of Compliance for a cask design to a cask vendor after a rulemaking determines its adequacy. Licensees are required to perform evaluations of their sites to demonstrate that the site is adequate for storing spent fuel in dry casks. These evaluations must show that the cask Certificate of Compliance conditions and technical specifications can be met. The licensee must also review its security program, emergency plan, quality assurance program, training program, and radiation protection program, and make any necessary changes to incorporate the ISFSl at its reactor site. The safety and environmental effects of long-term storage of spent fuel onsite have been evaluated by the NRC and, as set forth in the Waste Confidence Rule at 10 CFR 51.23 (available at http://www.nrc.qov/reading-rm/doc-collections/cfr/partO51/artO5. -0023.html), the NRC generically determined that "J..if necessary, spent fuel generated in any reactor can be stored safely and without significant environmental impacts for at least 30 years beyond the August 2006 A-59 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 Postulated
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Environmental Impacts of the Uraniu
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Environmental Impacts of Decommissi
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Environmental Impacts of Decommissi
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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
Page 249 and 250: Monticello Nuclear Generating Plant
Page 251 and 252: 3. General Comments Regarding Licen
Page 253 and 254: Appendix A nuclear power (I) and Mo
Page 255 and 256: Appendix A scoping process. If an i
Page 257 and 258: Appendix A Comment: The NRC does no
Page 259 and 260: Appendix A Comment: The EIS needs t
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Page 263 and 264: Appendix A cognitive impairment. We
Page 265 and 266: Appendix A Despite available eviden
Page 267 and 268: Appendix A Comment: The Hospital Di
Page 269 and 270: Appendix A Comment: The NRC also fa
Page 271 and 272: Appendix A The NRC fails to acknowl
Page 273 and 274: the coal chain What about all the s
Page 275 and 276: gasification generation balanced ag
Page 277 and 278: Appendix A 14. Comments Concerning
Page 279 and 280: Appendix A Part II Comments Receive
Page 281 and 282: Appendix A Table A-2. (contd) Comme
Page 283 and 284: Appendix A Table A-2. (contd) Comme
Page 285 and 286: Appendix A A.2.4 General Comments i
Page 287 and 288: Appendix A Comment: Page 2-7, Line
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Page 291 and 292: Appendix A A.2.12 Comments Concerni
Page 293 and 294: Appendix A Response: As described a
Page 295 and 296: information in the Final SEIS as pa
Page 297 and 298: Appendix A Response: The impacts to
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Page 303 and 304: Appendix A A-2 PURVES TODD: Just ba
Page 305 and 306: Appendix A PURVES TODD: Thank you v
Page 307 and 308: Appendix A So you don't look for wh
Page 309 and 310: Appendix A Yes CHUCK HOSTOVSKY: I t
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Page 323: Appendix B Contributors to the Supp
Page 326 and 327: Appendix B Name Karen McWilliams Na
Page 329 and 330: Appendix C: Chronology of NRC Staff
Page 331 and 332: Appendix C May 27, 2005 May 27, 200
Page 333 and 334: Appendix C June 1,2005 June 2, 2005
Page 335 and 336: Appendix C January 23, 2006 Februar
Page 337: Appendix D Organizations Contacted
Page 340 and 341: Appendix D Wright County Assessor,
Page 343 and 344: Appendix E: Nuclear Management Comp
Page 345 and 346: Cn N0 Table E-2. (contd) Expiration
Page 347 and 348: Appendix E UNITED STATES -" NUCLEAR
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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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