Environmental Impact Statement - radioactive monticello

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Description of Site and Environment draft SEIS, NMC issued the effluent release report for 2005 (NMC 2006) and reported no I abnormal liquid effluent releases during the calendar year. Based on the system description above, design, and previous performance, no liquid effluents, other than occasional abnormal releases, are expected from Monticello during the renewal period. If abnormal releases were to occur, they would result in doses to members of the public that are well below the dose design objectives of 10 CFR Part 50, Appendix I, as discussed in Section 2.2.7. 2.1.4.2 Gaseous Waste Processing Systems and Effluent Controls The gaseous radwaste system provides for sufficient off-gas holdup time to allow decay of the short-lived radioisotopes (such as nitrogen-1 6 and oxygen-1 9) and fission product noble gases (primarily xenon and krypton). The gaseous radwaste system also removes radioactive particulates and iodine from the off-gas stream, and recombines radiolytic hydrogen and oxygen to form liquid water to be treated in the liquid radwaste system. Radioactive gases are then filtered and released through the plant off-gas stack. During normal operations, the gaseous radwaste system operates on a continuous basis with effective monitoring and control provided so as not to exceed the limits of 10 CFR Part 20 or the dose objectives of Appendix I to 10 CFR Part 50 (NMC 2005b). Off gas from the main condenser air ejector effluent passes through a 42-in. diameter delay line and is stored in the compressed gas'storage system near the base of the off-gas stack. Five compressed gas storage tanks, approximately 1250 ft 3 each, provide for a minimum total holdup time of approximately 50 hours at a design off-gas release rate of 28 standard cubic feet per minute (scfm). For typical off-gas rate of 10 scfm, the holdup time could be as high as 140 hours. Off gases from the steam packing exhaust system, the mechanical vacuum pump effluent, and the high-pressure coolant injection (HPCI) gland seal effluent are all collected and processed in the steam packing exhauster off-gas subsystem. These gases are discharged on a continuous basis into a 1.75-minute holdup line and mixed with the air ejector off-gases at the stack base. The off-gas stack provides for mixing, dilution with fresh makeup air, monitoring, and release of the off gas to the atmosphere at an elevation of 328 ft above ground. The stack height and plume buoyancy aids in the dispersion of the gases into the atmosphere (NMC 2005b). A review of the 2004 Radioactive Effluent Release Report (NMC 2005e) provided data on radioactive effluent release rates for Monticello. For calendar year 2004, releases included 1371 Ci of fission and activation gases, 1.5 x 1 0- Ci of iodine-1 31, 1.2 x 10.3 Ci of particulates, and 16.2 Ci of tritium. These activities are typical of past years, and are expected during the renewal period. See Section 2.2.7 for a discussion of the theoretical doses to the maximally exposed individual as a result of these releases. Since issuance of the draft SEIS, NMC issued the effluent release report for 2005 (NMC 2006) and gaseous releases were consistent with past years. NUREG-1 437, Supplement 26 2-10 August 2006 1
Description of Site and Environment 2.1.4.3 Solid Waste Processing The solid radwaste system is designed to process, package, store, monitor, and provide shielded storage facilities for solid waste to allow for radioactive decay and/or temporary storage prior to shipment from the plant for off-site disposal. The solid radioactive waste is shipped off-site in vehicles equipped with adequate shielding to comply with Department of Transportation (DOT) regulations. Radioactive solid waste generated from the plant includes: process waste filter sludge and spent resins from the liquid processing systems; reactor system spent control rod blades, temporary control curtains, fuel channels, and in-core ion chambers; maintenance waste contaminated clothing, tools, rags and small pieces of equipment; operating waste laundry cartridge filters, paper, rags, off-gas filters, and ventilation filters; and miscellaneous solidified chemical and liquid wastes. A rapid dewatering system (RDS) is a waste processing system installed for use at Monticello. This self-contained system is used for accelerated dewatering of particulate waste material. Extracted water from this system is routed to the liquid drains and subsequently routed back to the plant for processing. Radioactive sludge from the RDS unit is stored in the radwaste storage building and shipped offsite to a licensed facility in accordance with applicable DOT and NRC regulations (NMC 2005b). In 2004, Monticello made a total of five low-level waste shipments. The solid waste volumes --were 3.41 m 3 of spent resins, filter sludge, evaporator bottoms, etc., with an activity of approximately 264 Ci; and 151 m 3 of dry compressible waste, contaminated equipment, etc., with an activity of approximately 3.81 Ci. No irradiated components or control rods were shipped. These solid waste volumes and radioactive material activity levels are typical of annual waste shipments for Monticello and are not expected to increase during the renewal period. 2.1.5 Nonradioactive Waste Systems Nonradioactive liquid waste at Monticello consists of wastewater from lavatories, showers, and sinks. These wastewaters are discharged from the Monticello sanitary sewer system to the City of Monticello sanitary sewage disposal system. A lift station and forced main were installed in 1983 to connect the plant to the city system. Nonradioactive solid waste at Monticello consists of hazardous waste (such as oils) and nonhazardous waste (such as office waste, garbage, and demolition debris materials). The Nuclear Management Company, LLC (NMC), is required to manage its hazardous waste in accordance with the Hazardous Waste Generator License from the State of Minnesota Pollution Control Agency (MPCA). 2.1.6 Plant Operation and Maintenance Maintenance activities conducted at Monticello include inspection, testing, and surveillance to maintain the current licensing basis of the facility and to ensure compliance with environmental August 2006 2-11 NUREG-1437, Supplement 26 1
Page 1 and 2: NUREG-1437 Supplement 26 Generic En
Page 3 and 4: Generic Environmental Impact Statem
Page 5 and 6: Abstract The U.S. Nuclear Regulator
Page 7 and 8: Contents Abstract........... ......
Page 9 and 10: Contents 4.8.7 Conclusions Regardin
Page 11 and 12: Figures Figure 2-1. Figure 2-2. Fig
Page 13: Contents Table 5-1. Category 1 Issu
Page 16 and 17: Executive Summary The Commission ha
Page 18 and 19: Executive Summary NMC and the staff
Page 21 and 22: 0 degree pCi microcurie(s) pCi/mL m
Page 23 and 24: Abbreviations/Acronyms IPE IPEEE J
Page 25: Abbreviations/Acronyms rem REMP RHR
Page 28 and 29: Introduction and (4) present the st
Page 30 and 31: Introduction (1) The environmental
Page 32 and 33: Introduction I assessment of the re
Page 34 and 35: Introduction This definition of pur
Page 37 and 38: 2.0 Description of Nuclear Power Pl
Page 39 and 40: Description of Site and Environment
Page 45: Description of Site and Environment
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Page 71 and 72: Table 2-10. Land Use in Sherburne C
Page 87: Description of Site and Environment
Page 90 and 91: Environmental Impacts of Refurbishm
Page 92 and 93: 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
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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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