Ii,'!CALC. NO.CALCULATION COVER SHEET i.,l.': ,: TXUT-001-ER-3.S-CALC-OOSREV. 1ENERCON SERVICES, INC.PAGE NO. Page 1 of 23Title:Client:LumlnantProject:MITSOO3CPNPP Transportation AnalysisItemCover Sheet ItemsYesNo1Does this calculation contain any open assumptions that require confirmation? IfYES, Identify the assumptionsD1812Does this calculation serve as an "Alternate Calculation"? If YES, identify thedesign verified calculation.D181D181Design Verified Calculation No.3Does this calculation supersede an existing calculation? If YES, Identify thesuperseded calculation.Superseded Calculation No.Scope of Revision:The scope of Revision 1 Is to add a heat load calculation to determine the amount of decay heat In onespent fuel shipping cask. Also, the number of fuel assemblies per new fuel shipping truck Is changed from28 to 12 to serve as a better estimate of actual shipments of PWR fuel.Revision Impact on Results:The dose per reactor year associated with shipments of new tuellncreased due to the change in therequired number of shipments. See Section 7.1. Also, the decay heat load calculated Is added to theresults In Sections 2 and 7.DDStudy CalculationSafety-RelatedNon-Safety RelatedJPr WDesign Verifier: Marvin MorrisApprover: Joanne G. MorrisI181181(Print Name and Sign).JOriginator: Jeffrey HeadFinal CalculationDate:1' \ I1AA """" 'V (), I"'\;)1/).0/100'Date: / /?--O,,"Date:t,(7(Jr3/ .zo/
10CALC. NO.CALCULATIONREVISION STATUS SHEETENERCON SERVICES, INC.TXUT-001-ER-3.8-CALC-OO8REV. 1PAGE NO. Page 2 of 23CALCULATION REVISION STATUSREVISIONDATEDESCRIPTION04/18/2008Initial issue.1Revision to calculate caskdecay heat and to adjustnumber of new fuelassemblies per truck.PAGE REVISION STATUSPAGE 31PAGE NO.REVISIONAPPENDIX REVISION STATUSAPPENDIX NO.PAGE NO.REVISION NO.APPENDIX NO.PAGE NO.REVISION NO.Appendix 11-41Appendix 210Appendix 31-40Appendix 41 -200
f.!1mCALC. NO.CPNPP Transportation AnalysisTXUT-001-ER-3. S-CALC-OOSREV. 0ENERCON SERVICES, INC.PAGE NO. Page 3 of 23TABLE OF CONTENTS1.0Purpose and Scope . 42.0Summary of Results and Conclusions . 53.0References . 64.0Assumptions . 75.0Design Inputs . 95.1TRAGIS Inputs . 95.2RADTRAN Inputs for Spent Fuel . 95.3RADTRAN Inputs for New FueL . 155.4Transportation of Radioactive Waste . 156.0Methodology . 176.1Regulatory Limits . 176.2RADTRAN Methodology . 187.0Calculations . 207.1Risks of Transporting New Fuel . 207.2Risks of Transporting Spent Fuel . 207.3Transportation of Radioactive Waste . 228.0Appendices . 23
0-CALC. NO.""cENERCON SERVICES, INC.CPNPP Transportation AnalysisTXUT-OO1-ER-3.8-CALC-008REV. 1PAGE NO. Page 4 of 231.0 Purpose and ScopeThe purpose of this calculation is to determine the effects (measured in person-rem) of shipping nuclearmaterial to and from the proposed Luminant nuclear plants, Comanche Peak Nuclear Power Plant(CPNPP) Units 3 & 4. The shipments of nuclear material include new fuel to the site, spent fuel away fromthe site, and radioactive waste away from the site. The results of this calculation will be used to supportthe Combined License Application (COLA) for the CPNPP to be submitted by Luminant.This calculation was performed using the RADTRAN computer program, which was developed tocalculate the risks of transporting radioactive materials. A NRC analysis of the risks of transportingnuclear materials is provided in NUREG-1817, "Environmental Impact Statement for an Early Site Permit(ESP) at the Grand Gulf ESP Site." NUREG-1817 procedures are largely based on the RADTRAN code.RADTRAN requires that a route be entered so that the risks of transporting the nuclear materials can beadequately modeled. Routes can be manually entered or acquired using a secondary program,Transportation Routing Analysis Geographic Information System (TRAGIS). TRAGIS uses mapping andpopulation data to output types of areas (rural, suburban, urban) along a route and population densitiesfor those areas around the route. RADTRAN then applies the risks of transporting the nuclear material tothe route supplied by TRAG IS. This calculation was performed using outputs from Web TRAG IS, the webbased Graphical User Interface (GUI) for the TRAGIS code. The method behind the creation of thoseinputs is outlined in Calculation TXUT-001-ER-3.8-CALC-009.A possible transportation accident while transporting spent fuel could lead to a breach of the shippingcontainer and a release of nuclear materials. To calculate the source term inside of the container, thiscalculation used ORIGEN-ARP, Automatic Rapid Processing for Spent Fuel Depletion, Decay, andSource Term Analysis. ORIGEN-ARP is part of the SCALE package. A simulated US-APWR assemblywas irradiated and then decayed to determine the activity of the spent fuel 5 years after a burnup periodof 62 GWd/MTU. The results of this computation are in Appendix 1.Revision 1 of this calculation determines the heat load of one spent fuel shipping container so that acomparison can be made to the heat load presented in Table 8-4 of 10 CFR 52.51. In addition, thenumber of fuel assemblies per new fuel shipment changes from 28 to 12.
0CALC. NO.CPNPP Transportation AnalysisTXUT-001-ER-3.S-CALC-OOSREV. 1ENERCON SERVICES, INC.PAGE NO. Page 5 of232.0 Summary of Results and ConclusionsA transportation accident involving a spent fuel shipping container could lead to a release of nuclearmaterial. The total calculated RADTRAN population dose for such an accident is 4.64E-06 person-rem fora spent fuel cask shipping container containing a single assembly. For a container of four assemblies, thepayload evaluated herein, the population dose increases to 1.86E-05 person-rem.For incident-free transport of spent fuel, Table 2.1 describes the dose risk for various people affected bythe shipment of 1 spent fuel container by truck. The route taken starts at the CPNPP site and ends atYucca Mountain. The crew is defined by the 2 operators of the truck. On link is defined by people in carsin the general area of a spent fuel shipping truck as it approaches its destination. Off link is defined asresidents within 800 meters of a spent fuel shipping truck. Public - Around Truck Stop is defined aspeople that are around a truck when it experiences a planned stop. This analysis assumes eight 30minute stops on the trip from the CPNPP to Yucca Mountain.For incident-free transport of new fuel, Table 2.2 describes the dose risk for various people affected bythe shipment of 1 new fuel container by truck. The route taken starts at the San Diego port and ends atthe CPNPP site. Eight 30 minute stops were also assumed on the trip from San Diego to the CPNPP.Table 2.1Proposed Dose to Population as a Result of Incident-Freeshipment of 1 spent fuel container by truckType of PopulationCrewOn LinkOff LinkDose (person-rem)1.18E-015.43E-023.93E-03Table 2.2Public - AroundTruck Stop5.39E-01Proposed Dose to Population as a Result of Incident-Freeshipment of 1 new fuel container by truckType of PopulationCrewOn LinkOff LinkDose (person-rem)2.74E-036.05E-042.84E-05Public - AroundTruck Stop4.15E-03Based on the results presented above, the risks associated with the transport of new and spent nuclearfuel are small. The doses to individual members of the public are small because these population dosesapply to large populations of people.The US-APWR is expected to generate 15278 cubic feet of solid radioactive waste every year. Becausetrucks have the capacity of approximately 1000 cubic feet per shipment, this waste will less than 1 truckper day and the weight limit of these trucks containing radioactive waste will weigh result in less than33,100 kg (73,000 Ib) to comply with 10 CFR 51.52(a).From Appendix 1, the decay heat load of one spent fuel assembly is 1970 watts. Therefore, the totaldecay heat of one spent fuel container is 7880 watts (26,888 BTU/hr). This value is less than the limit of250,000 BTU/hr given in Table S-4 of 10 CFR 51.52. Detailed results are presented in Section 7.
f.!ItdCALC. NO.CPNPP Transportation AnalysisENERCON SERVICES, INC.TXUT-001-ER-3.8-CALC-OO8REV. 1PAGE NO. Page 6 of233.0 References3.1U.S. Department of Energy (DOE), 2002, "Final Environmental Impact Statement for a GeologicRepository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at YuccaMountain, Nye County, Nevada," DOE/EIS-0250, Office of Civilian Radioactive WasteManagement, Washington D.C.3.2Mitsubishi Heavy Industries, Ltd., "Design Control Document for the United States AdvancedPressurized Water Reactor," Revision 1.3.3National Nuclear Data Center, Brookhaven National Laboratory, "Chart of the Nuclides," www.nndc.bnl.gov/chart .3.4U.S. Department of Energy (DOE), 2002, "A Resource Handbook on DOE Transportation RiskAssessment," DOE/EM/NTP/HB-01, Washington, D.C.3.5U.S. Census Bureau, 2004, "U.S. Interim Projections by Age, Sex, Rate, and Hispanic Origin,"3/24/2008, http://www.census.gov/ipc/www/usinterimproj/ .3.6U.S. Environmental Protection Agency, Federal Guidance Report No. 11, "Limiting Values ofRadionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation,Submersion, and Ingestion," 3/24/2008, http://homer.ornl.govNLAB/FedGR11.html .3.7U.S. Environmental Protection Agency, Federal Guidance Report No. 12, "External Exposures toRadionuclides in Air; Water; and Soil," http://homer.ornl.govNLAB/FedGR12.html .3.8NUREG/CR-6672, "Reexamination of Spent Fuel Shipment Risk Estimates," Volume 1, March2000.3.9NUREG-1817, " Environmental Impact Statement for an Early Site Permit (ESP) at the GrandGulf ESP Site," Final Report, April 2006.3.10Hostick, C.J., J.C. Lavender, and B.H. Wakeman. 1992. Time/Motion Observations and DoseAnalysis of Reactor Loading, Transportation, and Dry Unloading of an Overweight Truck SpentFuel Shipment. PNL-7206, Pacific Northwest Laboratory, Richland, Washington.3.11Sandia National Laboratories, "RadCat 2.3 User Guide - A Graphical User Interface for theRADTRAN Code, Version 2.3," September, 2006 (Revised December 2007).3.12ENERCON Computer Program Certification: "RADTRAN 5.6 1 RadCat 2.3, Code Used forCalculating the Risks for Transporting Nuclear Material," 4/18/2008.3.13Calculation TXUT-001-ER-3.8-CALC-009, 'Transportation Routing," Revision O.3.14U.S. Bureau of Transportation Services, Table 2-17, "Motor Vehicle Safety Data," 3/24/2008, ion statistics/html/table 02 17.html .3.15SCALE: "A Modular Code System for Performing Standardized Computer Analyses for LicensingEvaluations, ORNLITM-2005/39, Version 5, Vols. I-III, April 2005. Available from Radiation SafetyInformation Computational Center at Oak Ridge National Laboratory as CCC-725.3.16Comanche Peak Nuclear Power Plant Units 3 & 4, COL Application, Part 3 Environmental Report,Revision O.
f!1til.;; CALC. NO.""CPNPP Transportation AnalysisENERCON SERVICES, INC.TXUT-001-ER-3. 8-CALC-008REV. 1PAGE NO. Page 7 of 234.0 Assumptions4.1Population densities acquired from TRAGIS are from the 2000 census. These values weremultiplied by 1.49 to scale these population densities for the year 2050, which is the last year thatthe census bureau projected population [Reference 3.5]. 1.49 was obtained by dividing theprojected United States population in 2050 by the total United States population in 2000.Basis: The earliest date that fuel could potentially be shipped is around 2021, which is 5 yearsafter the approximate startup date of 2016. Scaling populations to 2050 is conservative becausemore people will experience the effects of the transportation of spent fuel at later dates.4.2The spent fuel shipping container and truck is assumed to abide by DOT regulatory guidance in49 CFR 173.441 stating that the dose rate at 2 meters away from the container is 10 mrem/hr.For the purposes of this analysis, the dose rate that RADTRAN sets is 13 mrem at 1 meter awayfrom the container. Also, the dose rate to the drivers of the truck is assumed to be 2 mrem/hr toabide by regulations set forth in 49 CFR 173.441.Basis: The actual dose rates will be smaller than their maximum allowed values. Setting the doserates to the highest value possible will lead to more conservative population exposure.4.3In the event of an accident involving a spent fuel shipment,