11.0 PLANT SYSTEMS This Chapter Describes The Mixed

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11.0 PLANT SYSTEMSThis chapter describes the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF) plant andsystems, along with the design basis for each system. In addition, the chapter provides design,operational, and process flow information to support the hazard and accident analysis provided inChapter 5, as well as to assist in understanding the overall design and function of the MFFF plantand systems. Therefore, both non-principal and principal structures, systems, and components(SSCs) are discussed. Chapter 11 is divided into the following sections:"*"*"*"*"*"*"*"*"*"*"*"*Civil Structural Systems (Section 11.1)MOX Process Description (Section 11.2)Aqueous Polishing Process Description (Section 11.3)HVAC Systems and Confinement (Section 11.4)Electrical Systems (Section 11.5)Instrumentation and Control Systems (Section 11.6)Material-Handling Equipment (Section 11.7)Fluid Transport Systems (Section 11.8)Fluid Systems (Section 11.9)Heavy Lift Cranes (Section 11.10)Laboratory (Section 11.11)Seismic Qualification of Equipment, Systems, and Components (Section 11.12).The sections of this chapter are generally organized to include the following subsections:"Function - Provides the purpose and functional requirements for each system. Chapter 5provides the safety function of the principal SSCs associated with each system."* Description - Describes the system, including principal and non-principal SSCs."* Major Components - Provides a list and description of major components."* Control Concepts - Discusses how the system is controlled (i.e., automatically ormanually)."* System Interfaces - Lists the interfaces with other major systems."* Design Basis for Non-Principal SSCs - Includes a summary of the design basis for theSSCs associated with this system, including non-safety codes and standards applicable toits design. This information is provided to acquaint the reader generally with the designand is not intended to constitute a commitment with respect to the non-safety aspects orfunctions of the system."* Design Basis for Principal SSCs - Provides the safety basis for the principal SSCsassociated with this system and the function, requirement, applicable codes andstandards, and design values applied to the principal SSCs. Chapter 5 lists the principalSSCs associated with each system. The assurance measures applicable to the principalSSCs will be described in the Integrated Safety Analysis (ISA) Summary accompanyingthe license application for possession and use of special nuclear material (SNM).MFFF Construction Authorization RequestDocket No. 070-03098Revision: 10/31/02Page: 11.0-1

The majority of this chapter is provided for information to acquaint the reader generally with thedesign, the details of which are subject to change during detailed design. Where applicable, thesubsection entitled "Design Basis for Principal SSCs" constitutes the design basis for that systemassociated with the safety assessment discussed in Chapter 5. The systems' safety functions,system descriptions, and relationship to the safety assessment are described to the extentsupported by information available in the preliminary design. Modifications to the design andadditional features will be described in the ISA Summary.Table 11.0-1 lists the designations used to identify the various buildings and systems presentedin Chapter 11.MFFF Construction Authorization RequestDocket No. 070-03098Revision: 10/31/02Page: 11.0-2

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Table 11.0-1. Building and System DesignationsIBuilding SMFFF BuildingAqueous Polishing AreaEmergency Generator BuildingSafe Haven BuildingsSecured Warehouse BuildingStandby Generator BuildingMOX Fuel Fabrication AreaShipping and Receiving AreaReagent Processing BuildingAdministration BuildingTechnical Support BuildingIAqueous Polishing UnitsDecanning UnitMilling UnitRecanning UnitDissolution UnitDechlorination and Dissolution UnitPurification CycleSolvent Recovery CycleOxalic Precipitation and Oxidation UnitHomogenization UnitCanning UnitOxalic Mother Liquor Recovery UnitAcid Recovery UnitOffgas Treatment UnitKDAKDMKDRKDBKDDKPAKPBKCAKCBKCCKCDKPCKWGLiquid Waste Reception UnitKWDUranium Oxide Dissolution UnitSampling SystemMOX Processing Units - Receiving AreaU0 2 Receiving and Storage UnitU0 2 Drum Emptying UnitPuO 2 Receiving UnitPuO2 3013 Storage UnitPuO 2 Buffer Storage UnitMOX Processing Units - Powder AreaPuO2 Can Receiving and Emptying UnitPrimary Dosing UnitPrimary Blend Ball Milling UnitKDCFinal Dosing UnitNDSPowder Auxiliary UnitNXRMFFF Construction Authorization RequestDocket No. 070-03098IIIDRSDDPDCPDCMDCENDDNDPNBXIRevision: 10/31/02Page: 11.0-5

Table 11.0-1. Building and System DesignationsSystemDesignationScrap Processing UnitNCRJar Storage and Handling UnitNTMHomogenization and Pelletizing UnitsNPE, NPFScrap Ball Milling UnitNBYSintering UnitsPFE, PFFGrinding UnitsPRE, PRFQuality Control and Manual Sorting UnitPQEPellet Repackaging UnitPADScrap Box Loading UnitPARGreen Pellet Storage UnitPSESintered Pellet Storage UnitPSFScrap Pellet Storage UnitPSIGround and Sorted Pellet Storage UnitPSJPellet Handling UnitPMLPellet Inspection and Sorting UnitsPTEMOX Processing Units - Fuel Rod Process AreaRod Cladding and Decontamination UnitGME, FRod Tray Loading UnitGMKRod Decladding UnitGDEX-Ray Inspection UnitsSXE, SXFHelium Leak Test UnitSEKRod Inspection and Sorting UnitSDKRod Scanning UnitSCERod Storage UnitSTKMOX Processing Units - Assembly AreaAssembly Mockup Loading UnitTGMAssembling Mounting UnitTGVAssembly Handling and Storage UnitTASAssembly Dry Cleaning UnitTCKAssembly Dimensional Inspection UnitTCPAssembly Final Inspection UnitTCLAssembly Packaging UnitTXEMOX Processing Units - Waste Handling AreasFilter Dismantling UnitVDRMaintenance and Mechanical Dismantling UnitVDUWaste Storage UnitVDQWaste Nuclear Counting UnitVDTMechanical Utiliy SystemsHVAC Chilled Water SystemCHHProcess Chilled Water SystemCHPDemineralized Water SystemDMWProcess Hot Water SystemHWSMFFF Construction Authorization RequestDocket No. 070-03098Revision: 10/31/02Page: 11.0-6

ITable 11.0-1. Building and System DesignationsSystemProcess Steam and Process Condensate SystemsPlant Water SystemEmergency Generator Fuel Oil SystemStandby Generator Fuel Oil SystemService Air SystemInstrument Air SystemBreathing Air SystemRadiation Monitoring Vacuum SystemBulk Gas SystemsNitrogen SystemArgon/Hydrogen SystemHelium SystemOxygen SystemReagent SystemsNitric Acid SystemSilver Nitrate SystemTributyl Phosphate SystemHydroxylamine Nitrate SystemSodium Hydroxide SystemOxalic Acid SystemDiluent SystemSodium Carbonate SystemHydrogen Peroxide SystemHydrazine SystemManganese Nitrate SystemDecontamination SystemNitrogen Oxide SystemHVAC SYteemsVery High Depressurization Exhaust SystemHigh Depressurization Exhaust SystemMedium Depressurization Exhaust SystemProcess Cell Exhaust SystemMIFFF Construction Authorization RequestDocket No. 070-03098DesignationSPS and HROARDORSCRHPRHZRMNDCSGNOVHDHDEMDEPOERevision: 10/31/02Page: 11.0-7

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11.1.7.3Codes and Standards for SC-I StructuresCodes and standards applied to the MFFF include the following:American Concrete Institute (ACI)" ACI-224R-90, Control of Concrete Crackingin Concrete Structures"* ACI-301-99, StandardSpecificationsfor StructuralConcrete"* ACI-315-99, Detailsand Detailingof Concrete Reinforcement" ACI-336.2R-88, Suggested Analysis and Design ProceduresforCombined FootingsandMats" ACI-349-97, Code RequirementsforNuclearSafety-Related ConcreteStructures &Commentary" ACI-349.1R-91, Reinforced Concrete Designfor Thermal Effects on Nuclear PowerPlantStructures,Reapproved 1996" ACI-35 1.1R-99, Groutingfor Support ofEquipment & Machinery"* ACI-352R-91, Recommendationsfor Design ofBeam-Column Joints in MonolithicReinforced Concrete Structures,Reapproved 1997"* ACI-352.1R-89, RecommendationsforDesign of Slab-Column Connections inMonolithic Reinforced Concrete Structures, Reapproved 1997"* ACI-349-01,Appendix B, Anchoring to Concrete (for anchoring to concrete only)"* ACI-360R-92, Design of Slabs on Grade,Reapproved 1997" ACI-351.2R-94, Foundationsfor Static Equipment"* ACI-439.3R-91, Mechanical Connectionsof Reinforcing Bars"* ACI-SP-152-95, Design and Performanceof Mat FoundationsMFFF Construction Authorization RequestDocket No. 070-03098Revision: 10/31/02Page: 11.1-11

"* ACI-503R-93, Use of Epoxy Compounds with Concrete"* ACI-442-88, Response of ConcreteBuildings to Lateral Forces"ACI-207.1R-96, Mass Concrete"ACI-207.2R-95, Effect of Restraint, Volume Change, and Reinforcement on Cracking ofMass Concrete"* ACI-207.4R-93, Cooling and InsulatingSystems for Mass Concrete.American Institute of Steel Construction (AISC) AISC ASD, Manual of Steel Construction,Allowable Stress Design, 9th Edition, 1989*ANSI/AISC N690-1994, Specificationfor the Design, Fabrication,and Erection of SteelSafety-Related Structuresfor Nuclear Facilities* AISC, Seismic Provisionsfor StructuralSteel Buildings, April 1997.American Society of Civil Engineers (ASCE)*ASCE Standard 4-98, Seismic Analysis of Safety RelatedNuclear Structures* ASCE Standard 7-98, Minimum DesignLoadsfor Buildings and Other Structures*ASCE Standard 8-91, Specificationforthe Design of n Welding Society (AWS)"* AWS-D1.1-98, StructuralWelding Code- Steel, 1998"* NCIG-01, Visual Weld Acceptance Criteriafor Structural Welding of Nuclear PowerPlants,Revision 2, EPRI NP-5380.American Association of State Highway and Transportation Officials (AASHTO)*StandardSpecificationsfor Highway Bridges, Sixteenth Edition, 1996.American National Standards Institute (ANSI) ANSI N101.4, QualityAssurancefor Protective CoatingsApplied to Nuclear Facilities,1972.American Iron and Steel Institute (AISI)*AISI, Specificationsfor the Design of Cold-Formed Steel StructuralMembers, 1986.MFFF Construction Authorization RequestDocket No. 070-03098Revision: 10/31/02Page: 11.1-12

American Society for Testing and Materials (ASTM)*Research Council on Structural Connections, Specificationfor StructuralJoints UsingASTM A325 and A490 Bolts, June 23, 2000.Code of Federal Regulations (CFR)*10 CFR Part 70, Domestic Licensing of Special NuclearMaterial*10 CFR Part 73, Physical Protectionof Plantsand Materials.SRS Engineering Standards Manual (WSRC-TM-95-1)"* Engineering Standard No. 01060, StructuralDesign Criteria,Revision 4, datedSeptember 1999"* Engineering Standard No. 01110, Civil Site Design Criteria,Revision 3, dated April 11,2000.US. Nuclear Regulatory Commission (NUREG)"* NUREG-0800, Standard Review Plan 3.5.3, BarrierDesign Procedures,July 1981"* NUREG-0800, Standard Review Plan 3.8.4, OtherSeismic Categoryl Structures,July1981"* NUREG-0800, Standard Review Plan 3.5.1.6, AircraftHazards,April 1996.MFFF Construction Authorization RequestDocket No. 070-03098Revision: 10/31/02Page: 11.1-13I

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Table 11.1-2. Summary of MFFF Site Design CriteriaCriterionSevere Wind(SC-I and SC-II)Extreme Wind/Tornado(Wind Loads)(SC-I)Tornado MissileSpectrum(SC-I)ValueThree-second wind speed: 130 mphMissile criteria: 2- by 4-inch timber plank, 15 lb at 50 mph (horizontal); max. height50 ft (see Note 1)Three-second wind speed: 240 mphAtmospheric pressure change: 150 psf at 55 psf/secRate of pressure drop: 55 psf/secI2- by 4-inch timber plankMass: 15 lbHorizontal Impact Speed: 150 mphVertical Impact Speed: 100 mphMaximum Height: 200 ft3-inch diameter standard steel pipeMass: 75 lbHorizontal impact speed: 75 mphVertical impact speed: 50 mphMaximum height: 100 ft3000-lb automobileHorizontal impact speed: 25 mph, rolls and tumbleWind (CS)Basic winds: 107 mph (Note 1)FloodsDesign flood level (DFL)above MSL: 207.9 ftProbable maximum flood level (PMF) above MSL: 224.5 ftSite grade level - 272 ft above mslAccumulative precipitation:Precipitation(SC-I)Snow and Ice Loads(SC-I)Seismic (Ground Motion)(SC-I and SC-U)Foundation DesignFifteen minutes: 3.9 inchesOne hour. 7.4 inchesThree hours: 14.1 inchesSix hours: 16.7 inchesTwenty-four hours: 22.7 inchesSnow/ice loading: 10 lb/ft2Exposure factor: 1.0Snow drift is considered in the designFor SC-I and SC-I , Importance factor 1.2Regulatory Guide 1.60 scaled to 0.20g peak ground acceleration(see Section 11.1.7.2.2.3)Bearing PressureGroundwaterExplosionsAircraft ImpactMaximum groundwater elevation above msl: 210.0 ft.(see Section 11.1.7.4.1.3)(Not a design basis event, see Section 11.1.7.4.1.3)Range Fires(Not a design basis event, see Section 11.1.7.4.1.3)Note 1: For determining wind loads using the ASCE 7-98 procedure, the following definitions apply: I 1.15 (SC-Iand SC-il), I 1.0 (CS); Exposure Category C; K, 1.0; and Kd 1.0.MFFF Construction Authorization RequestDocket No. 070-03098Revision: 10/31/02Page: 11.1-30I

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11.2 MOX PROCESS DESCRIPTIONThis section provides a description and overview of the MOX Process (MP), including design,operational, and process flow information. This information is provided to support the hazardand accident analysis provided in Chapter 5, as well as to assist in understanding the overalldesign and function of the MOX Process.11.2.1 FunctionThe MP Area receives polished PuO2 from the aqueous polishing (AP) process, U0 2 depleted in235U, and the required components for assembling light-water reactor (LWR) MOX fuelassemblies. The process mixes the plutonium and uranium oxides to form MOX fuel pellets.The pellets are loaded into fuel rods, which are then assembled into MOX fuel assemblies for usein commercial reactors. The MP Area is designed to process up to 70 MtHM annually. Thesafety functions of the principal SSCs associated with the MP process are discussed in Chapter 5.11.2.2 DescriptionThe MFFF uses the A-MLMAS process for the manufacture of MOX fuel assemblies.A-MIMAS (advanced MIMAS) represents the latest evolution of the successive MIMAASfabrication processes adopted by BELGONUCLEAIRE and COGEMA to produce MOX fuelpellets. A-MIMAS uses a two-step mixing process. In the first step, the PuO2 powder is mixedwith depleted U0 2 and recycled scrap powder to form a primary blend (master blend) with anominal PuO2 content of 20% of the total mass. This mix is then micronized. In the second step,the primary blend is forced through a sieve and poured into ajar and mixed with depleted U0 2and scrap powder to obtain the final blend with the specified plutonium content. The nominalPuO2 content in th

American Concrete Institute (ACI) " ACI-224R-90, Control of Concrete Cracking in Concrete Structures "* ACI-301-99, Standard Specifications for Structural Concrete "* ACI-315-99, Details and Detailing of Concrete Reinforcement " ACI-336.2R-88, Suggested Ana

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