ML15251A384
| ML15251A384 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 08/31/2015 |
| From: | AREVA |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML15251A394 | List:
|
| References | |
| RS-15-237 NP-3305NP, Rev 1 | |
| Download: ML15251A384 (50) | |
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{{#Wiki_filter:Attachment 9Mechanical Design Report(Non-Proprietary Version) Controlled DocumentARE VAMechanical Design Report for QuadCities and Dresden ATRIUM 10XM FuelAssembliesLicensing ReportAugust 2015AREVA Inc.AN P-3305N PRevision 1(c) 2015 AREVA Inc. Contrailed DocumentAN P-3305N PRevision 1Copyright © 2015AREVA Inc.All Rights Reserved Co~ntroI~ed Doc umentAREVA Inc. ANP-3305NPRevision IMechanical Design Report for Quad Cities and Dresden ATRIUM I1OXM Fuel AssembliesLicensingq Report PaqeiNature of ChangesRevision Section(s)Item Number or Page(s) Description and Justification1. 0 All This is a new document.2. 1As Changes to this revision are editorial only; thereindicated are no content changes to the document.Revised document to adjust proprietarybracketing. Changes made to reassessproprietary content and address consistencybetween sections per Condition Report2015-5753.Proprietary bracketing was updated in thefollowing sections: 1.0, 2.2, 2.2.1, 2.2.3, 3.3.3,3.3.5, 3.3.6, 3.3.8, 3.4.4, 3.5.1, 4.3, 4.4., 4.5, .4.7,4.8.Proprietary bracketing was updated in Table 3-1and Table 3-2 in the following Criteria Sections:3.3.1, 3.3.3, 3.3.5, 3.3.8, 3.3.9, 3.4.4, 3.5.1, 3.5.2. AREVA Inc. ANP-3305NPRevision 1Mechanical Design Report for Quad Cities and Dresden ATRIUM 10XM Fuel AssembliesLicensingq Report Pacqe iiContentsPacie
1.0 INTRODUCTION
.......................................................................I2.0 DESIGN DESCRIPTION .............................................................. 22.1 Overview ........................................................................ 22.2 Fuel Assembly .................................................................. 22.2.1 Spacer Grid.............................................................. 32.2.2 Water Channel.......................................................... 32.2.3 LowerTie Plate ......................................................... 42.2.4 Upper Tie Plate and Connecting Hardware........................... 52.2.5 Fuel Rods................................................................ 52.3 Fuel Channel and Components ............................................... 73.0 FUEL DESIGN EVALUATION ........................................................ 103.1 Objectives ..................................................................... 103.2 Fuel Rod Evaluation .......................................................... 113.3 Fuel System Evaluation ...................................................... 113.3.1 Stress, Strain, or Loading Limits on AssemblyComponents ........................................................... 113.3.2 Fatigue ................................................................. 123.3.3 Fretting Wear .......................................................... 133.3.4 Oxidation, Hydriding, and Crud Buildup ............................. 133.3.5 Rod Bow ............................................................... 143.3.6 Axial Irradiation Growth ............................................... 143.3.7 Rod Internal Pressure................................................. 153.3.8 Assembly Lift-off....................................................... 153.3.9 Fuel Assembly Handling.............................................. 163.3.10 Miscellaneous Component Criteria .................................. 173.4 Fuel Coolability................................................................ 183.4.1 Cladding Embrittlement ............................................... 183.4.2 Violent Expulsion of Fuel.............................................. 183.4.3 Fuel Ballooning........................................................ 183.4.4 Structural Deformations............................................... 183.5 Fuel Channel and Fastener .................................................. 203.5.1 Design Criteria for Normal Operation ................................ 203.5.2 Design Criteria for Accident Conditions.............................. 224.0 MECHANICAL TESTING ............................................................ 294.1 Fuel Assembly Axial Load Test .............................................. 30 Con trolled DocumentAREVA Inc. ANP-3305NPRevision 1Mechanical Design Report for Quad Cities and Dresden ATRIUM 1OXM Fuel AssembliesLicensinci Report Paaqe iii4.2 Spacer Grid Lateral Impact Strength Test................................... 304.3 Tie Plate Strength Tests ....................................................... 314.4 Debris Filter Efficiency Test...... ............................................. 324.5 Fuel Assembly Fretting Test.................................................. 324.6 Fuel Assembly Static Lateral Deflection Test ............................... 334.7 Fuel Assembly Lateral Vibration Tests ...................................... 334.8 Fuel Assembly Impact Tests ................................................. 3
45.0 CONCLUSION
........................................................................ 3
46.0 REFERENCES
........................................................................ 35APPENDIX A ILLUSTRATIONS............................................................. 36TablesTable 2-1 Fuel Assembly and Component Description..................................... 8Table 2-2 Fuel Channel and Fastener Description ................:......................... 9Table 3-1 Results for ATRIUM IOXM Fuel Assembly ..................................... 23Table 3-1 Results for ATRIUM 1OXM Fuel Assembly (Continued) ........................ 24Table 3-2 Results for Advanced Fuel Channel ............................................ 26Table 3-2 Results for Advanced Fuel Channel (Continued)............................... 27Table 3-3 "Results for Channel Fastener ................................................... 28Figure A-IFigure A-2Figure A-3Figure A-4Figure A-5Figure A-6Figure A-7FiguresATRIUM 10XM Fuel Assembly................................................. 37UTP with Locking Hardware.................................................... 38Improved FUELGUARD LTP................................................... 39ATRIUM 10XM ULTRAFLOW Spacer Grid ................................... 40Full and Part-Length Fuel Rods................................................ 41Advanced Fuel Channel........................................................ 42Fuel Channel Fastener Assembly.............................................. 43This document contains a total of 49 pages. ,AREVA Inc. ANP-3305NPRevision IMechanical Design Report for Quad Cities and Dresden ATRIUM 10OXM Fuel AssembliesLicensingq Report Paoqe ivNomenclatureAcronym DefinitionAFC Advanced fuel channelAOO Anticipated operational occu'rrencesASME American Society of Mechanical EngineersB&PV Boiler and pressure vesselBWR Boiling water reactorCRDA Control rod drop accidentEOL End of lifeLOCA Loss-of-coolant accidentLTP Lower tie plateMWd/kgU Megawatt-days per kilogram of UraniumNRC U. S. Nuclear Regulatory CommissionPLFR Part-length fuel rodspsi Pounds per square inchSm Design stress intensitySRA Stress relief annealedSRP Standard review planS,, Ultimate stressSy Yield stressUTP Upper tie plate Contoile Docum entAREVA Inc. ANP-3305NPRevision 1Mechanical Design Report for Quad Cities and Dresden ATRIUM 10XM Fuel AssembliesLicensingq Report Paaqe I
1.0 INTRODUCTION
This report provides a design description, mechanical design criteria, fuel structuralanalysis results, and test results for the ATRIUM TM* 10OXM fuel assembly and 100/75Advanced Fuel Channel (AFC) designs supplied by AREVA Inc. (AREVA) for use at theQuad Cities and Dresden nuclear generating plants beginning with Quad Cities Unit 2Cycle 24 and Dresden Unit 3 Cycle 25.The scope of this report is limited to an evaluation of the structural design of the fuelassembly and fuel channel. The fuel assembly structural design evaluation is not cycle-specific so this report is intended to be referenced for each cycle where the fuel designis in use. Minor changes to the fuel design and cycle-specific input parameters will bedispositioned for future reloads. AREVA will confirm the continued applicability of thisreport prior to delivery of each subsequent reload of ATRIUM 10XM fuel at Quad Citiesand Dresden in a cycle specific compliance document.The fuel assembly design was evaluated according to the AREVA boiling water reactor(BWR) generic mechanical design criteria (Reference 1). The fuel channel design wasevaluated to the criteria given in fuel channel topical report (Reference 2). The genericdesign criteria have been approved by the U.S. Nuclear Regulatory Commission (NRC)and the criteria are applicable to the subject fuel assembly and channel design.Mechanical analyses have been performed using NRC-approved design analysismethodology (References 1, 2, 3 and 4). The methodology permits maximum licensedassembly and fuel channel exposures of [ ] (Reference 3).* ATRIUM is a trademark of AREVA Inc.AREVA Inc. Controiled DocurmentAREVA Inc.Mechanical Design Report for Quad Cities and Dresden ATRIUM 10OXM Fuel AssembliesLicensina ReDortANP-3305NPRevision 1Paie 22.0DESIGN DESCRIPTIONThis report documents the structural evaluation of the ATRIUM I10XM fuel assembly andfuel channel described below. Reload-specific design information is available in thedesign package provided by AREVA for each reload delivery.2.1OverviewThis ATRIUM 10OXM fuel bundle geometry consists of a 1Oxi0 fuel lattice with a squareinternal water channel that displaces a 3x3 array of rods.Table 2-1 lists the key design parameters of the ATRIUM 10XM fuel assembly.2.2Fuel AssemblyThe ATRIUM 10OXM fuel assembly consists of a lower tie plate (LTP) and upper tie plate(UTP), 91 fuel rods, [ ] spacer grids, a central water channel with[] and miscellaneous assembly hardware. Of the 91 fuel rods,[ ] are PLFRs. The structural members of the fuel assembly include the tieplates, spacer grids, water channel, and connecting hardware. [].The fuel assembly is accompanied by a fuel channel, as described later in this section.Table 2-1 lists the main fuel assembly attributes, and an illustration of the fuel bundleassembly is provided in the appendix.AREVA Inc. Conroled~ D~Joc~ument IAREVA Inc.ANP-3305NPRevision 1Paae 3Mechanical Design Report for Quad Cities and Dresden ATRIUM 10XM Fuel AssembliesLicensina Reoort2.2.1 Spacer GridThe spacer grid is a [] version of the ULTRAFLOWTMt design. [ITable 2-1 lists the main spacer grid attributes, and an illustration of the spacer grid isprovided in the appendix.2.2.2 Water ChannelItULTRAFLOW is a trademark of AREVA Inc.AREVA inc. Controlled DocumentYAREVA Inc.Mechanical Design Report for Quad Cities and Dresden ATRIUM 1OXM Fuel AssembliesLicensinal ReportANP-3305NPRevision 1Paaqe 4I I I q q]Table 2-1 lists the main water channel attributes and the appendix provides anillustration of a section of the water channel.2.2.3 Lower Tie PlateThe diffuser box of the LTP [Appendix A provides an illustration of the LTP.*FUELGUARD is a trademark of AREVA Inc.AREVA Inc. ConroKe DocumentAREVA Inc.Mechanical Design Report for Quad Cities and Dresden ATRIUM 1OXM Fuel AssembliesI ir'ien.ina1 RenortANP-3305NPRevision 12.2.4[Upper Tie Plate and Connecting HardwareAppendix A provides an illustration of the UTP and locking components.2.2.5 Fuel Rods]AREVA Inc. AREVA Inc.Mechanical Design Report for Quad Cities and Dresden ATRIUM 10XM Fuel AssembliesLicensina ReportANP-3305NPRevision IPaae 6.......... ,7 ----r -- --[Table 2-1 lists the main fuel rod attributes, and the appendix provides an illustration ofthe full length and part length fuel rods.AREVA Inc. Cotole ocmnAREVA Inc.Mechanical Design Report for Quad Cities and Dresden ATRIUM 10XM Fuel AssembliesI icn! RenortANP-3305NPRevision 1Paae 7.......... ,"1 ' " --- -' --2.3Fuel Channel and Components[*Table 2-2 lists the fuel channel component attributes. The fuel channel and fuelchannel fastener are depicted in the appendix.AREVA Inc. Conroliled Documen~ntAREVA Inc.ANP-3305NPRevision 1Paae 8Mechanical Design Report for Quad Cities and Dresden ATRIUM 10OXM Fuel AssembliesLicensina Renort.......... 17 ----r- --.. iTable 2-1 Fuel Assembly and Component DescriptionAREVA Inc. Controfled DocumentAREVA Inc. ANP-3305NPRevision 1Mechanical Design Report for Quad Cities and Dresden ATRIUM 10XM Fuel AssembliesLicensingq Report Paqie 9Table 2-2 Fuel Channel and Fastener DescriptionAREVA Inc. C'ontroiied Documen.rtAREVA Inc. ANP-3305NPRevision 1Mechanical Design Report for Quad Cities and Dresden ATRIUM 10XM Fuel AssembliesLicensingq Report Paqe 103.0 FUEL DESIGN EVALUATIONA summary of the mechanical methodology and results from the structural designevaluations is provided in this section. Results from the mechanical design evaluationdemonstrate that the design satisfies the mechanical criteria to the analyzed exposurelimit.3.1 ObjectivesThe objectives of designing fuel assemblies (systems) to specific criteria are to provideassurance that:* The fuel assembly (system) shall not fail as a result of normal operation andanticipated operational occurrences (AOOs). The fuel assembly (system)dimensions shall be designed to remain within operational tolerances, and thefunctional capabilities of the fuels shall be established to either meet or exceedthose assumed in the safety analysis.*Fuel assembly (system) damage shall never prevent control rod insertion when it isrequired.*The number of fuel rod failures shall be conservatively estimated for postulatedaccidents.* Fuel coolability shall always be maintained.* The mechanical design of fuel assemblies shall be compatible with co-resident fueland the reactor core internals.* Fuel assemblies shall be designed to withstand the loads from handling andshipping.AREVA Inc. CotrlldDoum nAREVA Inc. ANP-3305NPRevision 1Mechanical Design Report for Quad Cities and Dresden ATRIUM 10XM Fuel AssembliesLicensinq Report Paqe 11The first four objectives are those cited in the Standard Review Plan (SRP). The lattertwo objectives are to assure the structural integrity of the fuel and the compatibility withthe existing reload fuel. To satisfy these objectives, the criteria are applied to the fuelrod and the fuel assembly (system) designs. Specific component criteria are alsonecessary to assure compliance. The criteria established to meet these objectivesinclude those given in Chapter 4.2 of the SRP.3.2 Fuel Rod EvaluationThe mechanical design report documents the fuel structural analyses only. The fuel rodevaluation will be documented in Quad Cities and Dresden plant specific fuel rodthermal-mechanical report.3.3 Fuel System EvaluationThe detailed fuel system design evaluation is performed to ensure the structuralintegrity of the design under normal operation, AQO, faulted conditions, handlingoperations, and shipping. The analysis methods are based on fundamental mechanicalengineering techniques--often employing finite element analysis, prototype testing, andcorrelations based on in-reactor performance data. Summaries of the majorassessment topics are described in the sections that follow.3.3.1 Stress, Strain, or Loading Limits on Assembly ComponentsThe structural integrity of the fuel assemblies is assured by setting design limits onstresses and deformations due to various handling, operational, and accident or faultedloads. AREVA uses Section III of the ASME B&PV Code as a guide to establishacceptable stress, deformation, and load limits for standard assembly components.These limits are applied to the design and evaluation of the UTP, LTP, spacer grids,springs, and load chain components, as applicable. The fuel assembly structuralcomponent criteria under faulted conditions are based on Appendix F of the ASMEB&PV Code Section III with some criteria derived from component tests.AREVA Inc. Co.ntroiied DocumentAREVA Inc. ANP-3305NPRevision 1Mechanical Design Report for Quad Cities and Dresden ATRIUM 10OXM Fuel AssembliesLicensinoq Report Paqie 12All significant loads experienced during normal operation, AOOs, and under faultedconditions are evaluated to confirm the structural integrity of the fuel assemblycomponents. Outside of faulted conditions, most structural components are under themost limiting loading conditions during fuel handling. See Section 3.3.9 for a discussionof fuel handling loads and Section 3.4.4 for the structural evaluation of faultedconditions. Although normal operation and AOO loads are often not limiting forstructural components, a stress evaluation may be performed to confirm the designmargin and to establish a baseline for adding accident loads. The stress calculationsuse conventional, open-literature equations. A general-purpose, finite element stressanalysis code, such as ANSYS, may be used to calculate component stresses.[See Table 3-1 for results from the component strength evaluations.3.3.2 FatigueFatigue of structural components is generally []1.AREVA Inc. ControIled DocumentAREVA Inc.Mechanical Design Report for Quad Cities and Dresden ATRIUM 1OXM Fuel AssembliesI iC~fn5inlf RP.nnrtANP-3305NPRevision 1Paae 133.3.3 Fretting WearFuel rod failures due to grid-to-rod fretting shall not occur.Fretting wear is evaluated by testing, as described in Section 4.5. The testing isconducted by [] .The inspection measurements for wearare documented. [1 and has operated successfullywithout incidence of grid-to-rod fretting in more than 20,000 fuel assemblies.3.3.4 Oxidation, Hydriding, and Crud BuildupBecause of the low amount of corrosion on fuel assembly structural components,1°AREVA Inc. Controlled1 DocumentAREVA Inc.Mechanicai Design Report for Quad Cities and Dresden ATRIUM 10XM Fuel AssembliesLicensina ReoortANP-3305NPRevision 1P~aa 143.3.5 Rod BowDifferential expansion between the fuel rods and cage structure, and lateral thermal andflux gradients can lead to lateral creep bow of the rods in the spans between spacergrids. This lateral creep bow alters the pitch between the rods and may affect thepeaking and local heat transfer. The AREVA design criterion for fuel rod bowing is that[Rod bow is calculated using the approved model described in Reference 4. [J .The predicted rod-to-rod gap closure due to bow is assessed for impact onthermal margins.3.3.6 Axial Irradiation GrowthFuel assembly components, including the fuel channel, shall maintain clearances andengagements, as appropriate, throughout the design life. Three specific growthcalculations are considered for the ATRIUM I0XM design:* Minimum fuel rod clearance between the LTP and UTP* Minimum engagement of the fuel channel with the LTP seal spring* External interfaces (e.g., channel fastener springs)AREVA Inc. Co~ntrolled Doc;umentAREVA Inc. ANP-3305NPRevision 1Mechanical Design Report for Quad Cities and Dresden ATRIUM 10OXM Fuel AssembliesLicensingq Report Paqe 15Rod growth, assembly growth, and fuel channel growth are calculated using correlationsderived from post-irradiation data. The evaluation of initial engagements andclearances accounts for the combination of fabrication tolerances on individualcomponent dimensions.The SRA fuel rod growth correlation was established from [] .Assembly growth is dictatedby the water channel growth. The growth of the water channel and the fuel channel isbased on [J1. These data and the resulting growthcorrelations are described in Reference 3. The upper and lower [1,as appropriate, are used to obtain EOL growth values.The minimum EOL rod growth clearance and EOL fuel channel engagement with theseal spring are listed in Table 3-1. The channel fastener spring axial compatibility isreported in Table 3-3.3.3.7 Rod Internal PressureThis will be addressed in the Quad Cities and Dresden fuel rod thermal-mechanicalreports.3.3.8 Assembly Lift-offFuel assembly lift-off is evaluated under both normal operating conditions (includingAQOs) and under faulted conditions. The fuel shall not levitate under normal operatingor AQO conditions. Under postulated accident conditions, the fuel shall not becomedisengaged from the fuel support. These criteria assure control blade insertion is notimpaired.AREVA Inc. AREVA Inc. ANP-3305NPRevision 1Mechanical Design Report for Quad Cities and Dresden ATRIUM I0XM Fuel AssembliesLicensingq Report Panqe 16For normal operating conditions, the net axial force acting on the fuel assembly iscalculated by adding the loads from gravity, hydraulic resistance from coolant flow,difference in fluid flow entrance and exit momentum, and buoyancy. The calculated netforce is confirmed to be in the downward direction, indicating no assembly lift-off.Maximum hot channel conditions are used in the calculation because the greater two-phase flow losses produce a higher uplift force.Mixed core conditions for assembly lift-off are considered on a cycle-specific basis, asdetermined by the plant and other fuel types. Analyses to date indicate a large marginto assembly lift-off under normal operating conditions. Therefore, fuel lift-off in BWRsunder normal operating conditions is considered to be a small concern.For faulted conditions, the ATRIUM 1OXM design was evaluated for fuel lift considering[] .The fuel will not lift and it will not becomedisengaged from the fuel support. The uplift is limited to be less than the axialengagement such that the fuel assembly neither becomes laterally displaced nor blocksinsertion of the control blade.3.3.9 Fuel Assembly HandlingThe fuel assembly shall withstand, without permanent deformation, all normal axialloads from shipping and fuel handling operations. Analysis or testing shall show thatthe fuel is capable of [AREVA Inc. Co ntroiied~ DocumentAREVA Inc. ANP-3305NP-.. Revision 1Mechanical Design Report for Quad Cities and Dresden ATRIUM 10OXM Fuel AssembliesLicensincq Report Pa~qe 17The fuel assembly structural components are assessed for axial fuel handling loads bytesting. To demonstrate compliance with the criteria, the test is performed by loading atest assembly to an axial tensile force greater than [I .An acceptable test shows no yielding after loading. The testing isdescribed further in Section 4.1.There are also handling requirements for the fuel rod plenum spring which areaddressed in the Quad Cities and Dresden fuel rod thermal-mechanical reports.3.3.10 Miscellaneous Component Criteria3.3.10.1 Compression Spring ForcesThe ATRIUM 10XM has a single large compression spring mounted on the centralwater channel. The compression spring serves the same function as previous designsby providing support for the UTP and fuel channel. The spring force is calculated basedon the deflection and specified spring force requirements. Irradiation-induced relaxationis taken into account for EOL conditions. The minimum compression spring force atEOL is shown to be greater than the combined weight of the UTP and fuel channel(including channel fastener hardware). Since the compression spring does not interactwith the fuel rods, no consideration is required for fuel rod buckling loads.3.3.10.2 LTP Seal SpringThe LTP seal spring shall limit the bypass coolant leakage rate between the LTP andfuel channel. The seal spring shall accommodate expected channel deformation whileremaining in contact with the fuel channel. Also, the seal spring shall have adequatecorrosion resistance and be able to withstand the operating stresses without yielding.AREVA Inc. ContrlAed DocumentAREVA Inc. ANP-3305NPRevision 1Mechanical Design Report for Quad Cities and Dresden ATRIUM IOXM Fuel AssembliesLicensinci Report Paaqe 18Flow testing is used to confirm acceptable bypass flow characteristics. The seal springis designed with adequate deflection to accommodate the maximum expected channelbulge while maintaining acceptable bypass flow. [ J is selected asthe material because of its high strength at elevated temperature and its excellentcorrosion resistance. Seal spring stresses are analyzed using a finite element method.3.4 Fuel CoolabilityFor accidents in which severe fuel damage might occur, core coolability and thecapability to insert control blades are essential. Chapter 4.2 of the SRP providesseveral specific areas important to fuel coolability, as discussed below.3.4.1 Cladding EmbrittlementThe LOCA evaluation is addressed in the Quad Cities and Dresden LOCA MAPLHGRanalysis for ATRIUM 10XM fuel reports.3.4.2 Violent Expulsion of FuelResults for the CRDA analysis are presented in the Quad Cities and Dresden ATRIUM10OXM fuel transition report and the subsequent cycle-specific reload licensing reports.3.4.3 Fuel BallooningThe LOCA evaluation is addressed in the Quad Cities and Dresden LOCA MAPLHGRanalysis for ATRIUM 10XM fuel reports.3.4.4 Structural DeformationsDeformations or stresses from postulated accidents are limited according torequirements contained in the ASME B&PV Code, Section III, Division 1, Appendix F,and SRP Section 4.2, Appendix A. The limits for each ATRIUM 10OXM structuralcomponent are derived from analyses and/or component load tests.AREVA Inc. Controile:d DcumecntAREVA Inc. ANP-3305NPRevision 1Mechanical Design Report for Quad Cities and Dresden ATRIUM 10OXM Fuel AssembliesLicensin~q Report Paaqe 19Testing is performed to obtain the dynamic characteristics of the fuel assembly andspacer grids. The stiffness, natural frequencies and damping values derived from thetests are used as inputs for analytical models of the fuel assembly and fuel channel.Fuel assemblies are tested with and without a fuel channel. In addition, the analyticalmodels are compared to the test results to ensure an accurate characterization of thefuel. In general, the testing and analyses have shown the dynamic response of theATRIUM 10XM design to be very similar to [] .See Section 4.0 for descriptions of the testing.The methodology for analyzing the channeled fuel assembly under the influence ofaccident loads is described in Reference 2. Evaluations performed for the fuel underaccident loadings include mechanical fracturing of the fuel rod cladding, assemblystructural integrity, and fuel assembly liftoff.The ATRIUM 10XM design was analyzed [].Tables 3-1and 3-2 list the minimum design margins for the fuel assembly structural componentsand fuel channel.Assembly liftoff under accident conditions is described in Section 3.3.8.AREVA Inc. Controlled DocumentAREVA Inc. ANP-3305NPRevision 1Mechanical Design Report for Quad Cities and Dresden ATRIUM 10XM Fuel AssembliesLicensingq Report Paqe 203.4.4.1 Fuel Storage Seismic QualificationThe New and Spent Fuel Storage Racks analysis accounts for the fuel as added massin calculating the structural integrity under postulated seismic loads. The weights oflegacy fuel assembly designs at Quad Cities and Dresden encompass the weight of theATRIUM 10XM fuel design. Therefore, the fuel storage racks remain qualified with theintroduction of the ATRIUM 10XM fuel design.3.5 Fuel Channel and FastenerThe fuel channel and fastener design criteria are summarized below, and evaluationresults are summarized in Table 3-2 and Table 3-3. The analysis methods aredescribed in detail in Reference 2.3.5.1 Design Criteria for Normal OperationSteady-State Stress Limits. The stress limits during normal operation are obtainedfrom the ASME B&PV Code, Section III, Division 1, Subsection NG for Service Level A.The calculated stress intensities are due to the differential pressure across the channelwall. The pressure loading includes the normal operating pressure plus the increaseduring AQO. The unirradiated properties of the fuel channel material are used since theyield and ultimate tensile strength increase during irradiation (Reference 8).As an alternative to the elastic analysis stress intensity limits, a plastic analysis may beperformed as permitted by paragraph NB-3228.3 of the ASME B&PV Code.In the case of AOOs, the amount of bulging is limited to that value which will permitcontrol blade movement. During normal operation, any significant permanentdeformation due to yielding is precluded by restricting the maximum stresses at theinner and outer faces of the channel to be less than the yield strength.AREVA Inc. AREVA Inc. ANP-3305NPRevision 1Mechanical Design Report for Quad Cities and Dresden ATRIUM 10OXM Fuel AssembliesLicensingq Report Paqe 21Fuel Channel Fatigue. Cyclic changes in power and flow during operation impose aduty loading on the fuel channel. [1.Corrosion and Hydrogen Concentration. Corrosion reduces the material thicknessand results in less load-carrying capacity. The fuel channels have thicker walls thanother components (e.g., fuel rods), and the normal amounts of oxidation and hydrogenpickup are not limiting provided: the alloy composition and impurity limits are carefullyselected; the heat treatments are also carefully chosen; and the water chemistry iscontrolled. []1Long-Term Creep Deformation. Changes to the geometry of the fuel channel occurdue to creep deformation during the long term exposure in the reactor coreenvironment. Overall deformation of the fuel channel occurs from a combination ofbulging and bowing. Bulging of the side walls occurs because of the differentialpressure across the wall. Lateral bowing of the channel is caused primarily from theneutron flux and thermal gradients. Too much deflection may prevent normal controlblade maneuvers and it may increase control blade insertion time above the TechnicalSpecification limits. The total channel deformation must not stop free movement of thecontrol blade.AREVA Inc. Controlled Dcm nAREVA Inc. ANP-3305NPRevision 1Mechanical Design Report for Quad Cities and Dresden ATRIUM 10XM Fuel AssembliesLicensinoq Report Paaqe 223.5.2 Design Criteria for Accident ConditionsFuel Channel Stresses and Limit Load. The criteria are based on the ASME B&PVCode, Section III, Appendix F, for faulted conditions (Service Level 0). Componentsupport criteria for elastic system analysis are used as defined in paragraphs F-I1332.1and F-1332.2. The unirradiated properties of the fuel channel material are used sincethe yield and ultimate tensile strength increase during irradiation.Stresses are alternatively addressed by the plastic analysis collapse load criteria givenin paragraph F-i1332.2(b). For the plastic analysis collapse load, the permanentdeformation is limited to twice the deformation the structure would undergo had thebehavior been entirely elastic.The amount of bulging remains limited to that value which will permit control bladeinsertion.Fuel Channel Gusset Load Rating. [AREVA Inc. AREVA Inc.Mechanical Design Report for Quad Cities and Dresden ATRIUM 10XM Fuel AssembliesLicensing ReportANP-3305NPRevision 1Paae 23Table 3-1 Results for ATRIUM 10XM Fuel AssemblyCriteriaSection Description Criteria Results3.3 Fuel System Criteria3.3.1Stress, strain and loadinglimits on assemblycomponentsWater channelFatigueFretting wearOxidation, hydriding, andcrud buildupRod bowThe ASME B&PV CodeSection III is used toestablish acceptable stresslevels or load limits forassembly structuralcomponents. The designlimits for accident conditionsare derived from Appendix Fof Section III.The pressure load includingAOO is limited to [1 according to ASMEB&PV Code Section II1. Thepressure load is also limitedsuch that [[3.3.23.3.33.3.43.3.5[1]Fretting was evaluated bytesting. Test results indicate[][INRC accepted model used tocompute impact on thermallimits.Protect thermal limits.(Table continued on next page)AREVA Inc. AREVA Inc.Mechanical Design Report for Quad Cities and Dresden ATRIUM 10OXM Fuel Assembliesi kensina ReportANP-3305NPRevision 1Paae 24.......... i-I I"" " --i w -- .Table 3-1 Results for ATRIUM 10XM Fuel Assembly (Continued)CriteriaSection Description Criteria_____Results__3,3 Fuel System Criteria (Continued) _____________3,3.63.3.73.3.83.3.93.3.103.3.10.13.3.10.2Axial irradiation growthUpper end cap clearanceSeal spring engagementRod internal pressureAssembly liftoffNormal operation(including AOOs)Postulated accidentFuel assembly handlingMiscellaneouscomponentsCompression springforcesLTP seal springClearance always exists.Remains engaged withchannel.N/ANo liftoff from fuel support.No disengagement from fuelsupport. No liftoff from fuelsupport.Assembly withstands [Support weight of UTP andfuel channel throughoutdesign life.Accommodate fuel channeldeformation, adequatecorrosion, and withstandoperating stresses.[Not covered in structuralreportNet force on assembly isdownward.Fuel assembly LTP nozzleremains engaged with fuelsupport. Net force onassembly is downward.Verified by testing to meetrequirement.The design criteria are met.The design criteria are met.(Table continued on next page)AREVA Inc. &nro~ docunerVAREVA Inc..Mechanical Design Report for Quad Cities and Dresden ATRIUM I10XM Fuel AssembliesLicensina ReportANP-3305NPRevision 1Paae 25.......... " ..... V IVTable 3-1 Results for ATRIUM 10XM Fuel Assembly (Continued)CriteriaSection Description Criteria Results3.4 Fuel Coolability3.4.1 Cladding embrittlement N/A Not covered in structuralreport.3.4.2 Violent expulsion of fuel N/A Not covered in structuralreport.3.4.3 Fuel ballooning N/A Not covered in structuralreport.3.4.4 Structural deformations Maintain coolable geometry See results below forand ability to insert control individual components.blades. SRP 4.2, App. A, and[ASME Section Ill, App. F.Fuel rod stresses [[]Spacer grid lateral load [[]Water channel load The combined seismic andpressure load is limited to the[1 according to ASMEB&PV Code Section III, App.F. The pressure load is alsolimited such thatUTP lateral load [LTP lateral load [[_ _ _ IAREVA Inc. Cont.ro ~ Doc;umentAREVA Inc.Mechanical Design Report for Quad Cities and Dresden ATRIUM 10OXM Fuel AssembliesLicensina ReoortANP-3305NPRevision 1Paae 28Table 3-2 Results for Advanced Fuel ChannelCriteriaIFSection Description jCriteria Results3.5.1 Advanced Fuel Channel -Normal Operation-Stress due to The pressure load including AOO The deformation during AOOpressure differential is limited to [ remains within functional limitsoprto n hfor normal control bladeaccording to ASME B&PV Code,oprtnadth[Section II1. The pressure load isalso limited such that ][ There is no significant plasticdeformation during normaloperation [Fatigue Cumulative cyclic loading to be Expected number of cyclesless than the design cyclic fatigue [ ] is less thanlife for Zircaloy. [ allowable.]Oxidation and [The maximum expectedhydriding oxidation is low in relation to] the wall thickness. [Long-term Bulge and bow shall not interfere Margin to a stuck control bladedeformation (bulge with free movement of the control remains positive.creep and bow) blade.(Table continued on next page)AREVA Inc. Controled DcumenAREVA Inc.ANP-3305NPRevision 1Paae 27Mechanical Design Report for Quad Cities and Dresden ATRIUM I0XM Fuel AssembliesLicensina ReportTable 3-2 Results for Advanced Fuel Channel (Continued)CriteriaSection Description JCriteria [Results3.5.2 Advanced Fuel Channel -Accident ConditionsFuel channel The pressure load is limited to The deformation duringstresses and load r blowdown does not interferelimit ] codn oA M .with control blade insertionB&PV Code, Section III, App. F.The pressure load is also limitedsuch that deformation remainswithin functional requirements.]Channel bending Allowable bending moment [from combined based on ASME Code,horizontal Section III, Appendix F plasticexcitations analysis collapse load.Fuel channel gusset ASME allowable [ ] [stregthof one gusset is [AREVA Inc. ControIled DocumentAREVA Inc.ANP-3305NPRevision 1Paae 28Mechanical Design Report for Quad Cities and Dresden ATRIUM 10XM Fuel AssembliesLicensina Re~ortI I I I ETable 3-3 Results for Channel FastenerCriteriaSection Description Criteria Results3.5 Channel FastenerCompatibility Spring height must extend to All compatibility requirementsthe middle of the control cell to are met. The spring will extendensure contact with adjacent beyond the cell mid-line.spring.Spring axial location must be The axial location of the springsufficient to ensure alignment flat will always be in contactwith adjacent spring at all with an adjacent spring; even ifexposures, a fresh ATRIUM 10XM isplaced adjacent to an EOL co-resident assembly.Strength Spring must meet ASME All ASME stress criteria arestress criteria and not yield met for the spring and capbeyond functional limit, screw. In addition, the springCap screw must meet ASME will not yield under thecriteria for threaded fastener. maximum deflection.AREVA Inc. Controlled DocumentAREVA Inc. ANP-3305NPRevision 1Mechanical Design Report for Quad Cities and Dresden ATRIUM 10XM Fuel AssembliesLicensingq Report Pagqe 294.0 MECHANICAL TESTINGPrototype testing is an essential element of AREVA's methodology for demonstratingcompliance with structural design requirements. Results from design verification testingmay directly demonstrate compliance with criteria or may be used as input to designanalyses. Test results and corresponding analyses confirm that the acceptance criteriaare met.Testing performed to qualify the mechanical design or evaluate assemblycharacteristics includes:* Fuel assembly axial load structural strength test* Spacer grid lateral impact strength test* Tie plate lateral load strength tests and LTP axial compression test* Debris filter efficiency test* Fuel assembly fretting test* Fuel assembly static lateral deflection test* Fuel assembly lateral vibration tests* Fuel assembly impact testsSummary descriptions of the tests are provided below.AREVA Inc. Con~trolled Document.AREVA Inc.Mechanical Design Report for Quad Cities and Dresden ATRIUM 1OXM Fuel AssembliesLicensina ReoortANP-3305NP.Revision 1Paae 304.1Fuel Assembly Axial Load TestAn axial load test was conducted by applying an axial tensile load between the LTP gridand UTP handle of a fuel assembly cage specimen. The load was slowly applied whilemonitoring the load and deflection. No significant permanent deformation was detectedfor loads in excess []4.2Spacer Grid Lateral Impact Strength TestSpacer grid impact strength was determined by a [].The maximum force prior to the onset of buckling was determined from the testing. Theresults were adjusted to reactor operating temperature conditions to establish anallowable lateral load.AREVA Inc. Controlled Docum~en~tAREVA Inc.ANP-3305NPRevision 1::1Mechanical Design Report for Quad Cities and Dresden ATRIUM 10OXM Fuel AssembliesL ic~n~inn R~nnrt.......... * "vr" ..... *;"1 v v .4.3Tie Plate Strength TestsIn addition to the axial tensile tests described above, [The UTP []1.For the Improved FUELGUARD LTP [To determine a limiting lateral load for accident conditions, the LTP [].AREVA Inc. Cont'rolled Document:ARE.A. In... ' w"wMechanical Design Report for Quad Cities and Dresden ATRIUM 10XM Fuel AssembliesLicensino RenortANP-3305NPRevision 1Page 324.4Debris Filter Efficiency TestDebris filtering tests were performed for the Improved FUELGUARD lower tie plate toevaluate its debris filtering efficiency. These tests evaluated the ability of the ImprovedFUELGUARD to protect the fuel rod array from a wide set of debris forms. In particular,testing was performed [] .These debris filteringtests demonstrate that the Improved FUELGUARD is effective at protecting the fuel rodarray from all high-risk debris forms.4.5Fuel Assembly Fretting TestA fretting test was conducted on a full-size test assembly to evaluate the ATRIUM 10XMfuel rod support design. [] .After the test, the assembly was inspected for signsof fretting wear. [AREVA Inc. ConroedDocumnAREVA Inc. tMechanical Design Report for Quad Cities and Dresden ATRIUM 10OXM Fuel AssembliesLicensinQ ReportANP-3305NPRevision 1Paae 334.6Fuel Assembly Static Lateral Deflection TestA lateral deflection test was performed to determine the fuel assembly stiffness, bothwith and without the fuel channel. The stiffness is obtained by supporting the fuelassembly at the two ends in a vertical position, applying a side displacement at thecentral spacer location, and measuring the corresponding force.4.7Fuel Assembly Lateral Vibration TestsThe lateral vibration testing consists of both a free vibration test and a forced vibrationtest [The test setup for the free vibration test [:1The forced vibration testing [1.AREVA Inc. Controlled DocumentAREVA Inc.Mechanical Design Report for Quad Cities and Dresden ATRIUM I10XM Fuel AssembliesLicensingq ReportANP-3305NPRevision 1Pace 344.8Fuel Assembly Impact TestsImpact testing was performed []. The measured impact loads are used in establishing the spacer gridstiffness.
5.0CONCLUSION
The fuel assembly and channel meet all the mechanical design requirements identifiedin References 1 and 2. Additionally, the fuel assembly and channel meet themechanical compatibility requirements for use in Quad Cities and Dresden. Thisincludes compatibility with both co-resident fuel and the reactor core internals.AREVA Inc. Controlled Docu3m entAREVA Inc. ANP-3305NPRevision 1Mechanical Design Report for Quad Cities and Dresden ATRIUM 10XM Fuel AssembliesLicensing Report Paqe 3
56.0 REFERENCES
- 1. ANF-89-98(P)(A) Revision 1 and Supplement 1, Generic Mechanical DesignCriteria for BWR Fuel Designs, Advanced Nuclear Fuels Corporation, May 1995.2. EMF-93-177(P)(A) Revision 1, Mechanical Design for BWR Fuel Channels,Framatome ANP Inc., August 2005.3. EMF-85-74(P) Revision 0 Supplement I (P)(A) and Supplement 2(P)(A),RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model, SiemensPower Corporation, February 1998.4. XN-NF-75-32(P)(A) Supplements 1 through 4, Computational Procedure forEvaluating Fuel Rod Bowing, Exxon Nuclear Company, October 1983. (Basedocument not approved.)5. W. J. O'Donnell and B. F. Langer, Fatigue Design Basis for ZircaloyComponents, Nuclear Science and Engineering, Volume 20, January 1964.6. XN-NF-81-51 (P)(A), LOCA -Seismic Structural Response of an Exxon NuclearCompany BWR Jet Pump Fuel Assembly, Exxon Nuclear Company, May 1986.7. XN-NF-84-97(P)(A), LOCA -Seismic Structural Response of an ENC 9x9 BWRJet Pump Fuel Assembly, Exxon Nuclear Company, August 1986.8. Huan, P. Y., Mahmood, S. T., and R. Adamson, R. B. "Effects ofThermomechanical Processing on In-Reactor Corrosion and Post-IrradiationProperties of Zircaloy-2", Zirconium in the Nuclear Industry: EleventhInternational Symposium, ASTM STP 1295, E. R. Bradley and G. P. Sabol, Eds.,American Society for Testing and Materials, 1996, pp. 726-757.AREVA Inc.
ControlOled DocumentfAREVA Inc.Mechanical Design Report for Quad Cities and Dresden ATRIUM 10XM Fuel AssembliesLicensina ReportANP-3305NPRevision 1Paae 36i I rw v I IAPPENDIX AILLUSTRATIONSThe following table lists the fuel assembly and fuel channel component illustrations inthis section:Description PageATRIUM 10XM Fuel Assembly 37UTP with Locking Hardware 38Improved FUELGUARD LTP 39ATRIUM 10XM ULTRAFLOW Spacer Grid 40Fuel and Part-Length Fuel Rods 41Advanced Fuel Channel 42Fuel Channel Fastener Assembly 43These illustrations are for descriptive purpose only. Please refer to the current reloaddesign package for product dimensions and specifications.AREVA Inc. Controlled DocumentAREVA Inc.ANP-3305NPRevision 1Paae 37Mechanical Design Report for Quad Cities and Dresden ATRIUM 10XM Fuel AssembliesLicensina Renort.......... " "wF ..... 11 w w *Figure A-I ATRIUM 10XM Fuel Assembly(not to scale)AREVA Inc. Controiled IDocumientAREVA Inc.Mechanical Design Report for Quad Cities and Dresden ATRIUM 1OXM Fuel AssembliesLicensina ReportANP-3305NPRevision 1Page 38I I I IFigure A-2 UTP with Locking HardwareAREVA Inc. Controlled Docum~entAREVA Inc.ANP-3305NPRevision 1Paqe 39Mechanical Design Report for Quad Cities and Dresden ATRIUM I10XM Fuel AssembliesLicensina Reoort.......... m mFigure A-3 Improved FUELGUARD LTPAREVA Inc. Controlled DocumentAREVA Inc.Mechanical Design Report for Quad Cities and Dresden ATRIUM 10XM Fuel AssembliesLicensina ReportANP-3305NPRevision 1Paae 40I I I =Figure A-4 ATRIUM 10XM ULTRAFLOW Spacer GridAREVA Inc. Controlled DocumentAREVA Inc.ANP-3305NPRevision 1Paae 41Mechanical Design Report for Quad Cities and Dresden ATRIUM 10OXM Fuel AssembliesLicensina Report.......... "1 * -vr- ...... i- --Figure A-5 Full and Part-Length Fuel Rods(not to scale)AREVA Inc. Controlied DocumentAREVA Inc.Mechanical Design Report for Quad Cities and Dresden ATRIUM 10XM Fuel AssembliesLicensina ReportANP-3305NPRevision 1Paoe 42i I I IFigure A-6 Advanced Fuel ChannelAREVA Inc. Controlled DocumentAREVA Inc.Mechanical Design Report for Quad Cities and Dresden ATRIUM 10XM Fuel AssembliesLicensina ReDortANP-3305NPRevision 1Paqe 43I I I =Figure A-7 Fuel Channel Fastener AssemblyAREVA Inc.}}