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U.S. EPR FINAL SAFETY ANALYSIS REPORT3.9.3ASME Code Class 1, 2, and 3 Components, Component Supports, and CoreSupport StructuresThis section describes the structural integrity of pressure-retaining components,component supports, and core support structures. These components and supports aredesigned in accordance with the ASME Boiler and Pressure Vessel Code, Section III,Division 1 (Reference 1) and GDC 1, 2, 4, 14, and 15. Compliance with the GDC isdescribed below:Tier 2 GDC 1 requires that structures, systems, and components (SSC) be designed toquality standards commensurate with the importance of the safety function thatthey perform. RG 1.26 and 10 CFR 50.55a define the use of ASME Code Classes 1,2, and 3 based on quality groups for plant systems and parameters. Quality groupsA, B, and C are safety-related groups that are designed to meet the requirements ofASME Code Classes 1, 2, and 3, respectively. This section describes the applicationof the ASME Code, Section III, Division 1 and ASME Code, Subsection NF to thedesign of Class 1, 2, and 3 pressure-retaining components, their support structures,and core support structures. As noted in Section 3.1, this design is in accordancewith the applicable codes required in 10 CFR 50.55a. Further information onquality group classifications is provided in Section 3.2. GDC 2 requires that structures, systems, and components important to safety bedesigned to withstand the effects of natural phenomena (e.g., earthquakes)combined with the effects of normal or accident conditions. The loadingcombinations described in this section include consideration of the effects ofexpected natural phenomena combined with the appropriate effects of normal andaccident conditions. SSC are designed so that the stresses are within ASME Codemandated limits in order to withstand these conditions without loss of theirintended functions. GDC 4 requires that SSC important to safety be designed to accommodate theeffects of, and be compatible with, the environmental conditions of normal andaccident conditions. The loading combinations described in this section includeconsideration of the loading effects and the resulting stresses associated withnormal operation, maintenance, testing, and postulated accidents, including a lossof-coolant accident (LOCA). GDC 14 requires that the reactor coolant pressure boundary (RCPB) be designed,fabricated, erected, and tested to have an extremely low probability of abnormalleakage, of rapidly propagating failure, and of gross rupture. GDC 15 requires thatthe reactor coolant system (RCS) and associated auxiliary, control, and protectionsystems be designed with sufficient margin to assure that the design conditions ofthe RCPB are not exceeded during conditions of normal operation, includinganticipated operational occurrences. Compliance with these GDCs is achievedthrough compliance with the ASME Code requirements for determining stressesand stress limits that are based on the loads and load combinations described inthis section. Compliance with these requirements demonstrates that RCPBcomponents are designed to have an extremely low probability of abnormalleakage, rapidly propagating failure, and gross rupture.Revision 1Page 3.9-29
U.S. EPR FINAL SAFETY ANALYSIS REPORTThis section refers to U.S. EPR Piping Analysis and Pipe Support Design TopicalReport (Reference 2) for information related to the design and analysis of safetyrelated piping. This topical report presents the U.S. EPR code requirements,acceptance criteria, analysis methods, and modeling techniques for ASME Class 1, 2,and 3 piping and pipe supports. Applicable COL action items in the topical report areidentified in the applicable portions of this section. The U.S. EPR design is based onthe 2004 ASME Code, Section III, Division 1, with no addenda subject to thelimitations and modification identified in 10 CFR 50.55a(b)(1) and the piping analysiscriteria and methods, modeling techniques, and pipe support criteria described inReference 2.A design specification is required by Section III of the ASME Code for Class 1, 2, and 3components, piping, supports, and core support structures. In addition, the ASMECode requires design reports for all Class 1, 2, and 3 components, piping, supports andcore support structures documenting that the as-designed and as-built configurationsadhere to the requirements of the design specification. A COL applicant thatreferences the U.S. EPR design certification will prepare the design specifications anddesign reports for ASME Class 1, 2, and 3 components, piping, supports and coresupport structures that comply with and are certified to the requirements of Section IIIof the ASME Code.Other sections that relate to this section are described below:3.9.3.1 Section 3.9.6 describes the snubber inspection and test program. Section 3.10 describes the methods and criteria for seismic qualification testing ofSeismic Category I mechanical equipment and a description of their seismicoperability criteria. Section 3.12 describes the design of systems and components that interface withthe RCS with regard to intersystem LOCAs. Section 3.13 describes bolting and threaded fastener adequacy and integrity. Section 5.2.2 describes the pressure-relieving capacity of the valves specified forRCPB. Section 10.3 describes the pressure-relieving capacity of the valves specified forthe steam and feedwater systems.Loading Combinations, System Operating Transients, and Stress LimitsSection 3.9.3.1.1 describes the design and service level loadings used for the design ofASME Class 1, 2, and 3 components, piping, supports, and core support structures,including the appropriate system operating transients. Sections 3.9.3.1.2 through3.9.3.1.8 define the loading combinations for the ASME Code Class 1, 2, and 3components, piping, supports, and core support structures; these sections also defineTier 2Revision 1Page 3.9-30
U.S. EPR FINAL SAFETY ANALYSIS REPORTthe stress limits applicable to the various load combinations. The loadingcombinations and corresponding stress limits for ASME Code design are defined forthe Design Condition, Service Levels A, B, C and D (also known as normal, upset,emergency, and faulted conditions), and test conditions.Internal parts of components, such as valve discs, seats, and pump shafts, comply withthe applicable ASME Code or Code Case criteria. In those instances where no ASMECode criteria exist, these components are designed so that no safety-related functionsare impaired.Calculation methods used to evaluate RCS components and their supports for faultedloading are provided in Appendix 3C. Calculation methods used to evaluate pipingand supports are described in Sections 4 and 6 of Reference 2.A COL applicant that references the U.S. EPR design certification will provide asummary of the maximum total stress, deformation (where applicable), andcumulative usage factor values for each of the component operating conditions forASME Code Class 1 components. For those values that differ from the allowable limitsby less than 10 percent, the COL applicant will provide the contribution of each of theloading categories (e.g., seismic, pipe rupture, dead weight, pressure, and thermal) tothe total stress for each maximum stress value identified in this range.3.9.3.1.1Loads for Components, Component Supports, and Core Support StructuresThe following sections describe the loadings considered in the design of thecomponents, piping, and support structures. Piping analysis methods are described inAppendix 3C and the Piping Analysis Topical Report (Reference 2). Section 3.9.1 liststhe design transients and number of events used in fatigue analyses.PressureDesign pressure is described in Section 3.3 of Reference 2 and applies to ASME CodeClass 1, 2, and 3 components and piping. The criteria for incorporating the effects ofboth internal and external pressures for components are described in the ASME Code,Section III, Articles NB-3000, NC-3000, and ND-3000.DeadweightDeadweight analyses consider the weight of the component, piping, or structure beinganalyzed and the additional weight of contained fluid, external insulation, and otherappurtenances. For piping and components, the deadweight present duringhydrostatic test loadings is also considered where such loadings exceed the normaloperational deadweights. Static and dynamic heads of liquid are also included in thedeadweight analyses of components. Deadweight loads are further described inSections 3.3.1.2 and 6.3.1 of Reference 2.Tier 2Revision 1Page 3.9-31
U.S. EPR FINAL SAFETY ANALYSIS REPORTThermal ExpansionThe effects of restrained thermal expansion and contraction on piping and supports aredescribed in Section 3.3.1.3 and Section 6.3.2 of Reference 2.SeismicAnalyses of seismic inertial loads and anchor movements on piping systems and theRCS are described in Sections 3, 4, and 6 of Reference 2 and Appendix 3C,respectively. In addition to the inertia and anchor movement stress effects due to aseismic event, the fatigue effects of such cyclic events are considered in the design ofClass 1 components and piping. The number of safe shutdown earthquake (SSE) stresscycles included in the fatigue analysis is identified in FSAR Section 3.7.3 and inSection 3.4.1 of Reference 2.System Operating TransientsAnalyses of system operating transients, including fluid transient loadings, on pipingsystems and the RCS are discussed in Sections 3.3.1.5 and 6.3.4 of Reference 2 andAppendix 3C, respectively. Thermal and pressure transients are described in Section3.3.1.8 of Reference 2. Section 3.3.1.5 of Reference 2 also describes water and steamhammer loads. The analysis of these transients results in force time histories forapplication in the piping analyses.Wind and TornadoWind and tornado loads are discussed in Sections 3.3.1.6, 6.3.5, and 6.3.6 ofReference 2. As noted in ANP-10264NP-A, should a COL applicant that referencesthe U.S. EPR design certification find it necessary to route Class 1, 2, and 3 piping notincluded in the U.S. EPR design certification so that it is exposed to wind andtornadoes, the design must withstand the plant design-basis loads for this event.Pipe BreakLoads due to pipe breaks are described in Section 3.3.1.7 of Reference 2. Additionally,the leak-before-break methodology is used to eliminate the dynamic effects of piperupture for the main coolant loop, pressurizer surge line, and portions of the mainsteam line piping (see Section 3.6.3).Pipe break load design condition and service level evaluations are described inSections 6.3.7, 6.3.8, and 6.3.9 of Reference 2. Design basis pipe breaks are categorizedas Level C. Main steam and main feedwater pipe breaks and LOCA are categorized asLevel D.Tier 2Revision 1Page 3.9-32
U.S. EPR FINAL SAFETY ANALYSIS REPORTFrictionFriction loads are described in Section 6.10 of Reference 2.Minimum Pipe Support Design LoadsMinimum design loads are described in Section 6.3.11 of Reference 2. Normalcondition allowable stresses are applicable to the stresses resulting from the describedapplied loads. Use of this criterion does not eliminate the requirement to analyzesupports for applicable service conditions.Thermal Stratification, Cycling, and StripingThermal stratification, cycling, and striping (including applicable NRC Bulletins 7913, 88-08, and 88-11) are described in Section 3.7 of Reference 2. The pressurizersurge line is analyzed with the main coolant loop piping and supports as described inAppendix 3C. As noted in ANP-10264NP-A, a COL applicant that references the U.S.EPR design certification will confirm that thermal deflections do not create adverseconditions during hot functional testing.A COL applicant that references the U.S. EPR design certification will examine thefeedwater line welds after hot functional testing prior to fuel loading and at the firstrefueling outage, in accordance with NRC Bulletin 79-13. A COL applicant thatreferences the U.S. EPR design certification will report the results of inspections to theNRC, in accordance with NRC Bulletin 79-13.Environmental FatigueThe effects of the environment on fatigue for Class 1 piping and components areaddressed in FSAR Section 3.12 and in Section 3.4 of Reference 2.3.9.3.1.2Load Combinations and Stress Limits for Class 1 ComponentsTable 3.9.3-1—Load Combinations and Acceptance Criteria for ASME Class 1Components provides the loading combinations and corresponding stress designcriteria per ASME Service Level for ASME Class 1 components.3.9.3.1.3Load Combinations and Stress Limits for Class 2 and 3 ComponentsTable 3.9.3-2—Load Combinations and Acceptance Criteria for ASME Class 2 and 3Components provides the loading combinations and corresponding stress designcriteria per ASME Service Level for ASME Class 2 and 3 components.3.9.3.1.4Load Combinations and Stress Limits for Class 1 PipingTable 3-1 of Reference 2 provides the loading combinations and corresponding stressdesign criteria per ASME Service Level for ASME Class 1 piping.Tier 2Revision 1Page 3.9-33
U.S. EPR FINAL SAFETY ANALYSIS REPORT3.9.3.1.5Load Combinations and Stress Limits for Class 2 and 3 PipingTable 3-2 of Reference 2 provides the loading combinations and corresponding stressdesign criteria per ASME Service Level for ASME Class 2 and 3 piping.3.9.3.1.6Load Combinations and Stress Limits for Core Support StructuresTable 3.9.3-3—Load Combinations and Acceptance Criteria for ASME Core SupportStructures provides the loading combinations and corresponding stress design criteriaper ASME Service Level for ASME core support structures.3.9.3.1.7Load Combinations and Stress Limits for Class 1, 2, and 3 ComponentSupportsTable 3.9.3-4—Load Combinations and Acceptance Criteria for ASME Class 1, 2, and 3Component Supports provides the loading combinations and corresponding stressdesign criteria per ASME Service Level for ASME Class 1, 2, and 3 componentsupports. In addition to the NF Sections listed
of the ASME Code, Section III, Division 1 and ASME Code, Subsection NF to the design of Class 1, 2, and 3 pressure-retai ning components, their support structures, and core support structures. As noted in Section 3.1, this design is in accordance with the applicable codes required in 10 CFR 50.55a. Further information on quality group classifications is provided in Section 3.2. GDC 2 requires .
