Safety Standards - Kta-gs.de

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Safety Standardsof theNuclear Safety Standards Commission (KTA)KTA 3211.2 (2013-11)Pressure and Activity Retaining Components of SystemsOutside the Primary CircuitPart 2: Design and Analysis(Druck- und aktivitätsführende Komponenten von Systemenaußerhalb des Primärkreises;Teil 2: Auslegung, Konstruktion und Berechnung)Previous version of this Safety Standardwas issued 1992-06If there is any doubt regarding the information contained in this translation, the German wording shall apply.Editor:KTA-Geschaeftsstelle c/o Bundesamt fuer kerntechnische Entsorgungssicherheit (BfE) Willy-Brandt-Strasse 5 38226 Salzgitter GermanyTelephone 49-30-18-333-1621 Telefax 49-30-18-333-1625

KTA SAFETY STANDARD2013-11Pressure and Activity Retaining Components ofSystems Outside the Primary Circuit;Part 2: Design and AnalysisKTA 3211.2CONTENTSFundamentals . 51Scope . 52 General requirements and Definitions . 52.1 Definitions . 52.2 General requirements. 63Load case classes as well as design, serviceand test loadings and limits of components. 73.1 General . 73.2 Load case classes . 73.3 Loadings levels . 744.14.24.34.44.5Effects on the components due to mechanicaland thermal loadings and fluid effects . 9General . 9Mechanical and thermal loadings . 9Documentation of component loadings . 9Superposition of loadings and assignment toloading levels . 9Fluid effects . 95 Design . 105.1 General requirements. 105.2 General requirements for components andtheir welds . 115.3 Component-specific requirements . 1466.16.26.36.46.56.66.76.8Dimensioning . 18General . 18Welds . 18Claddings . 18Wall thickness allowances. 18Wall thicknesses . 18Design stress intensities. 18Allowable stresses for dimensioning . 19Nominal operating stress. 1977.17.27.37.47.5General analysis of the mechanical behaviour . 20General . 20Loadings. 22Stress/strain loadings . 22Resulting deformations. 22Determination, evaluation and limitation ofmechanical forces and moments . 227.67.77.87.97.107.11Mechanical system analysis . 22Stress analysis . 23Fatigue analysis . 29Strain analysis . 32Structural analysis . 32Stress, strain and fatigue analyses forflanged joints . 327.12 Avoidance of thermal stress ratcheting forcomponents of test group A1 . 3888.18.28.38.48.58.69Component-specific analysis of themechanical behaviour . 39General . 39Vessels. 39Pumps 53Valve bodies . 56Piping systems . 65Integral areas of component supportstructures . 86Type and extent of verification of strengthand pertinent documents to be submitted . 86Annex A: Dimensioning. 87A1General . 87A2Dimensioning of parts of the pressureretaining wall . 87A3Pumps. 135A4Valves . 139A5Piping systems. 146Annex B: Requirements as to the primary stressanalysis in case of numericalreassessments . 160B1General . 160B2Prerequisites . 160B3Reassessment procedure . 160Annex C: Regulations and Literature referred to inthis Safety Standard . 161Annex D: Changes with respect to the edition1992-06 and explanations (informative) . 164PLEASE NOTE: Only the original German version of this safety standard represents the joint resolution of the35-member Nuclear Safety Standards Commission (Kerntechnischer Ausschuss, KTA). The German versionwas made public in Bundesanzeiger BAnz of January 17 th 2014. Copies may be ordered through the WoltersKluwer Deutschland GmbH, Postfach 2352, 56513 Neuwied, Germany (Telefax 49 (0) 2631 801-2223, E-Mail:info@wolterskluwer.de).All questions regarding this English translation should please be directed to:KTA-Geschaeftsstelle c/o BfE, Willy-Brandt-Strasse 5, D-38226 Salzgitter, Germany

Comments by the editor:Taking into account the meaning and usage of auxiliary verbs in the German language, in this translation the following agreements are effective:shallindicates a mandatory requirement,shall basicallyis used in the case of mandatory requirements to which specific exceptions (and onlythose!) are permitted. It is a requirement of the KTA that these exceptions - other thanthose in the case of shall normally - are specified in the text of the safety standard,shall normallyindicates a requirement to which exceptions are allowed. However, the exceptions used,shall be substantiated during the licensing procedure,shouldindicates a recommendation or an example of good practice,mayindicates an acceptable or permissible method within the scope of this safety standard.

KTA 3211.2 Page 5Fundamentals(1) The safety standards of the Nuclear Safety StandardsCommission (KTA) have the objective to specify safety-relatedrequirements, compliance of which provides the necessaryprecautions in accordance with the state of the art in scienceand technology against damage arising from the constructionand operation of the facility (Sec. 7 para. 2 subpara. 3 AtomicEnergy Act - AtG) in order to achieve the fundamental safetyfunctions specified in the Atomic Energy Act and the Radiological Protection Ordinance (StrlSchV) and further detailed in theSafety Criteria for Nuclear Power Plants, in the IncidentGuidelines and in the Safety Requirements for Nuclear PowerPlants.(2) Criterion 1.1, "Principles of Safety Precautions", of theSafety Criteria requires, among other things, a comprehensivequality assurance for fabrication, erection and operation, andCriterion 2.1, "Quality Assurance", requires, among otherthings, the application, preparation and observation of designrules, material specifications, construction rules, testing andinspection as well as operating instructions and the documentation of quality assurance.Further requirements relating to design and condition to bemet by the safety systems are specified in Criterion 4.2, "Residual Heat Removal in Specified Normal Operation"; Criterion4.3, "Residual Heat Removal after Loss of Coolant"; Criterion5.3, "Equipment for the Control and Shutdown of the NuclearReactor"; and Criterion 8.5, "Heat Removal from the Containment".Safety Standards KTA 3211.1 to KTA 3211.4 are intended tospecificy detailed measures which shall be taken to meetthese requirements within the scope of their application. Forthis purpose, a large number of standards from conventionalengineering, in particular DIN standards, are also used; theseare specified in each particular case.(3) The scope of application as defined in this Safety Standard comprises the pressure and activity-retaining systems andcomponents outside the pressure-retaining boundary (SafetyStandards of the KTA 3201 series) which are specifically significant in terms of reactor safety in accordance with the RSKGuidelines (Section 4.2).manner, taking into consideration multiple design (e.g. redundancy, diversity).b) If the plant component fails, great amounts of energy arereleased and the consequences of failure are not limitedby structural measures, physical separation or other safetymeasures to an extent which is reasonable in terms of nuclear safety.c) The failure of the plant component may lead, either directlyor in a chain of consequential events to be assumed, to anincident as defined in § 49 of the Radiological ProtectionOrdinance.(2) The following components fall under the scope of thisSafety Standard:a) pressure vessels,b) pipes and pipe components,c) pumps, andd) valvesincluding the integral areas of component support structures.(3) This Safety Standard does not apply to:a) pipes and valves equal to or smaller than DN 50, but mayapply to the performance of stress and fatigue analyses forpiping and valves with DN 50,Note:Simplified procedures are given in cl. 8.5.1 (5).Requirements for instrument lines are laid down in KTA 3507.b) internals of the components (which are not part of thepressure-retaining wall) and accessories,c) systems and plant components performing auxiliary functions for the systems dealt with by this safety standard,d) subsystems whose system pressure is determined exclusively by the static head in the suction area,e) parts used for the transmission of forces and power inpumps and valves as well as tests to demonstrate functional capability.(4) KTA 3211.2 specifies the detailed requirements to bemet bya) the classification into test groups, load case classes andlevel loadings,b) the design and analysis of components,c) the calculation procedures and design principles for obtaining and maintaining the required quality of the components,d) the documents for the certificates and demonstrations tobe submitted.21a) Active functional capability ensures that the specified mechanical movements (relative movements between parts)can be made (consideration of the possibility of closingclearances, generating or altering frictional forces).ScopeThis Safety Standard applies to the manufacture of pressureretaining walls of pressure and activity-retaining systems andcomponents of light water reactors which are not part of thereactor coolant pressure boundary, are operated up to designtemperatures of 673 K (400 C) and which are specificallysignificant to reactor safety. This is the case, if one of thefollowing criteria is fulfilled:a) The plant component is needed to cope with incidentsregarding shutdown, maintenance of long-term subcriticality and direct residual heat removal.Requirements to be met by components in systems whichonly indirectly serve residual heat removal, i.e. the nonactivity-retaining closed cooling water systems and servicecooling water systems, shall be specified in a plant-specific2.1General requirements and DefinitionsDefinitions(1) Functional capabilityFunctional capability means the capability of the componentbeyond the stability and integrity requirements to fulfil thespecified task at the respective event.Regarding functional capability distinction is made whether itis to be ensured during or after the event or during and afterthe event in which case distinction is also made between active and passive functional capability as well as between active and passive components.b) Passive functional capability means that distortions anddisplacement limits are not exceeded.c) Active components are components for which mechanicalmovements are specified to satisfy safety requirements,e.g. pumps, valves. All other components are passivecomponents, e.g. vessels, piping systems.(2) IntegrityIntegrity is the condition of a component or barrier, at whichthe safety requirements with regard to strength, resistance tofracture and leak tightness are met.

KTA 3211.2 Page 6(3) StabilityStability means the safety against inadmissible changes inposition and location of installation (e.g. overturning, fall, inadmissible displacement).2.2General requirements(1) For the components a classification regarding testgroups and materials shall be made in dependence of thedesign data and dimensions, taking the specified materialsand stress limits into account. When classifying components,different test groups may be selected for components within asystem, among certain circumstances also for parts of a component.Classification CriteriaTestgroupDesignstress intensitySize limitationA1Sm A2S A3Sin addition:PmNB 50 N/mm2(2) The allowable classification regarding test groups andmaterials is to be made in accordance with Table 2-1.(3) The stress intensity value in test group A1 is Sm. In testgroups A2 and A3 the stress intensity value is S.(4) For the load cases of the total plant or system the loadings on the component shall be indicated in accordance withSection 3 and be classified into operational load cases A, B,P, C, D in dependence of the safety-criteria to be satisfied. Forthe purpose of dimensioning the effective cross-sections, apertinent load case shall be determined from these loadingswhich shall be assigned to design loading (Level 0). Thesedata shall be specified for each component to form the basisfor design and calculation (see Section 4).Allocation of MaterialsFerritic MaterialsAustenitic MaterialsMaterials 1.4550,Materials inMaterials under the Materials inaccordance withscope of AD 2000- accordance1.4580, 1.4541,1.4571 under theKTA 3211.1Merkblatt W 0withKTA 3211.1 scope of AD 2000Merkblatt W 0WI(1) W II for:- PG 1small itemsWIRp0.2RT 370 N/mm2 - integralPermitted for:Materials wheresupportsa) PG 1-small items,for allfor vessels:2W II(2) Materials Rp0.2RT 370 N/mm dimensions b) integral supportss 16 mmfor PG 1-small itemsfor specialfor pipes,applicationpumps, valves:upon specific DN 150 1)agreement (1) These test groups are based on the same basic safety (see RSK Guidelines) in accordance with the varying hazard potential (stress, dimensions), observing the materials used.(2) Components within a system and subunits within a component may be allocated to different test groups.1)In the case of pumps: nominal diameter of the largest pressure nozzleIn the case of valves: nominal diameter of the inlet nozzle.Table 2-1:Test Groups: Classification criteria and allocation of materials(5) With respect to the safety criteria to be satisfied by thecomponent the stability, structural integrity and functionalcapability shall be verified as explained hereinafter.a) Stability of the componentStability is mainly proved by a verification of strength of thesupport, in which case the connection of the support to thecomponent and the anchorage (support, component) shallbe taken into account.b) Structural integrity of the componentWhen verifying the structural integrity the generally acceptedverification procedures shall be used and it shall be provedfor the part or component that they are capable of withstanding the loadings occurring during their service life.When verifying the structural integrity, the stability of thecomponent and, where required (e.g. in case of flangedjoints) the leak tightness shall also be taken into account.c) Functional capability of the componentWhen verifying the functional capability it shall be provedfor the part or component that the required distortion limitsfor the pressure-retaining walls are satisfied with regard tothe loadings occurring during the service life.Note:This safety standard only considers the requirements for pressure retaining walls for safeguarding the functional capability ofthe component.(6) Components shall be designed in accordance with therules of Section 5 "Design" according to which componentspecific design rules shall be considered in addition to thegeneral rules. The use of other designs is subject to specificverifications.(7) The loadings applied on the component shall be evaluated in dependence of the level loadings and be limited in accordance with Sections 6 to 8.(8) The service limits given in Section 7 apply to loadingsthat were determined on the basis of linear elastic materiallaws, unless other stipulations are made in the following Sections.(9) All level loadings specified in Sections 6 and 7 were fixedfrom the viewpoint of strength calculation and quality assurance such that a comparable safety is obtained for test groupsA1, A2 and A3.

KTA 3211.2 Page 7(10) The extent of the required verifications of strength is laiddown in dependence of the test groups. The verifications ofstrength for test group A1 shall be performed by way of dimensioning according to Section 6 and as general analysis of themechanical behaviour according to Section 7 or as component-specific analysis of the mechanical behaviour accordingto Section 8. Alternately, the use of equivalent design formulae is permitted (see clause 7.1.1 (6)). For test groups A2 andA3 dimensioning in accordance with Section 6, or if requiredwith Section 8, and depending on the individual case, a simplified analysis according to Section 7 or 8 shall be performed.3.2.3(11) The components of test groups A2 and A3 shall be designed and calculated under the same considerations in whichcase the calculation shall include a verification that the laws ofequilibrium of external fores are adhered to and a fatigueevaluation (in test group A3 only for piping systems).3.2.3.2(12) Within the verification of strength the stability of the structure shall also be proved, if required.(13) The verifications of strength, stability and functional capability required according to this safety standard shall bemade by way of calculation or experiments.(14) Component-specific rules for dimensioning are containedin Annex A and, depending on the respective case, Section 8.3.2.3.13.1Load case classes as well as design, service and testloadings and limits of componentsGeneral(1) Loadings on the systems resulting from the operation ofsystems and the events occurring in the total plant shall belisted according to their physical occurrence and chronologicalorder to form load cases which then shall be classified into theload case classes described in 3.2 with respect to their importance for the whole plant and adherence of protectivegoals. Corresponding to the load case classes the loadingsresulting from the load cases will be assigned to the levelloadings described in section 3.3 for the individual components of a system.(2) Connected to these level loadings are criteria for deciding whether to further operate the components or on themeasures to be taken in the event of the respective load caseoccurring (see Section 3.3).(3) Where loadings of considerable extent arise due to otherload cases (e.g. transport, assembly and repair cases) theyshall be verified by means of a strength calculation. The allowable service limits shall be determined for each individualcase.

scope of AD 2000-Merkblatt W 0 Materials in accordance with KTA 3211.1 Materials 1.4550, 1.4580, 1.4541, 1.4571 under the scope of AD 2000-Merkblatt W 0 A 1 Sm W I (1) W II for: - PG 1- small items - integral supports (2) Materials for: 2

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