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KTA 3201.1 Components of the Reactor Coolant …

Safety Standardsof theNuclear Safety Standards Commission (KTA)KTA (06/98) Components of the Reactor Coolant pressure Boundaryof Light Water ReactorsPart 1: Materials and Product Forms(Komponenten des Prim rkreises von Leichtwasserreaktoren;Teil 1: Werkstoffe und Erzeugnisformen)Previous versions of this safetystandard were issued 11/82 and 6/90If there is any doubt regarding the information contained in this translation, the German wording shall :KTA-Geschaeftsstelle c/o Bundesamt fuer Strahlenschutz (BfS)Willy-Brandt-Strasse 5 D-38226 Salzgitter GermanyTelephone +49-5341/885-(0) 901 Telefax +49-5341/885-905 Page 2 Page 3 KTA SAFETY STANDARDJune 1998 Components of the Reactor Coolant pressure Boundaryof Light Water Reactors; Part 1: Materials and Product FormsKTA.

Page 3. KTA SAFETY STANDARD. June 1998 Components of the Reactor Coolant Pressure Boundary of Light Water Reactors; Part 1: Materials and Product Forms

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Transcription of KTA 3201.1 Components of the Reactor Coolant …

1 Safety Standardsof theNuclear Safety Standards Commission (KTA)KTA (06/98) Components of the Reactor Coolant pressure Boundaryof Light Water ReactorsPart 1: Materials and Product Forms(Komponenten des Prim rkreises von Leichtwasserreaktoren;Teil 1: Werkstoffe und Erzeugnisformen)Previous versions of this safetystandard were issued 11/82 and 6/90If there is any doubt regarding the information contained in this translation, the German wording shall :KTA-Geschaeftsstelle c/o Bundesamt fuer Strahlenschutz (BfS)Willy-Brandt-Strasse 5 D-38226 Salzgitter GermanyTelephone +49-5341/885-(0) 901 Telefax +49-5341/885-905 Page 2 Page 3 KTA SAFETY STANDARDJune 1998 Components of the Reactor Coolant pressure Boundaryof Light Water Reactors; Part 1: Materials and Product FormsKTA.

2 41 Scope .. 52 General principles .. Selection and certification of Welding consumables .. General requirements regarding quality Requirements to be met by the Design review and quality In-process inspection .. Test and certification of material quality .. Repairs .. Material properties for strength 103 General requirements for and testing of materials .. Allowable materials .. Requirements .. Tests and examinations of materials andproduct forms .. Re-examinations .. Identification marking of the product forms.

3 Documentation .. 214 Seamless hollow parts, forged or rolled .. 225 Seamless hollow parts for nozzles, forged, rolledor pressed .. 256 Forged single-piece plates for tubesheets .. 287 Sheets and plates .. 318 Products dished, pressed, bent for rolled fromsheets and 359 Straight pipe sections .. 3810 Seamless, forged hollow bodies for primarycoolant pump casings .. 4111 pressure -retaining forged valve bodies .. 4312 Forged flat plates .. 4513 Hot dished or pressed products from forged plates. 4714 Forged or rolled bars for hollow-bored nozzlesand pipes.

4 4915 Forged or rolled and hollow-bored andhollow-forged bars .. 5016 Seamless pipes for 5017 Seamless elbows for pipe 5218 Steam generator 5519 Seamless extrusion-clad composite tubes .. 5820 Bars and rings for bolts, nuts and washers, as wellas bolts, nuts and washers(dimensions exceeding M 130).. 6121 Bars and rings for bolts, nuts and washer as wellas bolts, nuts and washers(dimensions equal to or smaller than M 130).. 6322 Sheets, plates, bar steel and forgings fromstainless austenitic steels .. 6423 Seamless pipes from stainless austenitic 7024 Seamless elbows from stainless austenitic 7125 pressure retaining parts from quenched andtempered cast steel.

5 7326 Valve bodies made from ferritic cast steel .. 8327 Valve bodies from austenitic cast steel .. 8928 Bars and forgings from stainless martensitic steel .. 9729 Product forms and Components from ferritic steelsfabricated by shape-welding .. 9830 Product forms from ferritic steels for integralconnections to the Reactor Coolant 10131 Product forms from austenitic steels for integralconnections to the Reactor Coolant 101 Annex AMaterial characteristics .. 103 Annex APCharacteristic values of physicalproperties .. 134 Annex BPerformance of manual ultrasonicexaminations.

6 138 Annex CPerformance of surface crack detectionexaminations by magnetic particle andliquid penetrant methods .. 148 Annex DProcedure for determining the deltaferrite content .. 150 Annex EForm 152 Annex FRegulations referred to in this SafetyStandard .. 159 Annex GChanges with respect to the edition6/90 and explanations (informative) .. 162 PLEASE NOTE: Only the original German version of this safety standard represents the joint resolution of the50-member Nuclear Safety Standards Commission (Kerntechnischer Ausschuss, KTA).

7 The German version wasmade public in Bundesanzeiger No. 170a on September 11, 1998. Copies may be ordered through the Carl Hey-manns Verlag KG, Luxemburger Str. 449, D-50939 Koeln (Telefax +49-221-94373-603).All questions regarding this English translation should please be directed to:KTA-Geschaeftsstelle c/o BfS, Willy-Brandt-Strasse 5, D-38226 Salzgitter, GermanyKTA 4 Comments by the editor:Taking into account the meaning and usage of auxiliary verbs in the German language, in this translation thefollowing agreements are effective:shallindicates a mandatory requirement,shall basicallyis used in the case of mandatory requirements to which specific exceptions (and onlythose!)

8 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 5 Fundamentals(1)The safety standards of the Nuclear Safety StandardsCommission (KTA)

9 Have the task of specifying those safetyrelated requirements which shall be met with regard to pre-cautions to be taken in accordance with the state of scienceand technology against the damage arising from the con-struction and operation of the facility (Sec. 7 para 2 subpara 3 Atomic Energy Act) in order to attain the protection goalsspecified in the Atomic Energy Act and the Radiological Pro-tection Ordinance (StrlSchV) and which are further detailed inthe Safety Criteria for Nuclear Power Plants and in the Guidelines for the Assessment of the Design of PWR NuclearPower Plants against Incidents pursuant to Sec.

10 28 para 3 ofthe Radiological Protection Ordinance (StrlSchV) - IncidentGuidelines .(2)Criterion , Principles of Safety Precautions of theSafety Criteria requires, among other things, a comprehensivequality assurance for fabrication, erection and operation andCriterion , 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 documen-tation of quality assurance.


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