RCC-M-Edition 2007 SECTION I：SUBSECTION G REACTOR INTERNALS.pdf

1、RCC-M-Edition 2007 SECTION I：SUBSECTION G REACTOR INTERNALS_REACTOR INTERNALSSECTION I : SUBSECTION G DESIGN AND CONSTRUCTION RULESFOR MECHANICAL COMPONENTS OF PWRNUCLEAR ISLANDSRCC-MRCC-M - Edition 2007 Subsection G G 1000 GENERAL G 1100 INTRODUCTION G 1110 APPLICATION OF SUBSECTION G G 1111 DEFINI

2、TION OF REACTOR VESSEL INTERNALS Reactor vessel internals comprise all mechanical structure items located inside the reactor vessel. The following items are not covered by Subsection G: - the core: fuel, fertile and dummy fuel assemblies, - reactivity control items: control rods and drive shafts, -

3、related core components: closures, poison and source rod assemblies - in-core instrumentation: non-mechanical parts. G 1112 CLASSIFICATION OF COMPONENTS In accordance with A 4310, component parts of reactor internals shall be classified into two categories: core support structures (CS) and internal

4、structures (IS). a) Core support structures (CS) are those structures or parts of structures which provide support and restraint of the fuel assemblies making up the core within the reactor pressure vessel. Structures designed to support or restrain the core only after the postulated failure of core

5、 support structures are classified as internal structures (IS). b) All other reactor internal structures shall be classified as internal structures (IS). c) For the purposes of chapters G 4000 and G 5000 only, welds joining internal structures (IS) to core support structures (CS) shall be considered

6、 to be core support structures (CS). d) Temporary fasteners which come in contact or are connected to the reactor internals but which are removed before commissioning are not covered by the present subsection. Temporary fasteners include, for example, tie plate alignment lugs, braces, supports and h

7、oods for pre-service instrumentation. n 113-2007 G 1000 / 1 RCC-M - Edition 2007 Subsection G G 1113 JURISDICTIONAL BOUNDARIES Internal equipment welded to the reactor vessel wall are considered to be part of the reactor vessel wall. Mechanical connections between reactor internals and reactor vesse

8、l shall meet the requirements of the present subsection. G 1120 ORGANIZATION OF SUBSECTION G Subchapter G 1200 specifies the documents to be prepared. Subchapter G 1300 specifies the procedure for identification of component parts and welded joints. Chapter G 2000 specifies the rules for selection o

9、f materials for all core support structures and for some internal structures. Chapter G 3000 specifies rules for design. Chapter G 4000 specifies rules for fabrication and examination. Chapter G 5000 specifies supplementary requirements for non-destructive examination given in SECTION III. G 1200 RE

10、QUIRED DOCUMENTS Chapter A 3000 defines these documents and describes their content. Documents required under this subsection shall be kept at the disposal of Surveillance Agents. The contract shall specify which documents are to be handed over to the relevant parties. G 1210 DOCUMENTS RELATING TO R

11、EACTOR INTERNALS The following documents shall be prepared for components failing within the scope of subsection G. Where production conditions so permit, an entire lot of components may be covered by the same documents. G 1211 DOCUMENTS ATTACHED TO THE PURCHASE ORDER FOR REACTOR INTERNALS Equipment

12、 specification (purchase order technical addenda) - A 3100. G 1212 PRELIMINARY DESIGN AND MANUFACTURING DOCUMENTS FOR REACTOR INTERNALS Comprehensive layout and referencing drawing - A 3201. Sizing report for core support structures (CS). Technical equipment manufacturing programme for reactor inter

13、nals - A 3301. G 1000 / 2 n 113-2007 RCC-M - Edition 2007 Subsection G G 1213 DOCUMENTS PREPARED AND UPDATED DURING FABRICATION Comprehensive layout and referencing drawing - A 3201. Stress report for core support structure (CS). Welding data package - A 3501. The welding data package shall be estab

14、lished for core support structures (CS) and shall be updated to take into account modifications in welding procedures. Non-conformance or deviation reports - A 3700. Follow-up documents - A 3801. G 1214 POST-MANUFACTURING DOCUMENTS End-of-manufacturing report - A 3805. Certificate of compliance - A

15、3804. G 1220 DOCUMENTS FOR COMPONENT PARTS OF REACTOR INTERNALS G 1221 PROCUREMENT DOCUMENTS Part and product manufacturing programme A 3301. Purchase order (technical and contractual clauses) - A 3302 (which refers in turn to SECTION II, chapter M 110). Procurement specification, SECTION II (chapte

16、r M 110) states the conditions under which a special procurement specification must be established. Filler material procurement specification - A 3502 (which refers in turn to S 2120). Filler material acceptance report - A 3503 (which refers in turn to S 2550). Component part follow-up documents - A

17、 3801. This quality plan is only drawn up for parts covered by a part procurement specification. (Other parts shall be included in the quality plan for the component of which they are a part.) G 1222 MANUFACTURING DOCUMENTS Fabrication instructions - A 3401 Welding instructions - A 3502 Welding repo

18、rt - A 3503 Examination instructions - A 3601 Examination report - A 3602 Production weld data sheet - A 3503 n 113-2007 G 1000 / 3 RCC-M - Edition 2007 Subsection G G 1223 INSPECTION DOCUMENTS List of examination personnel (in preparation). G 1224 NON-CONFORMANCE OR DEVIATION REPORTS See A 3700. G

19、1300 IDENTIFICATION G 1310 PURPOSE OF EQUIPMENT IDENTIFICATION SYSTEM The equipment identification system is a means of unequivocally associating a part or weld joint with a given set of documents. G 1320 ADAPTATION OF IDENTIFICATION SYSTEM TO PRODUCTION CONTROL METHODS Identification procedures mus

20、t, therefore, be adapted to the type of production control method applied to the part or weld: - control of individual items, using one identification number per item, - control by lot, using one identification number per lot. When a part is taken directly from stock and has only a steel grade numbe

21、r, the identification procedures set forth in the RCC-M shall not apply to the Manufacturer. G 1330 IDENTIFICATION METHODS Methods used to identify the components may include: - engraving, - temporary marking (with ink, paint, etc.), - labelling, - routing slips. Identification methods and shop orga

22、nization procedures shall be defined with a view to ensuring compliance with the objective set under B 1310. G 1340 TYPE OF IDENTIFICATION DATA The RCC-M does not require information related to the origin of any part or weld (such as lot No., heat-treatment No., welding operator No., heat No., etc.)

23、 to be marked or written on that item itself, its label, or its routing slip. G 1000 / 4 n 113-2007 RCC-M - Edition 2007 Subsection G However, marks or codes which provide clear reference to documents containing the information required for production control will always be acceptable. Where lots ar

24、e subdivided into one or more fabrication lots (e.g. for heat treatment) the original lot number need not appear on each item provided that the new identification system allows for accurate identification of the items origins. G 1350 RE-MARKING AND RELABELLING If an identification code is removed or

25、 erased during fabrication, the Manufacturer shall mark or label another portion of the part as appropriate. Machined items belonging to the same lot do not need to be re-marked after each machining operation, provided that: - fabrication procedures provide for total segregation of lots, - rejects a

26、re marked immediately, visibly and indelibly. In the particular case of plates, where rolling direction is of significance for subsequent fabrication or testing (e.g. removal of test sample), this information must appear on the item involved. Discard shall always be identified according to its inten

27、ded use. G 1360 MARKING METHODS Marking methods shall comply with requirements given in chapter F 2000. G 1370 REFERENCING OF WELDS G 1371 WELDS ON LARGE FABRICATED COMPONENTS A drawing shall be made of the location and position of welds on large fabricated components. This drawing, which may be the

28、 comprehensive layout drawing, shall give the dimensions of weld axes (whether the welds are flush or not) with respect to a set of identification marks (which may consist of marks on the part itself or of machined surfaces used as reference planes). It must mandatorily be possible to detect the mar

29、ks visually or by means of an optical instrument. For radiographically examined welds, the drawing or attached document must clearly indicate the location of the welds and the position of identification marks in order that radiographic films be interpreted and their position unequivocally establishe

30、d. n 113-2007 G 1000 / 5 RCC-M - Edition 2007 Subsection G G 1372 WELDS ON OTHER STRUCTURES A referencing drawing must be made for other structures particularly interchangeable structures, to indicate their location with respect to the equipment. Sufficient information must be provided for each stru

31、cture to enable the location and position of the structure to be determined. Azimuth indication shall not be required for such structures. G 1000 / 6 n 113-2007 RCC-M - Edition 2007 Subsection G G 2000 MATERIALS G 2100 GENERAL Chapter G 2000 sets out conditions for selection and use of materials for

32、 the manufacture of products and parts up to acceptance for the structures covered by Subsection G. Where appropriate, reference is made to SECTION II, MATERIALS. Note: The terms ferritic steels and austenitic steels have sometimes been wrongly used in the various sections of this Code. Materials co

33、rresponding to procurement specification series M 3300, M 3400 and M 4000 of SECTION II, shall be considered as belonging to the category austenitic steels. Other materials belong to the category ferritic steels. G 2200 APPLICATION OF SECTION II The requirements of chapter M 100 shall be applicable.

34、 Table G 2200 lists the procurement specifications to which the Manufacturer shall refer for core support structures and certain internal structures. Where a choice is involved, such choice may be limited by conditions specified in the equipment specification. Class 1 criteria shall be applicable fo

35、r the acceptance of materials for core support structures. G 2300 SUSCEPTIBILITY TO INTERGRANULAR CORROSION G 2310 RULES FOR CLASSIFYING MATERIALS ACCORDING TO SUSCEPTIBILITY TO INTERGRANULAR CORROSION Reactor internals made from austenitic or austenitic-ferritic stainless steel shall be classified

36、according to susceptibility to intergranular corrosion into one of the following two groups: Group 1: materials which are possibly contaminated and are heated after solution heat treatment to a temperature of more than 450C. n 113-2007 G 2000 / 1 RCC-M - Edition 2007 Subsection G All items subjected

37、 to any type of welding shall be classified group 1. Castings which may be repaired by welding shall also be classified group 1. Group 2: materials which are possibly contaminated and are never heated after solution heat treatment to a temperature of more than 450C. The potential impact of intergran

38、ular corrosion on safety is so serious that even the most remote risk of contamination must be taken into consideration. G 2320 REQUIREMENTS G 2321 SELECTION OF STEEL GRADES Selection of steel shall be subject to the following restrictions. Group 1 is more restrictive than group 2. For group 1: - ve

39、ry-low-carbon austenitic stainless (and, where appropriate, controlled nitrogen content) steels with or without molybdenum; or austenitic-ferritic steel castings. For group 2: - low-carbon austenitic stainless steels (type Z5 CN 18-10) with or without molybdenum and type Z6 CND 17-12 for bolting mat

40、erials. The equipment specification may stipulate which grade of steel in the group is to be used. G 2322 DETECTING SUSCEPTIBILITY TO INTERGRANULAR CORROSION Unless otherwise stated in the procurement specifications, detecting susceptibility to intergranular corrosion is required for group 1 materia

41、ls, in cases where the carbon content as determined by ladle analysis is: - above 0.030% for austenitic stainless steels, - above 0.035% for controlled nitrogen austenitic stainless steels, - above 0.040% for cast austenitic-ferritic stainless steels, Detecting susceptibility to intergranular corros

42、ion is required using test specimens for group 2 materials, after non-sensitized solution heat treatment as specified in MC 1300, in cases where the carbon content as determined by ladle analysis is above 0.030%. The requirements are given in the relevant procurement specifications. G 2000 / 2 n 113

43、-2007 RCC-M - Edition 2007 Subsection G G 2400 COBALT CONTENT OF STAINLESS STEELS USED FOR REACTOR INTERNALS AND OF NICKEL-CHROMIUM-IRON ALLOYS Where the component parts of reactor internals are covered by a part or product procurement specification relating specifically to such parts, the cobalt co

44、ntent shall be stipulated in the procurement specification. Other component parts fall into two groups: - components located near to the reactor core and subjected to high neutron bombardment shall have a maximum cobalt content of 0.10%. These components must be individually listed in the equipment

45、specification. This covers the following components in particular: lower core barrel, baffles, formers, upper and lower neutron pads. - other components shall have a maximum cobalt content of 0.20%. TABLE G 2200 CORE SUPPORT STRUCTURES INTERNAL STRUCTURES Forgings .M 3301 Castings.M 3405 Plates .M 3

46、310 Forgings for: - upper support plate - core support plate .M 3302 Tubes.M 3304 Bars for bolting material and fuel assembly positioning pins.M 3308 Bolts .M 5140 Inconel 600 forgings .M 4102 Parts made from Inconel X 750.M 4104 Outlet nozzles. M 3301 class 2 Thermal screens. M 3307 (where applicab

47、le) class 2 Bars for bolting materials. M 3308 M 5110 (1)Bolts. M 5140 Hold-down spring. M 3205 Inconel X 750 split pins. M 4104 (1) Only applies to the attachment screws for the guide tubes alignment frames. n 113-2007 G 2000 / 3 RCC-M - Edition 2007 Subsection G G 2000 / 4 n 113-2007 RCC-M - Editi

48、on 2007 Subsection G G 3000 DESIGN G 3010 GENERAL REQUIREMENTS FOR ACCEPTABILITY The requirements for the acceptability of core support structure design are provided by satisfying either (1) or (2) below. (1) ASME Code Section III: NG 3100, NG 3200 plus NCA paragraphs and various technical annexes cited. Code cases listed in the equipment specification. RCC-M G 3300. The applicable editions of each document shall be specified in the equipment specificat