Standard No.:	GB/T 16702-2019
English Name:	Design code for mechanical components in nuclear island of pressurized water reactor nuclear power plants
Chinese Name:	压水堆核电厂核岛机械设备设计规范
Chinese Classification:	F69    Nuclear reactor and nuclear island equipment of nuclear power plant
Professional Classification:	GB    National Standard
ICS Classification:	27.120.20 27.120.20    Nuclear power plants. Safety 27.120.20
Source Content Issued by:	SAMR; SAC
Issued on:	2019-12-31
Implemented on:	2020-7-1
Status:	superseded
Superseded by:	GB/T 16702.8-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants―Part 8：Low pressure or atmospheric storage tanks GB/T 16702.7-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants―Part 7：Supports GB/T 16702.6-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants―Part 6: Reactor vessel internals GB/T 16702.5-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants―Part 5：Small components GB/T 16702.4-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants―Part 4: Class 3 components GB/T 16702.3-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants―Part 3: Class 2 components GB/T 16702.2-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants―Part 2：Class 1 components GB/T 16702.1-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants―Part 1: General principle
Superseded on:	2025-2-28
Superseding:	GB/T 16702-1996 Design rules for mechanical components of PWR nuclear islands
Target Language:	English
File Format:	PDF
Word Count:	346000 words
Translation Price(USD):	10380.0
Delivery:	via email in 1 business day

GB/T 16702-2019 Design code for mechanical components in nuclear island of pressurized water reactor nuclear power plants 1 Scope This standard specifies the design rules for mechanical components in nuclear island of pressurized water reactor (PWR) nuclear power plants, including class 1 components, class 2 components, class 3 components, small components, reactor internals, supports, and low-pressure or atmospheric storage tanks. This standard is applicable to the design of mechanical components in nuclear island of PWR nuclear power plants. 2 Normative references The following referenced documents are indispensable for the application of this document. For dated references, only the edition cited applies. For undated references, the latest edition of the referenced document (including any amendments) applies. GB/T 150.3-2011 Pressure vessels - Part 3: Design GB/T 3098 Mechanical properties of fasteners GB/T 5310 Seamless steel tubes and pipes for high pressure boiler GB/T 5313 Steel plate with through-thickness properties GB/T 25778-2010 Procurement guidelines for welding consumables NB/T 20001-2013 Fabrication rules for mechanical components of PWR nuclear island NB/T 20002-2013 (all parts) Welding code for mechanical components of PWR nuclear islands NB/T 20003.1 Non-destructive testing for mechanical components in nuclear island of nuclear power plants - Part 1: General requirements NB/T 20003.2 Non-destructive testing for mechanical components in nuclear island of nuclear power plants - Part 2: Ultrasonic testing NB/T 20003.3 Non-destructive testing for mechanical components in nuclear island of nuclear power plants - Part 3: Radiographic testing NB/T 20003.4 Non-destructive testing for mechanical components in nuclear island of nuclear power plants - Part 4: Penetration testing NB/T 20003.5 Non-destructive testing for mechanical components in nuclear island of nuclear power plants - Part 5: Magnetic particle testing NB/T 20003.6 Non-destructive testing for mechanical components in nuclear island of nuclear power plants - Part 6: Eddy current testing of tubular products NB/T 20003.7 Non-destructive testing for mechanical components in nuclear island of nuclear power plants - Part 7: Visual testing NB/T 20003.8 Non-destructive testing for mechanical components in nuclear island of nuclear power plants - Part 8: Leak testing NB/T 20004-2014 Physical and chemical test methods for materials used in nuclear island components of nuclear power plants NB/T 20005.1 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants - Part 1: Class 1, 2 and 3 forgings NB/T 20005.2 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants - Part 2: Forgings for class 2 and 3 heat exchanger tube plates NB/T 20005.3 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants - Part 3: Forgings for class 2, 3 auxiliary pump shafts NB/T 20005.4 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants - Part 4: The forged or rolled parts for use in steam generator main steam systems, feedwater flow control systems, auxiliary feedwater systems and turbine bypass systems NB/T 20005.5 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants - Part 5: Class 1, 2 and 3 pressure retaining castings NB/T 20005.6 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants - Part 6: Motor support stand castings for reactor coolant pumps NB/T 20005.7 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants - Part 7: Class 1, 2, 3 steel plates NB/T 20005.8 Carbon steel and low alloy steel for PWR nuclear power plant - Part 8: Steel plates, beams and bars for class S1 and S2 supports NB/T 20005.9 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants - Part 9: Class 2, 3 seamless steel pipes NB/T 20005.10 Carbon and low alloy steels for pressurized water reactor nuclear power plants - Part 10: Class 2 and 3 steel pipes welded with filler metal NB/T 20005.11 Carbon steel and low alloy steel for pressurized water reactor nuclear power plant - Part 11: Seamless pipes for class S1 and S2 supports NB/T 20005.12 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants - Part 12: Seamless pipes for use in main steam systems, feedwater flow control systems, auxiliary feedwater systems and turbine bypass systems NB/T 20005.13 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants - Part 13: Seamless drawn carbon steel tubes for class 2 and 3 heat exchangers NB/T 20005.14 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants - Part 14: Class 2 and 3 butt-welding seamless pipe fittings NB/T 20005.15 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants - Part 15: Class 2 and 3 pipe fittings welded with filler metal NB/T 20005.16 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants - Part 16: Elbows for main steam systems NB/T 20005.17 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants - Part 17: Pushed formed elbows for use in main steam systems NB/T 20005.37 Carbon and low alloy steel for pressurized water reactor nuclear power plants - Part 37: 17Mn steel forgings for steam generator NB/T 20005.40 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants - Part 40: Low alloy steel plates for nuclear safety related equipment NB/T 20006.1 Alloy steel for pressurized water reactor nuclear power plants - Part 1: Mn-Ni-Mo steel forgings for reactor pressure vessel shells in the beltline region NB/T 20006.2 Alloy steel for pressurized water reactor nuclear power plants - Part 2: Mn-Ni-Mo steel forgings for reactor pressure vessel shells outside the beltline region NB/T 20006.3 Alloy steel for pressurized water reactor nuclear power plants - Part 3: Mn-Ni-Mo steel forgings for transition rings and flanges of reactor pressure vessels NB/T 20006.4 Alloy steel for pressurized water reactor nuclear power plants - Part 4: Mn-Ni-Mo steel forgings for reactor pressure vessel nozzles NB/T 20006.5 Alloy steel for pressurized water reactor nuclear power plants - Part 5: Mn-Ni-Mo alloy steel forgings for reactor pressure vessel heads NB/T 20006.6 Alloy steel for pressurized water reactor nuclear power plants - Part 6: Mn-Ni-Mo steel forgings for PWR steam generator tube plates NB/T 20006.7 Alloy steel for pressurized water reactor nuclear power plants - Part 7: Mn-Ni-Mo steel forgings for steam generators shells NB/T 20006.8 Alloy steel for pressurized water reactor nuclear power plants - Part 8: Mn-Ni-Mo steel forgings for steam generator upper heads NB/T 20006.9 Alloy steel for pressurized water reactor nuclear power plants - Part 9: Mn-Ni-Mo steel forgings for steam generator channel head NB/T 20006.10 Alloy steel for pressurized water reactor nuclear power plants - Part 10: Mn-Ni-Mo steel forgings for pressurizer and steam generator nozzles and covers NB/T 20006.11 Alloy steel for pressurized water reactor nuclear power plants - Part 11: Mn-Ni-Mo steel forgings for pressurizer shells and heads NB/T 20006.12 Alloy steel for pressurized water reactor nuclear power plants - Part 12: Mn-Ni-Mo steel main flange forgings for pressurized water reactor coolant pumps NB/T 20006.13 Alloy steel for pressurized water reactor nuclear power plants - Part 13: Alloy steel forgings for reactor coolant pump motor shaft assembles NB/T 20006.14 Alloy steel for pressurized water reactor nuclear power plants - Part 14: Forged nickel-chromium-molybdenum steel bars with or without vanadium for use in making Class 1 components bolts fastener NB/T 20006.15 Alloy steel for pressurized water reactor nuclear power plants - Part 15: Mn-Ni-Mo steel plates for pressure-retaining boundaries NB/T 20006.16 Alloy steel for pressurized water reactor nuclear power plants - Part 16: Mn-Ni-Mo steel plates for pressurizer supports NB/T 20006.36 Alloy steel for pressurized water reactor nuclear power plants - Part 36: 19MnNiMo steel forgings for reactor vessel core region NB/T 20006.37 Alloy steel for pressurized water reactor nuclear power plants - Part 37: 19MnNiMo steel forgings for reactor vessel non-core region NB/T 20006.41 Alloy steel for pressurized water reactor nuclear power plants - Part 41: Bars for bolts, nuts and washers of reactor vessel NB/T 20006.42 Alloy steel for pressurized water reactor nuclear power plants - Part 42: Alloy steel forgings used for nuclear safety related equipment NB/T 20007.1-2010 Stainless steel for pressurized water reactor nuclear power plants - Part 1: Class 1, 2 and 3 austenitic stainless steel forgings NB/T 20007.2 Stainless steel for pressurized water reactor nuclear power plants - Part 2: Austenitic stainless steel forgings for class 2 and 3 tube plates of heat exchanger NB/T 20007.3 Stainless steel for pressurized water reactor nuclear power plants - Part 3: Controlled nitrogen content austenitic stainless steel forgings for core supports and upper support plates NB/T 20007.4 Stainless steel for pressurized water reactor nuclear power plants - Part 4: Niobium stabilized austenitic stainless steel forgings for the shafts of reactor coolant pumps NB/T 20007.5-2010 Stainless steel for pressurized water reactor nuclear power plants - Part 5: Class 1, 2, 3 austenitic stainless steel plates NB/T 20007.6 Stainless steel for pressurized water reactor nuclear power plants - Part 6: Controlled nitrogen content austenitic stainless steel plate for reactor internal NB/T 20007.7 Stainless steel for pressurized water reactor nuclear power plants - Part 7: Austenitic stainless steel plate and strip for Class S1 and S2 supports NB/T 20007.8 Stainless steel for pressurized water reactor nuclear power plant - Part 8: Class 1, 2 and 3 austenitic stainless steel seamless pipes NB/T 20007.9 Stainless steel for pressurized water reactor nuclear power plants - Part 9: Class 1, 2 and 3 austenitic stainless steel seamless butt-welding pipe fittings NB/T 20007.10 Stainless steel for pressurized water reactor nuclear power plants - Part 10: Cold rolled or cold drawn seamless austenitic stainless steel tubes for class 2 and 3 heat exchangers NB/T 20007.11 Stainless steel for pressurized water reactor nuclear power plant - Part 11: Class 1, 2 and 3 austenitic stainless steel pipes welded with filler metal NB/T 20007.12 Stainless steel for pressurized water reactor nuclear power plant - Part 12: Class 1, 2 and 3 austenitic stainless steel pipe-fittings welded with filler metal NB/T 20007.13 Stainless steel for pressurized water reactor nuclear power plants - Part 13: Forged tubes and elbows made from controlled nitrogen austenitic stainless steel for reactor coolant piping NB/T 20007.14 Stainless steel for pressurized water reactor nuclear power plants - Part 14: Class 1, 2, 3 austenitic stainless steel forged or rolled bars NB/T 20007.15 Stainless steel for pressurized water reactor nuclear power plants - Part 15: Strain hardened hot worked rolled or forged bars made from austenitic stainless steel used for the fabrication of bolting material for reactor internals NB/T 20007.16 Stainless steel for pressurized water reactor nuclear power plants - Part 16: Class 2 and 3 martensitic stainless steel forgings NB/T 20007.17 Stainless steel for pressurized water reactor nuclear power plants - Part 17: Martensitic stainless steel forgings used for internal hold down springs NB/T 20007.18 Stainless steel for pressurized water reactor nuclear power plants - Part 18: Rolled or forged martensitic stainless steel parts for class 2 and 3 auxiliary pump drive shafts NB/T 20007.19 Stainless steel for pressurized water reactor nuclear power plants - Part 19: Class 1, 2 and 3 pressure-retaining martensitic stainless steel castings NB/T 20007.20 Stainless steel for pressurized water reactor nuclear power plant - Part 20: Martensitic stainless steel casting for non-pressure-retaining internal category A, B and C parts of pumps NB/T 20007.21 Stainless steel for pressurized water reactor nuclear power plants - Part 21: Martensitic stainless steel plates for use in making steam generator tube support plates NB/T 20007.22 Stainless steel for pressurized water reactor nuclear power plants - Part 22: Seamless pipes made from martensitic stainless steel for drive rods of reactor control rod drive mechanisms NB/T 20007.23 Stainless steel for pressurized water reactor nuclear power plants - Part 23: Class 1, 2 and 3 pressure-retaining austenitic-ferritic stainless steel castings NB/T 20007.24 Stainless steel for pressurized water reactor nuclear power plants - Part 24: Austenitic-ferritic stainless steel castings pressured for reactor coolant pump casing NB/T 20007.25 Stainless steel for pressurized water reactor nuclear power plants - Part 25: Chromium nickel austenitic-ferritic stainless steel containing no molybdenum for no-pressure-retaining cast internal pump parts of category A, B and C NB/T 20007.26 Stainless steel for pressurized water reactor nuclear power plants - Part 26: Austenitic-ferritic stainless steel centrifugally cast pipes for reactor coolant piping NB/T 20007.27 Stainless steel for pressurized water reactor nuclear power plants - Part 27: Cast elbows and inclined nozzles made from austenitic-ferritic stainless steel for reactor coolant piping NB/T 20007.33 Stainless steel for pressurized water reactor nuclear power plants - Part 33: 015Cr17Ni12Mo2N stainless steel forged pipes for reactor coolant piping NB/T 20007.36 Stainless steel for pressurized water reactor nuclear power plant - Part 36: Austenitic stainless steel forged bars used for pressure-retaining components of CRDM NB/T 20007.39 Stainless steel for pressurized water reactor nuclear power plants - Part 39: Martensitic stainless steel bars used for drive rod of CRDM NB/T 20007.40 Stainless steel for pressurized water reactor nuclear power plants - Part 40: Austenitic stainless steel forgings used for reactor vessel internals NB/T 20007.41 Stainless steel for pressurized water reactor nuclear power plants - Part 41: Austenitic stainless steel seamless pipes used for reactor vessel internals NB/T 20007.43 Stainless steel for pressurized water reactor nuclear power plants - Part 43: 022Cr17Ni12Mo2N austenitic stainless steel forgings used for nozzles for reactor coolant piping NB/T 20007.44 Stainless steel for pressurized water reactor nuclear power plants - Part 44: 015Cr17Ni12Mo2N austenitic stainless steel pipes for surge line pipe spool pieces NB/T 20007.45 Stainless steel for pressurized water reactor nuclear power plants - Part 45: 04Cr13Ni5Mo martensitic stainless steel for hold-down spring NB/T 20007.46 Stainless steel for pressurized water reactor nuclear power plant - Part 46: 06Cr13Al stainless steel plates used for steam generator NB/T 20007.47 Stainless steel for pressurized water reactor nuclear power plant - Part 47: 06Cr13Al stainless steel bars used for steam generator NB/T 20008.1 Other material for pressurized water reactor nuclear power plant - Part 1: Alloy steel forgings for use in reactor coolant system supports NB/T 20008.2 Other material for pressurized water reactor nuclear power plants - Part 2: Mn-Mo-V steel castings for use in the fabrication of steam generator and reactor coolant pump supports, main steam line supports NB/T 20008.3 Other material for pressurized water reactor nuclear power plants - Part 3: Class 3 copper-aluminium alloy castings for auxiliary system pumps and valves NB/T 20008.4 Other material for pressurized water reactor nuclear power plants - Part 4: Forged or rolled class 1, 2 and 3 nickel-chromium-iron alloy parts NB/T 20008.5 Other material for pressurized water reactor nuclear power plants - Part 5: Class 1 and 2 hot rolled nickel-chromium-iron alloy plates NB/T 20008.6 Other material for pressurized water reactor nuclear power plants - Part 6: Hot rolled nickel-chromium-iron alloy plates NB/T 20008.7 Other materials for pressurized water reactor nuclear power plants - Part 7: Seamless nickel-chromium-iron alloy for steam generator tubes bundles NB/T 20008.8 Other materials for pressurized water reactor nuclear power plants - Part 8: Hot extruded nickel-chromium-iron alloy pipes NB/T 20008.9 Other material for pressurized water reactor nuclear power plants - Part 9: Hot rolled or hot extruded nickel-chromium-iron alloy bars NB/T 20008.10 Other material for pressurized water reactor nuclear power plants - Part 10: Ni-Cr-Fe alloy rolled bars used for internal support pins and bolting NB/T 20008.11 Other material for pressurized water reactor nuclear power plant - Part 11: Rolled or forged bars for the manufacture of Class S1 and S2 shafts, tie-rods and support bolts NB/T 20008.12 Other material for pressurized water reactor nuclear power plant - Part 12: Forged or rolled bars for class 1, 2 and 3 bolts and nuts NB/T 20008.13 Other material for pressurized water reactor nuclear power plants - Part 13: Class 1, 2, 3 studs, bolts, screws, threaded rods and nuts NB/T 20008.15 Other material for pressurized water reactor nuclear power plants - Part 15: Titanium plate for use in the fabrication of class 3 heat exchanger plates NB/T 20008.17 Other material for pressurized water reactor nuclear power plants - Part 17: Class 2 and 3 unalloyed and alloy ductile iron castings NB/T 20008.24 Other material for pressurized water reactor nuclear power plants - Part 24: GH4145 alloy bars for reactor vessel internals NB/T 20008.27 Other materials for pressurized water reactor nuclear power plants - Part 27: ZCoCr29W4.5 castings used for CRDM NB/T 20008.28 Other material for pressurized water reactor nuclear power plants - Part 28: NS3105 alloy forgings for nuclear safety related equipment NB/T 20008.29 Other material for pressurized water reactor nuclear power plants - Part 29: NS3105 alloy plates and sheets for nuclear safety related equipment NB/T 20008.30 Other material for pressurized water reactor nuclear power plants - Part 30: NS3105 alloy pipes for nuclear safety related equipment NB/T 20008.31 Other material for pressurized water reactor nuclear power plants - Part 31: NS3105 alloy bars for nuclear safety related equipment NB/T 20008.32 Other material for pressurized water reactor nuclear power plants - Part 32: NS3306 alloy sheet and strip for CRDM NB/T 20008.34 Other material for pressurized water reactor nuclear power plants - Part 34: Alloy NS3105 U-blending tube used for steam generator NB/T 20010.9 PWR nuclear power plant valve - Part 9: Final examination and test in manufactory NB/T 20036.6-2011 Qualification of active mechanical equipment used in nuclear power plants - Part 6: Functional qualification requirements for valve assemblies 3 Terms and definitions For the purposes of this document, the following terms and definitions apply. 3.1 general contractor natural or legal person responsible for the overall design and the construction of the nuclear island structure, acting on behalf of the constructor in fulfilling duties 3.2 contractor natural or legal person responsible for the design and construction of the entire nuclear island or a portion thereof (e.g., the nuclear steam supply system) 3.3 manufacturer subcontractor natural or legal person who, on behalf of the contractor, is responsible for the factory manufacturing or on-site construction of specific components or a part of the components of the nuclear island, or for the provision of certain services 3.4 equipment specification document in which the general contractor or contractor undertaking the design and construction of a nuclear power plant specifies the technical requirements and quality assurance requirements to component manufacturers 3.5 equipment design specification document that specifies the design requirements for components within a system based on the design output of the process system 3.6 main primary system system consisting of all components and parts, including the reactor pressure vessel and its head components, the reactor coolant side of the steam generator, the reactor coolant pump and its first-stage shaft seal, the main piping and surge line, the pressurizer and its safety valves, the pressure-resistant housing of the control rod drive mechanism (CRDM), auxiliary systems connected to and belonging to the main loop, up to and including the second isolation valve 4 General provisions 4.1 Application of this standard 4.1.1 This standard, along with other relevant standards, shall constitute a set of technical rules for design and construction. 4.1.2 The version of this standard adopted, along with any supplementary provisions, shall be specified in the equipment specification and the order contract. For purchase contracts prepared by component manufacturers, the same version of this standard shall be adopted. 4.1.3 Entities engaged in design activities may use methods different from those specified in the "informative annexes," provided that they can demonstrate in advance that the specified objectives can be achieved and that they comply with the provisions of the contract and associated documents. 4.2 Processing of non-conformances 4.2.1 Internal non-conformances Internal non-conformances neither deviate from the provisions of the component purchase order/purchase contract nor from the provisions of this standard. Instead, they represent instances where the manufacturer deviates from or fails to meet its own specified requirements. In principle, processing of such internal non-conformances is the sole responsibility of the manufacturer. For internal non-conformances, a non-conformance report shall be prepared, but it may not be included in the component post-manufacturing documents. 4.2.2 External non-conformances External non-conformances are divided into two categories, including: a) Instances where the manufacturer deviates from or fails to meet the requirements specified in the technical documents attached to the component purchase order/purchase contract but satisfies the provisions of this standard. The manufacturer shall report to the contractor and negotiate corrective actions. If the manufacturer considers that no corrective actions are necessary, approval shall be obtained from the contractor. b) Instances where the manufacturer deviates from or fails to meet the requirements specified in the technical documents attached to the component purchase order/purchase contract and does not satisfy the provisions of this standard. The manufacturer shall report to both the contractor and the competent authority. Meanwhile, the manufacturer shall take corrective actions until the requirements of this standard are met. c) For the processing of both categories above, a non-conformance report shall be prepared and included in the component post-manufacturing documents. 4.3 Documents 4.3.1 Equipment specification 4.3.1.1 The equipment specification shall be a document with which the general contractor or contractor responsible for the design and construction of a nuclear power plant defines the technical and quality assurance requirements to component suppliers. A document that specifies design requirements for components within a system based on the design output of the process system may be referred to as an component specification or component design requirements. 4.3.1.2 The equipment specification shall include requirements in the following aspects: a) Purpose; b) Scope of supplies; c) Applicable documents, together with details of their conditions of application; d) Functional requirements; e) Design requirements (if any); f) Manufacturing requirements; g) Test and testing requirements; h) Document submission requirements; i) Quality assurance requirements; j) Quality certification documents. 4.3.2 General technical documents 4.3.2.1 Comprehensive layout and referencing documents 4.3.2.1.1 The comprehensive layout shall provide an overall description of a component or a major component part. It shall: a) Determine the geometrical characteristics of a component or a major component part; b) Give a understanding of the interconnection of parts, particularly from the perspectives of functionality, fabrication, and assembly. 4.3.2.1.2 The comprehensive layout, which may comprise plans, structural sketches, drawings, diagrams, charts or data sheets, shall describe the structural form and arrangement of a component or major component part. When necessary, the comprehensive layout shall also make reference to other more detailed documents. These documents specify: a) The identification number of all component parts (this number shall be the same number used in the component parts list); b) Main dimensions of the component including tolerances; c) Other parameters when relevant (tolerances for functional parameters, etc.). 4.3.2.2 Component parts list A component parts list covered by the technical requirements in this standard and the order contract shall be established. For each component part, this list shall indicate: a) Its name and description; b) Its reference in the comprehensive layout and referencing documents; c) Its characteristics or the reference of the referencing document which defines its characteristics. 4.3.2.3 Strength calculation sheet and stress report 4.3.2.3.1 The strength calculation sheet and stress report shall demonstrate that the component design meets the requirements of this standard and the equipment design specification. 4.3.2.3.2 The strength calculation sheet shall justify the selection of thicknesses and structural forms and, in particular, demonstrate that the requirements of 5.3, 6.3, 7.3, 8.3, 9.3, 10.3, and 11.3 with respect to minimum wall thicknesses and reinforcement rules have been complied with. 4.3.2.3.3 The stress report or strength calculation sheet shall justify compliance with the stress limitations of 5.3, 6.3, 7.3, 8.3, 9.3, 10.3, and 11.3 on bearing loads related to the conditions of the various categories and associated loading combinations indicated in the equipment specification. This report shall also cover compliance with any additional requirements likely to appear in the equipment specification. 4.3.3 Documents relating to procurement and fabrication processes (other than welding) 4.3.3.1 Description documents of fabrication workshops The description documents of fabrication workshops shall clearly specify the workshops and the work performed in them for the fabrication of components. 4.3.3.2 Part or product sub-purchase orders The part or product sub-purchase orders shall comply with the relevant provisions of this standard and the contractor's relevant technical documents (such as equipment specification). 4.3.3.3 Technical part and product manufacturing programme The technical part and product manufacturing programme shall specify the scope of component parts it applies to, the main stages in the manufacture and testing, the standards, specifications, procurement specifications, or contracts on which the programme is based, and control measures for the manufacturing process and critical processes, and demonstrate compliance with all requirements of this standard, the equipment specification, and the order contract. 4.3.3.4 Fabrication procedures or instructions The fabrication procedures or instructions shall be prepared based on the fabrication process, and shall meet the requirements specified in this standard and the contractor's relevant technical documents (such as equipment specification). They shall be adapted to the manufacturer's actual fabrication skills and capabilities. Each procedure or instruction may be specified by a set of properly identified documents. The contents of fabrication procedures or instructions are specified in the relevant provisions of NB/T 20001.

Contents Foreword III 1 Scope 2 Normative references 3 Terms and definitions 4 General provisions 4.1 Application of this standard 4.2 Processing of non-conformances 4.3 Documents 4.4 Components subject to this standard and component classes 4.5 Quality assurance 5 Class 1 components 5.1 General 5.2 Materials 5.3 Design 5.4 Fabrication and associated testings 5.5 Pressure tests of class 1 components in the main primary system 5.6 Overpressure protection 6 Class 2 components 6.1 General 6.2 Materials 6.3 Design 6.4 Fabrication and associated testings 6.5 Pressure tests of class 2 components 6.6 Overpressure protection 7 Class 3 components 7.1 General 7.2 Materials 7.3 Design of class 3 components 7.4 Fabrication and associated testings 7.5 Pressure tests of class 3 components 7.6 Overpressure protection 8 Small components 8.1 General 8.2 Materials 8.3 Design 8.4 Fabrication and its associated testings 8.5 Validation of pumps and acceptance tests 9 Reactor internals 9.1 General 9.2 Materials 9.3 Design 9.4 Fabrication and its associated testings 9.5 Non-destructive testing 10 Components supports 10.1 General 10.2 Materials 10.3 Design 10.4 Fabrication and associated testing 10.5 Standards supports and standard support members 11 Low-pressure or atmospheric storage tanks 11.1 General 11.2 Materials 11.3 Design 11.4 Fabrication and associated testings 11.5 Testing of low-pressure or atmospheric storage tanks Annex A (Normative) Properties of materials to be used in design Annex B (Normative) Experimental stress analysis Annex C (Normative) Determination of allowable basic stress limits Annex D (Normative) Design rules for components subjected to external pressure Annex E (Informative) Design of circular bolted flange connections Annex F (Normative) Design rules for linear supports Annex G (Normative) Rules for determination of opening reinforcement of class 1 vessels Annex H (Informative) Fatigue analysis of geometric discontinuities Annex I (Informative) Other rules applicable to the first-stage pipeline analysis under conditions requiring compliance with Level A criteria Annex J (Informative) Rules associated with level D criteria Annex K (Informative) Fast fracture resistance Annex L (Informative) Acceptable rules for determining usage factor Annex M (Normative) Supplementary requirements for materials Annex N (Normative) Acceptance of welding filler materials and welding procedure qualification for supports