Standard No.:	GB/T 16702.1-2025
English Name:	Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants―Part 1: General principle
Chinese Name:	压水堆核电厂核岛机械设备设计规范第1部分：总则
Professional Classification:	GB    National Standard
Source Content Issued by:	SAMR; SAC
Issued on:	2025-02-28
Implemented on:	2025-2-28
Status:	valid
Superseding:	GB/T 16702-2019 Design code for mechanical components in nuclear island of pressurized water reactor nuclear power plants
Target Language:	English
File Format:	PDF
Word Count:	220000 words
Translation Price(USD):	6600.0
Delivery:	via email in 1~5 business day

GB/T 16702.1-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants―Part 1: General principle English, Anglais, Englisch, Inglés, えいご This is a draft translation for reference among interesting stakeholders. The finalized translation (passing through draft translation, self-check, revision and verification) will be delivered upon being ordered. ICS 27.120.20 CCS F 69 National Standards of the People's Republic of China GB/T 16702.1-2025 Partially replaces GB/T 16702-2019 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part1: General principle 压水堆核电厂核岛机械设备设计规范 第1部分:总则 (English Translation) Issue date: 2025-02-28 Implementation date: 2025-02-28 Issued by the State Administration for Market Regulation the Standardization Administration of the People's Republic of China Contents Foreword Introduction 1 Scope 2 Normative references 3 Terms and definitions 4 General requirements 5 Device compliance with this document and its level 6 Documents 7 Quality assurance 8 Use of parts of GB/T 16702 Annex A (Normative) Properties of Design Materials Annex B (Normative) Experimental Stress Analysis Annex C(Normative) Determination of basic allowable stress limits Annex D (Normative) Design rules for equipment subjected to external pressure Annex E (Normative) Design of Circular Flange Bolted Connection Annex F (Normative) Design Rules for Linear Supports Annex G (Normative) Class 1 Container Opening Reinforcement Rules Annex H (Informative) Fatigue Analysis of Significant Geometric Discontinuities Annex I (Informative) Other Rules for Class I Pipeline Analysis Annex J (informative) Relevant rules for Class D guidelines Annex K (INFORMATIVE) Prevention of Rapid Fracture Annex L (informative) Rules to be followed for determining usage factors Annex M (Normative) Supplementary Requirements for Materials Annex N (Normative) Acceptance of supporting welding filler materials and welding process qualification Annex O (Informative) Stress Analysis Methods Annex P (Informative) Dynamic Analysis Method Annex Q (Informative) Design Qualification of Rectangular and Circular Section Welded Accessories on Class 1, 2 and 3 Piping Annex R (informative) Allowable installation deviations for review after completion of piping system Annex S (informative) Class 2 and 3 flexible hoses with metal braid Annex T (informative) Class FF flange design for Class 2 and 3 components Annex U (Normative) Integral flat head with large opening Bibliography Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants – Part 1: General principle 1 Scope This document specifies the general requirements for the design of mechanical equipment of nuclear island in PWR nuclear power plants. This document is applicable to the design of mechanical equipment (pressure-bearing equipment and its supports, internal components) of nuclear island in PWR nuclear power plant. 2 Normative references The contents of the following documents constitute the essential provisions of this document through normative references in the text. Among them, only the version corresponding to the date is applicable to this document for the referenced documents with a date; The latest version of the undated referenced document (including all amendments) is applicable to this document. GB/T 1954 Methods of measurement for ferrite content in austenitic Cr-Ni stainless steel weld metals GB/T 4960.2 Glossary for nuclear science and technology - Part 2: Fission reactor GB/T 16702 (all parts) Design code for mechanical components in nuclear island of pressurized water reactor nuclear power plants 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 16702.3-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 3: Class 2 components GB/T 16702.4-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 4: Class 3 components GB/T 16702.5-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 5：Small components 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 16702.7-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 7：Supports 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 3 Terms and Definitions The terms and definitions defined in GB/T 4960.2 and the following apply to this document. 3.1 general contractor natural or legal person responsible for overall design of nuclear power plants and construction of nuclear islands acting on behalf of the owner 3.2 contractor natural or legal person responsible for design and construction of entire nuclear islands or parts thereof such as nuclear steam supply systems 3.3 manufacturer subcontractor natural or legal person acting on behalf of a contractor responsible for factory manufacturing or site construction of certain equipment or part of equipment of nuclear islands or provision of certain services 3.4 equipment design specification document stipulating design requirements for equipment within a system based on design outputs of process systems 3.5 equipment specification document in which the general contractor or contractor responsible for design and construction of a nuclear power plant stipulates technical requirements and quality assurance requirements for equipment manufacturers 4 General requirements The design of mechanical equipment of nuclear island in PWR nuclear power plant shall be implemented in accordance with the provisions of GB/T 16702 (all parts). The version and supplementary provisions of this document should be specified in the equipment specification and order contract, and the purchase contract prepared by the equipment manufacturer should adopt the same version of this document. Units engaged in design activities can adopt methods different from those given in the "Informative Appendix" of this document, but they should prove in advance that they can achieve the specified purpose and abide by the provisions of the contract and ancillary documents. 5 Device compliance with this document and its level 5.1 Devices that comply with this document a) Pressure equipment: 1) Container; 2) Heat exchanger; 3) Pump; 4) Valve; 5) Pipeline. b) Other equipment: 1) Internal component of the stack; 2) Support of pressure-bearing equipment and storage tank; 3) Low pressure or atmospheric pressure storage tank. 5.2 Equipment classification 5.2.1 Classification of pressure equipment 5.2.1.1 Vessels, heat exchangers, pumps, valves, pipes The specification level of the equipment should be specified according to its safety level. The specification level is divided into three levels: specification level 1, specification level 2, and specification level 3. The specification level may be different from the safety level, but the specification level should be specified in the equipment design specification. The design requirements of Class 1 equipment shall comply with the provisions of GB/T 16702.2-2025. The design requirements of Class 2 equipment shall comply with the provisions of GB/T 16702.3-2025. The design requirements of Class 3 equipment shall comply with the provisions of GB/T 16702.4-2025.