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GB/T 16702.3-2025 English PDF

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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
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Basic data

Standard ID GB/T 16702.3-2025 (GB/T16702.3-2025)
Description (Translated English) Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 3: Class 2 components
Sector / Industry National Standard (Recommended)
Classification of Chinese Standard F69
Classification of International Standard 27.120.20
Word Count Estimation 254,235
Date of Issue 2025-02-28
Date of Implementation 2025-02-28
Issuing agency(ies) State Administration for Market Regulation, China National Standardization Administration

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


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GB/T 16702.3-2025 English version. Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 3.Class 2 components ICS 27.120.20 CCSF69 National Standard of the People's Republic of China Partially replaces GB/T 16702-2019 Design specification for mechanical equipment of nuclear island of pressurized water reactor nuclear power plant Part 3.Class 2 equipment waterreactornuclearpowerplants-Part 3.Class2components Released on 2025-02-28 2025-02-28 Implementation State Administration for Market Regulation The National Standardization Administration issued

Table of Contents

Preface III Introduction IV 1 Scope 1 2 Normative references 1 3 Terms and Definitions 2 4 General 2 4.1 Boundaries of equipment and piping components and accessories 2 4.2 File 6 4.3 Identification 6 5 Materials 8 5.1 Overview 8 5.2 Selection of materials 8 5.3 Intergranular corrosion susceptibility 13 5.4 Cobalt content of austenitic and austenitic-ferritic stainless steels and nickel-chromium-iron alloys 14 5.5 Classification of internal components (structural categories) 14 6 Design15 6.1 Design rules 15 6.2 Vessel Design Rules. First Approach 23 6.3 Vessel Design Rules. Second Approach 86 6.4 Pump Design 129 6.5 General rules for valves 159 6.6 Pipeline Design 188 7 Manufacturing and Inspection 228 7.1 Overview 228 7.2 Preliminary documentation and requirements for manufacturing and inspection 228 7.3 Manufacturing Process 228 7.4 Welding related technical requirements 229 8 Pressure test 230 8.1 Overview 230 8.2 Water pressure test 230 8.3 Additional test requirements for valves 234 8.4 Air pressure test 235 9 Overpressure protection 236 9.1 General Rules236 9.2 Overpressure Analysis Report 239 9.3 Displacement requirement 240 9.4 Set pressure of direct pressure limiting devices 241 9.5 Technical requirements for the design and operation of pressure relief valves 242 9.6 Non-reclosing pressure relief devices 247 9.7 Determination of displacement 247 References 248

Foreword

This document is in accordance with the provisions of GB/T 1.1-2020 "Guidelines for standardization work Part 1.Structure and drafting rules for standardization documents" Drafting. This document is Part 3 of GB/T 16702 "Design Specification for Mechanical Equipment of Nuclear Island in Pressurized Water Reactor Nuclear Power Plant". The following parts are published. --- Part 1.General; --- Part 2.Class 1 equipment; --- Part 3.Level 2 equipment; --- Part 4.Level 3 equipment; --- Part 5.Small equipment; --- Part 6.Reactor internals; --- Part 7.Equipment support; --- Part 8.Low-pressure or atmospheric pressure storage tanks. This document replaces Chapter 6 Level 2 Equipment of GB/T 16702-2019 "Design Specifications for Mechanical Equipment of Nuclear Island of Pressurized Water Reactor Nuclear Power Plant". Compared with Chapter 6 in GB/T 16702-2019, in addition to structural adjustments and editorial changes, the main technical changes are as follows. --- Added terms and definitions (see Chapter 3); --- Added "Boundaries of equipment and pipeline components and accessories" and made adjustments to the boundaries between level 2 equipment and pipeline components and accessories. Detailed provisions (see 4.1); --- Changed some of the "material standards adopted" and adopted the material standard unification and material The results of unified brand names (see 5.2, 6.2 of the.2019 edition); --- Changed the description of working condition classification (see 6.1.2, 6.3.1.2 of the.2019 edition); --- Added "T level criteria" (see 6.1.4.7); --- Added requirements for quick-opening closures (see 6.2.2.5); --- Added "Verification test to determine the maximum design pressure" (see 6.1.8); --- Change "overpressure protection report" to "overpressure analysis report" (see 9.2, 6.6.2 of the.2019 edition); --- Added "Archive of reports" (see 9.2.5); --- Changed the relevant requirements for "determination of displacement" (see 9.7, 6.6.7 of the.2019 edition). Please note that some of the contents of this document may involve patents. The issuing organization of this document does not assume the responsibility for identifying patents. This document was proposed and coordinated by the National Nuclear Energy Standardization Technical Committee (SAC/TC58). This document was drafted by. China Nuclear Power Engineering Co., Ltd., China Nuclear Power Research and Design Institute, Shanghai Nuclear Engineering Research and Design Institute Co., Ltd. Co., Ltd., CGN Engineering Co., Ltd., Nuclear and Radiation Safety Center of the Ministry of Ecology and Environment, China Machinery Productivity Promotion Center, Shanghai Electric Nuclear Power Group Co., Ltd., Nuclear Industry Standardization Institute. The main drafters of this document are. Zuo Shuchun, Qu Changming, Wang Yanping, Meng Xianggai, Zhang Yaochun, Huang Zongren, Guo Lifeng, Zhou Quan, Ran Xiaobing, Sun Zhan, Sun Yingxue, Zheng Yue, Wang Zhenfeng, Fan Zhang, Zhu Jingmei, Zhang Wei, Sun Jiali, Li Donghui, Liu Cuibo, Zhang Zhiming, Li Dongliang, Zhang Jilai, Niu Yanying, Zhao Ziyi, Xu Xiaogang, Dong An, Wang Chunming, Li Huanming, Li Bingjin, Zheng Guangyao, Wu Bingyang, Zheng Bin, Chen Lang, Tan Pengcheng, Huang Qing, Gu Chunhui, Lan Yinhui, Wang Binghong, Ma Guoshun, Sun Yiyun, Wen Jing, Li Hailong, Ling Ligong, Sheng Chaoyang, Su Xihui, Li Yingke, Wu Feifei, Li Cang. The previous versions of this document and the documents it replaces are as follows. ---First published in.1996 as GB/T 16702-1996 and first revised in.2019.

Introduction

GB/T 16702 "Design Specification for Mechanical Equipment of Nuclear Island of Pressurized Water Reactor Nuclear Power Plant" is a general technical specification for the design of mechanical equipment of nuclear island of pressurized water reactor nuclear power plant. The standard is to implement the spirit of my country's nuclear safety regulations, actively promote the unification of the standard technical route of mechanical equipment of the nuclear island of pressurized water reactor nuclear power plants, and promote the development of pressurized water reactors. GB/T 16702 is an important part of the relevant standards for the independent design and localization of nuclear island mechanical equipment. The basic and universal standards for design activities of mechanical equipment in the nuclear island of a pressurized water reactor nuclear power plant are planned to consist of eight parts. --- Part 1.General. The purpose is to specify the overall requirements and related requirements for the design of mechanical equipment in the nuclear island of a pressurized water reactor nuclear power plant. Appendix for his partial use. --- Part 2.Class 1 equipment. The purpose is to specify the materials, design, manufacture, inspection, pressure test and overpressure of Class 1 pressure equipment. Requirements that need to be followed in design such as protection. --- Part 3.Class 2 equipment. The purpose is to specify the materials, design, manufacture, inspection, pressure test and overpressure of Class 2 pressure equipment. Requirements that need to be followed in design such as protection. --- Part 4.Class 3 equipment. The purpose is to specify the materials, design, manufacture, inspection, pressure test and overpressure of Class 3 pressure equipment. Requirements that need to be followed in design such as protection. --- Part 5.Small equipment. The purpose is to specify the materials, design, manufacture, inspection, hydraulic test and pump of small pressure equipment. Requirements that need to be followed in the design, such as identification and acceptance testing. --- Part 6.In-core components. The purpose is to specify the materials, design, manufacturing, inspection and other design requirements of in-core components. Require. --- Part 7.Equipment Support. The purpose is to specify the requirements to be followed in the design of mechanical equipment supports in the nuclear island of a pressurized water reactor nuclear power plant. Require. --- Part 8.Low-pressure or atmospheric pressure storage tanks. The purpose is to specify the materials, design, manufacture, inspection and hydraulic test of low-pressure or atmospheric pressure storage tanks. Requirements that need to be followed in design, such as verification. GB/T 16702 (all parts) together with NB/T.20001~NB/T.20009 series of standards constitute the pressurized water reactor nuclear power plant applicable to my country. The technical standard system for the design and manufacture of nuclear island mechanical equipment in power plants is based on independent nuclear power engineering experience and incorporates the experience of nuclear island mechanical design and manufacture. The research results of the unified standard technical route are in line with the requirements of my country's nuclear power regulatory system and industrial foundation, and are the norms and guidance for my country's pressurized water reactor nuclear power It is an important basis for the design and manufacturing of nuclear island mechanical equipment and other related activities. This document focuses on the design principles of Class 2 pressure equipment, adds design requirements for special components and structures, and updates material standards. The standard improves the requirements for materials, design, manufacturing, inspection, pressure testing and overpressure protection of Class 2 pressure equipment. This document is used in conjunction with GB/T 16702.1-2025. Design specification for mechanical equipment of nuclear island of pressurized water reactor nuclear power plant Part 3.Class 2 equipment

1 Scope

This document specifies the materials, design, manufacturing, inspection and overpressure protection of the second-level pressure equipment in the nuclear island mechanical equipment of a pressurized water reactor nuclear power plant. Requirements and corresponding tests are described. This document applies to the design of Class 2 pressure equipment and its components as specified in Chapter 5 of GB/T 16702.1-2025.

2 Normative references

The contents of the following documents constitute the essential clauses of this document through normative references in this document. For referenced documents without a date, only the version corresponding to that date applies to this document; for referenced documents without a date, the latest version (including all amendments) applies to This document. GB/T 150.3-2024 Pressure Vessels Part 3.Design GB/T 151 Heat Exchanger GB/T 16702.1-2025 Specification for design of mechanical equipment of nuclear island of pressurized water reactor nuclear power plant Part 1.General GB/T 16702.2-2025 Specification for design of mechanical equipment of nuclear island of pressurized water reactor nuclear power plant Part 2.Level 1 equipment GB/T 16702.7-2025 Specification for design of mechanical equipment for nuclear island of pressurized water reactor nuclear power plant Part 7.Equipment support NB/T.20001-2023 Specification for the manufacture of mechanical equipment for nuclear island of pressurized water reactor nuclear power plant NB/T.20002.1-2021 Specification for welding of mechanical equipment in nuclear island of pressurized water reactor nuclear power plant Part 1.General requirements NB/T.20002.5-2013 Specification for welding of mechanical equipment in nuclear island of pressurized water reactor nuclear power plant Part 5.Assessment of manufacturing workshop NB/T.20002.6-2021 Specification for welding of mechanical equipment in nuclear island of pressurized water reactor nuclear power plant Part 6.Product welding NB/T.20002.7 Specification for welding of mechanical equipment in nuclear island of pressurized water reactor nuclear power plant Part 7.Wear resistant cladding NB/T.20003 Nondestructive testing of mechanical equipment in nuclear island of nuclear power plant NB/T.20004 Physical and chemical testing methods for mechanical equipment materials in nuclear island of nuclear power plant NB/T.20005.1 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants Part 1.Forgings and rolled products for level 1, 2 and 3 equipment NB/T.20005.5 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants Part 5.Grade 1, 2 and 3 pressure-bearing castings NB/T.20005.7 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants Part 7.Steel plates for level 1, 2 and 3 equipment NB/T.20005.9 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants Part 9.Seamless steel tubes for level 2 and 3 equipment NB/T.20005.10 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants Part 10.For use in level 2 and 3 equipment welded with filler metal Steel pipe NB/T.20005.12 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants Part 12.Seamless steel pipes for main steam pipes NB/T.20005.13 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants Part 13.Seamless steel for heat transfer tubes in 2nd and 3rd stage heat exchangers Steel pipe NB/T.20005.14 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants Part 14.Grade 2 and 3 butt-weld seamless pipe fittings NB/T.20005.15 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants Part 15.Grade 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 pipes NB/T.20007.1 Stainless steel for pressurized water reactor nuclear power plants Part 1.Austenitic stainless steel forgings for level 1, 2 and 3 equipment NB/T.20007.5 Stainless steel for pressurized water reactor nuclear power plants Part 5.Austenitic stainless steel plates for level 1, 2 and 3 equipment

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