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GB/T 16702.5-2025: Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 5: Small components
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Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 5: Small components
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GB/T 16702.5-2025
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Basic data | Standard ID | GB/T 16702.5-2025 (GB/T16702.5-2025) | | Description (Translated English) | Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 5: Small components | | Sector / Industry | National Standard (Recommended) | | Classification of Chinese Standard | F69 | | Classification of International Standard | 27.120.20 | | Word Count Estimation | 22,289 | | 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 16702.5-2025: Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 5: Small components
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GB/T 16702.5-2025 English version. Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 5.Small 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 5.Small equipment
waterreactornuclearpowerplants-Part 5.Smalcomponents
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 1
4 General Requirements 1
4.1 General 1
4.2 Documents to be delivered by the equipment manufacturer 2
5 Materials 2
5.1 General 2
5.2 Supplementary requirements for material selection 2
6 Design 3
6.1 General requirements 3
6.2 Design rules for vessels and heat exchangers 5
6.3 Pipeline design rules 6
7 Manufacturing and Inspection 7
7.1 Processing requirements 7
7.2 Welding procedure qualification and acceptance of filler materials 8
7.3 Product welding 8
7.4 Weld inspection 10
7.5 Water pressure test 12
8 Pump identification and acceptance test 13
8.1 Scope and purpose of identification 13
8.2 Prototype Identification 13
8.3 Validity of Identification 13
8.4 Validity of changes to pump components 14
8.5 Acceptance test 14
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 5 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 8 Small Equipment in GB/T 16702-2019 "Design Specifications for Mechanical Equipment of Nuclear Island in Pressurized Water Reactor Nuclear Power Plants"
Compared with Chapter 8 in GB/T 16702-2019, in addition to structural adjustments and editorial changes, the main technical changes are as follows.
--- For carbon steel and alloy steel to be welded, the requirements for S and P content in smelting analysis have been changed (see 5.2.1.1,.2019 edition
8.2.2.1.1);
--- Added evaluation criteria and stress limits corresponding to test conditions (see 6.1.4.6 and 6.1.6);
--- Changed the value of the instrument pipeline length reduction factor (see 6.3.4.2, 8.3.3.4.2 of the.2019 edition);
--- Changed the relevant requirements for cutting (see 7.1.1, 8.4.1.1 of the.2019 edition);
--- Added requirements for internal boring of component groups (see 7.1.4);
--- Changed the minimum thickness of the root weld in the welding pool gas protection (see 7.3.4, 8.4.3.4 of the.2019 edition);
--- Added the standards and acceptance criteria for ultrasonic testing in volume inspection (see 7.4.3.1);
--- Increased the requirements for temperature and pressure holding time of the hydrostatic test (see 7.5);
--- Deleted the relevant content of valves (see 8.1.1 and 8.3.4 of the.2019 edition);
--- For the effectiveness of pump identification, the sample design pressure range has been changed (see 8.3, 8.5.3 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 Research and Design Institute, Nuclear Industry Standardization Institute, Shanghai Nuclear Engineering Research and Design Institute Co., Ltd.
Company, China Nuclear Power Engineering Co., Ltd., CGN Engineering Co., Ltd., Nuclear and Radiation Safety Center of the Ministry of Ecology and Environment, China Machinery Productivity Promotion
center.
The main drafters of this section are. Tang Chenhang, Tang Chuanbao, Wu Feifei, Sun Yingxue, Huang Zongren, Li Donghui, Wei Wei, Zhang Yu, Liu Wenjin, Zhang Wei,
Tian Jun, Wang Yuyang, Zhang Peiran, Fu Xiaolong, Liu Hongbin, He Jinsong, Yang Chuansheng, Zeng Zhongxiu, Tang Huapeng, Feng Lina, Feng Zhipeng, Wang Zhonghui,
Liang Xueyuan, Deng Ruiyuan, Li Cang, Liu Shangyuan, Wu Xinzhuang, Yu Hong, Huang Ruotao, Shi You, Dong An, Tian Jinmei, Chen Wanqi, Yuan Zhanhang, Zhou Peng, Zhou Zile,
Zhang Wei, Li Xinghua, Wen Jing, Ling Ligong, Pan Jun, and Su Xihui.
The previous versions of this document and the documents it replaces are as follows.
---First published in.1996 as GB/T 16702-1996, 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. This standard system is based on independent nuclear power engineering experience and incorporates nuclear island mechanical equipment
The standard technical route unifies the research results, conforms to the requirements of my country's nuclear power regulatory system and industrial foundation, and is the standard and guide for my country's pressurized water reactor nuclear power plants.
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 small equipment, adds evaluation criteria and stress limits for test conditions, and adds water pressure test
The temperature requirements for testing are improved, thereby improving the requirements that need to be followed in the design of materials, design, manufacturing, inspection, pressure testing, etc. of small equipment.
This document is used in conjunction with GB/T 16702.1-2025 and GB/T 16702.3-2025.
Design specification for mechanical equipment of nuclear island of pressurized water reactor nuclear power plant
Part 5.Small equipment
1 Scope
This document specifies the requirements for materials, design, manufacturing, inspection, etc. of small and medium-sized equipment of nuclear island mechanical equipment of pressurized water reactor nuclear power plants, and describes the relevant
test.
This document applies to the design of small equipment specified in GB/T 16702.1-2025.
2 Normative references
The contents of the following documents constitute 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 16702.1-2025 Specification for design of mechanical equipment of nuclear island of pressurized water reactor nuclear power plant Part 1.General
GB/T 16702.3-2025 Specification for design of mechanical equipment of nuclear island of pressurized water reactor nuclear power plant Part 3.Level 2 equipment
NB/T.20001 Specification for the manufacture of mechanical equipment for nuclear island of pressurized water reactor nuclear power plant
NB/T.20002.3 Specification for welding of mechanical equipment in nuclear island of pressurized water reactor nuclear power plant Part 3.Welding procedure qualification
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.20003.2 Nondestructive testing of mechanical equipment in nuclear island of nuclear power plant Part 2.Ultrasonic testing
NB/T.20003.3 Nondestructive testing of mechanical equipment in nuclear island of nuclear power plant Part 3.Radiographic testing
NB/T.20003.4 Nondestructive testing of mechanical equipment in nuclear island of nuclear power plant Part 4.Penetrant testing
NB/T.20003.5 Nondestructive testing of mechanical equipment in nuclear island of nuclear power plant Part 5.Magnetic particle testing
NB/T.20003.7 Nondestructive testing of mechanical equipment in nuclear island of nuclear power plant Part 7.Visual inspection
3 Terms and definitions
The terms and definitions defined in GB/T 16702.1-2025 apply to this document.
4 General requirements
4.1 General
This document includes small equipment specified in 5.2 of GB/T 16702.1-2025.In the equipment specification or purchase order,
Provide a list of equipment manufactured in accordance with the requirements of this document and the scope of jurisdiction.
Chapters 4 to 7 specify requirements applicable to vessels, heat exchangers and piping.
The requirements applicable to pumps are specified in Chapters 4 and 8.
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