Standard No.:	GB/T 16702.5-2025
English Name:	Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants―Part 5：Small components
Chinese Name:	压水堆核电厂核岛机械设备设计规范第5部分：小型设备
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:	12500 words
Translation Price(USD):	375.0
Delivery:	via email in 1~5 business day

GB/T 16702.5-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants―Part 5：Small components 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 Standard of the People's Republic of China GB/T 16702.5-2025 Partly replaces GB/T 16702-2019 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 5: Small components 压水堆核电厂核岛机械设备设计规范 第5部分：小型设备 (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 Overall requirements 5 Materials 6 Design 7 Manufacturing and inspection 8 Qualification and acceptance test of pumps Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 5: Small components 1 Scope This document specifies the materials, design, manufacturing, inspection and other requirements of small and medium-sized equipment in nuclear island machinery and equipment of PWR nuclear power plant, and describes relevant tests. This document is applicable to the cable crane specified in GB/T 16702.1-2025. 2 Normative references The contents of the following documents constitute indispensable provisions of this document through normative references in this document. Among them, for referenced documents with a specified date, only the version corresponding to that date shall apply to this document; for referenced documents without a specified date, their latest version (including all amendment sheets) shall apply to this document. GB/T 16702.1-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 1: General principle 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 NB/T 20001 Fabrication rules for mechanical components of PWR nuclear island NB/T 20002.3 Specification for welding of nuclear island machinery and equipment in pressurized water reactor nuclear power plants - Part 3: Qualification of welding process NB/T 20002.6-2021 Specification for welding machinery and equipment of nuclear islands in pressurized water reactors - Part 6: Product welding NB/T 20003.2 Non-destructive testing of nuclear island machinery and equipment in nuclear power plants - Part 2: Ultrasonic testing NB/T 20003.3 Non-destructive testing of nuclear island machinery and equipment in nuclear power plants - Part 3: Radiographic testing NB/T 20003.4 Non-destructive testing of nuclear island machinery and equipment in nuclear power plants - Part 4: Penetration testing NB/T 20003.5 Non-destructive testing of nuclear island machinery and equipment in nuclear power plants - Part 5: Magnetic particle testing NB/T 20003.7 Non-destructive testing of nuclear island machinery and equipment in nuclear power plants - Part 7: Visual testing 3 Terms and definitions The terms and definitions defined in GB/T 16702.1-2025 apply to this document. 4 Overall requirements 4.1 General rules This document includes small equipment specified in 5.2 of GB/T 16702.1-2025. In the equipment specification or purchase order, the list and jurisdiction of the equipment manufactured in accordance with the requirements of this document should be listed. Clauses 4 to 7 specify the requirements applicable to vessels, heat exchangers and pipes. Clauses 4 and 8 specify the requirements applicable to pumps. 4.2 Documents to be delivered by the equipment manufacturer 4.2.1 Vessels, heat exchangers, pipes The equipment manufacturer shall at least provide the ordering party with the following documents: ——General drawing of equipment (for instrument pipe, axonometric drawing or equivalent drawing should be provided) and material list of main parts; ——Catalogue of welded joints (see N.1.1.2 in GB/T 16702.1-2025); ——Calculation book; ——Manufacturing certificate according to 6.8.2 of GB/T 16702.1-2025. 4.2.2 Pumps The pumps involved in this document shall be designed, manufactured and tested according to the requirements of the equipment design specification. These pumps are usually existing models produced by the manufacturer, with minor modifications if necessary. At least the manufacturer of the pump shall provide the ordering party with the following documents: ——Equipment identification documents; ——Calculation book (if specified in the purchase order); ——Manufacturing certificate according to 6.8.2 of GB/T 16702.1-2025. 5 Materials 5.1 General rules Specify the standards, grades and properties of materials used to manufacture the equipment in the equipment specification. When non-nuclear material standards are adopted, the requirements of 5.2 should also be met. 5.2 Supplementary requirements for material selection 5.2.1 Metallurgical process - Chemical composition 5.2.1.1 Carbon steel and alloy steel for welding For carbon steel and alloy steel to be welded, killed steel should be used, and the smelting analysis results should meet: C content ≤ 0.25%; S content ≤ 0.015%; P content ≤ 0.025%. 5.2.1.2 Austenitic or austenitic-ferritic stainless steels If the risk of intergranular corrosion is to be considered, it should be specified in the annex to the purchase order. For materials that need to consider the risk of intergranular corrosion, ultra-low carbon (austenitic stainless steel with carbon content less than 0.030%) or austenitic or austenitic-ferritic stainless steel containing stabilizing elements (ferrite content is 12% ~ 20%) materials should be used. 5.2.2 Heat-treated Materials shall be delivered in heat-treated condition. Unless otherwise specified, austenitic or austenitic-ferritic stainless steel materials shall be delivered in solid solution treatment condition. If the raw material needs to be stress relieved by heat treatment, the decrease of mechanical properties caused by heat treatment should be evaluated to ensure that the allowable stress value used in calculation is satisfied. 5.2.3 Inspection Material inspection requirements shall be specified in the equipment specification.