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GB/T 13629-2023 English PDF

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GB/T 13629-2023: Criteria for programmable digital devices in safety systems of nuclear power generating stations
Status: Valid

GB/T 13629: Evolution and historical versions

Standard IDContents [version]USDSTEP2[PDF] delivered inStandard Title (Description)StatusPDF
GB/T 13629-2023English1189 Add to Cart 7 days [Need to translate] Criteria for programmable digital devices in safety systems of nuclear power generating stations Valid GB/T 13629-2023
GB/T 13629-2008English1519 Add to Cart 6 days [Need to translate] Applicable criteria for digital computers in safety systems of nuclear power plants Obsolete GB/T 13629-2008
GB/T 13629-1998EnglishRFQ ASK 9 days [Need to translate] Applicable criteria for digital computers in safety systems of nuclear power plants Obsolete GB/T 13629-1998
GB/T 13629-1992English759 Add to Cart 5 days [Need to translate] Criteria for safety system for nuclear power plants Obsolete GB/T 13629-1992

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Basic data

Standard ID GB/T 13629-2023 (GB/T13629-2023)
Description (Translated English) Criteria for programmable digital devices in safety systems of nuclear power generating stations
Sector / Industry National Standard (Recommended)
Classification of Chinese Standard F83
Classification of International Standard 27.120.20
Word Count Estimation 54,564
Date of Issue 2023-12-28
Date of Implementation 2024-04-01
Older Standard (superseded by this standard) GB/T 13629-2008
Issuing agency(ies) State Administration for Market Regulation, China National Standardization Administration

GB/T 13629-2023: Criteria for programmable digital devices in safety systems of nuclear power generating stations


---This is a DRAFT version for illustration, not a final translation. Full copy of true-PDF in English version (including equations, symbols, images, flow-chart, tables, and figures etc.) will be manually/carefully translated upon your order.
ICS 27:120:20 CCSF83 National Standards of People's Republic of China Replace GB/T 13629-2008 Programmable digital devices in nuclear power plant safety systems Applicable criteria generatingstations 2024-04-01 Implementation State Administration for Market Regulation Released by the National Standardization Administration Committee

Table of contents

Preface III 1 Scope 1 2 Normative references 1 3 Terms and definitions, abbreviations 1 3:1 Terms and definitions 1 3:2 Abbreviations 2 4 Safety System Design Basis 3 5 Safety System Guidelines 3 5:1 Single Failure Criterion 3 5:2 Completion of protective action 3 5:3 Quality 3 5:4 Equipment Qualification 7 5:5 System integrity 7 5:6 Independence 9 5:7 Testing and calibration capabilities12 5:8 Information display 12 5:9 Access control14 5:10 Maintenance18 5:11 Identification 19 5:12 Auxiliary facilities19 5:13 Multi-unit nuclear power plants19 5:14 Human Factors Engineering Considerations 19 5:15 Reliability19 5:16 Common cause failure criterion 19 5:17 Use of commodity-grade digital devices20 5:18 Simplicity 20 6 Function and design requirements for monitoring command equipment 21 7 Function and design requirements of execution device 21 8 Requirements for power source 21 Appendix A (informative) Hazard identification and control 22 A:1 Background 22 A:2 Purpose of hazard analysis22 A:3 Hazard Analysis Implementation Guide 22 Appendix B (Informative) Communications Independence 34 B:1 Background 34 B:2 Discussion 34 Appendix C (informative) Determination of diversity needs 39 C:1 Diversity and Defense in Depth Analysis39 C:2 Sufficient diversity to eliminate common cause failures39 C:3 Increase diversity to address common cause failure vulnerabilities39 C:4 Diversity of manual controls and displays 39 C:5 Diversity of automatic control 40 Appendix D (informative) Confirmation of applicability of commodity-level items 41 D:1 General principles 41 D:2 Preparation for confirmation of applicability of commodity-level items 41 D:3 Development of applicability confirmation of commodity-level items 42 D:4 Maintenance of product-level item suitability confirmation 44 Reference 46

Foreword

This document complies with the provisions of GB/T 1:1-2020 "Standardization Work Guidelines Part 1: Structure and Drafting Rules of Standardization Documents" Drafting: This document replaces GB/T 13629-2008 "Applicable Guidelines for Digital Computers in Nuclear Power Plant Safety Systems" and is consistent with GB/T 13629- Compared with:2008, in addition to structural adjustments and editorial changes, the main technical changes are as follows: ---Changed the scope of application of the document, changing "digital computer" to "programmable digital device" (see Chapter 1,:2008 version Chapter 1); ---Changed the definitions of the terms "commodity-level items", "firmware", "hazard" and "hazard analysis" (see Chapter 3, Chapter 3 of the:2008 edition); ---Deleted the terms and definitions "acceptance testing", "application software", "structure", "complexity", "component", "computer" and "computer instructions" "Computer Program" "Computer System" "Configuration" "Configuration Control" "Configuration Items" "Configuration Management" "Correctness" "Data" "Data Structure" "Construction", "Design", "File", "Documentation", "Error", "Execution", "Failure", "Fault", "Function", "Functional Unit", "Hardware", "Implementation", "Interface" "Modules" "Procedures" "Qualification Tests" "Requirements" "Requirements Specifications" "Software" "Software Maintenance" "Software Quality Measurement" "Software Tools" "Specification", "System", "System Software", "System Test", "Test", "Test Outline", "Confirmation", "Verification", "Verification and Confirmation" (see Chapter 3 of the:2008 edition); ---Added terms and definitions "safety state", "functional state", "key characteristics", "basic components", "programmable digital device", "digital security" System-wide” (see Chapter 3); ---Added abbreviations (see 3:2); ---Added relevant criteria requirements for single faults (see 5:1); ---Changed the content of software tools used in digital devices, software and hardware development, firmware and programmable logic device development (see 5:3:3,:2008 version of 5:3:2); ---Added relevant requirements for function priority (see 5:5:5); ---Added detailed provisions on the redundant parts within the safety system and the independence between the safety system and other systems (see 5:6:5); ---Added 3 test and calibration criteria (see 5:7); --- Added relevant requirements for multi-sequence control and display (see 5:8); ---Increases the requirements for computer security prevention of security systems, especially provides relevant guidelines for safe development and operating environment (see 5:9); --- Added requirements for computer-related common cause failures (CCF) in safety systems (see 5:16); ---Added commodity-level applicability confirmation requirements for programmable equipment and software (see 5:17); ---Added requirements for safety system simplicity (see 5:18): Please note that some content in this document may be subject to patents: The publisher of this document assumes no responsibility for identifying patents: This document is proposed and coordinated by the National Nuclear Instrumentation Standardization Technical Committee (SAC/TC30): This document was drafted by: Nuclear Industry Standardization Institute, Beijing Guangli Nuclear System Engineering Co:, Ltd:, Ministry of Ecology and Environment Nuclear and Radiation Safety Center, State Nuclear Power Instrument System Engineering Co:, Ltd:, and CNNC Control System Engineering Co:, Ltd: The main drafters of this document: Jiao Liling, Cheng Jianming, Zhang Yadong, Du Qiaorui, Wang Xiaoyan, Du Jian, Deng Ruiyuan, Wu Feifei, Pei Hongwei, Wu Fangjie, Huang Junlong, Shi Qin, Liu Chunming, Wang Zhongqiu, Geng Wenxing, Liu Jingbin, Qiao Ning, Ren Chunxiang, Liu Zhikai, Wang Haifeng: The previous versions of this document and the documents it replaces are as follows: ---First published as GB/T 13629-1998 in:1998, first revised in:2008; ---This is the second revision: Programmable digital devices in nuclear power plant safety systems Applicable criteria

1 Scope

This document specifies the design guidelines for programmable digital equipment used in nuclear power plant safety systems, including safety system guidelines, monitoring command equipment The function and design requirements of the actuator, the function and design requirements of the actuator, and the requirements for the power source: This document applies to programmable digital devices in nuclear power plant safety systems:

2 Normative reference documents

The contents of the following documents constitute essential provisions of this document through normative references in the text: Among them, the dated quotations For undated referenced documents, only the version corresponding to that date applies to this document; for undated referenced documents, the latest version (including all amendments) applies to this document: GB/T 12727-2017 Qualification of safety-level electrical equipment for nuclear power plants GB/T 13284:1-2008 Nuclear power plant safety system Part 1: Design criteria GB/T 13625-2018 Seismic appraisal of safety-level electrical equipment in nuclear power plants GB/T 22032-2021 System and software engineering system life cycle process NB/T 20448-2017 Verification and validation of nuclear power plant systems and software 3 Terms and definitions, abbreviations 3:1 Terms and definitions The following terms and definitions apply to this document: 3:1:1 safestatesafestate A system state that is considered safe in its application scenario or a system condition that is consistent with the safety analysis of a nuclear power plant: 3:1:2 functionalstate functionalstate The operating state of a component or system specified by the programmable digital device (PDD) design: Note: Including operating mode, fault tolerance mode, and test/diagnosis/fault detection mode: 3:1:3 firmwarefirmware A combination of a hardware device and computer instructions and data that reside on the device as read-only software: Note: For consistency with this document, firmware is treated as software in a programmable device: 3:1:4 In order to ensure that commodity-level items can perform their intended safety functions, the important design, materials and performance of the items need to be verified (including the design process)

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