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GB/T 41142-2021 English PDF

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GB/T 41142-2021: Hardware design requirements of computer-based instrumentation and control systems important to safety for nuclear power plants
Status: Valid
Standard IDUSDBUY PDFLead-DaysStandard Title (Description)Status
GB/T 41142-2021439 Add to Cart 4 days Hardware design requirements of computer-based instrumentation and control systems important to safety for nuclear power plants Valid

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Basic data

Standard ID: GB/T 41142-2021 (GB/T41142-2021)
Description (Translated English): Hardware design requirements of computer-based instrumentation and control systems important to safety for nuclear power plants
Sector / Industry: National Standard (Recommended)
Classification of Chinese Standard: F81
Word Count Estimation: 23,240
Issuing agency(ies): State Administration for Market Regulation, China National Standardization Administration

GB/T 41142-2021: Hardware design requirements of computer-based instrumentation and control systems important to safety for nuclear power plants


---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.
Hardware design requirements of computer-based instrumentation and control systems important to safety for nuclear power plants ICS 27:120:99 CCSF81 National Standards of People's Republic of China Nuclear Power Plant Safety Important Digital Instrumentation and Control System Hardware Design requirements (IEC 60987:2007, Nuclearpowerplants-Instrumentationandcontrol systems,MOD) Published on 2021-12-31 2022-07-01 Implementation State Administration for Market Regulation Released by the National Standardization Administration directory Preface III 1 Scope 1 2 Normative references 1 3 Terms and Definitions 1 4 Project Development Organization 2 4:1 General Requirements 2 4:2 Project decomposition 3 4:3 Quality Assurance 3 4:4 Programmable logic device development 4 5 Hardware Requirements 4 5:1 General Requirements 4 5:2 Functional and Performance Requirements 4 5:3 Reliability and/or Availability Requirements 5 5:4 Environmental suitability requirements 6 5:5 Documentation Requirements 6 6 Design and Development 6 6:1 General Requirements 6 6:2 Design Activities 7 6:3 Reliability7 6:4 Maintenance 7 6:5 Interface 8 6:6 Modification 8 6:7 Power failure 8 6:8 Component selection 8 6:9 Design Documentation 8 7 Verification and Confirmation (V 7:1 General requirements9 7:2 Validation plan9 7:3 Independence of Verification 9 7:4 Method 9 7:5 Documentation 10 7:6 Non-conformance to Item 10 7:7 Changes and Modifications 10 7:8 Installation Verification 10 7:9 Confirmation 10 7:10 Validation of existing equipment platforms 10 8 Identification 11 9 Manufacturing 11 9:1 Quality Assurance 11 9:2 Personnel training 11 9:3 Planning and Organization of Manufacturing Activities 12 9:4 Entering data 12 9:5 Purchasing 12 9:6 Production 13 10 Installation and commissioning 15 11 Maintenance 15 11:1 General requirements 15 11:2 Maintenance Requirements 16 11:3 Fault data 16 11:4 Maintaining Documentation 17 12 Modification 17 13 run 17 Appendix A (informative) Changes in the structure of this document compared to IEC 60987:200718 Reference 19

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 of Standardization Documents" drafted: This document uses the redrafted law to modify and adopt IEC 60987:2007 "Computer-based system for instrumentation and control important to the safety of nuclear power plants" Systematic Hardware Design Requirements": Compared with IEC 60987:2007, this document has many adjustments in structure: Appendix A lists this document and IEC 60987:2007 chapter: Bar number change comparison list: The technical differences between this document and IEC 60987:2007 and their reasons are as follows: --- Regarding normative reference documents, this document has made adjustments with technical differences to adapt to the technical conditions of our country and the circumstances of the adjustment: The situation is reflected in Chapter 2 "Normative References", and the specific adjustments are as follows: ● Replace IEC 60780 with GB/T 12727 and GB/T 36044 (see Chapter 8); ● Replacing IEC 61513 with NB/T:20026-2014 which has been modified to adopt international standards (see 7:9, 10:4, 12:2); ● Replacing IEC 60880 with NB/T:20054 modified to adopt international standards (see 4:4, 5:2:3, 7:9); ● Replacing IEC 62138 with NB/T:20055 modified to adopt international standards (see 4:4, 5:2:3, 7:9); ● Replace IAEANS-G-1:3 with GB/T 13626 (see 5:3:2): --- Deleted some terms and definitions in IEC 60987:2007 to meet the needs of the standard; --- Added the terms "computer-based system" and "computer-based system important to safety" (see 3:1 and 3:2) to accommodate the standard need; --- Change the security classification of the system, from level 1 and level 2 to security level systems and other systems (see 4:4, 5:2:1, 5:3:5, 7:3:1, 7:3:2, 10:7) to adapt to the current state of technology in my country; --- Deleted "Compliance with ISO 9001 is an acceptable method to meet these requirements" in 4:3, which is consistent with the quality of my country's nuclear power plants: Quantity assurance requirements are inconsistent (see 4:3 of IEC 60987:2007); --- Deleted "International" in 9:1:9 (see 9:1:9 of IEC 60987:2007/Amd1:2013), to apply to my country's certified national conditions; --- Changed the requirements for dimensional control and sampling inspection plan in 9:5:4:5 (see IEC 60987:2007/Amd1:2013 9:5:4:5) to adapt to the technical conditions of our country and increase the operability: The following editorial changes have been made to this document: --- Incorporated the amendments to IEC 60987:2007/Amd1:2013, and the outer margins of the clauses involved use vertical Double lines (‖) are marked; --- Editorial changes were made to the scope of Chapter 1; --- Deleted the system lifetime overview, qualification diagram and maintenance procedure examples (see IEC 60987:2007 Appendix A, Appendix B and Appendix C); --- Revised references: Please note that some content of this document may be patented: The issuing agency of this document assumes no responsibility for identifying patents: This document is proposed and managed by the National Standardization Technical Committee of Nuclear Instrumentation (SAC/TC30): This document is drafted by: China Nuclear Control System Engineering Co:, Ltd:, China Nuclear Power Research and Design Institute, Beijing Guangli Nuclear System Engineering Co:, Ltd: Company, National Nuclear Auto-Instrument System Engineering Co:, Ltd: The main drafters of this document: Wang Huaijing, Liu Rui, Liang Jialin, Sun Wu, Jing Yang, Liu Yanyang, Wu Zhiqiang, Jiang Guojin, Guo Chun: Nuclear Power Plant Safety Important Digital Instrumentation and Control System Hardware Design requirements

1 Scope

This document specifies the hardware design requirements for computer-based systems important to safety in nuclear power plants, including hardware requirements, design and development, verification And confirmation, identification, manufacturing, installation and commissioning, operation, maintenance and other related content: This document applies to the design of computer-based system hardware important to safety in nuclear power plants and the evaluation of pre-developed hardware (including firmware); It is also applicable to the design process and design verification of programmable logic devices: This document does not apply to computer hardware facilities used for software download and inspection:

2 Normative references

The contents of the following documents constitute essential provisions of this document through normative references in the text: Among them, dated citations documents, only the version corresponding to that date applies to this document; for undated references, the latest edition (including all amendments) applies to this document: GB/T 12727 Appraisal of safety-grade electrical equipment for nuclear power plants GB/T 13626 Single Fault Criterion Applied to Nuclear Power Plant Safety System GB/T 36044 Code for Appraisal of Electrical Equipment Important to Safety in Nuclear Power Plants NB/T:20026-2014 General requirements for instrumentation and control systems important to safety in nuclear power plants (IEC 61513:2011, MOD) NB/T:20054 Computer software for performing Class A functions for instrumentation and control systems important to safety in nuclear power plants (NB/T:20054-2011, IEC 60880:2006, MOD) NB/T:20055 Computer software for instrumentation and control systems important to safety in nuclear power plants to perform Class B and Class C functions (NB/T:20055- 2011, IEC 62138:2004, MOD)

3 Terms and Definitions

The following terms and definitions apply to this document: 3:1 computer-basedsystem Instrumentation and control (I system: Note: Computer-based systems are equivalent to digital systems, software-based systems, and programmable systems: [Source: NB/T:20026-2014, 3:11] 3:2 computer-basedsystemimportanttosafety System safety functions are systems important to safety in nuclear power plants that are implemented through built-in computer systems: [Source: HAD102/16-2004, Glossary Explanation] 3:3 firmware firmware A combination of hardware devices and computer instructions and data residing in read-only software in the device:
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