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