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GB/T 17569-2021: Classification for the items of pressurized water reactor nuclear power plants
Status: Valid GB/T 17569: Evolution and historical versions
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| GB/T 17569-2021 | English | 639 |
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Classification for the items of pressurized water reactor nuclear power plants
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GB/T 17569-2021
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| GB/T 17569-2013 | English | 498 |
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Classification for the items of pressurized water reactor nuclear power pants
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| GB/T 17569-1998 | English | 959 |
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Classification for the items of pressurized water reactor nuclear power plants
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PDF similar to GB/T 17569-2021
Basic data | Standard ID | GB/T 17569-2021 (GB/T17569-2021) | | Description (Translated English) | Classification for the items of pressurized water reactor nuclear power plants | | Sector / Industry | National Standard (Recommended) | | Classification of Chinese Standard | F69 | | Word Count Estimation | 35,374 | | Issuing agency(ies) | State Administration for Market Regulation, China National Standardization Administration | GB/T 17569-2021: Classification for the items of pressurized water reactor 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.
Classification for the items of pressurized water reactor nuclear power plants
ICS 27.120.20
CCSF69
National Standards of People's Republic of China
Replace GB/T 17569-2013
Item classification of PWR nuclear power plant
Released on 2021-10-11
2022-05-01 implementation
State Administration for Market Regulation
Issued by the National Standardization Management Committee
Table of contents
Foreword Ⅲ
1 Scope 1
2 Normative references 1
3 Terms, definitions and abbreviations 1
3.1 Terms and definitions 1
3.2 Abbreviations 2
4 General requirements 3
4.1 General requirements for classification 3
4.2 Classification and basic basis 4
5 Safety rating 4
5.1 Overview of the safety classification process 4
5.2 Identifying safety functions 6
5.3 Determine the mitigation safety function classification 8
5.4 Determine design precautions 11
5.5 Grading objects 12
5.6 Completeness and correctness of item classification 17
5.7 General requirements for item classification 17
6 Seismic classification 19
6.1 General requirements 19
6.2 Seismic Class I 19
6.3 Seismic Class Ⅱ 19
6.4 Non-nuclear seismic class 19
7 Selection of engineering design rules 19
7.1 General requirements of engineering design rules 19
7.2 System design requirements 20
7.3 Specification requirements for structures and equipment 20
8 Quality Assurance Level 21
8.1 General requirements 21
8.2 Quality Assurance Level 1 21
8.3 Quality Assurance Level 2 21
8.4 Quality Assurance Level 3 21
Appendix A (informative) Examples of mitigating safety features 22
Appendix B (Informative) Correspondence between this document and the item safety level in the current civil nuclear safety equipment supervision and management system 23
Appendix C (informative) Item safety classification example 24
C.1 Safety classification of pressure-bearing mechanical components 24
C.2 Safety classification of non-pressure-bearing mechanical parts 25
C.3 Safety classification of fuel assemblies and fuel-related components 26
C.4 Safety classification of electrical components 26
C.5 Safety classification of structures 27
Appendix D (informative) Examples of recommended engineering design rules selection 29
Reference 31
Figure 1 Flow chart of the security classification process 5
Figure 2 Correspondence between frequency and severity of accident consequences 6
Figure 3 Initial safety classification of items performing safety mitigation functions 14
Figure 4 The adjustment process of the initial security classification 15
Figure 5 Classification of items (after functional classification is completed) 16
Table 1 Example of a list of functions used in the early design phase 6
Table 2 Example of function list for detailed design 7
Table 3 Examples of acceptance limits for different power plant states 9
Table 4 Power plant status and reference frequency or phenomenon of hypothetical initiating event 9
Table 5 Characteristics of controllable state and safe state in AOO and DBA mitigation 10
Table 6 The relationship between the mitigation safety function and the safety classification adopted in the hypothetical originating event analysis 11
Table 7 Differences between mitigation safety features and design precautions 11
Table 8 Examples of mitigating safety features and design preventive measures 12
Table 9 System security classification for performing mitigation security functions 13
Table 10 Security levels of different categories of items 18
Table 11 System typical design requirements 20
Table A.1 Examples of mitigating safety functions 27
Table B.1 Correspondence between the safety classification of this document and the safety classification of items in the civil nuclear safety equipment supervision and management system 23
Table D.1 Relationship between pressure equipment safety classification and engineering design rules 29
Table D.2 The relationship between the safety level of electrical instrument control systems and equipment and engineering design rules 30
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"
Drafting.
This document replaces GB/T 17569-2013 "Classification of Items for Pressurized Water Reactor Nuclear Power Plants". Compared with GB/T 17569-2013, except for structural adjustment
In addition to the overall and editorial changes, the main technical changes are as follows.
a) Relevant terms, definitions and abbreviations in Chapter 3 have been revised in accordance with the changes in the content of the document (see Chapter 3, Chapter 3 of the.2013 edition);
b) Change the "General Provisions" to "General Requirements", and refer to the latest domestic and foreign materials, reorganize the content (see Chapter 4), and list them as 2 articles (see
4.1, 4.2), instead of the original 4 (see 4.1, 4.2, 4.3, 4.4 in the.2013 edition); the new 2 is "General Requirements for Classification" and "Division
Level types and basic basis";
c) Six articles (see 5.1~5.6) are added to Chapter 5, which fully explain the methodology of item
"Classification process overview" "Identify safety functions" "Determine the mitigation safety function classification" "Determine design precautions" "Classification objects" "Items
The completeness and correctness of the classification"; the original safety classification example in Chapter 5 (see 5.2~5.6 in the.2013 edition) is moved to
Appendix C (informative) "Item Safety Classification Sample", and adapted specific items according to the classification method and code in Chapter 5
Responsive modification;
d) Refer to the latest safety classification material SSG-30 of the International Atomic Energy Agency to supplement the safety classification requirements and increase the response
Design the safety classification requirements of the extended working condition equipment (see 5.3.2, 5.7, etc.);
e) According to HAD102/02-2019 and the practical experience of domestic PWR nuclear power plant engineering, the seismic requirements have been revised and added
The seismic requirements of items that respond to the design expansion conditions (see 6.1~6.3);
f) Amend "Determination of Code Level and Selection of Standards" to "Selection of Engineering Design Rules" (see Chapter 7).
Please note that some of the contents of this document may involve patents. The issuing agency of this document is not responsible for identifying patents.
This document was proposed and managed by the National Nuclear Energy Standardization Technical Committee (SAC/TC58).
Drafting organizations of this document. Institute of Nuclear Industry Standardization, Nuclear and Radiation Safety Center of Ministry of Ecology and Environment, China General Nuclear Power Engineering Co., Ltd., China
Nuclear Power Engineering Co., Ltd., China Nuclear Power Research and Design Institute, Shanghai Nuclear Engineering Research and Design Institute Co., Ltd.
The main drafters of this document. Zhang Xueyao, Lu Yan, Sun Zaozhan, Si Hengyuan, Zhang Huafeng, Jiang Huiyu, Cai Kewei, Yu Xiaoquan, Zhang Huaiyuan,
Chu Qibao, Zhao Danni, Qiao Ning, Ji Jiangwei, He Fan, Liang Xueyuan, Deng Ruiyuan, Yao Weida, Li Dongyuan, Hu Zongwen, Huang Jun, Wu Feifei, Liu Shangyuan,
Sun Yecong, Jin Wujian, Xiong Guangming, Niu Jingjuan, Yang Wen, Dong Ruilin, Wang Jiayun, Xu Yu, Sun Qian, Yuan Xia, Zhao Ke.
The previous versions of the documents replaced by this document are as follows.
---In.1998, it was first published as GB/T 17569-1998, and it was first revised in.2013.
---This is the second revision.
Item classification of PWR nuclear power plant
1 Scope
This document specifies the requirements for the safety classification, seismic classification, selection of engineering design rules, and quality assurance classification for PWR nuclear power plants
And rules.
This document is applicable to the classification of PWR nuclear power plant items. Other reactor-type nuclear power plants can refer to this document.
2 Normative references
The content of the following documents constitutes an indispensable clause of this document through normative references in the text. Among them, dated quotations
Only the version corresponding to the date is applicable to this document; for undated reference documents, the latest version (including all amendments) is applicable to
This document.
HAF003 Nuclear Power Plant Quality Assurance Safety Regulations
3 Terms, definitions and abbreviations
3.1 Terms and definitions
The following terms and definitions apply to this document.
3.1.1
Item
Generic term for structures, systems or components.
3.1.2
Items important to safety
Items that are part of a certain safety combination, or whose failure or malfunction may cause radiation exposure to plant personnel or the public.
3.1.3
Reactor coolant pressure boundary; RCPB
All components that bear the pressure of the reactor coolant, including pressure vessels, pipes, pumps, valves, etc., are.
a) The components of the reactor coolant system;
b) The part connected to the reactor coolant system.
1) For the system pipeline, up to and including the outermost isolation device during the normal operation of the reactor;
2) For the reactor coolant safety relief system, up to and including the safety relief valve.
3.1.4
Activecomponent
Components that rely on external inputs such as triggers, mechanical movements, or power sources to perform their functions.
3.1.5
Active safety system activesafetysystem
A safety system that mainly relies on active components (pumps, active valves, power equipment, etc.) to perform safety functions.
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