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GB/T 13284-2025: Design criteria of safety systems in nuclear power plants
Status: Valid GB/T 13284: Evolution and historical versions
| Standard ID | Contents [version] | USD | STEP2 | [PDF] delivered in | Standard Title (Description) | Status | PDF |
| GB/T 13284-2025 | English | 539 |
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Design criteria of safety systems in nuclear power plants
| Valid |
GB/T 13284-2025
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| GB/T 13284.1-2008 | English | 599 |
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The safety systems for nuclear power plants -- Part 1: Design criteria
| Valid |
GB/T 13284.1-2008
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| GB 13284-1998 | English | 959 |
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Criteria for safety systems for nuclear power plants
| Obsolete |
GB 13284-1998
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| GB 13284-1991 | English | RFQ |
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3 days [Need to translate]
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Design basis criteria for safety systems in nuclear power plants
| Obsolete |
GB 13284-1991
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PDF similar to GB/T 13284-2025
Basic data | Standard ID | GB/T 13284-2025 (GB/T13284-2025) | | Description (Translated English) | Design criteria of safety systems in nuclear power plants | | Sector / Industry | National Standard (Recommended) | | Classification of Chinese Standard | F83 | | Classification of International Standard | 27.120.20 | | Word Count Estimation | 26,236 | | Date of Issue | 2025-04-25 | | Date of Implementation | 2025-11-01 | | Older Standard (superseded by this standard) | GB/T 13284.1-2008 | | Issuing agency(ies) | State Administration for Market Regulation, China National Standardization Administration | GB/T 13284-2025: Design criteria of safety systems in 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.
ICS 27.120.20
CCSF83
National Standard of the People's Republic of China
Replaces GB/T 13284.1-2008
Design criteria for safety systems in nuclear power plants
Released on 2025-04-25
2025-11-01 Implementation
State Administration for Market Regulation
The National Standardization Administration issued
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 for standardization documents"
Drafting.
This document replaces GB/T 13284.1-2008 "Nuclear power plant safety system Part 1.Design criteria" and GB/T 13284.1-
Compared with.2008, in addition to structural adjustments and editorial changes, the main technical changes are as follows.
--- Changed the definition of terms (see Chapter 3, Chapter 3 of the.2008 edition);
--- Deleted the contents of set value and safe state limit (see 4.4.4 of the.2008 edition);
--- Changed the safety classification of the interface equipment of the safety system (see 5.7.4.2, 5.6.3.1 of the.2008 edition);
--- Changed the content of common cause failure (see 5.17, 5.16 of the.2008 edition);
--- The manual control method has been changed (see 6.3, 6.2 of the.2008 edition);
--- Added maintenance bypass requirements (see 6.8).
Please note that some of the contents of this document may involve patents. The issuing organization of this document does not assume the responsibility for identifying patents.
This document was proposed and coordinated by the National Technical Committee for Standardization of Nuclear Instruments (SAC/TC30).
This document was drafted by. Nuclear Industry Standardization Institute, Beijing Guangli Nuclear System Engineering Co., Ltd., and China Nuclear Power Research and Design Institute.
The main drafters of this document are. Liang Xueyuan, Jiao Liling, Wang Xiaoyan, Du Jian, Pei Hongwei, Wu Fangjie, Ma Jianxin, Huang Junlong, Liu Chunming, Liu Hongchun,
Chen Peng and He Liang.
The previous versions of this document and the documents it replaces are as follows.
--- First issued as GB 13284-1991 in.1991 and first revised in.1998;
--- In the second revision in.2008, the standard number was changed to GB/T 13284.1-2008;
---This is the third revision.
Design criteria for safety systems in nuclear power plants
1 Scope
This document specifies the minimum functional and design requirements for the power source, instrumentation and control parts of the nuclear power plant safety system.
This document applies to the design of those systems required to prevent or mitigate the consequences of design basis events and to protect public health and safety.
It is used as a reference for the design of all safety-related systems, structures and equipment required to protect the safety of the entire nuclear power plant.
2 Normative references
The contents of the following documents constitute essential clauses of this document through normative references in this document.
For referenced documents without a date, only the version corresponding to that date applies to this document; for referenced documents without a date, the latest version (including all amendments) applies to
This document.
GB/T 5204 Periodic testing and monitoring of safety systems in nuclear power plants
GB/T 12727 Identification of electrical equipment important to safety in nuclear power plants
GB/T 12788 Safety-grade power system standards for nuclear power plants
GB/T 13286 Criteria for the independence of safety-class electrical equipment and circuits in nuclear power plants
GB/T 13626 Application of the single failure criterion to nuclear power plant safety systems
GB/T 13627 Standard for accident monitoring instrumentation in nuclear power plants
GB/T 13629 Applicable criteria for programmable digital devices in safety systems of nuclear power plants
NB/T.20061 Application of human factors engineering in nuclear power plant systems, equipment and facilities
NB/T 20394 Design and qualification of safety-class control panels, screens and racks for nuclear power plants
3 Terms and definitions
The following terms and definitions apply to this document.
3.1
Safety function
To ensure that nuclear facilities or activities can prevent and mitigate the radioactive consequences of normal operation of nuclear power plants, anticipated transient operation and accident conditions.
Specific functions that must be completed to ensure nuclear safety.
[Source. GB/T 41143-2021, 3.16, modified]
3.2
Safety systemsafety system
Safety factors used to ensure safe shutdown of the reactor, remove residual heat from the core, or limit the consequences of anticipated operational events and design basis events.
Need system.
3.3
Safety class safetyclass
Level 1E
A safety level for electrical equipment and systems in nuclear power plants.
Note 1.These equipment and systems are necessary to complete reactor emergency shutdown, containment isolation, core cooling, and heat removal from the containment and reactor.
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