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GB/T 5204-2021: Periodic surveillance testing of the safety system of nuclear power plant
Status: Valid GB/T 5204: Evolution and historical versions
| Standard ID | Contents [version] | USD | STEP2 | [PDF] delivered in | Standard Title (Description) | Status | PDF |
| GB/T 5204-2021 | English | 269 |
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Periodic surveillance testing of the safety system of nuclear power plant
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GB/T 5204-2021
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| GB/T 5204-2008 | English | 439 |
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Periodic tests and monitoring of the safety system of nuclear power plant
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GB/T 5204-2008
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| GB/T 5204-1994 | English | 359 |
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Periodic tests and monitoring of the safety system of nuclear power plant
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GB/T 5204-1994
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| GB 5204-1985 | English | RFQ |
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Periodic tests and monitoring of the protection system of nuclear reactors
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GB 5204-1985
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PDF similar to GB/T 5204-2021
Basic data | Standard ID | GB/T 5204-2021 (GB/T5204-2021) | | Description (Translated English) | Periodic surveillance testing of the safety system of nuclear power plant | | Sector / Industry | National Standard (Recommended) | | Classification of Chinese Standard | F65 | | Word Count Estimation | 13,11 | | Issuing agency(ies) | State Administration for Market Regulation, China National Standardization Administration | GB/T 5204-2021: Periodic surveillance testing of the safety system of nuclear power plant---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.
Periodic surveillance testing of the safety system of nuclear power plant
ICS 27:120:20
CCSF65
National Standards of People's Republic of China
Replacing GB/T 5204-2008
Periodic test and monitoring of nuclear power plant safety system
Published on 2021-12-31
2022-07-01 Implementation
State Administration for Market Regulation
Released by the National Standardization Administration
directory
Preface I
1 Scope 1
2 Normative references 1
3 Terms and Definitions 1
4 General Requirements 3
5 Design Requirements 3
6 Periodic testing and monitoring program requirements 4
7 Test types and methods 5
8 Test interval 8
Reference 10
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 replaces GB/T 5204-2008 "Nuclear Power Plant Safety System Periodic Testing and Monitoring", compared with GB/T 5204-2008, except
In addition to structural adjustments and editorial changes, the main technical changes are as follows:
--- Changed the content not involved in the scope (see Chapter 1, Chapter 1 of the:2008 edition);
--- Added normative reference document GB/T 13284:1 (see Chapter 2);
--- Added the terms "sequence", "channel", "test start", "test input", "test end" (see 3:4, 3:5, 3:12, 3:13, 3:14), delete
In addition to the term "monitoring" (see 3:8 of the:2008 edition), the terms "safety system", "safety function", "channel calibration", "channel inspection" have been changed
Check the definition of "load group" (see 3:1, 3:2, 3:6, 3:7, 3:10, 3:1, 3:2, 3:13, 3:12, 3:6 of the:2008 edition);
--- Added design requirements for periodic tests (see 5:11, 5:13, 5:17, 5:18, 5:19), and integrated some design requirements (see
5:5, 5:5, 5:6 of the:2008 edition), changed some design requirements (see 5:8, 5:10, 5:12, 5:14, 5:16, 5:20,
5:9, 5:11, 5:12, 5:13, 5:15, 5:16 of the:2008 edition);
--- Change the relevant content of the basic requirements of the regular test and monitoring program [see 6:1, 6:1b), 6:1:1, 6:1:3 of the:2008 edition];
--- Changed the content related to the objectives of the regular test and monitoring program [see 6:2b), g),:2008 edition 6:2b), g)];
--- Added the content of "online monitoring" (see 7:1:3:2);
--- Change the relevant requirements for response time verification (see 7:1:4:2, 7:1:4:3, 6:3:4:3, 6:3:4:2 of the:2008 edition);
--- Added the relevant content of the test method (see 7:2:6);
--- Added the test method for "simulated equipment/system" (see 7:2:9);
--- Added the test method for "digital equipment/system" (see 7:2:10);
--- Added the factors for determining the initial test interval based on risk guidance technology [see 8:5e), f)], and changed some factors [see
8:5c), d), 6:5:4c), d) of the:2008 edition];
--- Deleted "program format and file" (see 6:6 of the:2008 edition):
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 Power Research and Design Institute, Institute of Nuclear Industry Standardization:
The main drafters of this document: Zhu Pan, Liu Hongchun, Li Xiejin, Wu Qiaofeng, Chen Peng, Xu Dongfang, Zhou Jixiang, Du Jian, Feng Wei, Jiao Liling:
The previous versions of this document and its superseded documents are as follows:
--- First published in 1985 as GB/T 5204-1985, first revised in:1994, second revised in:2008;
---This is the third revision:
Periodic test and monitoring of nuclear power plant safety system
1 Scope
This document specifies the design criteria and requirements for the implementation of periodic testing and monitoring of nuclear power plant safety systems:
This document applies to the design of periodic testing and monitoring of safety systems in nuclear power plants:
This document does not involve the verification test after the maintenance and modification of the safety system of the nuclear power plant:
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 13284:1 Nuclear Power Plant Safety System Part 1: Design Criteria
GB/T 13629 Guidelines for the Application of Digital Computers in Nuclear Power Plant Safety Systems
HAD003/09 Quality Assurance During Commissioning and Operation of Nuclear Power Plants
3 Terms and Definitions
The terms and definitions defined in GB/T 13284:1 and the following terms and definitions apply to this document:
3:1
safety system safetysystem
Systems important to safety to ensure safe shutdown of the reactor, to remove residual heat from the core or to limit anticipated operational and design basis events
the consequences of this:
3:2
safetyfunction
To ensure that a facility or activity is capable of preventing and mitigating radioactivity during normal plant operation, anticipated operational transients and accident conditions
A specific purpose that must be achieved to ensure safety:
3:3
safetygroup
A minimal set of components, assemblies and equipment combinations that can perform the required safety function when a PIE occurs:
NOTE: A security group consists of one or more sequences:
[Source: GB/T 13284:1-2008, 3:19]
3:4
Sequence division
The name of a given system or group of equipment that is physically, electrically, and functionally independent of other redundant systems or groups of equipment:
3:5
channel
A configuration in which several interconnected components within a system emit a single output signal:
NOTE: A channel is terminated where a single output signal is combined with signals from other channels (eg monitoring channels or safety drive channels):
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