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GB/T 12727-2023: Qualification of electrical equipment important to safety for nuclear power plants
Status: Valid GB/T 12727: Evolution and historical versions
| Standard ID | Contents [version] | USD | STEP2 | [PDF] delivered in | Standard Title (Description) | Status | PDF |
| GB/T 12727-2023 | English | 439 |
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Qualification of electrical equipment important to safety for nuclear power plants
| Valid |
GB/T 12727-2023
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| GB/T 12727-2017 | English | 639 |
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Qualification of safety class electrical equipment for nuclear power plants
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GB/T 12727-2017
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| GB/T 12727-2002 | English | 799 |
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Nuclear power plants -- Electrical equipment of the safety system -- Qualification
| Obsolete |
GB/T 12727-2002
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| GB/T 12727-1991 | English | 479 |
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Qualification of electrical items of the safety systems for nuclear power generating stations
| Obsolete |
GB/T 12727-1991
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PDF similar to GB/T 12727-2023
Basic data | Standard ID | GB/T 12727-2023 (GB/T12727-2023) | | Description (Translated English) | Qualification of electrical equipment important to safety for nuclear power plants | | Sector / Industry | National Standard (Recommended) | | Classification of Chinese Standard | F83 | | Classification of International Standard | 27.120.20 | | Word Count Estimation | 21,238 | | Date of Issue | 2023-05-23 | | Date of Implementation | 2023-12-01 | | Older Standard (superseded by this standard) | GB/T 12727-2017 | | Issuing agency(ies) | State Administration for Market Regulation, China National Standardization Administration | GB/T 12727-2023: Qualification of electrical equipment 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.
ICS 27:120:20
CCSF83
National Standards of People's Republic of China
Replacing GB/T 12727-2017
Appraisal of electrical equipment important to safety in nuclear power plants
(IEC /IEEE60780-323:2016, Nuclear facilities-
Released on 2023-05-23
2023-12-01 Implementation
State Administration for Market Regulation
Released by the National Standardization Management Committee
table of contents
Preface III
1 Scope 1
2 Normative references 1
3 Terms and Definitions 1
4 Equipment qualification principles 3
4:1 Identification purpose 3
4:2 Qualification Lifetime and Qualification Status 4
4:3 Identification elements 4
4:4 Identification documents 4
5 identification method 4
5:1 Selection of identification method 4
5:2 Initial identification 5
5:3 Reassessment of qualification life5
5:4 Condition Monitoring 6
6 Appraisal Outline 6
6:1 General 6
6:2 Equipment specification 7
6:3 Qualification plan 8
6:4 Implementation of the qualification plan9
7 files 15
7:1 General requirements 15
7:2 General document requirements 15
7:3 Mitigation Environment Specific Documentation Requirements 16
7:4 Severe environment specific documentation requirements 16
Reference 17
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 12727-2017 "Appraisal of Safety-level Electrical Equipment in Nuclear Power Plants": Compared with GB/T 12727-2017, except knot
In addition to structural adjustments and editorial changes, the main technical changes are as follows:
a) Changed the "Definition of terms" (see Chapter 3, Chapter 3 of the:2017 edition);
b) Changed "identification target" to "identification purpose", and changed some descriptions (see 4:1, 4:1 of the:2017 edition);
c) Changed the description of "certification life and certification status" (see 4:2, 4:2 of the:2017 edition);
d) Added instructions that the equipment contains software (see 5:2:1, 5:4, 6:4:1:2, 6:4:1:8, 6:4:4, 7:2);
e) Changed "extending identification life" to "re-evaluation of identification life", and added a method for evaluating identification life (see 5:3, 5:3 of the:2017 edition);
f) Changed the description of condition monitoring (see 5:4, 5:4 of the:2017 edition);
g) Added "General Provisions" (see 6:1);
h) Changed "identification" to "equipment identification" and modified its content (see 6:2:2, 6:1:2 of the:2017 edition);
i) Added "Design extension condition" (see 6:2:6:3);
j) Added "electromagnetic environment conditions" (see 6:2:6:4);
k) Change "appraisal margin" to "service condition margin" (see 6:3:5, 6:2:4 of the:2017 edition);
l) The requirements for documents have been changed (see Chapter 7, Chapter 7 of the:2017 edition):
This document is modified to adopt IEC /IEEE60780-323:2016 "Identification of Electrical Equipment Important to Safety of Nuclear Facilities":
Compared with IEC /IEEE60780-323:2016, this document has made the following structural adjustments:
--- Delete the abbreviations in Chapter 4 of IEC /IEEE60780-323:2016, and the subsequent chapter numbers are extended;
--- Added 5:1 Selection of identification methods, after which the number of chapters will be extended:
The technical differences between this document and IEC /IEEE60780-323:2016 and their reasons are as follows:
--- Replaced IEEE Std344TM2013 (see Chapter 3) with the normative referenced GB/T 13625 to adapt to my country's national conditions;
--- Deleted the normative reference document IEC 60980 to adapt to my country's national conditions;
--- Deleted the terms 3:2, 3:3, 3:4, 3:5, 3:6, 3:11 to avoid confusion with definitions used in other standards;
--- Increased the term 3:19 to adapt to my country's national conditions;
--- Added 5:1 Selection of identification methods to improve the operability of the standard:
The following editorial changes have been made to this document:
--- In order to coordinate with the existing standards, the name of the standard is changed to "Appraisal of Electrical Equipment Important to Safety in Nuclear Power Plants";
---Changed references:
Please note that some contents of this document may refer to patents: The issuing agency of this document assumes no responsibility for identifying patents:
This document is proposed and managed by the National Nuclear Instruments Standardization Technical Committee (SAC/TC30):
This document is drafted by: Institute of Nuclear Industry Standardization, China General Nuclear Power Research Institute Co:, Ltd: Beijing Branch, China Guangdong Nuclear Power Engineering Co:, Ltd:
Division, Shanghai Nuclear Engineering Research and Design Institute Co:, Ltd:, China Nuclear Power Engineering Co:, Ltd:
The main drafters of this document: Jiao Liling, Wang Jiajun, Du Jian, Wang Gensheng, Qiu Jianwen, Gu Shenjie, Zhang Liqin, Zhang Jianbo, Jiang Hui, Zhou Liang,
Fan Sui and Wang Jin:
The release status of previous versions of this document and the documents it replaces are as follows:
--- First published as GB/T 12727-1991 in:1991, first revised in:2002, and second revised in:2017;
--- This is the third revision:
Appraisal of electrical equipment important to safety in nuclear power plants
1 Scope
This document specifies the relevant requirements for the appraisal principles, appraisal methods, appraisal program and appraisal documents of electrical equipment important to safety in nuclear power plants:
This document is applicable to the initial identification, maintenance of identification status and extension of identification life of electrical equipment important to safety in nuclear power plants and their interfaces:
It is used for the qualification of updating according to requirements after equipment changes:
2 Normative references
The contents of the following documents constitute the essential provisions of this document through normative references in the text: Among them, dated references
For documents, 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:
GB/T 13625 Seismic Appraisal of Safety-level Electrical Equipment in Nuclear Power Plants
3 Terms and Definitions
The following terms and definitions apply to this document:
3:1
Aging treatment ageconditioning
The sample equipment is exposed for a period of time under simulated environmental, operating and system conditions (excluding design basis accident conditions) to make the equipment performance
It can be degraded to the state where design basis accident simulation test is allowed:
[Source: GB/T 41143-2021, 7:2:11, modified]
3:2
status indicator condition indicator
A characteristic of a structure, system, or component that can be observed, measured, or exhibits a tendency to infer or directly indicate that the structure, system, or component
The current and future ability of a system or component to operate within acceptance criteria:
[Source: GB/T 41143-2021, 7:1:17, modified]
3:3
design basis events designbasisevents; DBE
A hypothetical initiating event used in the design to determine the acceptable performance requirements of a structure, system or component:
[Source: GB/T 41143-2021, 3:6]
3:4
Accident conditions that are not considered in the scope of design basis accidents are considered in the design process according to the best estimate method, and the accident conditions
The release of radioactive material is within acceptable limits:
Note: Design extension conditions include conditions that do not cause significant damage to the core and core melting (severe accident) conditions:
[Source: HAF102-2016, explanation of terms, with revisions]
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