2025-6-15 18.97.9.169
Code of China Chinese Classification Professional Classification ICS Classification Latest News Value-added Services

Position: Chinese Standard in English/GB/T 15474-2010
GB/T 15474-2010   Classification on instrumentation and control function important to safety for nuclear power plants (English Version)
Standard No.: GB/T 15474-2010 Status:valid remind me the status change

Email:

Language:English File Format:PDF
Word Count: 9000 words Price(USD):220.0 remind me the price change

Email:

Implemented on:2011-5-1 Delivery: via email in 1 business day
,,
Standard No.: GB/T 15474-2010
English Name: Classification on instrumentation and control function important to safety for nuclear power plants
Chinese Name: 核电厂安全重要仪表和控制功能分类
Chinese Classification: F82    Nuclear instrument for reactor
Professional Classification: GB    National Standard
Issued by: AQSIQ;SAC
Issued on: 2010-11-10
Implemented on: 2011-5-1
Status: valid
Superseding:GB/T 15475-1995 Classification of quality assurance for instrumentation and control system and their electrical equipment of nuclear power plants
GB/T 15474-1995 Safety classification of instrumentation and control systems and their electrical equipment of nuclear power plants
Language: English
File Format: PDF
Word Count: 9000 words
Price(USD): 220.0
Delivery: via email in 1 business day
1 Scope This standard specifies the classification method for instrumentation and control function important to safety for nuclear power plants and their functional system and equipment, and determines the technical requirements and quality assurance requirements of each category in terms of functionality, reliability, performance, environmental durability and seismic performance. This standard is applicable to the design of all instrumentation and control systems (including safety systems and safety-related instrumentation systems) important to safety for new nuclear power plants. Note: Reference power plants and new nuclear power plants that have been designed may conditionally implement this standard according to the actual situation. 2 Normative References The following normative document contains provisions which, through reference in this text, constitute provisions of this standard. For dated references, subsequent amendments to, or revisions of, any of these publications do not apply. However, parties to agreements based on this standard are encouraged to investigate the possibility of applying the most recent edition of the normative document indicated below. For undated references, the latest edition of the normative document referred to applies. GB/T 12727 Nuclear Power Plants — Electrical Equipment of the Safety System — Qualification (GB/T 12727-2002, IEC 60780:1998, MOD) GB/T 13625 Seismic Qualification of Electrical Equipment of the Safety System for Nuclear Power Plants (GB 13625-1992, eqv IEC 60980:1988) GB/T 13626 Application of the Single Failure Criterion to Safety Systems in Nuclear Power Plant (GB/T 13626-2008, IEEE 379-2000, MOD) GB/T 13630 Design for Control Rooms of Nuclear Power Plants (GB/T 13630-1992, eqv IEC 60964) EJ/T 1143 Nuclear Power Plants — Design of Control Rooms — Function Analysis and Assignment (IEC 61839, MOD) HAF 003 Safety Provisions for Quality Assurance of Nuclear Power Plants HAD 102/14 Safety-related Instrumentation and Control Systems for Nuclear Power Plants 3 Terms and Definitions For the purposes of this standard, the following terms and definitions apply. 3.1 Anticipated operational occurrences All operational processes deviating from normal operation which are expected to occur once or several times during the operating life of the plant and which, in view of appropriate design provisions, do not cause any significant damage to items important to safety or lead to accident conditions. 3.2 Design basis accident (DBA) Accident conditions against which the nuclear power plant is designed according to established design criteria, and for which the damage to the fuel and the release of radioactive material are kept within authorized limits. 3.3 Design basis event (DBE) Term used to address the group of design basis accidents and anticipated operational occurrences. 3.4 I&C function Controlling, operating and/or monitoring implemented on the identified processes. 3.5 Functionality Attribute of a function which defines the operations which transform input information into output information. 3.6 I&C systems important for safety I&C systems (includes safety systems and safety related I&C systems.) whose malfunction or failure could lead to undue radiation exposure of the site personnel or members of the public, and those I&C systems that prevent anticipated operational occurrences from leading to a unacceptable consequences. 3.7 Safety systems Systems important to safety, provided to assure the safe shutdown of the reactor or the residual heat removal from the core, or to limit the consequences of anticipated operational occurrences and design basis accidents. 3.8 Safety related I&C systems Those I&C systems important for safety that are not part of the safety systems. 3.9 Postulated initiating events (PIE) Events identified during design as capable of leading to anticipated operational occurrences or accident conditions.
Foreword II Introduction IV 1 Scope 2 Normative References 3 Terms and Definitions 4 Classification Criteria and Methods 5 Description of Function Categories 6 Classification Procedure 7 Assignment of Technical Requirements to Categories Annex A (Informative) Applicable Standards and Technical Requirements on Different Categories of Functions Annex B (Informative) Comparison List of the Clauses in This Standard and the Equivalent Clauses in IEC 61226:2005 Annex C (Informative) Examples of Categories
Referred in GB/T 15474-2010:
*GB/T 12727-2017 Qualification of safety class electrical equipment for nuclear power plants
*GB/T 13625-2018 Seismic qualification of safety class electrical equipment for nuclear power plants
*GB/T 13626-2008 Application of the single failure criterion to safety systems in nuclear power plant
*GB/T 13630-2015 Design of control room of nuclear power plants
*EJT1143-
*HAF 003-1991 Nuclear power plant safety requirements for quality assurance
*HAD10214-
GB/T 15474-2010 is referred in:
* EJ/T 1180-2005 Design Criteria for Installed Radiation Monitoring System in PWR Nuclear Power Plant Buildings
* NB/T 20010.1-2010 PWR Nuclear Power Plant Valve - Part 1: General Standard for Design and Manufacture
* NB/T 20060-2012 The Separation Criterion for Instrumentation and Control Systems Important to Safety in Nuclear Power Plants
Code of China
Standard
GB/T 15474-2010  Classification on instrumentation and control function important to safety for nuclear power plants (English Version)
Standard No.GB/T 15474-2010
Statusvalid
LanguageEnglish
File FormatPDF
Word Count9000 words
Price(USD)220.0
Implemented on2011-5-1
Deliveryvia email in 1 business day
Detail of GB/T 15474-2010
Standard No.
GB/T 15474-2010
English Name
Classification on instrumentation and control function important to safety for nuclear power plants
Chinese Name
核电厂安全重要仪表和控制功能分类
Chinese Classification
F82
Professional Classification
GB
ICS Classification
Issued by
AQSIQ;SAC
Issued on
2010-11-10
Implemented on
2011-5-1
Status
valid
Superseded by
Superseded on
Abolished on
Superseding
GB/T 15475-1995 Classification of quality assurance for instrumentation and control system and their electrical equipment of nuclear power plants
GB/T 15474-1995 Safety classification of instrumentation and control systems and their electrical equipment of nuclear power plants
Language
English
File Format
PDF
Word Count
9000 words
Price(USD)
220.0
Keywords
GB/T 15474-2010, GB 15474-2010, GBT 15474-2010, GB/T15474-2010, GB/T 15474, GB/T15474, GB15474-2010, GB 15474, GB15474, GBT15474-2010, GBT 15474, GBT15474
Introduction of GB/T 15474-2010
1 Scope This standard specifies the classification method for instrumentation and control function important to safety for nuclear power plants and their functional system and equipment, and determines the technical requirements and quality assurance requirements of each category in terms of functionality, reliability, performance, environmental durability and seismic performance. This standard is applicable to the design of all instrumentation and control systems (including safety systems and safety-related instrumentation systems) important to safety for new nuclear power plants. Note: Reference power plants and new nuclear power plants that have been designed may conditionally implement this standard according to the actual situation. 2 Normative References The following normative document contains provisions which, through reference in this text, constitute provisions of this standard. For dated references, subsequent amendments to, or revisions of, any of these publications do not apply. However, parties to agreements based on this standard are encouraged to investigate the possibility of applying the most recent edition of the normative document indicated below. For undated references, the latest edition of the normative document referred to applies. GB/T 12727 Nuclear Power Plants — Electrical Equipment of the Safety System — Qualification (GB/T 12727-2002, IEC 60780:1998, MOD) GB/T 13625 Seismic Qualification of Electrical Equipment of the Safety System for Nuclear Power Plants (GB 13625-1992, eqv IEC 60980:1988) GB/T 13626 Application of the Single Failure Criterion to Safety Systems in Nuclear Power Plant (GB/T 13626-2008, IEEE 379-2000, MOD) GB/T 13630 Design for Control Rooms of Nuclear Power Plants (GB/T 13630-1992, eqv IEC 60964) EJ/T 1143 Nuclear Power Plants — Design of Control Rooms — Function Analysis and Assignment (IEC 61839, MOD) HAF 003 Safety Provisions for Quality Assurance of Nuclear Power Plants HAD 102/14 Safety-related Instrumentation and Control Systems for Nuclear Power Plants 3 Terms and Definitions For the purposes of this standard, the following terms and definitions apply. 3.1 Anticipated operational occurrences All operational processes deviating from normal operation which are expected to occur once or several times during the operating life of the plant and which, in view of appropriate design provisions, do not cause any significant damage to items important to safety or lead to accident conditions. 3.2 Design basis accident (DBA) Accident conditions against which the nuclear power plant is designed according to established design criteria, and for which the damage to the fuel and the release of radioactive material are kept within authorized limits. 3.3 Design basis event (DBE) Term used to address the group of design basis accidents and anticipated operational occurrences. 3.4 I&C function Controlling, operating and/or monitoring implemented on the identified processes. 3.5 Functionality Attribute of a function which defines the operations which transform input information into output information. 3.6 I&C systems important for safety I&C systems (includes safety systems and safety related I&C systems.) whose malfunction or failure could lead to undue radiation exposure of the site personnel or members of the public, and those I&C systems that prevent anticipated operational occurrences from leading to a unacceptable consequences. 3.7 Safety systems Systems important to safety, provided to assure the safe shutdown of the reactor or the residual heat removal from the core, or to limit the consequences of anticipated operational occurrences and design basis accidents. 3.8 Safety related I&C systems Those I&C systems important for safety that are not part of the safety systems. 3.9 Postulated initiating events (PIE) Events identified during design as capable of leading to anticipated operational occurrences or accident conditions.
Contents of GB/T 15474-2010
Foreword II Introduction IV 1 Scope 2 Normative References 3 Terms and Definitions 4 Classification Criteria and Methods 5 Description of Function Categories 6 Classification Procedure 7 Assignment of Technical Requirements to Categories Annex A (Informative) Applicable Standards and Technical Requirements on Different Categories of Functions Annex B (Informative) Comparison List of the Clauses in This Standard and the Equivalent Clauses in IEC 61226:2005 Annex C (Informative) Examples of Categories
About Us   |    Contact Us   |    Terms of Service   |    Privacy   |    Cancellation & Refund Policy   |    Payment
Tel: +86-10-8572 5655 | Fax: +86-10-8581 9515 | Email: coc@codeofchina.com | QQ: 672269886
Copyright: TransForyou Co., Ltd. 2008-2040
 
 
Keywords:
GB/T 15474-2010, GB 15474-2010, GBT 15474-2010, GB/T15474-2010, GB/T 15474, GB/T15474, GB15474-2010, GB 15474, GB15474, GBT15474-2010, GBT 15474, GBT15474