Design Criteria for Installed Radiation Monitoring System in PWR Nuclear Power Plant Buildings
1 Scope
This standard specifies the function and composition of installed radiation monitoring system in PWR nuclear power plant buildings, arrangement radiation monitoring point and the classification and requirements of measuring channel.
This standard is applicable to the design for installed radiation monitoring system in PWR nuclear power plant buildings.
This standard is not applicable to the design for controlled area access monitoring system and personal dose monitoring system.
2 Normative References
The following standards contain provisions which, through reference in this text, constitute provisions of this standard. For dated reference, subsequent modification to, or revisions of, any of these publications do not apply. However, all parties coming to an agreement according to this standard are encouraged to study whether the latest edition of these documents is applicable. For undated references, the latest edition of the normative document is applicable to this standard.
GB/T 8993 "Environmental Conditions and Testing Procedures for Nuclear Instrumentation"
GB/T 12727 "Qualification of Electrical Items of the Safety Systems for Nuclear Power Generating Stations"
GB/T 13625 "Seismic Qualification of Electrical Equipment of the Safety System for Nuclear Power Plants"
GB/T 15474 "Safety Classification of Instrumentation and Control Systems and Their Electrical Equipment of Nuclear Power Plants"
GB/T 15475 "Classification of Quality Assurance for Instrumentation and Control System and Their Electrical Equipment of Nuclear Power Plants"
3 Terms and Definitions
3.1 Area radiation monitoring
It is used for continuously monitoring the radiation dose rate and air activity concentration of a certain installed area in nuclear power plants.
3.2 Effluents monitoring
It is used for continuously monitoring the radioactive activity of effluents in nuclear power plants. The effluents include gas and liquid effluents, and the gas effluent generally refers to aerosol, iodine and inert gases.
3.3 Safety barrier monitoring
In nuclear power plants, the safety barrier refers to fuel element jacket, reactor coolant bearing boundary and containment. The safety barrier monitoring is used for monitoring the integrity of these three barriers (leakage situation).
3.4 Process monitoring
It is used for supervising the working state of certain important system and equipment in nuclear power plants utilizing the monitoring process media or the change of certain position radioactivity level. And the process monitoring includes safety barrier monitoring.
3.5 Single failure
It refers to a kind of random failure resulting in a certain component not implementing the intended function. All kinds of secondary failures caused by single random event shall be taken as the constituent of single failure.
3.6 Single failure criteria
It means that the equipment combination for implementing the same measurement mission can maintain the planned function when single random failure occurs to any part in it.
3.7 Physical separation
The physical separation shall include:
a) Geometric separation, such as distance and direction;
b) Appropriate barrier separation;
c) Combination of above
3.8 Function separation
It refers to all kinds of methods that make the function of a certain circuit or system free from the influence of another circuit or system.
3.9 Electrical separation
It refers to the loop that there is no electricity among component, equipment, channel or system.
3.10 Independent equipment
It refers to the equipment that is independent and has two following characteristics:
a) The capacity for implementing the required function is free from the influence of other equipment operation or failure;
b) The capacity for implementing the function is free from the influence of the consequence caused by functionated supposed initial incident.
4 Function of Radiation Monitoring System
The installed radiation monitoring system in PWR nuclear power plant buildings (hereinafter referred as monitoring system) shall be provided with three following functions at least.
4.1 Area Radiation Monitoring
The monitoring system shall truly monitor and indicate the radiation level and radioactive air contamination level of each important area, and guarantee the power plant staff free from unnecessary radiation exposure. The monitoring system shall also provide the radiation level information of each important area in power plant for radiation protection personnel, technical support personnel and radiation emergency personnel. This information may be used for analyzing, searching and judging the possible fault by relevant personnel so as to promptly handle the fault and guarantee the safe operation of nuclear power plants.
Foreword I
1 Scope
2 Normative References
3 Terms and Definitions
4 Function of Radiation Monitoring System
4.1 Area Radiation Monitoring
4.2 Effluents Monitoring
4.3 Process Monitoring
5 Monitoring System Composition and Measuring Channel Classification
6 Arrangement of Radiation Monitoring Equipment
6.1 General Principles
6.2 Arrangement of Area Gamma Radiation Monitoring Point
6.3 Arrangement of Air activity Concentration Monitoring Points
6.4 Arrangement of Effluents Monitoring Points
6.5 Arrangement of Process Monitoring Points
7 Requirements of Measuring Channel
7.1 General Requirements
7.2 Safety Class of Measuring Channel
7.3 Seismic Classification of Measuring Channel
7.4 Quality Assurance Classification of Measuring Channel
7.5 Quality Appraisal Classification of Channel
8 Applicable Standards of Each Measuring Channel Instrument
Annex A (Informative) Main Measuring Channels of Radiation Monitoring System in Ling Ao Nuclear Power Plants
Annex B (Informative) Applicable Standards of Radiation Monitoring System Instrument
EJ/T 1180-2005 Design Criteria for Installed Radiation Monitoring System in PWR Nuclear Power Plant Buildings (English Version)
Standard No.
EJ/T 1180-2005
Status
valid
Language
English
File Format
PDF
Word Count
5000 words
Price(USD)
100.0
Implemented on
2005-7-1
Delivery
via email in 1 business day
Detail of EJ/T 1180-2005
Standard No.
EJ/T 1180-2005
English Name
Design Criteria for Installed Radiation Monitoring System in PWR Nuclear Power Plant Buildings
Chinese Name
压水堆核电厂房固定式辐射监测系统设计准则
Chinese Classification
Professional Classification
EJ
ICS Classification
Issued by
CSTIND
Issued on
2005-04-11
Implemented on
2005-7-1
Status
valid
Superseded by
Superseded on
Abolished on
Superseding
Language
English
File Format
PDF
Word Count
5000 words
Price(USD)
100.0
Keywords
EJ/T 1180-2005, EJ 1180-2005, EJT 1180-2005, EJ/T1180-2005, EJ/T 1180, EJ/T1180, EJ1180-2005, EJ 1180, EJ1180, EJT1180-2005, EJT 1180, EJT1180
Introduction of EJ/T 1180-2005
Design Criteria for Installed Radiation Monitoring System in PWR Nuclear Power Plant Buildings
1 Scope
This standard specifies the function and composition of installed radiation monitoring system in PWR nuclear power plant buildings, arrangement radiation monitoring point and the classification and requirements of measuring channel.
This standard is applicable to the design for installed radiation monitoring system in PWR nuclear power plant buildings.
This standard is not applicable to the design for controlled area access monitoring system and personal dose monitoring system.
2 Normative References
The following standards contain provisions which, through reference in this text, constitute provisions of this standard. For dated reference, subsequent modification to, or revisions of, any of these publications do not apply. However, all parties coming to an agreement according to this standard are encouraged to study whether the latest edition of these documents is applicable. For undated references, the latest edition of the normative document is applicable to this standard.
GB/T 8993 "Environmental Conditions and Testing Procedures for Nuclear Instrumentation"
GB/T 12727 "Qualification of Electrical Items of the Safety Systems for Nuclear Power Generating Stations"
GB/T 13625 "Seismic Qualification of Electrical Equipment of the Safety System for Nuclear Power Plants"
GB/T 15474 "Safety Classification of Instrumentation and Control Systems and Their Electrical Equipment of Nuclear Power Plants"
GB/T 15475 "Classification of Quality Assurance for Instrumentation and Control System and Their Electrical Equipment of Nuclear Power Plants"
3 Terms and Definitions
3.1 Area radiation monitoring
It is used for continuously monitoring the radiation dose rate and air activity concentration of a certain installed area in nuclear power plants.
3.2 Effluents monitoring
It is used for continuously monitoring the radioactive activity of effluents in nuclear power plants. The effluents include gas and liquid effluents, and the gas effluent generally refers to aerosol, iodine and inert gases.
3.3 Safety barrier monitoring
In nuclear power plants, the safety barrier refers to fuel element jacket, reactor coolant bearing boundary and containment. The safety barrier monitoring is used for monitoring the integrity of these three barriers (leakage situation).
3.4 Process monitoring
It is used for supervising the working state of certain important system and equipment in nuclear power plants utilizing the monitoring process media or the change of certain position radioactivity level. And the process monitoring includes safety barrier monitoring.
3.5 Single failure
It refers to a kind of random failure resulting in a certain component not implementing the intended function. All kinds of secondary failures caused by single random event shall be taken as the constituent of single failure.
3.6 Single failure criteria
It means that the equipment combination for implementing the same measurement mission can maintain the planned function when single random failure occurs to any part in it.
3.7 Physical separation
The physical separation shall include:
a) Geometric separation, such as distance and direction;
b) Appropriate barrier separation;
c) Combination of above
3.8 Function separation
It refers to all kinds of methods that make the function of a certain circuit or system free from the influence of another circuit or system.
3.9 Electrical separation
It refers to the loop that there is no electricity among component, equipment, channel or system.
3.10 Independent equipment
It refers to the equipment that is independent and has two following characteristics:
a) The capacity for implementing the required function is free from the influence of other equipment operation or failure;
b) The capacity for implementing the function is free from the influence of the consequence caused by functionated supposed initial incident.
4 Function of Radiation Monitoring System
The installed radiation monitoring system in PWR nuclear power plant buildings (hereinafter referred as monitoring system) shall be provided with three following functions at least.
4.1 Area Radiation Monitoring
The monitoring system shall truly monitor and indicate the radiation level and radioactive air contamination level of each important area, and guarantee the power plant staff free from unnecessary radiation exposure. The monitoring system shall also provide the radiation level information of each important area in power plant for radiation protection personnel, technical support personnel and radiation emergency personnel. This information may be used for analyzing, searching and judging the possible fault by relevant personnel so as to promptly handle the fault and guarantee the safe operation of nuclear power plants.
Contents of EJ/T 1180-2005
Foreword I
1 Scope
2 Normative References
3 Terms and Definitions
4 Function of Radiation Monitoring System
4.1 Area Radiation Monitoring
4.2 Effluents Monitoring
4.3 Process Monitoring
5 Monitoring System Composition and Measuring Channel Classification
6 Arrangement of Radiation Monitoring Equipment
6.1 General Principles
6.2 Arrangement of Area Gamma Radiation Monitoring Point
6.3 Arrangement of Air activity Concentration Monitoring Points
6.4 Arrangement of Effluents Monitoring Points
6.5 Arrangement of Process Monitoring Points
7 Requirements of Measuring Channel
7.1 General Requirements
7.2 Safety Class of Measuring Channel
7.3 Seismic Classification of Measuring Channel
7.4 Quality Assurance Classification of Measuring Channel
7.5 Quality Appraisal Classification of Channel
8 Applicable Standards of Each Measuring Channel Instrument
Annex A (Informative) Main Measuring Channels of Radiation Monitoring System in Ling Ao Nuclear Power Plants
Annex B (Informative) Applicable Standards of Radiation Monitoring System Instrument
