EJ/T 531-2001 Qualification of actuators for power--operated valve assemblies with safety--related functions for nuclear power plants (English Version)
1 Scope
This standard establishes the minimum requirements for, and guidance regarding, the methods and procedures for qualification of power-driven valve actuators with safety-related functions (hereinafter referred to as qualification).
This standard is applicable to qualification of safety-related valve actuators and actuator components in nuclear power plant.
2 Normative References
The following standards contain provisions which, through reference in this standard, constitute provisions of this standard. For dated reference (including editions), subsequent amendments to or revisions of, any of these publications do not apply. However, the parties coming to an agreement based on this standard are encouraged to investigate whether the most recent editions of the standards apply. For undated references (including editions), the latest editions of the normative documents referred to apply.
GB 6249 Regulations for Environmental Radiation Protection of Nuclear Power Plant
GB/T 12727 Qualification of Electrical Items of the Safety Systems for Nuclear Power Generating Stations(eqv IEC 780: 1984)
GB/T 13625 Seismic Qualification of Electrical Equipment of the Safety System for Nuclear Power Plants (eqv IEC 980: 1989)
3 Definitions
For the purpose of this standard, the following definitions apply.
3.1
Aging
The effects of operational, environmental, and system conditions on equipment during a period of time up to, but not including design basis events, or the process of simulating these events.
3.2
Air equivalent radiation dose
The energy that is absorbed per unit mass of air at the geometric center of the volume occupied by the specimen if it were replaced with air and a uniform flux were incident at the boundary of the volume, directed toward the center.
3.3
Analysis
A course of reasoning showing that a certain result is a consequence of assumed premises.
Foreword I
IEEE Introduction III
1 Scope
2 Normative References
3 Definitions
4 Communication Process
4.1 Requirements
4.2 Identification of the Generic Actuator Group
4.3 Qualification Testing of Selected Actuators in Generic Actuator Group
4.4 Qualification of Actuator for Specific Application
4.5 Documentation
5 Qualification Cases
5.1 Scope
5.2 Multiple Operations
5.3 Single Operation
6 Qualification Test
6.1 Baseline Operability Test
6.2 Normal Thermal Ageing Test
6.3 Normal Pressurization Cycle Test
6.4 Normal Radiation Aging Test
6.5 Vibration Aging Test
6.6 Seismic Simulation Test
6.7 Design Basis Event (DBE) Radiation Exposure Test
6.8 DBE Environment Test
Appendix A (Informative) Method of Selection of Representative Actuator(s) for Type Testing
Appendix B (Informative) Representative Normal and Design Basis Event Environmental Conditions
Appendix C (Informative) Rationale for Normal Thermal Aging
Appendix D (Informative) Rationale for vibration and seismic test methods
Appendix E (Informative) Performance Verification Test
EJ/T 531-2001 Qualification of actuators for power--operated valve assemblies with safety--related functions for nuclear power plants (English Version)
Standard No.
EJ/T 531-2001
Status
superseded
Language
English
File Format
PDF
Word Count
15000 words
Price(USD)
300.0
Implemented on
2002-2-1
Delivery
via email in 1 business day
Detail of EJ/T 531-2001
Standard No.
EJ/T 531-2001
English Name
Qualification of actuators for power--operated valve assemblies with safety--related functions for nuclear power plants
EJ/T 531-2001, EJ 531-2001, EJT 531-2001, EJ/T531-2001, EJ/T 531, EJ/T531, EJ531-2001, EJ 531, EJ531, EJT531-2001, EJT 531, EJT531
Introduction of EJ/T 531-2001
1 Scope
This standard establishes the minimum requirements for, and guidance regarding, the methods and procedures for qualification of power-driven valve actuators with safety-related functions (hereinafter referred to as qualification).
This standard is applicable to qualification of safety-related valve actuators and actuator components in nuclear power plant.
2 Normative References
The following standards contain provisions which, through reference in this standard, constitute provisions of this standard. For dated reference (including editions), subsequent amendments to or revisions of, any of these publications do not apply. However, the parties coming to an agreement based on this standard are encouraged to investigate whether the most recent editions of the standards apply. For undated references (including editions), the latest editions of the normative documents referred to apply.
GB 6249 Regulations for Environmental Radiation Protection of Nuclear Power Plant
GB/T 12727 Qualification of Electrical Items of the Safety Systems for Nuclear Power Generating Stations(eqv IEC 780: 1984)
GB/T 13625 Seismic Qualification of Electrical Equipment of the Safety System for Nuclear Power Plants (eqv IEC 980: 1989)
3 Definitions
For the purpose of this standard, the following definitions apply.
3.1
Aging
The effects of operational, environmental, and system conditions on equipment during a period of time up to, but not including design basis events, or the process of simulating these events.
3.2
Air equivalent radiation dose
The energy that is absorbed per unit mass of air at the geometric center of the volume occupied by the specimen if it were replaced with air and a uniform flux were incident at the boundary of the volume, directed toward the center.
3.3
Analysis
A course of reasoning showing that a certain result is a consequence of assumed premises.
Contents of EJ/T 531-2001
Foreword I
IEEE Introduction III
1 Scope
2 Normative References
3 Definitions
4 Communication Process
4.1 Requirements
4.2 Identification of the Generic Actuator Group
4.3 Qualification Testing of Selected Actuators in Generic Actuator Group
4.4 Qualification of Actuator for Specific Application
4.5 Documentation
5 Qualification Cases
5.1 Scope
5.2 Multiple Operations
5.3 Single Operation
6 Qualification Test
6.1 Baseline Operability Test
6.2 Normal Thermal Ageing Test
6.3 Normal Pressurization Cycle Test
6.4 Normal Radiation Aging Test
6.5 Vibration Aging Test
6.6 Seismic Simulation Test
6.7 Design Basis Event (DBE) Radiation Exposure Test
6.8 DBE Environment Test
Appendix A (Informative) Method of Selection of Representative Actuator(s) for Type Testing
Appendix B (Informative) Representative Normal and Design Basis Event Environmental Conditions
Appendix C (Informative) Rationale for Normal Thermal Aging
Appendix D (Informative) Rationale for vibration and seismic test methods
Appendix E (Informative) Performance Verification Test
