Standard No.:	EJ/T 531-2001
English Name:	Qualification of actuators for power--operated valve assemblies with safety--related functions for nuclear power plants
Chinese Name:	核电厂安全级阀门驱动装置的鉴定
Professional Classification:	EJ    Professional Standard - Nuclear Industry
Issued on:	2001-11-15
Implemented on:	2002-2-1
Status:	superseded
Superseded by:	NB/T 20093-2012 Qualification of Safety-related Valve Actuators for Nuclear Power Plants
Superseded on:	2012-4-6
Language:	English
File Format:	PDF
Word Count:	15000 words
Price(USD):	300.00
Delivery:	via email in 1 business day

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