IEEE DRAFT 382 : D05 2006
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
QUALIFICATION OF SAFETY-RELATED ACTUATORS FOR NUCLEAR POWER GENERATING STATIONS
15-03-2007
12-01-2013
Part I - Process
1 Overview
1.1 Scope
1.2 Purpose
2 Normative References
3 Definitions
4 Introduction
4.1 General
4.2 Requirements
5 Identification of the generic actuator group
5.1 Generic actuator group identification
5.2 Selection of actuator units for type testing
6 Qualification testing of selected actuators in generic
actuator group
6.1 Type test parameter values
6.2 Type test plan
6.3 Type test procedure
6.4 Inspection
6.5 Acceptance criteria
6.6 Generic actuator group design modification
7 Qualification of actuator for specific application
7.1 General
7.2 Actuator specification
7.3 Relationship to generic actuator group
7.4 Relationship to specification
8 Documentation
8.1 General
8.2 Documentation for qualification of generic actuator group
8.3 Documentation for qualification for a specific application
Part II - Tests
1 Baseline functional test
1.1 Scope
1.2 Test setup requirements
1.3 Test conduct
2 Normal thermal aging test
2.1 Scope
2.2 Test setup requirements
2.3 Test conduct
3 Normal radiation aging test
3.1 Scope
3.2 Test setup requirements
3.3 Test conduct
4 Cycle aging test
4.1 Scope
4.2 Test setup requirements
4.3 Test conduct
5 Vibration aging test
5.1 Scope
5.2 Test setup requirements
5.3 Test conduct
6 Seismic simulation test
6.1 Scope
6.2 Test setup requirements
6.3 Test conduct
7 DBE radiation exposure test
7.1 Scope
7.2 Test setup requirements
7.3 Test conduct
8 Normal pressurization cycle test Error! Bookmark not defined
8.1 Scope
8.2 Test setup requirements
8.3 Test conduct
9 DBE environment test
9.1 Scope
9.2 Test setup requirements
9.3 Test conduct
Annex A (informative) Method of selection of representative
actuator(s) for type testing
Annex B (informative) Rationale for vibration and seismic
test methods
Annex C (informative) Performance verification test
Annex D (informative) Glossary
Annex E (informative) Bibliography
Lays down criteria for qualification of safety-related actuators, and actuator components, in Nuclear Power Generating Stations in order to demonstrate their ability to perform their intended safety functions.
DocumentType |
Draft
|
PublisherName |
Institute of Electrical & Electronics Engineers
|
Status |
Superseded
|
IEEE 344-2013 | IEEE Standard for Seismic Qualification of Equipment for Nuclear Power Generating Stations |
IEEE 101 : 1987 | GUIDE FOR THE STATISTICAL ANALYSIS OF THERMAL LIFE TEST DATA |
IEEE 1205-2014 | IEEE Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Nuclear Power Generating Stations and Other Nuclear Facilities |
IEEE 323-2003 | IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations |
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