IEEE 382-2006
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
View Superseded by
IEEE Standard for Qualification of Safety-Related Actuators for Nuclear Power Generating Stations
25-11-2019
English
15-03-2007
Important note : Users cannot be edited or removed once added to your Multi user PDF.
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
9 Baseline functional test
9.1 Scope
9.2 Test setup requirements
9.3 Test conduct
10 Normal thermal aging test
10.1 Scope
10.2 Test setup requirements
10.3 Test conduct
11 Normal radiation aging test
11.1 Scope
11.2 Test setup requirements
11.3 Test conduct
12 Cycle aging test
12.1 Scope
12.2 Test setup requirements
12.3 Test conduct
13 Normal pressurization cycle test
13.1 Scope
13.2 Test setup requirements
13.3 Test conduct
14 Vibration aging
14.1 Scope
14.2 Test setup requirements
14.3 Test conduct
15 Seismic simulation test
15.1 Scope
15.2 Test setup requirements
15.3 Test conduct
16 DBE radiation exposure test
16.1 Scope
16.2 Test setup requirements
16.3 Test conduct
17 DBE environment test
17.1 Scope
17.2 Test setup requirements
17.3 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
Presents 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.
| Committee |
Nuclear Power Engineering Committee
|
| DevelopmentNote |
Supersedes IEEE DRAFT 382. (03/2007)
|
| DocumentType |
Standard
|
| Pages |
38
|
| PublisherName |
Institute of Electrical & Electronics Engineers
|
| Status |
Superseded
|
| SupersededBy | |
| Supersedes |
| CSA N289.4 : 2012 | TESTING PROCEDURES FOR SEISMIC QUALIFICATION OF NUCLEAR POWER PLANT STRUCTURES, SYSTEMS, AND COMPONENTS |
| ASME AG-1 : 2019 | CODE ON NUCLEAR AIR AND GAS TREATMENT |
| ASME AG 1 : 2012 | CODE ON NUCLEAR AIR AND GAS TREATMENT |
| ASME QME 1 : 2017 | QUALIFICATION OF ACTIVE MECHANICAL EQUIPMENT USED IN NUCLEAR FACILITIES |
| IEEE/ANSI N42.4-1971 | American National Standard for High Voltage Connectors for Nuclear Instruments |
| IEEE 334 : 2007 | QUALIFYING CONTINUOUS DUTY CLASS 1E MOTORS FOR NUCLEAR POWER GENERATING STATIONS |
| 15/30249614 DC : 0 | BS IEC/IEEE 60780-323 ED 1.0 - NUCLEAR FACILITIES - ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY - QUALIFICATION |
| BS IEC/IEEE 60780-323 : 2016 | NUCLEAR FACILITIES - ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY - QUALIFICATION |
| IEEE 279-1971 | IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations |
| IEEE 387-1995 | IEEE Standard Criteria for Diesel-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations |
| CSA N289.1 : 2008 | GENERAL REQUIREMENTS FOR SEISMIC DESIGN AND QUALIFICATION OF CANDU NUCLEAR POWER PLANTS |
| IEEE 1290-2015 | IEEE Guide for Motor-Operated Valve (MOV) Motor Application, Protection, Control, and Testing in Nuclear Power-Generating Stations |
| IEC/IEEE 60780-323:2016 | Nuclear facilities - Electrical equipment important to safety - Qualification |
| CSA N289.1 : 2008 : INC : UPD 1 : 2014: R201300 | GENERAL REQUIREMENTS FOR SEISMIC DESIGN AND QUALIFICATION OF CANDU NUCLEAR POWER PLANTS |
| CSA N289.1 : 2008 : INC : UPD 1 : 2015 : R201300 | GENERAL REQUIREMENTS FOR SEISMIC DESIGN AND QUALIFICATION OF CANDU NUCLEAR POWER PLANTS |
| CSA N290.8 : 2015 | TECHNICAL SPECIFICATION REQUIREMENTS FOR NUCLEAR POWER PLANT COMPONENTS |
| BS EN 60780-323:2017 | Nuclear facilities. Electrical equipment important to safety. Qualification |
| IEEE 323-2003 | IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations |
| 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 344-2013 | IEEE Standard for Seismic Qualification of Equipment for Nuclear Power Generating Stations |
| I.S. EN 60780-323:2017 | NUCLEAR FACILITIES - ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY - QUALIFICATION |
| EN 60780-323:2017 | Nuclear facilities - Electrical equipment important to safety - Qualification |
| IEEE 627-2010 | IEEE Standard for Qualification of Equipment Used in Nuclear Facilities |
| ANSI N13.4 : 71(R1983) | PORTABLE X-OR GAMMA RADIATION SURVEY INSTRUMENTS, SPECIFICATION OF, |
| IEEE 572-2019 | IEEE Standard for Qualification of Class 1E Connection Assemblies for Nuclear Power Generating Stations and Other Nuclear Facilities |
| ASME QME 1 : 2012 | QUALIFICATION OF ACTIVE MECHANICAL EQUIPMENT USED IN NUCLEAR FACILITIES |
| ASME B16.41 : 83(R1989) | POWER OPERATED ACTIVE VALVE ASSEMBLIES FOR NUCLEAR POWER PLANTS, FUNCTIONAL QUALIFICATION REQUIREMENTS FOR, |
| 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 1205-2000 | IEEE Guide for Assessing, Monitoring, and Mitigating Aging Effects on Class 1E Equipment Used in Nuclear Power Generating Stations |
| 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 344-2004 | IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations |
| IEEE 323-2003 | IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations |
Access your standards online with a subscription
Features
-
Simple online access to standards, technical information and regulations.
-
Critical updates of standards and customisable alerts and notifications.
-
Multi-user online standards collection: secure, flexible and cost effective.