IEEE 382 1985

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IEEE Standard for Qualification of Actuators for Power Operated Valve Assemblies with Safety-Related Functions for Nuclear Power Plants

Published By	Publication Date	Number of Pages
IEEE	1985	48

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Description

Revision Standard – Inactive – Superseded. The qualification of all types of power-driven valve actuators, including damper actuators, for safety-related functions in nuclear power generating stations, is described. This standard may also be used to separately qualify actuator components. The minimum requirements for, and guidance regarding, the methods and procedures for qualification of power-driven valve actuators with safety-related functions are provided.

PDF Catalog

PDF Pages	PDF Title
11	1 Scope and Purpose 2 Definitions
13	3 References 4 Introduction 4.1 General 4.2 Requirements 5 Identification of the Generic Actuator Group 5.1 Generic Actuator Group Identification
14	5.2 Selection of Actuator Units for Type Testing Qualification Testing of Selected Actuators in Generic Actuator Group 6.1 Type Test Parameter Values 6.2 Type Test Plan
15	6.3 Type Test Procedure 6.4 Inspection 6.5 Acceptance Criteria 6.6 Generic Actuator Group Design Modification
16	7 Qualification of Actuator for Specific Application 7.1 General 7.2 Valve Actuator Specification 7.3 Relationship to Generic Actuator Group
17	7.4 Relationship to Specification 8 Documentation 8.1 General 8.2 Documentation for Qualification of Generic Actuator Group
18	8.3 Documentation for Qualification for a Specific Application
19	1 Scope 2 Multiple Operations 3 Single Operation
20	Drywell and Steam Tunnel Case
21	Drywell and Steam Tunnel Case I1
22	Qualification Type Test Parameters LOCA Inside (PWR) Containment Case I11 Fig
23	Qualification Type Test Parameters MSLB Inside (PWR) Containment Case
24	Qualification Type Parameters Outside Containment (BWR and PWR Case
25	1 Baseline Operability 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
26	2.3 Test Conduct 2.4 Deviation 3 Normal Pressurization Cycle Test 3.1 Scope 3.2 Test Setup Requirements 3.3 Test Conduct 4 Normal Radiation Aging Test 4.1 Scope 4.2 Test Setup Requirements 4.3 Test Conduct
27	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
28	Fig 6 Seismic Qualification Required Input Motion (RIM)
29	Fig 7 Seismic Qualification Required Response Spectrum (RRS)
30	7 DBE Radiation Exposure Test 7.1 Scope 7.2 Test Setup Requirements 7.3 Test Conduct 8 DBE Environment Test 8.1 Scope
31	8.2 Test Setup Requirements 8.3 Test Conduct
33	Method of Selection of Representative Actuator(s) for Type Testing A1 Introduction A2 Example
34	Table A1 Significant Parameter Values [Step (3)]
35	Identification of Eligible Models Table A3 Selection of Test Models
36	Representative Normal and Design Basis Event Environmental Conditions B1 General B2 Normal Service Conditions
37	Containment BWR. Mark Inside Containment (PWR)
38	Containment (PWR)
39	Design Basis Event Conditions
40	Containment (BWR and PWR) BWR or PWR Plant
42	Rationale for Normal Thermal Aging
43	Rationale for Vibration and Seismic Test Methods D1 Vibration Aging D2 Seismic Aging
45	Performance Verification Test Electric Pneumatic-Motor or Hydraulic-Motor Actuators Rams Rotary Vanes and Diaphragm Double Acting or Spring Return) Integral Valve-Solenoid Type Actuators

Additional information

Standard Title	IEEE Standard for Qualification of Actuators for Power Operated Valve Assemblies with Safety-Related Functions for Nuclear Power Plants
Published Code	IEEE
Publication Date	1985
Pages Count	48

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IEEE 382 1985

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