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ASME OM-2020
M00050833
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ASME OM-2020 Operation and Maintenance of Nuclear Power Plants
standard by ASME International, 06/30/2020
Full Description
Establishes the requirements for preservice and inservice testing and examination of certain components to assess their operational readiness in light-water reactor power plants. It identifies the components subject to test or examination, responsibilities, methods, intervals, parameters to be measured and evaluated, criteria for evaluating the results, corrective action, personnel qualification, and record keeping. These requirements apply to:(a) pumps and valves that are required to perform a specific function in shutting down a reactor to the safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of an accident;
(b) pressure relief devices that protect systems or portions of systems that perform one or more of these three functions; and
(c) dynamic restraints (snubbers) used in systems that perform one or more of these three functions.
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Operation and Maintenance of Nuclear Power Plants
AN A MERICAN NA TIONAL S T AND ARD
ASME OM-2020
(Revision of ASME OM-2017)
ASME OM-2020
(Revision of ASME OM-2017)
Operation and
Maintenance of Nuclear Power Plants
AN AMERICAN NATIONAL STANDARD
Two Park Avenue • New York, NY • 10016 USA
Date of Issuance: June 30, 2020
The next edition of this Standard is scheduled for publication in 2022.
ASME issues written replies to inquiries concerning interpretations of technical aspects of this Standard. Periodically certain actions of the ASME OM Committee may be published as Cases. Cases and interpretations are published on the ASME website under the Committee Pages at https://cstools.asme.org/ as they are issued.
Errata to codes and standards may be posted on the ASME website under the Committee Pages to provide corrections to incorrectly published items, or to correct typographical or grammatical errors in codes and standards. Such errata shall be used on the date posted.
The Committee Pages can be found at https://cstools.asme.org/. There is an option available to automatically receive an e-mail notification when errata are posted to a particular code or standard. This option can be found on the appropriate Committee Page after selecting “Errata” in the “Publication Information” section.
ASME is the registered trademark of The American Society of Mechanical Engineers.
This code or standard was developed under procedures accredited as meeting the criteria for American National Standards. The Standards Committee that approved the code or standard was balanced to assure that individuals from competent and concerned interests have had an opportunity to participate. The proposed code or standard was made available for public review and comment that provides an opportunity for additional public input from industry, academia, regulatory agencies, and the public-at-large.
ASME does not “approve,” “rate,” or “endorse” any item, construction, proprietary device, or activity.
ASME does not take any position with respect to the validity of any patent rights asserted in connection with any items mentioned in this document, and does not undertake to insure anyone utilizing a standard against liability for infringement of any applicable letters patent, nor assume any such liability. Users of a code or standard are expressly advised that determination of the validity of any such patent rights, and the risk of infringement of such rights, is entirely their own responsibility.
Participation by federal agency representative(s) or person(s) affiliated with industry is not to be interpreted as government or industry endorsement of this code or standard.
ASME accepts responsibility for only those interpretations of this document issued in accordance with the established ASME procedures and policies, which precludes the issuance of interpretations by individuals.
No part of this document may be reproduced in any form, in an electronic retrieval system or otherwise,
without the prior written permission of the publisher.
The American Society of Mechanical Engineers Two Park Avenue, New York, NY 10016-5990
Copyright © 2020 by
THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS
All rights reserved Printed in U.S.A.
CONTENTS
Foreword . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . xiv
Committee Roster . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . xv
Correspondence With the OM Committee xviii
Preface . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . xx
Summary of Changes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . xxii
Applicability Index for ASME OM Cases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . xxv
Cross-Referencing and Stylistic Changes in ASME OM xxvii
Division 1 | OM Code: Section IST . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 1 |
Subsection ISTA | General Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 1 |
ISTA-1000 | Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 1 |
ISTA-2000 | Definitions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 2 |
ISTA-3000 | General Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 3 |
ISTA-4000 | Instrumentation and Test Equipment . . . . . . . . . . . . . . . . . . . . . . . . | 4 |
ISTA-5000 | Specific Test Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 5 |
ISTA-6000 | Monitoring, Analysis, and Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . | 5 |
ISTA-7000 | To Be Provided at a Later Date . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 5 |
ISTA-8000 | To Be Provided at a Later Date . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 5 |
ISTA-9000 | Records and Reports . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 5 |
Subsection ISTB | Inservice Testing of Pumps in Water-Cooled Reactor Nuclear Power Plants — Pre-2000 Plants . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 6 |
ISTB-1000 | Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 6 |
ISTB-2000 | Supplemental Definitions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 6 |
ISTB-3000 | General Testing Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 6 |
ISTB-4000 | To Be Provided at a Later Date . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 9 |
ISTB-5000 | Specific Testing Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 9 |
ISTB-6000 | Monitoring, Analysis, and Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . | 16 |
ISTB-7000 | To Be Provided at a Later Date . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 16 |
ISTB-8000 | To Be Provided at a Later Date . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 16 |
ISTB-9000 | Records and Reports . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 16 |
Subsection ISTC | Inservice Testing of Valves in Water-Cooled Reactor Nuclear Power Plants . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 18 |
ISTC-1000 | Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 18 |
ISTC-2000 | Supplemental Definitions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 18 |
ISTC-3000 | General Testing Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 19 |
ISTC-4000 | Instrumentation and Test Equipment . . . . . . . . . . . . . . . . . . . . . . . . | 22 |
ISTC-5000 | Specific Testing Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 23 |
ISTC-6000 | Monitoring, Analysis, and Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . | 27 |
ISTC-7000 | To Be Provided at a Later Date . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 27 |
ISTC-8000 To Be Provided at a Later Date . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27
ISTC-9000 Records and Reports . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27
Subsection ISTD Preservice and Inservice Requirements for Dynamic Restraints
(Snubbers) in Water-Cooled Reactor Nuclear Power Plants . . . . 28
ISTD-1000 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28
ISTD-2000 Definitions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29
ISTD-3000 General Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 30
ISTD-4000 Specific Examination Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . 30
ISTD-5000 Specific Testing Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32
ISTD-6000 Service Life Monitoring Requirements . . . . . . . . . . . . . . . . . . . . . . . . 37
ISTD-7000 To Be Provided at a Later Date . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 37
ISTD-8000 To Be Provided at a Later Date . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 37
ISTD-9000 Records and Reports . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 37
Subsection ISTE Risk-Informed Inservice Testing of Components in Water-Cooled
Reactor Nuclear Power Plants . . . . . . . . . . . . . . . . . . . . . . . . . . 39
ISTE-1000 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 39
ISTE-2000 Supplemental Definitions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 39
ISTE-3000 General Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 40
ISTE-4000 Specific Component Categorization Requirements . . . . . . . . . . . . . . . . 41
ISTE-5000 Specific Testing Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 44
ISTE-6000 Monitoring, Analysis, and Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . 46
ISTE-7000 To Be Provided at a Later Date . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46
ISTE-8000 To Be Provided at a Later Date . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46
ISTE-9000 Records and Reports . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46
Subsection ISTF Inservice Testing of Pumps in Water-Cooled Reactor Nuclear Power
Plants — Post-2000 Plants . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47
ISTF-1000 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47
ISTF-2000 Supplemental Definitions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47
ISTF-3000 General Testing Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47
ISTF-4000 To Be Provided at a Later Date . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50
ISTF-5000 Specific Testing Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50
ISTF-6000 Monitoring, Analysis, and Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . 52
ISTF-7000 To Be Provided at a Later Date . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 53
ISTF-8000 To Be Provided at a Later Date . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 53
ISTF-9000 Records and Reports . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 53
Mandatory Appendix I Inservice Testing of Pressure Relief Devices in Water-Cooled Reactor
Nuclear Power Plants . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55
Mandatory Appendix II Check Valve Condition Monitoring Program . . . . . . . . . . . . . . . . . . 65
Mandatory Appendix III Preservice and Inservice Testing of Active Electric Motor-Operated
Valve Assemblies in Water-Cooled Reactor Nuclear Power Plants 67
Mandatory Appendix IV Preservice and Inservice Testing of Active Pneumatically Operated
Valve Assemblies in Nuclear Reactor Power Plants . . . . . . . . . . 72
Mandatory Appendix V Pump Periodic Verification Test Program . . . . . . . . . . . . . . . . . . . 78
Nonmandatory Appendix A Preparation of Test Plans . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 79
Supplement to Nonmandatory Appendix A
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
81
Nonmandatory Appendix B Dynamic Restraint Examination Checklist Items . . . . . . . . . . . . . . 82
Nonmandatory Appendix C Nonmandatory Appendix D | Dynamic Restraint Design and Operating Information . . . . . . . . . . Comparison of Sampling Plans for Inservice Testing of Dynamic | 83 |
Restraints . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 84 | |
Nonmandatory Appendix E | Flowcharts for 10% and 37 Snubber Testing Plans . . . . . . . . . . . . | 85 |
Nonmandatory Appendix F | Dynamic Restraints (Snubbers) Service Life Monitoring Methods . | 88 |
Nonmandatory Appendix G | Application of Table ISTD-4252-1, Snubber Visual Examination . . | 90 |
Nonmandatory Appendix H | Test Parameters and Methods . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 92 |
Nonmandatory Appendix J | Check Valve Testing Following Valve Reassembly . . . . . . . . . . . . . | 94 |
Nonmandatory Appendix K | Sample List of Component Deterministic Considerations . . . . . . . . | 96 |
Nonmandatory Appendix L | Acceptance Guidelines . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 97 |
Nonmandatory Appendix M | Design Guidance for Nuclear Power Plant Systems and Component Testing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 100 |
Division 2 | OM Standards . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 106 |
Part 2 | Performance Testing of Closed Cooling Water Systems in Light-Water Reactor Power Plants . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 106 |
Part 3 | Vibration Testing of Piping Systems . . . . . . . . . . . . . . . . . . . . . . . . | 107 |
1 | Scope . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 107 |
2 | Definitions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 107 |
3 | General Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 108 |
4 | Visual Inspection Method . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 112 |
5 | Simplified Method for Qualifying Piping Systems . . . . . . . . . . . . . . . . | 112 |
6 | Rigorous Verification Method for Steady-State and Transient Vibration . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 117 |
7 | Instrumentation and Vibration Measurement Requirements . . . . . . . . | 118 |
8 | Corrective Action . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 119 |
Nonmandatory Appendix A | Instrumentation and Measurement Guidelines . . . . . . . . . . . . . . . . . . | 120 |
Nonmandatory Appendix B | Analysis Methods . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 123 |
Nonmandatory Appendix C | Test/Analysis Correlation Methods . . . . . . . . . . . . . . . . . . . . . . . . . . | 124 |
Nonmandatory Appendix D | Velocity Criterion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 125 |
Nonmandatory Appendix E | Excitation Mechanisms, Responses, and Corrective Actions . . . . . . . . . | 126 |
Nonmandatory Appendix F | Flowchart — Outline of Vibration Qualification of Piping Systems . . . . | 129 |
Nonmandatory Appendix G | Qualitative Evaluations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 131 |
Nonmandatory Appendix H | Guidance for Monitoring Piping Steady-State Vibration Per Vibration Monitoring Group 2 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 132 |
Nonmandatory Appendix I | Acceleration Limits for Small Branch Piping . . . . . . . . . . . . . . . . . . . . | 137 |
Part 5 | Inservice Monitoring of Core Support Barrel Axial Preload in Pressurized Water Reactor Power Plants . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 139 |
1 | Purpose and Scope . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 139 |
2 | Background . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 139 |
3 | Program Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 141 |
4 | Baseline Phase . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 141 |
5 | Surveillance Phase . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 143 |
6 | Diagnostic Phase . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 143 |
Nonmandatory Appendix A | Theoretical Basis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 145 |
Nonmandatory Appendix B | Data Reduction Techniques . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 147 |
Nonmandatory Appendix C |
|