ASME 0M-2022 (RevisionofASMEOM-2020) Operation and Maintenance of Nuclear Power Plants ANAMERICANNATIONALSTANDARD The American Society of Mechanical Engineers ASME 0M-2022 (Revision of ASME OM-2020) Operation and Maintenance of Nuclear Power Plants AN AMERICAN NATIONAL STANDARD The American Society of Mechanical Engineers Two Park Avenue ·New York, NY·10016 USA Date of Issuance:January20,2023 The next edition of this Code is scheduled for publication in 2024. This code or standard was developed under procedures accredited as meeting the criteria for American National Standards. The concerned interests had an opportunity to participate.The proposed codeor standard was made availableforpublic and the public-at-large. ASME does not"approve,""certify,"“"rate," or“endorse"” any item, construction, proprietary device, or activity. ASME does not document, and does not undertake to insure anyone utilizing a standard against liability for infringement of any applicable the validity of any such patent rights, and the risk of infringement of such rights, is entirely their own responsibility. industry endorsement of this code or standard. procedures and policies,which precludes the issuance of interpretations by individuals. The endnotes and preamble in this document (if any) are part of this American National Standard. ASME Collective Membership Mark 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,NewYork,NY10016-5990 Copyright @ 2023 by THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS All rights reserved CONTENTS Foreword: xiv Committee Roster XV Correspondence With the OM Committee . xix Preface. xxi ASME OM Cases and Applicability Index for ASME OM Cases xxili Cross-Referencing and Stylistic Changes in ASME OM xxiv Summary of Changes XXV Division 1 OM Code: Section IST Subsection ISTA General Requirements 1 ISTA-1000 Introduction....... ISTA-2000 Definitions .... 2 ISTA-3000 General Requirements..... 3 ISTA-4000 Instrumentation and Test Equipment ...... 5 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..... 7 ISTB-1000 Introduction.. 7 ISTB-2000 SupplementalDefinitions 7 ISTB-3000 General Testing Requirements 7 ISTB-4000 To Be Provided at a Later Date . 11 ISTB-5000 Specific Testing Requirements 11 ISTB-6000 Monitoring, Analysis, and Evaluation . 18 ISTB-7000 To Be Provided at a Later Date 19 ISTB-8000 To Be Provided at a Later Date . 19 ISTB-9000 Records and Reports 19 Subsection ISTC Inservice Testing of Valves in Water-Cooled Reactor Nuclear Power Plants 20 ISTC-1000 Introduction. 20 ISTC-2000 Supplemental Definitions . 20 ISTC-3000 General Testing Requirements . . 21 ISTC-4000 Instrumentation and Test Equipment . .. . 25 ISTC-5000 Specific Testing Requirements 25 ISTC-6000 Monitoring, Analysis, and Evaluation . 29 ISTC-7000 To Be Provided at a Later Date . 29 ii 29 ISTC-8000 To BeProvided at a Later Date. ISTC-9000 Records and Reports... 29 Subsection ISTD Preservice and Inservice Requirements for Dynamic Restraints (Snubbers) in Water-Cooled Reactor Nuclear Power Plants 30 ISTD-1000 Introduction. 30 ISTD-2000 Definitions.. 31 ISTD-3000 General Requirements .. 32 ISTD-4000 Specific Examination Requirements 32 ISTD-5000 Specific Testing Requirements .... 34 ISTD-6000 Service Life Monitoring Requirements 39 ISTD-7000 To Be Provided at a Later Date . : 40 ISTD-8000 To Be Provided at a Later Date . 40 ISTD-9000 40 Subsection ISTE Risk-Informed Inservice Testing of Components in Water-Cooled Reactor Nuclear Power Plants . . 42 ISTE-1000 Introduction........ 42 ISTE-2000 Supplementa