Operation and Maintenance of Nuclear Power Plants

AN A MERICAN NA TIONAL S T AND ARD

ASME OM-2017

(Revision of ASME OM-2015)

ASME OM-2017

(Revision of ASME OM-2015)

Operation and Maintenance of Nuclear Power Plants

AN AMERICAN NA TIONAL S T AND ARD

Two Park Avenue • New York, NY • 10016 USA

Date of Issuance: May 31, 2017

The next edition of this Code is scheduled for publication in 2019.

ASME issues written replies to inquiries concerning interpretations of technical aspects of this Code. Periodically certain actions of the ASME OM Committee may be published as Cases. Cases and interpretations are published on the ASME Web site under the Committee Pages at https://cstools.asme.org/ as they are issued.

Errata to codes and standards may be posted on the ASME Web site 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 © 2017 by

THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS

All rights reserved Printed in U.S.A.

CONTENTS

(A Detailed Contents Precedes Each Division)

Foreword iv

Preparation of Technical Inquiries v

Committee Roster vii

Preface ix

Summary of Changes xi

Division 1 OM Code: Section IST 1

Division 2 OM Standards 109

Division 3 OM Guides 339

FOREWORD

This document was developed and is maintained by the ASME Committee on Operation and Maintenance (OM Committee) of Nuclear Power Plants. The OM Committee develops, revises, and maintains codes, standards, and guides applicable to the safe and reliable operation and maintenance of nuclear power plants. The Committee operates under procedures accredited by the American National Standards Institute as meeting the criteria of consensus procedures for American National Standards.

This publication, the 2017 edition of Operation and Maintenance of Nuclear Power Plants, was approved by the ASME Board on Nuclear Codes and Standards. ASME OM-2017 was approved by the American National Standards Institute on May 4, 2017.

PREPARATION OF TECHNICAL INQUIRIES TO THE COMMITTEE ON OPERATION

AND MAINTENANCE OF NUCLEAR POWER PLANTS

INTRODUCTION

The ASME Committee on Operation and Maintenance of Nuclear Power Plants meets regularly to conduct standards development business. This includes consideration of written requests for interpretations, Code Cases, and revisions to the Operation and Maintenance Code and develop- ment of new requirements as dictated by technological development. This supplement provides guidance to Code users for submitting technical inquiries to the Committee. Technical inquiries include requests for revisions or additions to the Code requirements, requests for Code Cases, and requests for Code interpretations.

Code Cases may be issued by the Committee when the need is urgent. Code Cases clarify the intent of existing Code requirements or provide alternative requirements. Code Cases are written as a question and a reply, and are usually intended to be incorporated into the Code at a later date. Code interpretations provide the meaning or the intent of existing requirements in the Code and are also presented as a question and reply. Both Code Cases and Code interpretations are published by the Committee.

The Code requirements, Code Cases, and Code interpretations established by the Committee are not to be considered as approving, recommending, certifying, or endorsing any proprietary or specific design or as limiting in any way the freedom of manufacturers or constructors to choose any method of design or any form of construction that conforms to the Code requirements. Moreover, ASME does not act as a consultant on specific engineering problems or on the general application or understanding of the Code requirements. If, based on the inquiry informa- tion submitted, it is the opinion of the Committee that the inquirer should seek assistance, the

inquiry will be returned with the recommendation that such assistance be obtained.

As an alternate to the requirements of this supplement, members of the Committee and its subcommittees, subgroups, and working groups may introduce requests for Code revisions or additions, Code Cases, and Code interpretations at their respective Committee meetings or may submit such requests to the secretary of a subcommittee, subgroup, or working group.

All inquiries that do not provide the information needed for the Committee’s full understanding will be returned.

INQUIRY FORMAT

Submittals to the Committee shall include:

1. Purpose. Specify one of the following:

   1. revision of present Code requirement(s)

   2. new or additional Code requirement(s)

   3. Code Case

   4. Code interpretation

2. Background. Provide the information needed for the Committee’s understanding of the inquiry, being sure to include reference to the applicable Code subsection, appendix, edition, addenda, paragraphs, figures, and tables. Preferably, provide a copy of the specific referenced portions of the Code.

3. Presentations. The inquirer may desire or be asked to attend a meeting of the Committee to make a formal presentation or to answer questions from the Committee members with regard to the inquiry. Attendance at a committee meeting shall be at the expense of the inquirer. The inquirer’s attendance or lack of attendance at a meeting shall not be a basis for acceptance or rejection of the inquiry by the Committee.

CODE REVISIONS AND ADDITIONS

Requests for Code revisions or additions shall provide the following:

1. Proposed Revisions or Additions. For revisions, identify the requirements of the Code that require revision and submit a copy of the appropriate requirements as they appear in the Code, marked up with the proposed revision. For additions, provide the recommended wording, refer- enced to the existing Code requirements.

2. Statement of Need. Provide a brief explanation of the need for the revision(s) or addition(s).

3. Background Information. Provide background information to support the revision(s) or addi- tion(s), including any data or changes in technology that form the basis for the request that will allow the Committee to adequately evaluate the proposed revision(s) or addition(s). Sketches, tables, figures, and graphs should be submitted as appropriate. When applicable, identify any pertinent paragraph in the Code that would be affected by the revision(s) or addition(s) and paragraphs in the Code that reference the paragraphs that are to be revised or added.

CODE CASES

Requests for Code Cases shall provide a Statement of Need and Background Information similar to that defined in subparas. (b) and (c) of the “Code Revisions and Additions” section. The proposed Code Case should identify the Code Section and Division, and be written as a Question and Reply in the same format as existing Code Cases. Requests for Code Cases should also indicate the applicable Code edition(s) and addenda to which the proposed Code Case applies.

CODE INTERPRETATIONS

Requests for Code interpretations shall provide the following:

1. Inquiry. Provide a condensed and precise question, omitting superfluous background infor- mation and, when possible, composed in such a way that a “yes“ or a “no“ Reply, possibly with brief provisos, is acceptable. The question should be technically and editorially correct.

2. Reply. Provide a proposed Reply that will clearly and concisely answer the Inquiry question. Preferably, the Reply should be “yes” or ”no,” possibly with brief provisos.

3. Background Information. Provide any background information that will assist the Committee in understanding the proposed Inquiry and Reply.

SUBMITTALS

All inquiries from Code users shall be submitted through: https://cstools.asme.org/Interpretation/InterpretationForm.cfm

COMMITTEE ON OPERATION AND MAINTENANCE OF NUCLEAR POWER PLANTS

As of September 2016

STANDARDS COMMITTEE

R. Lippy, Chair G. E. Schinzel

C. N. Pendleton, Vice Chair C. D. Sellers

T. P. Ruggiero, Jr., Vice Chair S. R. Swantner

L. T. Powers, Staff Secretary P. W. Turrentine

J. E. Allen S. M. Unikewicz

T. N. Chan R. J. Wolfgang

K. Chang-Seog J. J. Zudans

1. D. Comstock R. M. Emrath, Contributing

2. S. Daugherty Member

K. DeWall R. S. Hartley, Contributing

G. W. Doody Member

C. A. Glass B. Scott, Contributing

M. Gowin Member

M. Honjin F. F. Martinez, Alternate

W. Justice A. Dermenjian, Honorary

J. W. Kin Member

J. W. Meyer J. H. Ferguson, Honorary

D. E. Olson Member

G. R. Palmer S. D. Hyten, Honorary

B. Parry Member

R. Rana C. W. Rowley, Honorary

J. H. Riley Member

D. Robinson D. Swann, Honorary

T. Robinson Member

J. G. Rocasolano J. S. G. Williams, Honorary

W. J. Roit Member

EXECUTIVE COMMITTEE

R. Lippy, Chair B. Parry

L. T. Powers, Secretary C. N. Pendleton

S. D. Comstock T. P. Ruggiero, Jr.

M. Gowin G. E. Schinzel

W. Justice C. D. Sellers

J. W. Meyer R. J. Wolfgang

G. R. Palmer

SUBCOMMITTEE ON STANDARDS PLANNING

G. E. Schinzel, Chair C. D. Sellers

R. Haessler, Secretary R. J. Wolfgang

T. S. Daugherty J. J. Zudans

M. Honjin A. Dermenjian, Contributing

D. E. Olson Member

J. H. Riley

SUBCOMMITTEE ON NEW REACTORS

C. N. Pendleton, Chair I. T. Kisisel

A. Cardillo, Vice Chair G. M. Kopanakis

P. Gionta, Secretary D. Ludovisi

J. G. Billerbeck G. R. Palmer

R. Binz IV W. R. Peebles, Jr.

M. Catugas W. J. Roit

S. D. Comstock T. P. Ruggiero, Jr.

G. W. Doody T. G. Scarbrough

J. J. Dore, Jr. S. M. Unikewicz

R. S. Hartley

SUBCOMMITTEE ON VALVES

M. Gowin, Chair S. R. Khan

R. Binz IV, Vice Chair H. Koski, Jr.

H. A. Krause Browner, R. Lippy

Secretary B. Moenkedick

J. G. Billerbeck R. Rana

S. D. Comstock J. G. Rocasolano

J. J. Dore, Jr. T. Rogers

C. A. Glass S. R. Seman

SUBCOMMITTEE ON PUMPS

T. Robinson, Chair T. Loebig

R. Binz IV M. McGaha

G. W. Doody B. Moenkedick

M. Gowin D. Patel

R. S. Hartley C. N. Pendleton

R. D. Jacks T. P. Ruggiero, Jr.

W. Justice N. Stockton

J. W. Kin W. R. Tomlinson

I. T. Kisisel R. J. Wolfgang

H. A. Krause Browner

SUBCOMMITTEE ON DYNAMIC RESTRAINTS

G. R. Palmer, Chair J. G. Kanute

S. E. Norman, Vice Chair R. Labeaf

M. Shutt, Vice Chair M. Palmer

H. Koski, Jr., Secretary L. A. Phares

K. Asmundsson R. L. Portmann, Jr.

G. S. Bedi M. A. Pressburger

D. P. Brown R. Rana

W. G. Chatterton O. Rosenbaum

R. E. Day D. K. Shetler

M. Etten-Bohm C. Smith

R. Fandetti R. E. Richards, Contributing Member

SUBCOMMITTEE ON RISK

C. D. Sellers, Chair J. G. Rocasolano

R. Haessler, Secretary G. E. Schinzel

J. G. Billerbeck B. Scott

M. Honjin J. J. Zudans

F. F. Martinez A. Dermenjian, Contributing

M. Ralstin Member

Subgroup on Air-Operated Valves

F. Setzer, Chair W. Fitzgerald

M. Barlok, Vice Chair R. G. Kershaw

D. Lurk, Secretary C. Linden

K. F. Beasley M. A. McDaniel

N. Camilli J. A. Neyhard

K. Chang-Seog M. Ruff

K. L. Cortis T. P. Sanders, Jr.

J. L. Daniels S. M. Unikewicz

M. F. Farnan T. A. Walker

Subgroup on Check Valves

E. Noviello, Chair R. D. Jacks

D. A. Cruz, Vice Chair J. L. Sabina

V. T. Ataman R. S. Smith

F. A. Bensinger T. E. Thygesen

1. I. Ezekoye P. Twaddle

2. F. Farnan

SUBCOMMITTEE ON FUNCTIONAL SYSTEMS

J. R. Hayes, Chair D. Ludovisi

T. S. Daugherty J. W. Meyer

J. J. Dore, Jr. W. R. Peebles, Jr.

F. P. Ferraraccio S. R. Swantner

Subgroup on Motor-Operated Valves

C. Smith, Chair S. Hale

W. E. Densmore, Vice Chair G. A. Mingo

D. A. Cruz, Secretary T. S. Neckowicz

T. N. Chan J. E. Thilking

K. DeWall T. A. Walker

M. F. Farnan

SUBCOMMITTEE ON PIPING SYSTEMS

D. E. Olson, Chair P. E. Grazier

G. Antaki J. R. Rajan

K. E. Atkins M. Trubelja

K. K. Fujikawa B. J. Voll

1. Gilada Y. Wong

   Subgroup on Relief Valves

2. D. Comstock, Chair M. Mir

B. R. Collier, Secretary T. P. Nederostek

J. G. Billerbeck R. O’Neill

N. Camilli W. J. Roit

S. Cammeresi C. Shepherd

A. DiMeo P. W. Turrentine

C. A. Glass P. Twaddle

S. P. Jansen

Subgroup on Rotating Equipment

1. Justice, Chair R. D. Jacks

   T. Loebig, Vice Chair I. T. Kisisel

   R. F. Bosmans D. Robinson

   T. S. Daugherty W. R. Tomlinson

   P. E. Grazier B. J. Voll

   
   

   China International Working Group

2. Chen, Chair Z. Liu

1. Tang, Vice Chair X. Lu

   J. Yang, Vice Chair C. Qu

   Z. Chen, Secretary G. Sun

   H. Ai H. Sun

   L. Chen Z. Wu

2. Di J. Xxu

B. Dong Y. Zhang

D. Du Q. Zhao

Z. Hua W. Zhao

G. Huang K. Zheng

P. Lio Z. Zhou

PREFACE

GENERAL

In 2008, the OM Committee directed that the two separately published OM Code and the OM Standards and Guides (OM-S/G) publications be combined into one document. This was done to ensure all of our standards and guides documents were readily available to users of the OM Code products. Some of the standards and guides were originally developed as part of the current operating nuclear power plants preoperational testing program conducted during the 1970s and 1980s. These standards and guides will be useful for power uprate projects and for new reactor design plant construction. Combining the OM Code and OM-S/G into one document makes the publication schedules for the Committee more efficient and easier to track.

ORGANIZATION

The consolidated code, standards, and guides for nuclear power plants, titled Operation and Maintenance of Nuclear Power Plants, are arranged into three distinct divisions. The titles of some of the sections were shortened to simplify the presentation purely for the user’s ease of review and use. Reference to the individual published code, standard, or guide should be made for the specific title and the application requirements. Subsequent changes made to the Division contents will be detailed in future publications in separately listed summary of changes sections. Code Cases are included as a separate section following Division 3 for the user’s convenience.

Division 1: OM Code: Section IST

Subsection ISTA General Requirements

Subsection ISTB Inservice Testing of Pumps — Pre-2000 Plants1 Subsection ISTC Inservice Testing of Valves

Subsection ISTD Preservice and Inservice Examination and Testing of Dynamic Restraints (Snubbers)

Subsection ISTE Risk-Informed Inservice Testing of Components Subsection ISTF Inservice Testing of Pumps — Post-2000 Plants2

Mandatory Appendices

I Inservice Testing of Pressure Relief Devices II Check Valve Condition Monitoring Program

III Preservice and Inservice Testing of Active Electric Motor-Operated Valve Assemblies IV Pneumatically and Hydraulically Operated Valves

V Pump Periodic Verification Test Program

Nonmandatory Appendices

1. Preparation of Test Plans

2. Dynamic Restraint Examination Checklist Items

3. Dynamic Restraint Design and Operating Information

4. Comparison of Sampling Plans for Inservice Testing of Dynamic Restraints E Flowcharts for 10% and 37 Snubber Testing Plans

F Dynamic Restraints (Snubbers) Service Life Monitoring Methods G Application of Table ISTD-4252-1, Snubber Visual Examination H Test Parameters and Methods

1. Check Valve Testing Following Valve Reassembly

2. Sample List of Component Deterministic Considerations

   
   

   
   

   1 Pre-2000 plant: a nuclear power plant that was issued its construction permit by the applicable regulatory authority prior to January 1, 2000.

   2 Post-2000 plant: a nuclear power plant that was issued (or will be issued) its construction permit, or combined license for construction and operation, by the applicable regulatory authority on or following January 1, 2000.

3. Acceptance Guidelines

4. Design Guidance for Nuclear Power Plant Systems and Component Testing

Division 2: OM Standards

Part 3 Vibration Testing of Piping Systems

Part 5 Inservice Monitoring of Core Support Barrel Axial Preload in Pressurized Water Reactor Power Plants

Part 12 Loose Part Monitoring

Part 16 Performance Testing and Monitoring of Standby Diesel Generator Systems Part 21 Inservice Performance Testing of Heat Exchangers

Part 24 Reactor Coolant and Recirculation Pump Condition Monitoring

Part 26 Determination of Reactor Coolant Temperature From Diverse Measurements Part 28 Standard for Performance Testing of Systems

Part 29 Alternative Treatment Requirements for RISC-3 Pumps and Valves

Division 3: OM Guides

Part 7 Requirements for Thermal Expansion Testing of Nuclear Power Plant Piping Systems

Part 11 Vibration Testing and Assessment of Heat Exchangers

Part 14 Vibration Monitoring of Rotating Equipment in Nuclear Power Plants Part 19 Preservice and Periodic Performance Testing of Pneumatically and

Hydraulically Operated Valve Assemblies

Part 23 Inservice Monitoring of Reactor Internals Vibration in Pressurized Water Reactor Power Plants

ASME OM-2017 SUMMARY OF CHANGES

Following approval by the ASME Committee on Operation and Maintenance and ASME, and after public review, ASME OM-2017 was approved by the American National Standards Institute on May 4, 2017.

Changes given below are identified on the pages by a margin note, (17), placed next to the affected area.