ASME OM-2012

(Revision of ASME OM-2009)

Operation and Maintenance of Nuclear Power Plants

AN A MERICAN NA TIONAL S T AND ARD

ASME OM-2012

(Revision of ASME OM-2009)

ASME OM-2012

(Revision of ASME OM-2009)

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: April 8, 2013

The next edition of this Code is scheduled for publication in 2015.

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 Code Cases. Code 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.

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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.

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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 assumes 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.

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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 © 2013 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 309

iii

FOREWORD

This document was developed and is maintained by the ASME Committee on Operation and Maintenance (OM Committee) of Nuclear Power Plants. The Committee operates under proce- dures accredited by the American National Standards Institute as meeting the criteria of consensus procedures for American National Standards.

Due to the additional time required to consolidate the OM Code and OM-S/G documents, the 2009 edition encompasses all material that would have been included in the 2007 edition, 2008 addenda, and 2009 addenda.

The 2012 edition of Operation and Maintenance of Nuclear Power Plants includes revisions to various sections of Division 1, along with the addition of Mandatory Appendix V. Approved code cases and interpretations have also been added.

The OM Committee develops, revises, and maintains Codes, Standards, and Guides applicable to the safe and reliable operation and maintenance of nuclear power plants.

This publication, the 2012 edition of Operation and Maintenance of Nuclear Power Plants, was approved by the ASME Board on Nuclear Codes and Standards. ASME OM-2012 was approved by the American National Standards Institute on December 21, 2012.

iv

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 Operation and Maintenance Code and development of new requirements as dictated by technological development. This supplement provides guid- ance 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 of 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.

v

CODE REVISIONS AND ADDITIONS

Requests for Code revisions or additions shall provide the following:

1. Proposed Revision(s) or Addition(s). 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 “Code Revisions or 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

Submittals to and responses from the Committee shall meet the following:

1. Submittal. Inquiries from Code users shall preferably be submitted in typewritten form; however, legible handwritten inquiries will also be considered. They shall include the name, address, telephone number, and fax number, if available, of the inquirer and be mailed to the following address:

   Secretary

   Committee on Operation and Maintenance of Nuclear Power Plants

   The American Society of Mechanical Engineers Two Park Avenue

   New York, NY 10016-5990

   
   

2. Response. The Secretary of the Operation and Maintenance Committee shall acknowledge receipt of each properly prepared inquiry and shall provide a written response to the inquirer upon completion of the requested action by the Committee.

vi

COMMITTEE ON OPERATION AND MAINTENANCE OF NUCLEAR POWER PLANTS

As of October, 2012

STANDARDS COMMITTEE

J. J. Zudans, Chair J. G. Rocasolano

A. A. Dermenjian, Vice Chair W. J. Roit

R.I. Parry, Vice Chair C. W. Rowley

F. Huang, Staff Secretary T. P. Ruggiero, Jr.

J. E. Allen G. E. Schinzel

T. N. Chan B. J. Scott

1. D. Comstock C. D. Sellers

2. S. Daugherty S. R. Seman

K. G. DeWall D. M. Swann

G. W. Doody S. R. Swanter

R. S. Hartley C. L. Thibault

M. Honjin G. L. Zigler

W. L. Justice R. M. Emrath, Contributing

R. G. Kershaw Member

R. C. Lippy J. H. Ferguson, Honorary

A. C. McMurtray Member

J. W. Meyer S. D. Hyten, Honorary

G. R. Palmer Member

C. N. Pendleton J. H. Shortt, Honorary

R. Rana Member

J. H. Riley J. S. G. Williams, Honorary

T. V. Robinson Member

SPECIAL COMMITTEE ON STANDARDS PLANNING

G. E. Schinzel, Chair M. Honjin

G. L. Zigler, Vice Chair A. C. McMurtray

R. Haessler, Secretary C. D. Sellers

T. S. Daugherty C. L. Thibault

A. A. Dermnejian J. J. Zudans

SUBCOMMITTEE ON OM CODES

D. M. Swann, Chair T. G. Loebig

W. L. Justice, Vice Chair A. C. McMurtray

T. N. Chan G. R. Palmer

1. D. Comstock C. N. Pendleton

2. S. Daugherty R. Rana

A. A. Dermenjian J. G. Rocasolano

K. G. DeWall W. J. Roit

G. W. Doody T. P. Ruggiero, Jr.

R. S. Hartley B. J. Scott

1. G. Kershaw C. D. Sellers

2. R. Khan S. R. Seman

H. S. Koski, Jr. G. L. Zigler

1. C. Lippy J. J. Zudans

   
   

   Subgroup ISTA/ISTC (SC-OMC)

2. R. Seman, Chair R. S. Hartley

J. W. Perkins, Secretary S. R. Khan

A. N. Anderson H. S. Koski, Jr.

J. G. Billerbeck R. C. Lippy

1. Binz IV G. E. McGovern

2. D. Comstock R. Rana

J. J. Dore, Jr. J. G. Rocasolano

Subgroup ISTB (SC-OMC)

T. P. Ruggiero, Jr., Chair M. L. McGaha

W. L. Justice, Secretary C. N. Pendleton

R. Binz IV T. V. Robinson

M. Gowin N. B. Stockton

R. S. Hartley D. M. Swann

R. D. Jacks W. R. Tomlinson

J. W. Kin R. J. Wolfgang

I. T. Kisisel P. R. Hitchcock Contributing

T. G. Loebig Member

M. C. Mancini

Subgroup ISTD (SC-OMC)

G. R. Palmer, Chair M. Palmer

R. Rana, Vice Chair L. A. Phares

H. S. Koski, Jr., Secretary R. L. Portmann, Jr.

K. Asmundsson M. A. Pressburger

G. S. Bedi O. Rosenbaum

D. P. Brown P. G. Scholar

R. E. Day M. D. Shutt

J. G. Kanute R. E. Richards Contributing

1. E. Labeaf Member

2. A. Norman

Subgroup ISTE (SC-OMC)

G. L. Zigler, Chair A. A. Dermenjian

C. D. Sellers, Vice Chair M. Honjin

R. Haessler, Secretary J. G. Rocasolano

G. E. Schinzel, Secretary C. W. Rowley

J. G. Billerbeck

vii

Subgroup on Air-Operated Valves (SC-OMC)

R. G. Kershaw, Chair R. C. Lippy

F. R. Setzer, Vice Chair D. T. Lurk

M. J. Barlok M. A. McDaniel

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

M. F. Farnan C. L. Thibault

C. S. Ko S. Unikewicz

R. L. Lake

Subgroup on Check Valves (SC-OMC)

B. J. Scott, Chair R. D. Jacks

1. A. Cruz, Vice Chair B. P. Lindenlaub

2. Noviello, Secretary T. B. Maanavi

   V. T. Ataman J. L. Sabina

3. A. Bensinger A. R. Simon

1. I. Ezekoye T. E. Thygesen

2. F. Farnan

Subgroup on Diesel Generators (SC-S/G)

A. L. Ho, Chair S. J. Loeper

A. G. Killinger, Vice Chair N. Trager

J. B. B. Abernathy W. D. Wah

T. N. Chan D. D. Weeks

R. A. Kayler, Jr. R. J. Wolfgang

A. Little D. V. Zink

Subgroup on Functional Systems (SC-S/G)

J. R. Hayes, Chair J. W. Meyer

T. S. Daugherty D. O’Connor

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

F. P. Ferraraccio S. R. Swantner

Subgroup on Motor-Operated Valves (SC-OMC)

K. G. DeWall, Chair C. H. Hansen

C. W. Smith, Vice Chair R. G. Kershaw

T. N. Chan T. S. Neckowicz

D. A. Cruz C. S. Song

J. Doyal C. L. Thibault

M. F. Farnan J. E. Thilking

S. Hale D. G. Van Pelt

Subgroup on OM-29 (SC-S/G)

B. J. Scott, Chair T. S. Neckowicz

R. G. Kershaw

Task Group on New Reactor OM Codes

R. C. Lippy, Chair J. S. McCrickard

J. G. Billberbeck J. W. Meyer

R. Binz IV G. R. Palmer

A. Cardillo C. N. Pendleton

S. D. Comstock T. P. Ruggiero

J. J. Dore, Jr. T. G. Scarbrough

R. S. Hartley S. Unikewicz

Subgroup on Piping Systems (SC-S/G)

D. E. Olson, Chair A. N. Nguyen

G. A. Antaki J. R. Rajan

K. E. Atkins M. Trubelja

K. K. Fujikawa B. J. Voll

R. G. Gilada Y. Wong

K. A. Khuzaie

Task Group on Pump Performance Based IST

R. F. Bosmans M. C. Mancini

D. J. Kanuch

Subgroup on Relief Valves (SC-OMC)

S. D. Comstock, Chair R. J. O’Neill

B. R. Collier, Secretary W. J. Roit

J. G. Billerbeck A. H. Rollo

C. A. Glass S. R. Seman

W. F. Hart C. Shepherd

M. Mir P. W. Turrentine

T. P. Nederostek

Subgroup on Rotating Equipment (SC-S/G)

W. L. Justice, Chair T. G. Loebig

R. F. Bosmans B. J. Voll

R. D. Jacks

viii

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 pre-operational 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 will make the publication schedules for the Committee more efficient and easier to track.

ORGANIZATION

The 2012 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 have been 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 addenda publications in separately listed summary of changes sections. Interpretations and 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 (in course of preparation)

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 Flowchart 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

   
   

   (12)

   
   

   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.

   
   

   ix

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 12 Loose Part Monitoring

Part 16 Performance Testing and Inspection of Diesel Drive Assemblies 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 5 Inservice Monitoring of Core Support Barrel Axial Preload in Pressurized Water Reactor Power Plants

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-2012 SUMMARY OF CHANGES

Following approval by the ASME Committee on Operation and Maintenance (OM Committee) and ASME, and after public review, ASME OM-2012 was approved by the American National Standards Institute on December 21, 2012.

ASME OM-2012 is a consolidation of ASME OM Code and ASME OM-S/G. This edition includes editorial changes, revisions, and corrections introduced in ASME OM Code-2004, ASME OMa Code-2005, ASME OMb Code-2006, ASME OM-S/G-2007, and ASME OM-2009, as well as the following changes identified by a margin note, (12).