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ASME OM-2015 Operation and Maintenance of Nuclear Power Plants
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Operation and Maintenance of Nuclear Power Plants
AN A MERICAN NA TIONAL S T AND ARD
ASME OM-2015
(Revision of ASME OM-2012)
ASME OM-2015
(Revision of ASME OM-2012)
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: September 30, 2015
The next edition of this Code is scheduled for publication in 2017.
ASME issues written replies to inquiries concerning interpretations of technical aspects of this Code. Interpretations are published on the Committee Web page and under go.asme.org/InterpsDatabase. Periodically certain actions of the ASME OM Committee may be published as Cases. Cases are published on the ASME Web site under the OM Committee Page at go.asme.org/OMcommittee 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.
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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.
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 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.
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 © 2015 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 105
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 encompassed 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 included revisions to various sections of Division 1, along with the addition of Mandatory Appendix V. Approved code cases and interpretations were also 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 2015 edition of Operation and Maintenance of Nuclear Power Plants, was approved by the ASME Board on Nuclear Codes and Standards. ASME OM-2015 was approved by the American National Standards Institute on January 8, 2015.
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 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:
Purpose. Specify one of the following:
revision of present Code requirement(s)
new or additional Code requirement(s)
Code Case
Code interpretation
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.
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:
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.
Statement of Need. Provide a brief explanation of the need for the revision(s) or addition(s).
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:
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.
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.
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:
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
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 July 2014
STANDARDS COMMITTEE
J. J. Zudans, Chair J. G. Rocasolano
A. Dermenjian, Vice Chair W. J. Roit
R. Parry, Vice Chair C. W. Rowley
L. T. Powers, Staff Secretary T. P. Ruggiero, Jr.
J. E. Allen G. E. Schinzel
T. N. Chan B. Scott
D. Comstock C. D. Sellers
S. Daugherty S. R. Seman
K. DeWall S. R. Swantner
G. W. Doody C. Thibault
R. S. Hartley G. L. Zigler
M. Honjin R. M. Emrath,
W. Justice Corresponding Member
R. G. Kershaw J. H. Ferguson, Honorary
J. W. Kin Member
R. Lippy S. D. Hyten, Honorary
T. Lupold Member
J. W. Meyer J. H. Shortt, Honorary
G. R. Palmer Member
C. N. Pendleton D. Swann, Honorary
R. Rana Member
J. H. Riley J. S. G. Williams, Honorary
D. Robinson Member
T. Robinson
SPECIAL COMMITTEE ON STANDARDS PLANNING
G. E. Schinzel, Chair T. Lupold
G. L. Zigler, Vice Chair D. E. Olson
R. Haessler, Secretary J. H. Riley
T. S. Daugherty C. D. Sellers
A. Dermenjian C. Thibault
M. Honjin J. J. Zudans
TASK GROUP ON NEW REACTOR OM CODE
R. Lippy, Chair G. M. Kopanakis
C. N. Pendleton, Vice Chair J. S. McCrickard
J. G. Billerbeck J. W. Meyer
R. Binz IV M. Neyhard
A. Cardillo G. R. Palmer
M. Catugas W. R. Peebles, Jr.
S. D. Comstock W. J. Roit
P. P. Difilipo T. P. Ruggiero, Jr.
G. W. Doody T. G. Scarbrough
J. J. Dore, Jr. S. M. Unikewicz
R. S. Hartley
SUBCOMMITTEE ON OM CODES
T. P. Ruggiero, Jr., Chair R. Rana
W. Justice, Vice Chair D. Robinson
N. Stockton, Secretary J. G. Rocasolano
Binz IV W. J. Roit
D. Comstock B. Scott
S. Daugherty C. D. Sellers
K. DeWall S. R. Seman
S. Hartley F. Setzer
R. Khan C. Smith
H. Koski, Jr. G. L. Zigler
R. Lippy A. Dermenjian, Contributing
T. Loebig Member
T. Lupold J. J. Zudans, Contributing
R. Parry Member
C. N. Pendleton
Subgroup ISTA/ISTC
M. Gowin, Chair S. R. Khan
R. Binz IV, Vice Chair H. Koski, Jr.
J. W. Perkins, Secretary R. Lippy
A. N. Anderson R. Rana
J. G. Billerbeck J. G. Rocasolano
S. D. Comstock T. Rogers
J. J. Dore, Jr. S. R. Seman
R. S. Hartley
Subgroup ISTB
W. Justice, Chair M. C. Mancini
T. Robinson, Vice Chair M. McGaha
R. Binz IV D. Patel
G. W. Doody C. N. Pendleton
M. Gowin T. P. Ruggiero, Jr.
R. S. Hartley N. Stockton
R. D. Jacks W. R. Tomlinson
J. W. Kin R. J. Wolfgang
I. T. Kisisel P. R. Hitchcock, Contributing
T. Loebig Member
Subgroup ISTD
G. R. Palmer, Chair S. A. Norman
R. Rana, 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 D. K. Shetler
O. Cable M. Shutt
R. Fandetti R. E. Richards,
J. G. Kanute Corresponding Member
R. Labeaf
vii
Subgroup ISTE
C. D. Sellers, Chair M. Honjin
G. L. Zigler, Vice Chair J. G. Rocasolano
R. Haessler, Secretary C. W. Rowley
J. G. Billerbeck G. E. Schinzel
A. Dermenjian B. Scott
Subgroup on Air-Operated Valves
F. Setzer, Chair R. G. Kershaw
M. Barlok, Vice Chair M. A. McDaniel
D. Lurk, Secretary J. A. Neyhard
N. Camilli T. P. Sanders, Jr.
B. Carneal D. M. Satkoski
Chang-Seog C. Thibault
K. L. Cortis S. M. Unikewicz
J. L. Daniels T. A. Walker
W. Fitzgerald
Subgroup on Check Valves
E. Noviello, Chair R. D. Jacks
D. A. Cruz, Vice Chair B. P. Lindenlaub
F. A. Bensinger J. L. Sabina
I. Ezekoye B. Scott
F. Farnan T. E. Thygesen
Subgroup on Diesel Generators
A. L. Ho, Chair N. Treager
A. G. Killinger, Vice Chair W. D. Wah
J. B. Abernathy R. J. Wolfgang
T. N. Chan D. V. Zink
A. Little
Subgroup 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 C. H. Hansen
D. A. Cruz, Secretary R. G. Kershaw
T. N. Chan T. S. Neckowicz
K. DeWall C. Thibault
J. W. Doyal, Jr. J. E. Thilking
M. F. Farnan D. G. Van Pelt
Subgroup on Piping Systems
D. E. Olson, Chair K. A. Khuzaie
G. Antaki J. R. Rajan
K. E. Atkins M. Trubelja
K. K. Fujikawa B. J. Voll
Gilada Y. Wong
Subgroup on Relief Valves
D. Comstock, Chair T. P. Nederostek
B. R. Collier, Secretary R. O’Neill
J. G. Billerbeck W. J. Roit
A. DiMeo S. R. Seman
C. A. Glass C. Shepherd
W. F. Hart P. W. Turrentine
M. Mir
Subgroup on Rotating Equipment
W. Justice, Chair T. Loebig
R. F. Bosmans D. Robinson
T. S. Daugherty W. R. Tomlinson
R. D. Jacks B. J. Voll
I. T. Kisisel
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 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. 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 (to be provided at a later date)
V Pump Periodic Verification Test Program
Nonmandatory Appendices
Preparation of Test Plans
Dynamic Restraint Examination Checklist Items
Dynamic Restraint Design and Operating Information
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
Check Valve Testing Following Valve Reassembly
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.
ix
Acceptance Guidelines
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 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 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-2015 SUMMARY OF CHANGES
Following approval by the ASME Committee on Operation and Maintenance and ASME, and after public review, ASME OM-2015 was approved by the American National Standards Institute on January 8, 2015.
Changes given below are identified on the pages by a margin note, (15), placed next to the affected area.
Page 7 | Location ISTA-2000 | Change Definitions of cold shutdown outage and |
refueling outage added | ||
24, 25 | ISTC-3521 | Revised in its entirety |
ISTC-3522 | Revised in its entirety | |
33 | ISTD-1750 | Revised |
34 | ISTD-2000 | (1) Definitions of fuel cycle, successful test campaign, test campaign, test interval, and unanticipated transient dynamic |
event added
(2) Definition of inaccessible snubbers
revised
35 | ISTD-3240 | Added |
38, 39 | ISTD-5200 | Revised |
ISTD-5240 | Revised | |
ISTD-5252 | Revised | |
ISTD-5262 | Revised | |
ISTD-5263 |
|