companion guide to the asme boiler & pressure vessel...

Companion Guide to the ASME Boiler & Pressure Vessel Code

Criteria and Commentary on Select Aspects of the Boiler & Pressure Vessel and Piping Codes

Fourth Edition

VOLUME 2

EDITOR

K. R. RAO

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The Library of Congress has cataloged the previous edition as follows:

Companion guide to the ASME boiler & pressure vessel and piping codes : criteria and commentary on select aspects of the Boiler & pressure vessel and piping codes / editor, K.R. Rao. — 4th ed.

p. cm.Includes bibliographical references and indexISBN 978-0-7918-5986-5 (alk. paper) — ISBN 978-0-7918-5987-2 (alk. paper)

1. Steam-boilers—Standards. 2. Pressure vessels—Standards. I. Rao, K. R., 1933– II. American Society of Mechanical Engineers. III. ASME Boiler and Pressure Vessel Committee. ASME boiler and pressure vessel code.

TJ289.C66 2012621.1’83021873—dc23

2012019784

Cover photos:Volumes 1 & 2: Cover designer: Paul MoranPaul Nehrenz, photographer; Courtesy of Entergy Corporation:Volume 1: Ninemile Point; Volume 2: Waterford Nuclear Plant


THIS MONUMENTAL EFFORT IS DEDICATED TO THEASME PRESSURE VESSELS AND PIPING DIVISION ANDTO TWO SIGNIFICANT CONTRIBUTORS TO THE DEVEL-OPMENT OF THE DESIGN-BY-ANALYSIS CONSTRUCTIONRULES IN THE MODERN ASME CODE.

This two-volume compendium dedication is not the first recog-nition of the achievements of Bernard F. Langer and William E.Cooper. The Bernard F. Langer Nuclear Codes and StandardsAward, established in 1977, provides a posthumous and lastingtribute to one of these contributors, an intellectual giant who wasinstrumental in providing the leadership and statesmanship thatwas essential to the creation of construction rules for nuclear ves-sels and related equipment. William E. Cooper, the first recipientof the Bernard F. Langer Nuclear Codes and Standards Award, isanother intellectual giant instrumental in the creation of the mod-ern ASME Code. In addition, Dr. Cooper acted in a number ofASME Codes and Standards leadership positions. It was my plea-sure to join many of my colleagues in April 2001 for the presenta-tion to Dr. Cooper of the ASME President's Award from the 120thPresident of ASME International, William A. Weiblen. That mostprestigious award recognized a lifetime of achievement in ASMEand, in particular, in ASME Code activities.

Bernie Langer and Bill Cooper were essential in both the devel-opment of the modern ASME Code and in the creation of theforums for technical information exchange that support the Coderules. The publication of these two volumes by ASME Interna-tional is a legacy of that duality. These volumes continue a longand productive relationship between the development of the mod-ern ASME Code and the technical exchanges on pressure vesseland piping technology sponsored by the ASME Pressure Vesselsand Piping Technical Division. This process of technical informa-tion exchange, through conference paper and panel presentations,and through refereed paper publication, is an essential step in thereduction to standard practice, standard practice that is eventuallyembodied in the rules of the ASME Code. Information exchangeat technical conferences and in technical publications goes handin hand with the deliberations of ASME Code bodies.

This relationship goes back to the pivotal events leading up tothe development of the modern ASME Code — the appointmentof the Special Committee to Review Code Stress Basis in the late1950s. The principles formulated by that group became the basisfor Section III and Section VIII, Division 2 (design by analysis)of the Code. These basic principles were published by ASME in1968 under the title “Criteria of the ASME Boiler and PressureVessel Code for Design by Analysis in Sections III and VIII,Division 2.” At the same time that the work of the SpecialCommittee to Review Code Stress Basis was nearing fruition,leaders in the field of pressure vessel design, including BernieLanger and Bill Cooper, recognized that an improved forum forfundamental technical information exchange was needed. The

need eventually led to the formation of an ASME technical divi-sion, the Pressure Vessel and Piping (PVP) Division, in 1966.

Many of us who became involved in the PVP Division in theearly years were drafted by the leaders in the field to help pre-pare a compendium of the technical information on pressure ves-sel and piping technology. The Decade of Progress volumes, asthey were known then, were published by ASME in the early1970s, covering the most significant contributions to pressurevessel and piping design and analysis; materials and fabrication;and operations, applications, and components. The Decade ofProgress volumes should be considered the antecedents of thesetwo volumes. Both sets of volumes should be considered as inte-gral parts of the technical literature supporting the Code and theCriteria document.

The PVP Division has acted with great vigor over the years tocontinue to provide the technical forums needed to supportimprovements in the modern ASME Code. This year marks theDivision's 35th anniversary. When I first became involved in PVPDivision activities, the second year had just been completed, withVito Salerno as the second Chair of the Division Executive Com-mittee. Dana Young had been the first Chair, during 1966–1967,and Gunther Eschenbrenner was ready to become the third Chair,for the 1968–1969 year. Planning was well underway for the firstInternational Conference on Pressure Vessel Technology(ICPVT), scheduled for Delft, the Netherlands, in the followingyear. The plan was to hold such an international conference everyfour years, with the Secretariat rotating between Europe (1969),the United States (San Antonio, 1973), and Asia (Tokyo, 1977).Nine of these international conferences have now been held, themost recent in Sydney, Australia, in April 2000.

At the same time, initial planning for the First U.S. NationalCongress on Pressure Vessels and Piping, to be held every fouryears in the United States, was also underway. It was my privilegeto be the Technical Program Chair for the Second U.S. NationalCongress on PVP in 1975 in San Francisco, and the ConferenceChair for the Third U.S. National Congress on PVP in 1979, alsoin San Francisco. In addition, the activity within the PVP Divi-sion was such that we cosponsored ASME technical conferenceswith the Materials Division, the Nuclear Engineering Division,and the Petroleum Division in alternate years. This has since ledto the annual PVP Conference, the most recent being PVP 2001in Atlanta, Georgia, in July 2001.

The paper flow from the technical conferences and the networkof contributors for the Decade of Progress volumes eventually ledto the creation of the ASME Transactions Journal of PressureVessel Technology in late 1973, only seven years after formationof the Pressure Vessel and Piping Technical Division. Dr. IrwinBerman was its first Senior Technical Editor, with two TechnicalEditors representing the PVP Division and the Petroleum Divi-sion. Once again, I consider it a privilege to have been selected as

DEDICATION TO THE FIRST EDITION


iv • Dedication

the Technical Editor for the PVP Division, later becoming theSenior Technical Editor in 1978. The Journal and the technicalconferences have provided robust mechanisms for the neededtechnical information exchange.

But ASME Code rules and the associated technical informationexchange is not enough. In one of the very early issues (Novem-ber 1974) of the Journal of Pressure Vessel Technology, two arti-cles were published on the duty and responsibility of engineersand their engineering societies to address public concerns aboutthe safety and reliability of power plants. One, by Bernie Langer,was titled “The Role of the Engineering Societies in ObtainingPublic Acceptance of Power Plants.” The other, by Bill Cooper,was titled “Nuclear — Pressure Vessels and Piping — Materials:

Where to Next.” Both articles clearly identified the additionalcommitment that we all share to bring sound information to theattention of the general public and to policymakers in federal,state, and local jurisdictions. In the almost three decades since thepublication of those two articles, this commitment has beenextended, as the reach of ASME International, the ASME Boilerand Pressure Vessel Code, and the PVP Division covers the entireworld. We owe a debt of gratitude to these two giants, and thesetwo volumes represent a “down payment” on that debt.

Robert E. Nickell, Ph.D. William E. Cooper, Ph.D, P.E. 1999–2000 President


The editor is indebted to several individuals and organiza-tions in the preparation of this two-volume book. Some of themare identified for their assistance in completion of this effort.My thanks are to all of the thirty-nine contributors whose dedi-cated efforts made this possible by their singular attention todetail, even while they succinctly conveyed the voluminousinformation.

I wish to thank Dr. Jack Ware, Pressure Vessels and PipingDivision who suggested this effort. My thanks are in particular toMartin D. Bernstein who had from the start of this project beenmy inspiration to rally around during several ups and downs. Ialso thank Dr. Robert E. Nickell for his encouragement to see theend of the tunnel.

This effort would not have been possible but for the encourage-ment and support provided by my employer, Entergy OperationsInc., and in particular by Frederick W. Titus, William R.Campbell, John R. Hamilton, Willis F. Mashburn, Raymond

S. Lewis, Jaishanker S. Brihmadesam, Brian C. Gray, and Paul H. Nehrenz.

My special thanks to Professor Dr. Robert T. Norman,University of Pittsburgh, for the untiring pains he had taken intraining me to undertake efforts such as these — from their veryinitiation to their logical conclusion.

This unique two-volume publication, which Dr. FrederickMoody aptly called a "monumental effort," would have nevertaken off had it not been for the vision and sustained support pro-vided by the staff of ASME Technical Publishing. My thanks tothem for their support.

Finally, all of this saga-type effort, spread over three years, wouldhave never been possible had it not been for the constant encourage-ment and untiring support provided by my wife, Dr. Indira Rao, thatincluded all of the sundry chores associated with this project. Inaddition, I wish to thank other members of my family, Uma andSunder Sashti, and Dr. Ishu V. Rao, for their zealous support.

ACKNOWLEDGEMENTS TO THE FIRST

EDITION

This second edition following the success of the first editionhas an enlarged scope including the addition of a third volume.This warranted the addition of several contributors who are allexperts in their respective specialties. The editor appreciates theircontributions, as well as the continued support of the contributorsfrom the first edition.

Editor intends to once again thank Entergy Operations for theircontinued support. Thanks are especially due to Dr. Indira Raowhose support in several capacities made this voluminous effortpossible. My thanks are to the staff of ASME publishing for theircontinued zeal and support.

ACKNOWLEDGEMENTS TO THE SECOND

EDITION


This third edition follows the unprecedented success of the pre-vious two editions.

As mentioned in the first edition, this effort was initiated withthe ‘end user’ in mind. Several individuals and a few organiza-tions had provided support ever since this effort started.

In the second edition the success of the first edition wasenlarged in scope with the addition of a third volume, withexperts in their respective specialties to contribute chapters theyauthored.

In response to the changing priorities of Boiler and PressureVessel (B&PV) industry and global use of ASME B&PV Codesand Standards the scope and extent of this edition has increased.The result of the current effort is in a 2,550 page book spread inthree volumes.

The editor pays homage to the authors Yasuhide Asada, MartinD. Bernstein, Toshiki Karasawa, Douglas B. Nickerson andRobert F. Sammataro who passed away and whose expertiseenriched the chapters they authored in the previous editions.

This comprehensive Companion Guide with multiple editionsspanning over several years has several authors contributing to thiseffort. The editor thanks authors who had contributed to the previ-ous editions but did not participate in the current edition and theyare Tom Ahl, Domenic A. Canonico, Arthur E. Deardorff, Guy H.Deboo, Jeffrey A. Gorman, Harold C. Graber, John Hechmer,Stephen Hunt, Yoshinori Kajimura, Pao-Tsin Kuo, M. A. Malek,Robert J. Masterson, Urey R. Miller, Kamran Mokhtarian, DennisRahoi, Frederick A. Simonen, John D. Stevenson, Stephen V.Voorhees, John I. Woodworth and Lloyd W. Yoder.

The editor appreciates the effort of the continuing contributorsfrom the previous editions, who had a remarkable influence onshaping this mammoth effort, few of them from the very begin-ning to this stage. The editor gratefully acknowledges the follow-ing authors Kenneth Balkey, Warren Bamford, UmaBandyopadhyay, Jon E. Batey, Charles Becht IV (Chuck), SidneyA. Bernsen, Alain Bonnefoy, Marcus N. Bressler, Marvin L.Carpenter, Edmund W. K. Chang, Kenneth C. Chang, PeterConlisk, Joel G. Feldstein, Richard E. Gimple, Jean-MarieGrandemange, Timothy J. Greisbach, Ronald S. Hafner, GeoffreyM. Halley, Peter J. Hanmore, Owen F. Hedden, Greg L. Hollinger, Robert I. Jetter, Guido G. Karcher, William J. Koves,John T. Land, Donald F. Landers, Hardayal S. Mehta, Richard A.Moen, Frederick J. Moody, Alan Murray, David N. Nash, W. J.O’Donnell, David E. Olson, Frances Osweiller, Thomas P. Pastor,Gerard Perraudin, Bernard Pitrou, Mahendra D. Rana, Douglas K.

Rodgers, Sampath Ranganath, Roger F. Reedy, Wolf Reinhardt,Peter C. Riccardella, Everett C. Rodabaugh, Robert J. Sims Jr.,James E. Staffiera, Stanley Staniszewski, Richard W. Swayne(Rick), Anibal L.Taboas, Elmar Upitis and Nicholas C. Van DenBrekel.

Similarly the editor thanks the contribution of authors whojoined this effort in this third edition. Sincerity and dedication ofthe authors who joined in this effort is evident from two instances— in one case, a contributor hastened to complete his manuscriptbefore going for his appointment for heart surgery! In anothercase, when I missed repeatedly a correction made by a contribu-tor, he never failed to draw my attention to the corrections that Imissed!

Thus, the editor wishes to appreciate efforts of authors who joinedin this edition and worked zealously to contribute their best for thecompletion of this ‘saga’. The authors are Joseph F. Artuso, HansrajG.Ashar, Peter Pal Babics, Paul Brinkhurst, Neil Broom, Robert G.Brown, Milan Brumovsky, Anne Chaudouet, Shin Chang, Yi-BinChen, Ting Chow, Howard H. Chung, Russell C. Cipolla, CarlosCueto-Felgueroso, K. B. Dixit, Malcolm Europa, John Fletcher, LucH. Geraets, Stephen Gosselin (Steve), Donald S. Griffin, KunioHasegawa, Philip A. Henry, Ralph S. Hill III, Kaihwa Robert Hsu,D. P. Jones, Toshio Isomura, Jong Chull Jo, Masahiko Kaneda,Dieter Kreckel, Victor V. Kostarev, H. S. Kushwaha, Donald WayneLewis, John R. Mac Kay, Rafael G. Mora, Dana Keith Morton,Edwin A. Nordstrom, Dave A. Osage, Daniel Pappone, MartyParece, Michael A. Porter, Clay D. Rodery, Wesley C. Rowley,Barry Scott, Kaisa Simola, K. P. Singh (Kris), Alexander VSudakov, Peter Trampus, K. K. Vaze, Reino Virolainen, Raymond(Ray) A. West, Glenn A. White, Tony Williams.

The editor thanks Steve Brown of Entergy Operations for hishelp in the search for expert contributors for this edition.

This edition was initiated by me in August 2006 and has takenover 3000 hours of computer connection time. My thanks areespecially to my wife, Dr. Indira Rao whose sustained support forthis effort and participation in several chores related to editing. Inaddition, I appreciate her tolerating my working on it during a 4-month overseas vacation.

The editor thanks the staff of ASME Technical Publications fortheir unstinted zeal and support in aiming at this publication’starget of ‘zero tolerance’ for ‘errors and omissions’.

Finally, the editor thanks all of you, readers and users of this ‘Companion Guide’ and hopes it serves the purpose of thispublication.

ACKNOWLEDGEMENTS TO THE THIRD

EDITION


This fourth edition follows the unprecedented success of theprevious three editions.

As mentioned in the first edition, this effort was initiated withthe ‘end user’ in mind. Hundreds of individuals and several orga-nizations had provided support ever since this effort started.

The success of the first two editions prompted us to enlarge thescope with the addition of a third volume, with experts in the USand around the world to contribute the chapters. In response to thechanging priorities of Boiler and Pressure Vessel (B&PV) indus-try and global use of ASME B&PV Codes and Standards thescope and extent of the third edition had vastly increased resultingin a “mammoth” 2,550 page book spread in three volumes.

The editor in the “acknowledgements to the third edition” paidhomage to the authors Yasuhide Asada, Martin D. Bernstein,Toshiki Karasawa, Douglas B. Nickerson and Robert F.Sammataro who passed away since the first edition and whoseexpertise enriched the chapters they authored. Since then it is withprofound regret editor notes the passing away of Marcus N.Bressler and Peter J. Conlisk who were not merely contributors tothis “monumental effort” but were in several ways the “stan-chions” of not only the chapters they authored but ‘ardent advi-sors’ from the onset of this effort to the time of their passing away.

This comprehensive Companion Guide spanning over severalyears had several authors contributing to this effort. The editorthanks authors who had contributed to the previous editions butdid not participate in the current edition and they are Edmund W.K. Chang, Geoffrey M. Halley, Greg L. Hollinger, Donald F.Landers, John T. Land, Hansraj Ashar, Barry Scott, Chuck BechtIV, Guido G. Karcher and Richard E. Gimple. Most of thesecontributors had been associated with this effort from the verybeginning and to them the editor salutes them for their signal con-tribution, direction and continued support.

The editor appreciates the effort of the continuing contributorsfrom the previous editions, who had a remarkable influence onshaping this mammoth effort, few of them from the very begin-ning to this stage. The editor gratefully acknowledges the follow-

ing authors John R. MacKay, Elmar Upitis, Richard A. Moen,Marvin L. Carpenter, Roger F. Reedy, Richard W. Swayne (Rick),David P. Jones, Uma S. Bandyopadhyay, Robert I. Jetter, JosephF. Artuso, Dana Keith Morton, Donald Wayne Lewis, Edwin A.Nordstrom, Jon E. Batey, Thomas P. Pastor, Dave A. Osage, ClayD. Rodery, Robert G. Brown, Philip A. Henry, Robert J. Sims Jr.,Joel G. Feldstein, Owen F. Hedden, Russell C. Cipolla, James E.Staffiera, Warren Bamford, Hardayal S. Mehta, Mahendra D.Rana and Stanley Staniszewski.

Similarly the editor appreciates contribution of authors whojoined this effort in the current edition and worked zealously to con-tribute their best for the completion of this ‘saga’. The authors areJames T. Pillow, John F. Grubb, Richard C. Sutherlin, Jeffrey F.Henry, C.W. Rowley, Anne Chaudouet, Wesley C. Rowley, C.Basavaraju, Jack R. Cole, Richard O. Vollmer, Robert E. CornmanJr., Guy A. Jolly, Clayton T. Smith, Arthur Curt Eberhardt, MichaelF. Hessheimer, Ola Jovall, James C. Sowinski, Bernard F. Shelley,Jimmy E. Meyer, Joseph W. Frey, Michael J. Rosenfeld and LouisE. Hayden Jr.

The editor thanks Jimmy E. Meyer for his help in the search fortopics and expert contributors for several B31 Piping Chapters forthis edition.

This edition was initiated by me in May 2011 and has takenjust over a year for completing this edition.

My thanks, as has been since I embarked on the first editionover a decade back, are especially to my wife, Dr. Indira Raowhose sustained support for this effort and participation in severalchores related to editing of this edition. In addition, I appreciateher tolerating my working on it during several vacations.

The editor thanks the staff of ASME Technical Publications fortheir continued patience, undivided support and focused effort inaiming once again at this publication’s target of ‘zero tolerance’for ‘errors and omissions’.

Finally, the editor thanks all of you, readers and users of this‘Companion Guide’ and hopes it serves the purpose of thispublication.

ACKNOWLEDGEMENTS TO THE FOURTH

EDITION


AHL, THOMAS J.

Thomas J. Ahl earned a B.S.C.E. in 1960and M.S.C.E. in 1961 from University ofWisconsin. He is a Registered Structuraland Professional Engineer in Illinois. Heheld the position of Principal Engineer inNuclear & Pressure Vessel Design De-partment, Chicago Bridge & Iron Co.,Plainfield, IL, (1961–1998), and wasengaged in design and analysis of nuclear

related vessels and structural components. Ahl was a Member ofANSI Working Group ANS-56.8 that prepared the ANSI/ANS-56.8-1981—Containment System Leakage Testing Requirementsstandard.

Ahl is a Member of ASCE, Member of ASCE HydropowerDevelopment Committee, and Conventional Hydropower Sub-committee. He served as Co-Chair of the Task Committee preparing the publication “Manual of Practice for Steel Penstocks ASCE Manual No. 79,” Vice-Chair-ASCE Committeepreparing the “Guidelines for Evaluating Aging Penstocks,” andmember of ASCE Hydropower Committee preparing “CivilEngineering Guidelines for Planning and Design of HydroelectricDevelopments.”

Two of these publications received the ASCE Rickey AwardMedal in 1990 and 1994. Thomas Ahl is a member of the PeerReview Group to Sandia National Laboratories and the U.S.Nuclear Regulatory Structural Engineering Branch for the SafetyMargins for Containment’s Research Program, 1980–2001.

ARTUSO, JOSEPH F.

Joseph F. Artuso is the CEO of Construc-tion Engineering Consultants, Inc. He hasover 40 years experience in developingand managing quality control inspectionand testing programs for constructionmaterials. He is also actively involved inthe Code and Standards writing bodies ofACI and ASME. Mr. Artuso earned a B.S.in Civil Engineering at Carnegie Institute

of Technology in 1948 and became a Level III InspectionEngineer at the National Council of Engineering Examiners in1975. He is a registered Professional Engineer in the states ofPennsylvania, Ohio, New York, Florida, Maryland and WestVirginia, as well as being registered as Quality Control Engineerin state of California. His memberships in national committeesinclude A.S.C.E. (Task committee on Inspection Agencies),A.C.I (Committees 214, 304 and 311), A.N.S.I (N-45-3.5

Structural Concrete and Steel), A.S.M.E. (Committee 359(ASME Sec. III, Div. 2) Construction Materials and Exam.),ACI-ASME (Committee on Concrete Pressure Components forNuclear Service), ASTM, and NRMCA. He was a contributingeditor of McGraw-Hill “Concrete Construction Handbook”. Mr.Artuso was the Director of Site Quality Control for theDuquesne Light Company, Beaver Valley, Unit 2. He also super-vised construction quality control activities on many nuclearpower plants during the period of high construction activityfrom the 1970’s to 1980’s.

ASHAR, HANSRAJ, G.

Mr. Ashar has a Master of Science degreein Civil Engineering from the University ofMichigan. He has been working with theNuclear Regulatory Commission for thelast 35 years as a Sr. Structural Engineer.Prior to that Mr. Ashar has worked with anumber of consultants in the U.S. andGermany designing Bridges and Buildings.Mr. Ashar has authored 30 papers related

to structures in nuclear power plants.Mr. Ashar’s participation in National and International Standards

Organization includes Membership of the NSO and INSOCommittees such as American Institute of Steel Construction(AISC), Chairman of Nuclear Specification Committe (January1996 to March 2008), (AISC/ANSI N690); Member of BuildingSpecification Committee, and Corresponding of Seismic ProvisionsCommittee.

Mr. Ashar’s professional activities with The AmericanConcrete Institute (ACI) 349 Committees include Member ofthe Main committee, Subcommittee 1 on General Requirements,Materials and QA, and Subcommittee 2 on Design. His profes-sional activities also include American Society of MechanicalEngineers (ASME), Corresponding Member, Working Group onlnservice Inspection of Concrete and Steel Containments(Subsections IWE and IWL of ASME Section XI Code), Mem-ber, ASME/ACI Joint Committee on Design, Construction,Testing and Inspection of Concrete Containments and PressureVessels; Member, RILEM Task Committee 160-MLN: Meth-odology for Life Prediction of Concrete Structures in NuclearPower Plants; Member, Federation Internationale du Beton(FIB) Task Group 1.3: Containment Structures, and Con-sultant to IAEA on Concrete Containment Database (2001 to 2005).

Mr. Ashar is a Professional Engineer in the State of Ohio andState of Maryland; Fellow, American Concrete Institute; Fellow,American Society of Civil Engineers; Professional Meer –

CONTRIBUTOR BIOGRAPHIES


x • Contributor Biographies

Posttensioning Institute. Mr. Ashar is a Peer Reviewer of thePapers to be published in ASCE Material Journal, Nuclear Engi-neering and Design (NED) Periodicals and ACI Material Journal.

BAMFORD, WARREN

Warren Bamford has been a member ofSection XI since 1974, and now serves asChairman of the Subgroup on EvaluationStandards, whose charter is to develop andmaintain flaw evaluation procedures andacceptance criteria. He is a member of theExecutive Committee of Section XI, andwas also a charter member of the ASMEPost Construction Committee, whose goal

is to develop inspection, evaluation and repair criteria for non-nuclear plants. He has taught a course on the Background andTechnical Basis of the ASME Code, Section III and Section XI.Warren has been educated at Virginia Tech, Carnegie MellonUniversity, and the University of Pittsburgh.

Warren’s research interests include environmental fatigue crackgrowth and stress corrosion cracking of pressure boundary materi-als, and he has been the lead investigator for two major programsin this area. He was a charter member of the InternationalCooperative Group for Environmentally Assisted Cracking, whichhas been functioning since 1977.

Warren Bamford has been employed by Westinghouse Electricsince 1972, and now serves as a consulting Engineer. He special-izes in applications of fracture mechanics to operating powerplants, with special interest in probabilistic applications. Over 80technical papers have been published in journals and conferenceproceedings.

BANDYOPADHYAY, UMA S.

Bandyopadhyay received his BSME fromJadavpur University (1970), Calcutta,India, MSME from the PolytechnicInstitute of Brooklyn (1974). He is a reg-istered Professional Engineer in the statesof New York, New Jersey, Connecticut,Massachusetts, Virginia, Wyoming andDistrict of Columbia. He has 28 years ofextensive experience in design, engineer-

ing and manufacturing of pipe supports and pipe support prod-ucts for Water Treatment and Waste Water Treatment Facilities,Oil Refineries, Co-generation, Fossil and Nuclear Power Plants.Bandyopadhyay is currently employed by Carpenter andPaterson, Inc. as Chief Engineer and works as a consultant andRegistered Professional Engineer for affiliate Bergen-PowerPipe Supports, Inc. Prior to his current employment, he held thepositions of Design Engineer (1977–1980), Project Engineer(1980–1986) and Chief Engineer (1986–1992) with Bergen-Paterson Pipesupport Corp. Bandyopadhyay is a member,Working Group on Supports (Subsection NF), since 1993; wasan alternate member, Subsection NF (1986–1993). He is also analternate member, Manufacturer’s Standardization Society(MSS), Committee 403-Pipe hangers (MSS-SP-58, 69, 89, 90and 127) since 1992.

BASAVARAJU, CHAKRAPANI

Dr. Chakrapani Basavaraju, P.E., has over30 years of experience, which includesmore than 28 years in the power industryinvolving design of nuclear and non-nuclear power plants, and 3 years in theteaching profession. He received Ph.D. inMechanical Engineering from Texas A&MUniversity. He is a registered ProfessionalEngineer. He is a fellow of the American

Society of Mechanical Engineers (ASME).He has been working as a Mechanical Engineer at the United

States Nuclear Regulatory Commission (USNRC) in the office ofNuclear Reactor Regulation (NRR) since 2006. Previously, heworked Bechtel Power Corporation, Stone & Webster Corporation,and Duke Power Company. He has been recognized with severalawards which include Technical Specialist Award, OutstandingTechnical Paper awards (Bechtel 1993, 2005), and Instructor of theYear award for his exceptional achievements, contributions, andinnovative solutions to practical engineering problems. Dr.Basavaraju has published 22 technical papers, which are of value,and practical significance to the industry and Engineering commu-nity on various topics in the areas of design and analysis of powerplant piping systems and components, Creep, Fatigue, FlowInduced Vibration, Applications of Finite Element Analysis,Extrusion, Weld shrinkage, and Hypervelocity Impact.

He contributed 3 chapters for internationally recognized refer-ence handbooks. Technical papers written by him have brokennew grounds in providing innovative and cost effective approaches to complex industry issues. He also has peer reviewed severaltechnical papers. His in-depth knowledge of analytical methods,expertise in finite element analysis techniques, and extensiveapplication experience in applying those techniques for designand analysis of power plant piping and mechanical componentshave earned him the respect of his peers and superiors. He haschaired sessions of the ASME Conferences and he is serving as a member of the ASME PVP Design & Analysis TechnicalCommittee.

Dr. Basavaraju has contributed chapters to the Piping Handbook(6th Edition, 1992, & 7th Edition , 1999) and the Piping Databook(6th Edition, 2002) published by McGraw-Hill, Inc. New York, NY.In addition, he has reviewed sections of these two internationallyused reference books. His input, suggestions and contributions haveenriched the contents of these publications. Basavaraju providedsupport and background information for code changes to ASCE 7code, Tanks Seismic Group.

Technical Program Representative (TPR) for D&A Track ofASME PVP/CREEP8 Conference (2007).

Dr. Basavaraju is a member of the PVP Design and AnalysisTechnical Committee.

Serving as chair/vice chair at ASME PVP conference sessionssince 2002.

Basavaraju also chaired & co-chaired sessions for ASMEICONE10 conference.

Member, ASME Section III B&PV Code , SC III SG-D, WGPD(Working Group on Piping Design).

Member, ASME Section III B&PV Code , SC III SG-D, WGV(Working Group on Vessels).

Member, ASME Section III B&PV Code , SC III, SWG (SpecialWorking Group on Plastic Piping).


COMPANION GUIDE TO THE ASME BOILER & PRESSURE VESSEL CODE • xi

BATEY, JON E.

Jon Batey is an ASME Fellow who hasbeen a member of ASME StandardsCommittee V since 1995 and has served asChairman since 2002. Jon has served onvarious sub-tier committees of StandardsCommittee V since 1990 and currently is amember of the Subgroup on VolumetricExamination Methods, the Subgroup onGeneral Requirements, Personnel Quali-

fications and Interpretations, the Working Group on Radio-graphy, the Working Group on Acoustic Emission, and theWorking Group on Guided Wave Ultrasonic Examination. He isalso a member of the ASME Post Construction StandardsCommittee and is Chairman of its Subcommittee on InspectionPlanning. Jon was also a member of the ASME B-16 StandardsCommittee from 1979 to 1993.

Jon is the Global Inspection Leader for The Dow ChemicalCompany in Freeport, TX. In his current role, Jon is responsiblefor inspection performed by Dow or third-party inspectors at sup-plier fabrication shops. He received a B.S. in Physics from TexasState University. His certifications include NDT Level III inRadiography, Ultrasound, Liquid Penetrant, Magnetic Particle,Visual and Leak Test Methods.

BECHT IV, CHARLES

Dr. Becht is a recognized authority inpressure vessels, piping, expansion joints, and elevated temperature design. He isPresident of Becht Engineering Co. Inc, aconsulting engineering company providingservices to the process and power indus-tries (www.becht.com, www.bechtns.comfor the nuclear services division, andwww.techtraining.info for technical train-

ing); President of Becht Engineering Canada Ltd.; President ofHelidex, LLC (www.helidex.com); and Director of SonomaticLtd. (also dba Becht Sonomatic, www.vsonomatic.com) a NDEcompany that provides advanced ultrasonic imaging. Chuck waspreviously with Energy Systems Group, Rockwell Internationaland Exxon Research and Engineering where he was a pressureequipment specialist. He received a PhD from MemorialUniversity in Mechanical Engineering (dissertation: Behavior of Bellows), a MS from Stanford University in StructuralEngineering and BSCE from Union College, New York. Chuck isa licensed professional engineer in 16 states and provinces, anASME Fellow since 1996, recipient of the ASME DedicatedService Award in 2001, and has more than 60 publications includ-ing the book, Process Piping: The Complete Guide to ASMEB31.3, and five patents.

Dr. Becht is Chair of the ASME B31.3, Process PipingCommittee; Chair (founding) of the Post Construction Sub-committee on Repair and Testing (PCC), and member of otherASME Committees including the Post Construction StandardsCommittee (past Chair); Post Construction Executive Com-mittee (past Chair); B&PV Code Subcommittee on TransportTanks; B&PV Code Subgroup on Elevated TemperatureDesign (past Chair); B31 Code for Pressure Piping Standards

Committee; B31 Mechanical Design Committee; B31 Exe-cutive Committee; and is a past member of the Board onPressure Technology Codes and Standards; the B&PV CodeSubcommittee on Design; and the B&PV Code TG on Class 1Expansion Joints for liquid metal service. He is a member ofASTM Committee F-17, Plastic Piping Systems Main Com-mittee; and the ASME PVP Division, Design and AnalysisCommittee.

BERNSTEIN, MARTIN D.

Mr. Bernstein was involved in the designand analysis of steam power equipmentsince joining Foster Wheeler EnergyCorporation in 1960. Retired in 1996, hecontinued to serve as a consultant toFoster Wheeler and as their representativeon the ASME Boiler and Pressure VesselCommittee, on which he had served formore than 25 years. He was Vice Chair,

Subcommittee on Power Boilers, Chair, Subcommittee onSafety Valve Requirements, a member of the Main Committee(Standards Committee) and past Chair of Subgroup GeneralRequirements and the Subgroup Design of the Subcommittee onPower Boilers. Since 1986 he and Lloyd Yoder taught a two-daycourse on Power Boilers for the ASME Professional De-velopment Department. In 1998, ASME Press published PowerBoilers—A Guide to Section I of the ASME Boiler and PressureVessel Code that Bernstein and Yoder developed from theircourse notes.

Mr. Bernstein was active for many years in ASME’s PVPDivision. He was also author and editor of numerous ASME pub-lications, including journal articles on ASME design criteria,ASME rules for safety valves, flow-induced vibration in safetyvalve nozzles, and tubesheet design. Mr. Bernstein obtained aB.S. and M.S. in civil engineering from the Columbia School ofEngineering and Applied Science. He was elected an ASMEFellow in 1992, received the ASME Dedicated Service Award in1994, and was awarded the ASME J. Hall Taylor Medal in 1998.He was a Registered Professional Engineer in New York State.Mr. Bernstein passed away in 2002.

BRESSLER, MARCUS N.

Mr. Bressler is President of M. N.BRESSLER, PE, INC., an engineeringconsulting firm founded in 1977, specializ-ing in codes and standards, quality assur-ance, design, fabrication, inspection andfailure analysis for the piping, power,petroleum and chemical industries. He hasover 54 years of experience. He joinedTVA in 1971 as Principal Engineer and

was promoted in 1979 to Senior Engineering Specialist, CodesStandards and Materials. He took early retirement in 1988 to openup a private consulting practice. His previous experience was withthe US Army (1952) where he served as an Industrial HygieneEngineer; the Babcock & Wilcox Company(1955), where he heldthe positions of Engineering Draftsman, Stress Analyst, and


xii • Contributor Biographies

Boiler Division Materials Engineer; Gulf & Western LenapeForge Division (1966) where he became Senior Design Engineer,and Taylor Forge Division (1970) as Product DevelopmentManager. At Lenape Forge he developed a design for a quick-opening manway for pressure vessels and piping that was granteda patent in 1971.

Mr. Bressler began his activities in Codes, Standards andMaterials in 1960. He has been a member of the ASME B&PVStandards Committee since 1979 to 2009, and is now a member ofthe Technical Oversight Management Commitee. He is a memberand past Vice Chair of the Committee on Nuclear Certification. Heis a member of the Standards Committees on Materials and onNuclear Power, the subgroup on Design (SCIII), the special work-ing group on Editing and Review (SC III), the Boards on NuclearCodes and Standards and on Conformity Assessment. He is theChair of the Honors and Awards Committee (BNCS). Mr. Bressleris a member of the ASTM Committees A-01 and B-02 and many oftheir subcommittees.

Mr. Bressler holds a BME degree from Cornell University(1952) and an MSME degree from Case Institute of Technology(1960). In 1989 he received a Certificate of Achievement fromCornell University for having pursued a course that, under today’srequirements, would have resulted in a Master of Engineeringdegree. He was awarded the ASME Century Medallion (1980),and became a Fellow of ASME in 1983. He is now a Life Fellow.He received the 1992 ASME Bernard F. Langer Nuclear Codesand Standards Award. and is the 1996 recipient of the ASME J.Hall Taylor Medal. He received the 2001 ASME DedicatedService Award. He is a Registered Professional Engineer in theState of Tennessee (Retired).

Mr. Marcus N. Bressler passed away since the publication ofthe third edition.

BROWN, ROBERT G.

Mr. Brown is a Principal Engineer andDirector of Consulting for the Equity Engi-neering Group in Shaker Heights, Ohio. Hehas experience as both an owner-user andconsultant providing engineering support torefineries and chemical plants worldwide.Mr. Brown uses advanced skills in FiniteElement Analysis to provide practical andcost effective solutions to solve design and

operational issues related to fixed equipment.Mr. Brown assisted with the development of API 579 Fitness-

For-Service and has been a consultant for the PVRC effort todevelop the new ASME, Section VIII, Division 2, Boiler andPressure Vessel Code, taking into consideration the latest de-velopments in materials, design, fabrication, and inspectiontechnologies.

Mr. Brown is an active member of the Battelle InternationalJoint Industry Project on the Structural Stress Method forFatigue Assessment of Welded Structures and performs fatigueassessments/reviews of equipment in cyclic service. Mr. Brownalso serves on the ASME Subgroup on Design Analysis and per-forms code compliance calculations and interpretations for pres-sure vessels. Mr. Brown is a registered Professional Engineer inthe States of Ohio and Pennsylvania.

CANONICO, DOMENIC A.

Dr. Canonico received his B. S. fromMichigan Technological University, M.S.and Ph.D. from Lehigh University. He hasover 40 years experience in pressure partsmanufacturing. Dr. Canonico is currentlyemployed by ALSTOM POWER facilitiesin Chattanooga, Tennessee. He is Past Chairof the ASME Boiler Pressure Vessel (BPV)Code Main Committee and a member of the

ASME Council on C. & S. and Vice President-elect PressureTechnology, C&S. He is a Fellow in ASME, the American WeldingSociety (AWS) and the American Society for Metals (ASM). In1999 Dr. Canonico received the ASME Melvin R. Green C&SMedal. He was the 1994 recipient of the ASME J. Hall TaylorMedal, in 1996 and 1999 respectively he was awarded the De-dicated Service Award., and the ASME Region XI Industry Exe-cutive Award. In 1978, 1979, and 1985 respectively AWS awardedhim the Dr. Rene Wasserman Award, the James F. Lincoln GoldMedal, and the William H. Hobart Memorial Medal; he was the1983 Adams Lecturer. He is a member of the State of TennesseeBoiler Rules Board.

He has written over 100 technical papers and given technicaltalks in U.S., Canada, Mexico, Europe and Asia. He is named inWho’s Who in Engineering and Men and Women of Science. Dr.Canonico is an Adjunct Professor at the University of Tennessee,Knoxville and on the Advisory Committee of the School ofEngineering, University of Tennessee, Chattanooga.

CARPENTER, MARVIN L.

Marvin L. Carpenter graduated with honorsfrom Michigan Technological University(MTU) with a B.S. in Metallurgical Eng-ineering. He continued at MTU and receivedhis Masters in Metallurgical Engineering in1974. Since graduating, his career has beenfocused on welding fabrication and testingin accordance with the ASME Boiler andPressure Vessel Code. ASME Code Com-

mittees first caught his attention in the late seventies and he hasremained active in the Code ever since. He serves on theSubcommittee on Welding (IX), Chaired the Subgroup on Brazing(IX) and currently Chairs the Subgroup on Materials (IX).

Mr. Carpenter gained expertise in production welding, brazing,failure analysis, coatings, and material testing while working formajor corporations including Westinghouse Electric Corporation,The Trane Company, and Bechtel. His experience ranges fromsupervising a Welding Engineering Develop group to setting upand operating a materials testing laboratory that performed chem-ical analysis, mechanical testing, metallography, and weldingqualification.

In addition to his extensive materials and welding background,he was granted a patent in 1995 for a GTAW-HW circular weld-ing system. His current position is as a Principal Engineer with amajor U.S. company that provides power plant equipment. Mr.Carpenter resides in Pittsburgh, PA with his wife, Denise, and twochildren, Scott and Michelle.


COMPANION GUIDE TO THE ASME BOILER & PRESSURE VESSEL CODE • xiii

CHANG, EDMUND W. K.

Edmund W.K. Chang, P.E., received hisBSME from the University of Hawaii(UHM), 1969. Mr. Chang is currently em-ployed as the Boiler & Welding Main-tenance Engineer with Hawaiian ElectricCompany, Inc., Power Supply EngineeringDepartment, Honolulu, Hawaii. Mr. Chang’sresponsibilities include being in-charge ofall company boiler condition assessments,

and National Board (NB) “R” and “VR” Symbol Stamp repairprograms. Mr. Chang is also a NB commissioned O/U Inspector,in charge of in-service and acceptance inspections. He is a AWSCertified Welding Inspector (CWI), in charge of welding pro-gram, and the company’s NDT Level III in PT and MT in chargeof the NDT program.

Mr. Chang’s professional affiliations include ASME Mem-bership since 1971; association with ASME Hawaii Section asChairman 2008–2009, Honors & Awards Committee Chair,Webmaster, Newsletter Editor, and Section Chair 1993–1994;ASNT Hawaii Section Director and Webmaster; AWS HawaiiSection Webmaster; and Chair 1996 of Hawaii Council ofEngineering Societies. Mr. Chang is a member of the Departmentof Mechanical Engineering, UHM, Industry Advisory Board.

Mr. Chang’s professional publications include as a lead author of“T91 Secondary Superheater Tube Failures Investigation,” 1997,ASME PVP Conference, Orlando, Florida; and “Tangential-FiredBoiler Tube Failures, A Case Study,” 2007, EPRI InternationalConference on Boiler & HRSG Tube Failures, Calgary, Alberta,Canada.

CHAUDOUET, ANNE

Ms. Chaudouet earned a Master of PureMaths at Paris XIII University in 1974 andthen obtained a Mechanical EngineeringDegree from ENSMP (Mines) in Paris-France in 1976. The same year, she startedher career at Cetim (French TechnicalCentre of Mechanical Industries) in R&Din the field of solid mechanics analysed bythe Boundary Element Method (BEM).

Soon after, she became in charge of the team responsible forthe development of all software developed at Cetim in the domainof 2D and 3D heat transfer and solid mechanics. In that role shehad the direct responsibility for the analyses of components byBEM and for fracture mechanics. In 1984, she became head of theLong Term Research Service involved in more theoretical studiesand development of design rules for pressure vessels. In the sameyear she initiated Cetim's participation in PVRC (Pressure VesselResearch Council).

Since 2003, Ms Chaudouet has been actively involved inASME Boiler and Pressure Vessel Code organization where sheis now a member of the Standard Committee on Materials, ofSC II/International Material Specifications (currently Chair ofthis SG), of the Standard Committee on Pressure Vessels of SCVIII/Heat Transfer Equipment and of the Technical OversightManagement Committee. She is also an active member of theASME/API Joint Committee on Fitness for Service.

In France, Ms. Chaudouet is a member of the Liaison Com-mittee dealing with the European Directive on Pressure Equip-ment and of the Liaison Committee dealing with the French Orderon Nuclear Pressure Equipment.

Ms. Chaudouet has published over 30 papers in French and inEnglish in the domain of Boundary Elements, Fracture Mechanicsand more recently on Fitness-For-Service. Most of these werepresented at International Conferences. Member of several Ph Dtheses, she has developed professional courses on these topics. Inthe domain of pressure equipment she has also given short cours-es on the European Directive (PED).

CIPOLLA, RUSSELL C.

Mr. Russell Cipolla is Principal Engineerfor Intertek APTECH, Sunnyvale, Cali-fornia (USA). Mr. Cipolla received hisB.S. degree in Mechanical Engineeringfrom Northeastern University in 1970, andhis M.S. in Mechanical Engineering fromMassachusetts Institute of TechnologyMechanics in 1972. He has been active inthe Nuclear Power Industry since the early

1970s having worked at the nuclear divisions of Babcock &Wilcox and General Electric in the area of ASME Section IIIdesign associated with both naval and commercial power plantssystems.

Mr. Cipolla has specialized in stress analysis and fatigue andfracture mechanics evaluations of power plant components inoperating plants. He has applied his skills to many service prob-lems to include stress corrosion cracking (SCC) of J-grooveattachments welds in reactor vessel head penetrations and pres-surizer heater sleeves, mechanical and thermal fatigue in piping,SCC in low pressure steam turbine rotors and blades, and fitness-for-service of components supports. He was also involved inresolving the NRC Generic Safety Issues A-11 and A-12 regard-ing fracture toughness and bolted joint integrity. He is well versedin the integrity of threaded fasteners for both structural joints andpressure boundary closures.

In recent years, he has been active in both deterministic andprobabilistic methods and acceptance criteria for nuclear steamgenerators (SG) regarding pressure boundary integrity in compli-ance with NEI 97-06 requirements. In support of industry groupefforts, he has made significant contributions to the industryguidelines for the assessment of tube integrity and leakage perfor-mance for various degradation mechanisms affecting Alloy 600and 690 tubing materials. He has development methods for pre-dicting tube burst and leak rates under various service conditions,which have become part of the industry standards.

Mr. Cipolla has been very active in ASME Section XI sincejoining the Working Group on Flaw Evaluation in 1975, for whichhe is currently Chairman. He is also a member of the Subgroup on Evaluation Standards and Subcommittee Section XI, and hasparticipated in many ad hoc committees on such topics as envi-ronmental fatigue, SCC of austenitic materials, and fracturetoughness reference curves for pressure vessels and piping, andSG tube examination. Mr. Cipolla has authored/coauthored over80 technical papers on various subjects and assessments from hispast work.


xiv • Contributor Biographies

COLE, JACK R.

Jack Cole is a Senior Advisory Engineerfor Becht Engineering Nuclear ServicesDivision. Mr. Cole has over thirty fiveyears of experience in the nuclear powerindustry, including nuclear waste manage-ment, nuclear plant construction, and 30years in commercial nuclear power plantdesign and operation. Prior to joiningBecht Engineering, Mr. Cole worked 30

years for Energy Northwest, the operator of the ColumbiaGenerating Station BWR. At Energy Northwest, Mr. Cole servedas the Design Authority responsible for plant Civil/Structural/Stresslicensing basis compliance. Mr. Cole’s work activities haveincluded design of pressure vessels and piping systems, develop-ment of ASME Design Specifications for pressure components,operability assessments for degraded components, repair andreplacement activities for mechanical components, plant vibrationand thermal fatigue monitoring and support for major projectssuch as plant power uprate, pump and valve replacement, replace-ment of the plant condenser and heaters, and time limited agingevaluations for license renewal. Mr. Cole has served as technicalconsultant to IAEA in the area of aging management for mechani-cal components for plant life extension and is an instructor forcourses in ASME Section III Design and Fitness for Service.

Mr. Cole has been an active member of the ASME Section IIICodes and Standards for the past 28 years. He is currently ViceChairman of BPV Committee on Construction of Nuclear FacilityComponents (BPV III), Chairman of the BPV III ExecutiveCommittee on Strategy and Project Management, Chairman of theSpecial Committee on Interpretations (BPV III), Member of theSubgroup on Component Design (BPV III), Member and PastChairman of the Working Group on Piping, and past member ofthe Working Group on Supports (III).

Mr. Cole has a B.S. degree in Mechanical Engineering fromOregon State University (1972) with additional graduate studiesat the University of Washington and Washington State Uni-versity. Mr. Cole is a Registered Professional Engineer. He haspublished several papers on piping fatigue analysis and vibrationassessment.

CONLISK, PETER J.

Dr. Conlisk’s has a B.S. in MechanicalEngineering and M.S. in EngineeringScience from the University of NotreDame and Ph.D. in Engineering Mechanicsfrom the University of Michigan. He hasforty years experience applying engineer-ing principles, computers, experimentaltechniques, and Codes and Standards tosolving design of processing equipment

and vessels in the chemical industry. From 1960 until 1968, heworked in the Aerospace industry and from 1968 until his earlyretirement in 1993, Dr. Conlisk worked for the MonsantoCorporation, the last 19 years in the Engineering Department. Hewas a key member in a team at Monsanto that developed acousticemission examination for fiberglass and metal tanks and vessels.His services are now available through Conlisk EngineeringMechanics, Inc., a consulting firm he formed in 1994. He has

concentrated on design of tanks and pressure vessel, especiallyfiberglass composite (FRP) vessels. Dr. Conlisk is a nationallyrecognized authority in FRP equipment design and analysis. He isa member of the ASME committee that developed the ASME/ANSI Standard: “Reinforced Thermosetting Plastic CorrosionResistant Equipment, RTP-1.”

Dr. Conlisk is past chairman and current vice-chairman of theASME B&PV Code subcommittee, Section X, governing FRPpressure vessels. He is also a past member of the main committeeof the ASME B&PV Code. Dr. Conlisk is a registered profession-al engineer in Missouri.

Dr. Peter J. Conlisk passed away since the publication of thethird edition.

CORNMAN, E. ROBERT JR.

Bob Cornman is a Director of ProductEngineering for the Flow Solutions Groupof the Flowserve Corporation. He holds aBS degree in Civil Engineering fromLehigh University and an MBA fromLehigh University. Bob Cornman is aRegistered Professional Engineer in the

State of Pennsylvania. He is an active ASME member and hasbeen chairman of ASME Nuclear Section III Working Group onPumps for many years.

Bob Cornman’s engineering career spans more than 40years all of which has been spent working for Flowserve or itslegacy companies in the design and manufacturing of centrifu-gal pumps. His primary areas of expertise are in the design,application, and manufacturing of very large vertical singlepumps and vertical multi-stage can pumps. He has authorednumerous papers on vertical pump design, applications, andother associated equipment.

Past projects and work experience has involved major fossiland nuclear power generating stations, large drainage and floodcontrol projects, and pump manufacturing test facilities.

DEARDORFF, ARTHUR F.

Arthur F. Deardorff has a MechanicalEngineering B.S, from Oregon StateUniversity (1964) and MS, University ofArizona (1966). He is a RegisteredMechanical Engineer, State of California.He is a Vice President, Structural IntegrityAssociates, San Jose, California. His pro-fessional experience includes 1987 to pre-sent with Structural Integrity Associates,

San Jose, CA, 1976–1987 with NUTECH, San Jose, CA,1970–1976 with General Atomic Company, San Diego, CA and1966–1970 with The Boeing Company, Seattle, WA. His profes-sional associations include American Society of MechanicalEngineers and American Nuclear Society. He is a Past Member ofthe ASME Code Section XI Subgroup Water Cooled Systems,Working Group on Implementation of Risk-Based Inspection,Task Group on Erosion-Corrosion Acceptance Criteria, TaskGroup on Fatigue in Operating Plants, and Task Group onOperating Plant Fatigue Assessment, and the ASME Code PostConstruction Committee, Subgroup on Crack-Like Flaws.


COMPANION GUIDE TO THE ASME BOILER & PRESSURE VESSEL CODE • xv

Mr. Deardorff has expertise in fracture mechanics, stressanalysis and reactor systems evaluation, with a strong academicbackground in thermal-hydraulics and fluid system. His exper-tise includes PWR and BWR systems and fossil-fired powerplants. Art is known internationally for providing ASME Codetraining in Section III design and analysis and Section XI flawevaluation.

EBERHARDT, ARTHUR CURT

Dr. Eberhardt has a Bachelor of Architec-tural Engineering from Iowa State Uni-versity. Ames, IA and a Ph.D. from theUniversity of Illinois at Urbana, IL. He is aRegistered Structural Engineer in the Stateof Illinois and a Registered ProfessionalEngineer in the States of Texas and Illinois.Dr. Eberhardt is a Senior Manager/Senior

Consultant at Sargent & Lundy, LLC in Chicago, Illinois, where hehas worked for 37 years on projects involving nuclear plant designand analysis. Dr. Eberhardt has gained a wide variety of structuralengineering experience in many areas including containmentdesign, dry spent fuel storage structures, seismic analysis, blastanalysis, plant modifications, heavy loads analysis, design criteriadevelopment, design basis reconstitution, configuration baselinedocumentation, high-density spent fuel pool analysis, structuralmaintenance rule evaluations, and 10CFR 50.59 safety evaluations.He has worked on projects associated with more than 14 nuclearpower plants.

Dr. Eberhardt has served on ASME BP&V Code Committees formore than 23 years. He currently is Chair of the Joint ACI/ASMECommittee on Concrete Components for Nuclear Service (alsoknown as ACI Committee 359), which is responsible for the ASMESection III, Division 2 Code for Concrete Containments. He is alsoa member of the ASME Section III Committee on Construction ofNuclear Facility Components and an ex-officio member of theASME Board on Nuclear Codes and Standards.

FELDSTEIN, JOEL G.

Joel Feldstein has a Metallurgical Engi-neering B.S. (1967) and M.S. (1969) fromBrooklyn Polytechnic Institute. He hasmore than 30 years’ experience in thewelding field ranging from welding re-search for a filler metal manufacturer towelding engineering in the aerospace andpower generation industries. He began hiscareer in power generation with Babcock

& Wilcox in 1972 at their R&D Division working on manufactur-ing-related projects and moved into plant manufacturing in 1984as the Manager of Welding. There he became familiar with theconstruction of components for both nuclear and fossil applica-tions. His first assignment on coming to Foster Wheeler in 1993was in the Technical Center as Manager of Metallurgical Serviceslater taking on the additional responsibility of the WeldingLaboratory. In 1998 he assumed the responsibility of ChiefWelding Engineer.

Joel, who is currently Chairman of the ASME BPV CodeTechnical Oversight Management Committee, a member of the

Board on Pressure Technology Codes & Standards and theCouncil on Standards & Certification, began his ASME Codeinvolvement with the Subcommittee on Welding (the responsiblecommittee for Section IX) in 1986. In 1992 he became Chairmanof the Subcommittee on Welding and became a member of theB&PVC Standards Committee. He is an ASME Fellow and recip-ient of the J Hall Taylor Medal from ASME for the advancementof standards for welding in pressure vessel and piping construc-tion. He is also been a member of the BPV Committee on PowerBoilers (Section I).

He is also active in other professional societies including AWSand the Welding Research Council where he served as Chairmanof the Stainless Steel Subcommittee, the High Alloys Committeeand a member of their Board of Directors.

FREY, JOSEPH W.

Joe Frey is currently the Chair of theASME B31.1 Power Piping Code Com-mittee. He has been a member of the B31.1Code committee since 1992 and has fo-cused mainly on the fabrication, erection,examination, and maintenance of powerpiping. Joe is the Power Practice Lead atStress Engineering Services, Inc. (SES) in

Houston, Texas. Joe is a licensed engineer who has spent 31 yearsdeveloping fitness for service programs for piping systems. Partof his work is the emergency repair of piping and pressurevessels. Since joining SES, in 2004 Joe has worked several moreemergency repairs, including twelve fire assessments in the lastfour years (Oct 2011).

GIMPLE, RICHARD E.

Richard Gimple has a BSME from KansasState University (1974) and is a RegisteredProfessional Engineer. Since 1982 he hasbeen employed by the Wolf Creek NuclearOperating Corporation. Previous employ-ment was with Sauder Custom Fabrication(1979–1982) and Fluor Engineers andConstructors (1974–1979).

As a nuclear utility employee, he hasprimarily been involved in implementation of ASME’s Boiler& Pressure Vessel Code Section III and Section XI duringconstruction and operation activities. Previous non-nuclearexperience involved Section VIII pressure vessel and heatexchanger design and construction. At present, as a PrincipalEngineer, Mr. Gimple provides company wide assistance in the use of ASME Codes, with emphasis on Section III andSection XI.

Mr. Gimple has been active in the Codes and Standards devel-opment process since 1984. Mr. Gimple was the 2005 recipient ofthe ASME Bernard F. Langer Nuclear Codes and StandardsAward. He is currently a member of the B&PV StandardsCommittee (since 2000), the Subcommittee on InserviceInspection of Nuclear Power Plant Components (since 1994, serv-ing 5 years as Chairman of Subcommittee XI during 2000–2004),the Section XI Executive Committee (since 1992), and theSubgroup on Repair/Replacement Activities (since 1987, serving


xvi • Contributor Biographies

as Chairman for 7 of those years). Past Codes and Standards par-ticipation included 6 years on the Board on Nuclear Codes andStandards and memberships on the Subcommittee on NuclearAccreditation, Subgroup on Design (in Section III), and threeSection XI Working Groups.

GRABER, HAROLD C.

Harold Graber works as an IndependentConsultant. Previously he was with theBabcock Wilcox Company in the NuclearEquipment Division for 34 years. He wasManager of NDT Operations and Managerof Quality Assurance Engineering. HaroldGraber is a Member of ASME for 15years.

He is an active participant on the B&PVCode, Subcommittee V on Nondestructive Examination. He wasVice Chair Subcommittee V; Chair, Subgroup on Surface Exam-ination. He was Member of Subcommittee V on NondestructiveExamination, Subgroup of Volumetric Examination, Subgroup onPersonnel Qualification and Inquiries.

Harold Graber is a Member, American Society for TestingMaterials (ASTM) for 26 years. He was Chairman, SubcommitteeE7.01 on Radiology. His Committee memberships include Com-mittee E-7 on Nondestructive Examination, Subcommittee E7.02—Reference Radiological Images, Subcommittee E7.06– UltrasonicMethod. He is a Member, American Society for NondestructiveTesting (ASNT). He is a Past Chair, Cleveland, Ohio Section—1971.

Harold Graber is the recipient of ASTM Merit Fellow Award(1992); ASTM Committee E-7—C.W Briggs Award (1989);ASNT Fellow Award (1978). His Certifications include ASNT;Level III certificates in Radiography, Ultrasonic, Liquid Penetrantand Magnetic Particle Methods.

GRUBB, JOHN F.

Dr. Grubb received his B. S. from LehighUniversity, M.S. and Ph.D. from RensselaerPolytechnic Institute. He has over 30 years’experience with corrosion-resistant alloys.His primary areas of expertise are in mate-rials environmental resistance, behavior andapplications. He is the author of more than50 papers as well as several handbookchapters. Dr. Grubb is currently employed

by ATI Allegheny Ludlum. He is co-inventor of several patentedcorrosion-resistant alloys.

Dr. Grubb has been active with the ASME Boiler andPressure Vessel Committees since 2001 and is the current chair-man of the ASME Sub-Group on Physical Properties forSection II as well as chairman of the ASME Sub-Group onMaterials for Section VIII. He is also an active member of theSub-Groups on External Pressure, Ferrous Specifications, andNon-Ferrous Alloys (all BPV II). Dr. Grubb is a Fellow ofASM International (the former American Society for Metals).He is active in ASTM where he has revised several materialsand testing specifications.

HALLEY, GEOFFREY M.

Geoffrey M Halley, P.E. holds degrees inElectrical Engineering, Mechanical Engi-neering, and Engineering Administration(Masters). He is a Registered ProfessionalEngineer in Illinois. From 1993 to the pre-sent he is the President of Sji Consultants,Inc., a technical consulting company, provid-ing services to the boiler industry in theareas of product design, development, trou-

ble shooting and forensic investigation/expert witness work. He has40 years of boiler industry experience, ranging from research/prod-uct development, design and applications/installation., primarily inthe institutional and industrial segments of the marketplace. He heldvarious positions at Kewanee Boiler Corporation from 1968 to 1986,initially as Supervisor of Research and Development, and as VicePresident – Technical Director from 1979 onwards. From 1986through 1992 he was president of Halcam Associates a MechanicalContracting Company specializing in commercial, institutional andindustrial design/build/service and repair of boiler and HVAC sys-tems. From 1959 through 1968 he was employed in the Aerospaceand the Nuclear Engineering industries.

Geoffrey Halley was Chair of ABMA Joint Technical Committee(1981–1986), and has been a member of several boiler industryadvisory groups to the USEPA and USDOE. He currently is ABMADirector of Technical Affairs, and was Editor of ABMA PackagedBoiler Engineering Manual. He has been an Instructor at boilerindustry technician training schools offered by ABMA/NBBI, andboiler manufacturers. He has authored a number of papers on boilerrelated topics, published in The National Board Bulletin, BoilerSystems Engineering, and Maintenance Management.

Geoffrey Halley currently is a member of the ASME CSD-1Committee, and the National Board Inspection Code Sub-committeeon Installation.

HAYDEN JR., LOUIS E.

Louis Hayden has over 40 years of experi-ence as a mechanical engineer, projectmanager and vice president of engineering.This experience has been in the design,analysis, fabrication, installation, startupand maintenance of industrial piping andequipment Systems have included aboveand below ground piping and pipelines inprocess plants, fossil and nuclear power

plants, transmission pipelines and industrial manufacturing facili-ties. He has managed and directed the manufacturer of high yieldpipeline pipe fittings and developed new pipeline closure andflange products as well as managed the efforts of new productdevelopment and research groups.

Currently a consulting mechanical engineer and adjunct profes-sor of mechanical engineering at Lafayette College, Easton, PA. Previous employers have been Fluor Corp., Houston;Brown&Root Inc.,

Houston; Tube Turns, Inc., Louisville; Victaulic Corp., Easton,PA.

Member of ASME B31 Piping Standards Committee since1985.


COMPANION GUIDE TO THE ASME BOILER & PRESSURE VESSEL CODE • xvii

Vice Chair ASME B31 Piping Standards Committee 1990–1993and 2001–2004.

Chairman ASME B31 Piping Standards Committee 1993–2001.Member ASME Board on Pressure Technology Codes and

Standards 1993–2005.Vice President of ASME Board on Pressure Technology Codes

and Standards 2008–2011.Vice Chair ASME Board on Pressure Technology Codes and

Standards 2005–2008.Chairman ASME Task Group for development of B31.12

Hydrogen Piping and Pipeline Code.Member Board on Pressure Technology Codes and Standards

Materials for Hydrogen Service Task Group.

HECHMER, JOHN

Mr. John Hechmer has a degree in IMechanical Engineering from the Uni-versity I of Notre Dame (1957). He joinedthe I Babcock & Wilcox Co. (now ownedby I McDermott, Inc.) for design and analy-sis I work for pressure vessels. His workwas I primarily for the power generationand I defense industries. His experienceincluded project and engineering manage-

ment, technology development, and management. His PowerGeneration products were for both BWR and PWR nuclear electricplants. Defense Industries work addressed Class 1 pressure vesselsfor the nuclear navy program, primarily nuclear reactors and steamgenerators for aircraft carriers and submarines. Research productsincluded Breeder Reactor Program, Sodium-steam Generator,Molten Salt Steam Generator. Technology Development was spentin developing tools and procedures for design-analysis interfacingwith the Research Center and Engineering Fabrication of Babcock &Wilcox Co. This was enhanced by many years of participation inASME B&PV Committees, PVRC, and PV&P Conferences.These engineering efforts occurred for 40 years.

Mr. John Hechmer has more than 25 publications, addressingprimary and secondary stress evaluation, stress intensity factors,finite element methods and its applications, brittle fracture, weld-ing capability for fatigue, and material’s characteristic, examplesof this are PVRC Bulletins #429 (3D Stress Criteria GuidelinesFor Application) and #432 (Fatigue-Strength-Reduction Factorsfor Welds Based on NDE).

HEDDEN, OWEN F.

Owen F. Hedden retired from ABB Com-bustion Engineering in 1994 after over 25years of ASME B&PV Committee activitieswith company support. His responsibilitiesincluded reactor vessel specifications, safetycodes and standards, and interpretation ofthe B&PV Code and other industry stan-dards. He Continued working part-time forthat organization into 2002. Subsequently,

he has been a part-time consultant to the ITER project and severalother organizations. Prior to joining ABB he was with FosterWheeler Corporation (1956–1967), Naval Nuclear program. Since

1968 Mr. Hedden has been active in the Section XI CodeCommittee, Secretary (1976–1978), Chair (1991–2000). In additionto Section XI, Owen has been a member of the ASME C&S Boardon Nuclear Codes and Standards, the Boiler and Pressure VesselCommittee, and B&PV Subcommittees on Power Boilers, Design,and Nondestructive Examination. He is active in ASME’s PVPDivision. Mr Hedden was the first Chair of the NDE EngineeringDivision 1982–1984. He has presented ASME Code short coursesin the US and overseas. He was educated at Antioch College andMassachusetts Institute of Technology.

His publications are in the ASME Journal of Pressure VesselTechnology, WRC Bulletins and in the Proceedings of ASMEPVP, ICONE, IIW, ASM, and SPIE. He is an ASME Fellow(1985), received the Dedicated Service Award (1991), and theASME Bernard F. Langer Nuclear Codes and Standards Award in1994.

HENRY, JEFFREY F.

Jeff Henry currently works as a SeniorAssociate at Structural Integrity Associates,Inc. and formerly was Director of ALSTOMPower Inc.’s Materials Technology Center inChattanooga, TN. His professional experi-ence has been concentrated on the serviceperformance of power plant materials, withparticular focus on high temperature be-havior, welding, and the Creep Strength-

Enhanced Ferritic Steels, such as Grade 91. He has authored over 60technical papers. Mr. Henry is an ASME Fellow and is active on anumber of the ASME Boiler & Pressure Vessel Code technicalcommittees where he chairs BPV II, the Materials StandardsCommittee, as well as the Task Group on Creep Strength-EnhancedFerritic Steels. He also is a member of BPV I (Power Boilers) andof the Management Oversight Technical Committee (TOMC).

HENRY, PHILIP A.

Mr. Henry, Principal Engineer for the EquityEngineering Group in Shaker Heights, Ohio,is a specialist in the design, installation, siz-ing and selection of pressure relief devicesand relieving systems. He is currently chair-man of the API Pressure Relieving SystemSubcommittee’s Task Force on RP 520 re-lated to the design and installation of pres-sure relieving systems. He conducts audits

of pressure relieving systems to ensure compliance with OSHAPSM legislation and ASME, API and DIERs standards, codes andpublications. He also teaches the official API Pressure RelievingSystems course.

Mr. Henry is actively involved in the development of techno-logy for the API Risk-Based Inspection (RBI) methodology. He isco-author of the re-write of API 581, Risked-Based InspectionBase Resource Document and is responsible for the developmentand implementation of Risk-Based Inspection programs for pres-sure relief valves and heat exchanger bundles at refining andpetrochemical plants. He also teaches the official API 580/581Risk-Based Inspection course.


xviii • Contributor Biographies

Mr. Henry provides technical support and engineering consultingto all levels of refinery capital projects. He has been responsible forthe preparation of purchase specifications, bid tabulations, designreviews and the development and validation of approved vendorslists. He conducts project safety reviews for construction and pre-startup phases of major capital projects. His responsibilities includedeveloping and maintaining engineering specifications in the pres-sure relief and heat transfer areas and providing overall coordination.

Mr. Henry is a registered Professional Engineer in the States ofOhio and Texas.

HESSHEIMER, MICHAEL F.

Mike Hessheimer is currently the Managerfor Mechanical Environments testing in theEngineering Sciences Center’s Validationand Qualification Sciences ExperimentalComplex at Sandia National Laboratories inAlbuquerque, New Mexico. Prior to his cur-rent assignment, he managed the NuclearPower Plant Security Assessment programsconducted for the US Nuclear Regulatory

Commission and was the Project Manager and PrincipalInvestigator for the Cooperative Containment Research Project,jointly funded by the Nuclear Power Engineering Corporation ofJapan and the US NRC. His technical expertise is focused on theresponse of structures (with a special emphsis on containment ves-sels) subjected to extreme loads due to natural, accident and hostileevents and is the author of numerous reports and papers on this sub-ject. Prior to his employment at Sandia National Laboratories, Mr.Hessheimer was a consultant in private practice and was alsoemployed by BDM International, Morrison-Knudsen Co. Inc. andSargent and Lundy Engineers where he worked on the design andanalysis of nuclear containment structures. Mr. Hessheimerreceived his Bachelor and Master of Science degrees in Structuraland Civil Engineering from Michigan Technological University. Heis a Registered Professional Engineer in New Mexico. He is also amember of the American Society of Civil Engineers, the AmericanConcrete Institute and the American Society of MechanicalEngineers. He is a member and past chair of the ACI/ASME JointCommittee on Concrete Components for Nuclear Service (ASMEBoiler and Pressure Vessel Code Section III, Division 2 Code forConcrete Containments.

HOLLINGER, GREG L.

Greg L. Hollinger is a Senior PrincipalEngineer for BWX Technologies, Inc. inBarberton, Ohio. He has responsibility forMechanical/Structural Technology Appli-cations and Design Analysis of NavyNuclear Pressure Vessel Components anduse of the ASME Boiler & Pressure VesselCode. He chairs the Engineering Depart-ment’s Technical Support Team responsible

for developing technology procedures. He is involved with bothnuclear and non-nuclear ASME Certificates of Authorization forBWXT’s Nuclear Equipment Division.

Greg is a Fellow Member of ASME, and was the 2004 recipi-ent of the ASME Pressure Vessels and Piping Medal. He is theChairman of the Subgroup on Design Analysis of the Sub-

committee on Design of the ASME Boiler and Pressure VesselCode. Greg is a member of the Pressure Vessel Research Council(PVRC) and the International Council on Pressure VesselTechnology (ICPVT). He has served on several Boards within theASME Council on Codes and Standards, and he served as Chairof the ASME Pressure Vessels and Piping Division in 1995.

Greg is an Registered Professional Engineer (Ohio) with 30 years of engineering practice in power-related industries.

JETTER, ROBERT I.

Mr. Jetter has over 40 years experience inthe design and structural evaluation ofnuclear components and systems for ele-vated temperature service where the effectsof creep are significant. He was a contribu-tor to the original ASME Code Caseseventually leading to Subsection NH. Forover 20 years he was Chair of the Sub-group on Elevated Temperature Design

responsible for the design criteria for elevated temperaturenuclear components. He was Chair of the Subgroup on ElevatedTemperature Construction, Vice Chairman of the Subcommitteeon Design and a member of the Subcommittee on Nuclear Power.He currently again chairs the SG-ETD. Mr. Jetter has participatedin domestic and international symposia on the elevated tempera-ture design criteria. He was a member of a Department of Energy(DOE) steering committee responsible for the design criteria, andwas a consultant and reviewer on various DOE projects. As a longtime employee of Rockwell International/Atomics International,he was associated from the early sodium cooled reactors andspace power plants through all the US LMFBR programs.

Recently he was an International Fellow for the Power Reactorand Nuclear Fuel Development Corporation at the Monju FastBreeder Reactor site in Japan. He is a graduate in MechanicalEngineering from Cal Tech (BS) and Stanford (MS) and has adegree from UCLA in Executive Management. He is a fellow ofthe ASME.

JOLLY, GUY A.

Guy A. Jolly is a consultant engineer forVogt Valves/Flowserve Corporation of Sul-phur Springs, Texas. Guy Jolly retired asChief Engineer of Vogt Valve in 2001. Heholds a BS degree in Mechanical Engi-neering from the University of Kentuckyand a MA degree in Mathematics from theUniversity of Louisville. Guy Jolly is aRegistered Professional Engineer in the

State of Kentucky. Guy Jolly is active on the American Society ofMechanical Engineers (ASME), the American Petroleum Institute(API), and the Manufacturing Standardization Society of theValve and Fitting Industry (MSS) standards writing committees.He is an ASME Fellow and received the ASME DedicatedService Award in 2008. He is a past president of MSS. He is acurrent member of ASME B16 and B31 Standards Committeesand is past Chair of ASME B16 Subcommittee F for fittings. Hecurrently serves as Vice Chair of ASME B16 Standards Com-mittee and Vice Chair of B16 SC-N, Valve Committee. He servesas Chair of the Honors and Award Committee for both ASME


COMPANION GUIDE TO THE ASME BOILER & PRESSURE VESSEL CODE • xix

B16 and B31 Standards Committees. He also serves on theASME Nuclear Section III Working Group on Valves. He serveson API Refinery Subgroups on Valves and Quality. He is currentChair of MSS Technical Committee (TC) 114 (Steel Valves) andTC 105 (Steel Flanges and Fittings). Guy Jolly has served as aUSA expert of industrial valves at International Organization forStandardization (ISO) conferences in the USA, Yugoslavia,England, France, Italy and the Netherlands.

Guy Jolly’s engineering career spans more than fifty years. Hehas made significant contributions to the piping industry while anemployee of a NASA Contractor and a large manufacturer of valvesand fittings. While at Chrysler Space Division in Huntsville, AL hewas the Project Engineer for developing a multishape piping stan-dard for high-pressure liquid hydrogen fuel systems that was pub-lished for use in space vehicles’ piping systems. While withChrysler Space Division he was a representative on the “MarshallCenter Zero Leakage Committee” with a goal to reduce leakagefrom piping and components aboard space vehicles. Mr. Jolly’saccomplishments include the establishment and management of aNuclear Products Group for the Henry Vogt Machine Co., whichmanufactured “N” stamp valves for the nuclear power industry. Hehas published a number of papers including those dealing with“leakage fluid mechanics” and “fugitive emission issues”. Guy A.Jolly, Colonel, USAR, Retired, is a retired 30-year veteran of theArmy Reserve Program. His military education included the AirWar College and the Command and General Staff College.

JONES, DAVID P.

Dr. Jones has 40 years experience in struc-tural design analysis and is lead consultantand developer on structural design proce-dures for SDB-63 (Structural Design Basis,Bureau of Ships, Navy Dept., Washington,D.C.). Dr. Jones is an expert on brittle frac-ture, fatigue crack growth, fatigue crack initi-ation, elastic and elastic-plastic finite elementmethods, elastic and elastic-plastic perforated

plate methods, limit load technology, linear and non-linear computa-tional methods and computer applications for structural mechanics.Dr. Jones’s key contributions have been developing computer pro-grams that allow use of complex three-dimensional finite elementstress and strain results for the evaluation of ASME structural designstress limits. He introduced numerical methods to compute fatigueusage factors, fatigue crack growth, brittle fracture design marginsand the like that have now become standards for use in naval nucleardesign. He is currently working on using finite element elastic-plasticanalysis tools for evaluation of limit load, fatigue, shakedown, andratchet failure modes.

Dr. Jones has been an active contributor to the ASME Boilerand Pressure Vessel Code Committees; secretary and member ofSubgroup on Fatigue strength, Member and chairman of theSubgroup on Design Analysis, Chairman of the Subcommittee onDesign, and Chairman of the Task Force on Elastic-Plastic FEA.Dr. Jones was Chairman of Metal Properties Council Task Forceon Fatigue Crack Growth Technology. He has also served asAssociate Editor of the ASME Journal of Pressure Vessels andPiping. He has published over thirty papers on the topics offatigue, fatigue crack growth, fracture mechanics, perforated platetechnology, computational structural mechanics methods, non-linear structural analysis methods, finite element code developmentfor fracture mechanics applications, finite element applications for

perforated plate analysis (elastic and elastic-plastic), post-processing finite element results for ASME Boiler and PressureVessel Code Section III assessment, limit load technology, andelastic-plastic fracture mechanics. He has been awarded ASMEPVP Literature Award – Outstanding Survey Paper of 1992 inASME Journal of Pressure Vessels and Piping and ASME PVPDConference Award – Outstanding Technical Paper form Codes &Standards – July 26, 2000. Dr. Jones received his BS and MSdegrees from the University of Toledo in 1967 and 1968 and hisPhD from Carnegie Mellon University in 1972. Dr. Jones is aFellow of ASME and has worked at the Bettis Atomic PowerLaboratory in West Mifflin, Pennsylvania since 1968 where hecurrently holds the position of Consultant Engineer.

JOVALL, OLA

Ola Jovall has a Master of Science degree inCivil Engineering from Chalmers Universityof Technology, Gothenburg, Sweden. He isan Associate and Head of EngineeringDepartment of Scanscot Technology AB,Lund, Sweden. His professional experienceincludes more than 25 years working in thefield of Structural Design Engineering. Mr.Jovall has during his profession been in-

volved in structural investigations of 9 of the 12 reactor containmentunits present in Sweden. Since 2004 he is involved in Nuclear PowerPlant (NPP) New Built projects in Scandinavia, including the thirdreactor at Olkiluoto, Finland, now under construction. His engage-ment has mainly been related to issues regarding the reactor contain-ment structure. During the years, Mr. Jovall has also been heavilyinvolved in developing design requirements and guidelines fordesign of safetyrelated Civil structures at NPPs including reactorcontainments. He is Co-Author of a NPP Swedish Industry Standardfor concrete design in force at the NPP units in Sweden. He is on thebehalf of the Swedish Radiation Safety Authority the Main Authorof the document “Guidelines for the design of concrete contain-ments and other concrete safety-related structures at NPPs” (inSwedish) to be published 2012. Mr. Jovall is a current member ofvarious ASME Section III and ACI committees regarding design,construction, testing and inspection of concrete containments andconcrete nuclear structures including Joint ACI-ASME Committeeon Concrete Components for Nuclear Service (ASME Sect III Div2/ACI 359), Working Group on Modernization (Vice Chair),Working Group on Design, ACI Committe 349 Concrete NuclearStructures, and ACI 349 and ACI 359 Joint Committee Task Group.

KARCHER, GUIDO G.

Guido G. Karcher, P.E. is a consultingengineer with over 48 years of experiencein the mechanical engineering aspects ofpressure containing equipment. He retiredfrom the Exxon Research and EngineeringCo. after serving 30 years as an interna-tionally recognized engineering advisor onpressure vessel, heat exchangers, pipingand tankage design, construction and

maintenance. On retire from Exxon Research & Engineering Co.in 1994; he became a Consulting Engineer on fixed equipment for the petrochemical industry and related industry codes and


xx • Contributor Biographies

standards. Guido has also functioned as the Technical Director ofthe Pressure Vessel Manufactures Association, for 15 years, in theareas of mass produced pressure vessel construction and inspec-tion requirements.

Guido’s code activities include over 35 years of participationin ASME, PVRC and API Codes and Standards activities serv-ing on numerous committees and technical development taskgroups. He was elected to the position of Chairman of theASME Boiler & Pressure Vessel Standards Committee for twoterms of office (2001–2007) and was elected to the office ofVice President Pressure Technology Codes and Standards(2005–2008). Guido also served as Chairman of the PressureVessel Research Council and the American Petroleum InstituteSubcommittee on Pressure Vessels and Tanks. He has writtennumerous technical papers on subjects related to pressure con-taining equipment.

Guido is an ASME Life Fellow and a recipient of the J. HallTaylor Medal for outstanding contributions in the development ofASME Pressure Technology Codes and Standards. Guido wasalso recently awarded the 2007 Melvin R. Green Codes andStandards Medal for outstanding contributions to the developmentand promulgation of ASME Codes and Standards within the USAand Internationally. Other awards include the API Resolution ofAppreciation and Honorary Emeritus Membership of PressureVessel Research Council. He earned a B.S.M.E. from PrattInstitute and M.S.M.E. from Rensselaer Polytechnic Institute andis a registered Professional Engineer in the States of New Yorkand New Jersey.

LAND, JOHN T.

John T. Land, P.E., has been involved in the design, analyses and manufacturing ofWestinghouse’s PWR nuclear primaryequipment products for almost thirty years.His product design experience includesreactor internals, steam generators, presur-izers, valves, and heat exchangers. Mr.Land also contributed to the design anddevelopment of the AP600 and AP1000

MWe Advanced Power Plants, the Westinghouse/MitsubishiAPWR 4500 MWt Reactor Internals, and many of the currentlyoperating Westinghouse PWR domestic and international reactorinternals components. In addition, he has directed and reviewedthe design and analysis efforts of engineers from Italy (FIAT andANSALDO), Spain (ENSA), Czech Republic, and Japan (MHI)on several collaborative Westinghouse international efforts. Hisexperience included five years with Westinghouse as a stressanalyst on nuclear valves in support of the Navy’s NuclearReactor Program. Prior to working for Westinghouse, Mr. Landspent eleven years with the General Electric Company on thedesign and development of Cruise Fan and XV-5A VerticalTake-Off and Landing aircraft propulsion systems. He also holdseleven patents from General Electric, and Westinghouse. Mr.Land received his BS in Mechanical Engineering from DrexelUniversity and his MS in Applied Mechanics from the Uni-versity of Cincinnati.

Over the past thirty years, John has been active in ASMEB&PV Code work. Mr. Land is currently member of the WorkingGroup Core Support Structures and participates in the rule mak-ing and maintenance of Sub-Section NG. John is also a member

of Sub-Group Design that oversees Section III and Section VIIIDesign Rules.

LANDERS, DONALD F.

Donald F. Landers, P.E., is currently ChiefEngineer of Landers and Associates. He wasGeneral Manager and President of TeledyneEngineering Services where he was em-ployed from 1961 to 1999. Mr. Landers, anASME Fellow, has been involved in ASMECode activities since 1965 serving as aMember of B31.7 and Chairman of theirTask Group on Design, Section III Working

Group on Piping Design and Subgroup on Design. He continues as amember of these Section III groups as well as Subcommittee III andalso served as a member of section XI and the BPVC StandardsCommittee.

Mr. Landers also served as a member of the Board on NuclearCodes and Standards and as Vice Chairman. He has served onPVRC committees and was heavily involved in the PVRCresearch that led to the new seismic design rules in Section III.

He is an internationally recognized expert in piping design andanalysis and application of ASME Code and regulatory require-ments. Mr. Landers has authored over 20 technical papers relatedto design and analysis of pressure components.

He is currently involved in providing consulting services to theutility industry in the areas of Life Extension, Code compliance,and Operability issues. Don continues to provide training andseminars on Code Criteria and application internationally. He isrecipient of the Bernard F. Langer Award, J. Hall Taylor Award,and ASME Dedicated Service Award.

LEWIS, D. WAYNE

Mr. Donald Wayne Lewis is a Project Engineer for Shaw Stone & WebsterNuclear with over 27 years of experiencein commercial nuclear power and Depart-ment of Energy (DOE) nuclear relatedprojects. He has worked on a variety ofMechanical/Structural engineering appli-cations including nuclear power systemdesign and construction, MOX fuel as-

sembly design, spent fuel management and related NRC licens-ing. He has spent 17 years in his primary area of expertisewhich is related to dry spent nuclear fuel storage and is current-ly Project Engineer for several Independent Spent Fuel StorageInstallation (ISFSI) projects. He has also served as a designreviewer for the DOE Yucca Mountain Project concerning spentfuel processing and disposal.

Mr. Lewis is a Member of the ASME Subgroup on Con-tainment Systems for Spent Fuel and High-Level Waste TransportPackagings. He is the author of two publications related to spentfuel storage which are in the 2003 and 2005 proceedings of theInternational Conference on Environmental Remediation and Radioactive Waste Management (ICEM) sponsored by ASME.

Mr. Lewis received a B.S. in Civil Engineering from MontanaState University in 1980. He is a Registered Professional Engi-neer in New York, Maine, Iowa, Utah and Colorado.


COMPANION GUIDE TO THE ASME BOILER & PRESSURE VESSEL CODE • xxi

MACKAY, JOHN R.

Mr. John Mackay has over 50 years expe-rience as a mechanical engineering spe-cialist in boilers, pressure vessels, steamaccumulators, ASME Code construction,Nondestructive examination, heat transfersystems, combustion and municipal incin-erator design and construction. John has aBachelor of Engineering (Mech.), 1951from McGill University, Montreal and

followed it by numerous courses over the years in Management,Management Techniques, and Post-graduate engineering andmanagement courses at Concordia University.

Mr. John Mackay was an employee of Dominion BridgeCompany Limited in Montreal from 1951 to 1984 and has sincecontinued to work as a private consultant in his field. His majoraccomplishments of the hundreds of projects he has been involvedinclude the Primary System Feeder Pipes for the CANDU nuclearreactors, boilers for waste/refuse mass burn disposal systems anddesign and maintenance of API Storage Tanks. John has extensiveexperience in the design and construction of heat recovery boilersfor the metallurgical industry. John is recognized as one of theleading practitioners of his specialties in Canada.

Mr. John Mackay has been a member of ASME for over 40 years,during which he has served on a variety of committees engaged inupdating existing Codes, introduction of new Codes, and the investi-gation and resolution of questions referred to these committees. Hehas been a member of Section I Power Boiler Subcommittee since1968 to present time, Chaired it 1989–2004; Member StandardsCommittee, 1971–present; Subgroup Electric Boilers (SCI) andchaired it in 1978–84; Member & Chairman Adhoc Task group onAcceptance Criteria. John was a Member and Chair of the Section VSubcommittee on Nondestructive Examination; Joint Task groupB31.1/SCI. John is a member of Subgroup on General requirements &Surface Examination (SCV); and is a member of Subgroup onMaterials (SCI). John was a member of Honors & AwardsCommittee (B&PV) from 1989–2006, and chaired in 1995–2006. He was a Member Executive Committee (B&PV Main Committee)from 1992–2004. In addition to ASME John is affiliated with severalprofessional organizations including Engineering Institute of Canadaand Quebec Order of Engineers.

John Mackay has several publications and has given lectures onengineering topics both in Canada and USA. John was a partici-pant of several PVP conferences and ASHRAE. He has severalhobbies that include Contract Bridge and John is happily marriedwith adult children.

MALEK, M. A.

M. A. Malek is a Professional Engineer(P.E.) registered in the state of Maine,P.Eng. Canada registered in the Province ofI New Brunswick and Prince EdwardIsland. Mohammad is a Certified Plant En-gineer, CPE, U.S.A., and has more than 27years experience in boiler and pressurevessel technology. Presently he is the ChiefBoiler Inspector for the state of Florida.

Prior to his present position, he was Chief Boiler, Elevator andTramway Inspector for the state of Maine, Deputy Chief Inspectorof state of Louisiana and Chief Boiler Inspector, Bangladesh.

Mr. Malek has demonstrated leadership in B&PV boiler andpressure vessel industry. His achievements include developing and designing a special husk-fired, fire-tube boiler of capacity 500 lbs/hr at 50 psi for developing countries. He has vast knowl-edge and experience in writing, and enforcing boiler and pressurevessel laws, rules, and regulations. He has written numerous arti-cles and published in several technical journals. Malek obtained hisBSME degree from Bangladesh Engineering and Technology,Dhaka (1972) and MBA from Institute of Business Admini-stration, University of Dhaka (1979).

Malek has been a member of ASME since 1980 and Fellow ofInstitution of Engineers, Bangladesh. He is an instructor of ASMEProfessional Development courses, and serves on three ASMECommittees including CSD-1 Committee, QFO-1 Committee, andConference Committee of the ASME B&PV Committee. Malekhas been a member of the National Board of Boiler and PressureVessel Inspectors since 1997.

MASTERSON, ROBERT J.

Masterson has a BSME from University ofRhode Island (1969) and course work forMSME, University of Rhode Island (1973).He is a Registered Professional Engineer instates of RI, MA, IL, NE, MI and AK, andis currently self-employed at RJM Asso-ciates in Fall River, MA. Masterson is aretired Captain, U.S. Army Corp of Engi-neers (1986). His professional experience

included New England Electric System (1969–1970), ITT GrinnellCorporation, Pipe Hanger Division, Providence, RI (1972–1979).With ITT Grinnell he was a Manager of Piping and StructuralAnalysis for the Pipe Hanger Division (1974) and developed stressanalysis, and testing for ASME Section III Subsection NF and pro-vided training in Subsection NF for ITT Grinnell, several Utilities,AEs and support for NRC Audit. In 1978 he became ManagerResearch, Development and Engineering. He was Manager ofEngineering (1979) at Engineering Analysis Services, Inc. EastGreenwich RI later in 1990 called EAS Energy Services. He wasVice President of Operations (1984) and tasks included NRC auditsupport, turnkey projects and valve qualification.

Masterson was an alternate member, Working Group onComponent Supports (Subsection NF), 1973–1979; MemberSubsection NF 1979 to the present. Chaired Task Groups forSubsection NF jurisdiction; Chair of Working Group on Supports(SG-D) (SC III) since May, 2000 and Member of Committee forthe First Symposium on Inservice Testing of Pumps and Valves,1989, Washington, DC, NUREG/CP-0111.

MEHTA, HARDAYAL S.

Dr. Mehta received his B.S. in Mechani-cal Engineering from Jodhpur University(India), M.S. and Ph.D. from University of California, Berkeley. He was elected an ASME Fellow in 1999 and is a Regis-tered Professional Engineer in the State ofCalifornia.

Dr. Mehta has been with GE NuclearDivision (now, GE-Hitachi Nuclear Energy)

since 1978 and currently holds the position of Chief Consulting


xxii • Contributor Biographies

Engineer. He has over 40 years of experience in the areas of stressanalysis, linear-elastic and elastic-plastic fracture mechanics, resid-ual stress evaluation, and ASME Code related analyses pertaining toBWR components. He has also participated as principal investigatoror project-manager for several BWRVIP, BWROG and EPRI spon-sored programs at GE, including the Large Diameter Piping CrackAssessment, IHSI, Carbon Steel Environmental Fatigue Rules, RPVUpper Shelf margin Assessment and Shroud Integrity Assessment.He is the author/coauthor of over 50 ASME Journal/Volume papers.Prior to joining GE, he was with Impell Corporation where hedirected various piping and structural analyses.

For more than 25 years, Dr. Mehta has been an active member ofthe Section XI Subgroup on Evaluation Standards and associatedworking an task groups. He is also a member of Section III WorkingGroup on Core Support Structures. He also has been active for manyyears in ASME’s PVP Division as a member of the Material &Fabrication and Codes & Standards Committees and as conferencevolume editor and session developer. His professional participationalso included several committees of the PVRC, specially theSteering Committee on Cyclic Life and Environmental Effects inNuclear Applications. He had a key role in the development of envi-ronmental fatigue initiation rules that are currently under considera-tion for adoption by various ASME Code Groups.

MEYER, JIMMY E.

Jimmy Meyer has over 35 years of experi-ence in refining petrochemical, chemical,power generation and industrial facilities. Heis a principal engineer at Louis Perry andAssociates, a full service engineering andarchitectural firm in Wadsworth Ohio. Jim isexperienced in overall project coordina-tion/management, pressure equipment, pip-ing design, analysis, specifications, support

design, mechanical system requirements and documentation require-ments. Particular areas of technical competence include ASME pip-ing and pressure vessel codes, stress analysis, and field troubleshoot-ing piping system support, vibration and expansion problems.

Mr. Meyer is a member of ASME and has been involved in theASME B31.1 and ASME B31.3 Section committees for over 30years. He is currently Chair of the ASME B31.3 Process PipingSection Committee, Vice Chair of the ASME Standards Committeeand serves on the ASME Board on Pressure Technology Codes andStandards. Jim has also served as Chair of ASME B31.1 PowerPiping Code Section Committee.

Past projects and work experience has involved major oil refiner-ies, petrochemical plants, fossil, nuclear, solar and alternative ener-gy generation as well as cryogenic and vacuum test facilities.

MILLER, UREY R.

Mr. Miller is an ASME Fellow and hasmore than 30 years of experience in thepressure vessel industry. He has partici-pated in ASME Pressure Vessel CodeCommittee activity for well more than 20years. He is a Registered ProfessionalEngineer in Indiana and Texas. He is cur-rently a member of the following ASMEBoiler and Pressure Vessel Committees:

Boiler and Pressure Vessel Standards Committee Subcommittee Pressure Vessels—Section VIII Subgroup Design—Section VIII (Chairman) Special Working Group for Heat Transfer Equipment (pastChairman) Special Committee on Interpretations—Section VIIISubcommittee Design.

Mr. Miller has been the Chief Engineer with the KelloggBrown & Root Company (KBR), a major international engi-neering and construction company for the petrochemical indus-try, since 1992. In this position, he consults on a wide array ofsubjects including pressure vessesl, heat exchanger, and pipingdesign issues, including application and interpretation of allASME Code requirements. He has had extensive experiencewith international projects. He has provided significant engi-neering support and advice to KBR projects throughout theworld. In the role as Chief Engineer, he has traveled extensivelyproviding engineering support for projects in Brazil, Malaysia,Egypt, Algeria, Nigeria, Philippine Islands, South Africa,United Kingdom, Mexico, etc. in addition to a variety of pro-jects in United States. He has experience in refinery, petro-chemical, liquefied natural gas, ammonia, phenol, and othertypes of projects. Previously, he held responsible positionsrelated to process pressure equipment at Union CarbideCorporation and Foster Wheeler Energy Corporation. In addi-tion, he has had over eight years experience in designing pres-sure vessels for nuclear power generation applications with theBabcock and Wilcox Co. Mr. Miller has a Bachelor’s Degree inMechanical Engineering (cum laud) from the University ofEvansville (Indiana).

MOEN, RICHARD A.

Richard (Dick) Moen has been a mem-ber of numerous Boiler and PressureVessel Code committees since 1969.Richard (Dick) Moen was an activemember of various Boiler and PressureVessel Code committees from 1969,until his retirement in 2005. During thattime span, he served on the StandardsCommittee, the Subcommittee on Mate-

rials, the Subcommittee on Nuclear Power, and additionalSubgroups and Task Groups serving in those areas. He is alife member of ASM International.

Richard Moen earned a BS degree in Metallurgical Engineeringfrom South Dakota School of Mines and Technology in 1962,with additional graduate studies through the University of Idahoand the University of Washington. He has spent his entire profes-sional career in the field of nuclear energy, beginning in researchand development, and then with commercial power plant con-struction, operation support, and maintenance. He now consultsand teaches through Meon Technical Services.

Richard Moen’s primary area of expertise is in materials behav-ior and applications. He has authored numerous papers and hasbeen involved in several national materials handbook programs.And with his long-time involvement in the ASME Boiler andPressure Vessel Code, he has authored a popular book entitled“Guidebook to ASME Section II, B31.1, and B31.3—MaterialsIndex”. His classes are built around that book.


COMPANION GUIDE TO THE ASME BOILER & PRESSURE VESSEL CODE • xxiii

MOKHTARIAN, KAMRAN

Kam Mokhtarian graduated from the North-western University with a Master of Sciencedegree, in 1964. He worked for ChicagoBridge and Iron Company from 1964through 2000, in a variety of assignments.He was responsible for design and analysisof nuclear vessels and pressure vessels for anumber of years. He also provided technicalconsulting to the engineering staff.

Mr. Mokhtarian has been involved with the ASME B&PVCode Committee, since 1980. He has served as member andchairman of several committees. He was Chairman of SubgroupDesign of Subcommittee VIII and the Vice-chairman of SubgroupFabrication and Inspection. He is presently the Vice-chairman ofSubcommittee VIII.

Mr. Mokhtarian is also a member of the Post ConstructionStandards Committee and the Vice-chairman of the Subcommitteeon Flaw Evaluation. He has also served as an associate editor ofthe ASME’s Journal of Pressure Vessel Technology for severalyears.

Mr. Mokhtarian has been an active member of the PressureVessel Research Council (PVRC) since 1980 and has served asChairman of several committees. He is presently the Chairman ofthe PVRC. He has authored several WRC Bulletins, includingBulletin 297 that has become a major resource for pressure vesseldesigners. He has also been teaching a number of pressure vesselrelated ASME courses.

MORTON, D. KEITH

Mr. D. Keith Morton is a Senior ConsultingEngineer at the Department of Energy’s(DOE) Idaho National Laboratory (INL),operated by Battelle Energy Alliance. Hehas worked at the INL for over 36 years.Mr. Morton has gained a wide variety ofstructural engineering experience in manyareas, including performing nuclear pip-ing and power piping stress analyses,

completing plant walk downs, consulting with the NuclearRegulatory Commission, developing life extension strategies forthe Advanced Test Reactor, performing full-scale seismic andimpact testing, and helping to develop the DOE standardizedspent nuclear fuel canister. His most recent work activitiesinclude performing full-scale drop tests of DOE spent nuclearfuel canisters, developing a test methodology that allows for thequantification of true stress-strain curves that reflect strain rateeffects, and supporting the Next Generation Nuclear Plant(NGNP) Project as well as DOE’s Used Fuel DispositionCampaign.

Mr. Morton is a Member of the ASME Working Group on theDesign of Division 3 Containments, is the Secretary for theASME Subgroup on Containment Systems for Spent Fuel andHigh-Level Waste Transport Packagings, a Member of the ASMEWorking Group on High Temperature Gas-Cooled Reactors, aMember of the Subgroup on High Temperature Reactors, aMember of the Subgroup on Elevated Temperature Construction,a Member of the Executive Committee on Strategy and ProjectManagement, Chair of the Subgroup on Editing and Review, and

is a Member of the ASME BPV III Standards Committee. He hasco-authored over twenty-five conference papers, one journalarticle, co-authored an article on DOE spent nuclear fuel canistersfor Radwaste Solutions, and co-authored two chapters for thefourth edition of the Companion Guide to the ASME Boiler &Pressure Vessel Code.

Mr. Morton received a B.S. in Mechanical Engineering fromCalifornia Polytechnic State University in 1975 and a Masters ofEngineering in Mechanical Engineering from the University ofIdaho in 1979. He is a Registered Professional Engineer in thestate of Idaho for both mechanical engineering and structuralengineering.

NICKERSON, DOUGLAS B.

Douglas B. Nickerson graduated fromCal-Tech with a BSME. He was a regis-tered Engineer in the State of Californiaand is a Fellow of ASME. He worked inthe Aerospace Industry until 1965 whenhe founded his consulting business, StressAnalysis Associates. During his tenure in the Aerospace Industry he developedthe Hi-V/L ® pump for aerocraft booster

pump application. He was active in dynamic analyses of pumpsand valves as a consultant to most of the commercial pumpmanufacturers including those manufacturing nuclear pumps.

As a corollary to the dynamic analysis of pumps and valvesMr. Nickerson developed a number of computer programs tocarry out these analyses. Some of these programs were success-fully marketed. Not only active in Engineering he helped orga-nize the Fluid Machinery Section of the Local ASME Section.In recognition of his activities he was made “Engineer of theMonth” of Southern California for August 1973.

Mr. Nickerson was on the SURF Board of CalTech and wasformerly its Chairman.

Douglas Nickerson had served on a number of ASME Section IIICommittees and was Chairman of QR Subcommittee of QME.Mr. Douglas B. Nickerson passed away since the completion ofthe first edition.

NORDSTROM, EDWIN A.

On the personal side, Ed is a native ofKansas who was educated at the Universityof Kansas as an undergraduate and theMassachusetts Institute of Technology wherehe earned graduate degrees in both Chem-istry and Management – the latter from theSloan School. He served in administrativepositions for 16 years on school boards and40 years in the Episcopal Church.

Without an engineering degree, Ed rose to be Manager ofProcess Engineering for a chemical company and then to VPEngineering for A O Smith Water Products Division. In the latterpost, he became active in ASME where he has served on SectionIV for 25 years. This activity continued across job changes toAmtrol [Manager, Hot Water Maker Sales]; Viessmann Manu-facturing [COO for US operations]; Gas Appliance ManufacturersAssociation; and Heat Transfer Products.


xxiv • Contributor Biographies

OSAGE, DAVID A.

Mr. Osage, President and CEO of the EquityEngineering Group in Shaker Heights, Ohio,is internationally recognized as an industryexpert and leader in the development anduse of FFS technology. As the architect andprincipal author of API 579 Fitness-For-Service, he developed many of the assess-ment methodologies and supporting techni-cal information. As the chairperson for the

API/ASME Joint Committee on Fitness-For-Service, he was instru-mental in completing the update to API 579 entitled API 579-1/ASME FFS-1 Fitness-For-Service. Mr. Osage provides instructionon Fitness-For-Service technology to the international communityunder the API University Program.

Mr. Osage is also a recognized expert in the design of newequipment. As the lead investigator and principal author of thenew ASME, Section VIII, Division 2, Boiler and Pressure VesselCode, he developed a new organization and writing style for thiscode and was responsible for introducing the latest developmentsin materials, design, fabrication and inspection technologies.These technologies include a new brittle fracture evaluationmethod, new design-by-analysis procedures including the intro-duction of elastic-plastic analysis methods, and a new fatiguemethod for welded joints. Mr. Osage has delivered lectures on thenew pressure vessel code in Europe and Japan and will be offer-ing a training course highlighting advantages of the new code foruse with refinery and petrochemical equipment.

Mr. Osage was a lead investigator in revamping the API Risk-Based Inspection (RBI) technology and software. The main focusof this effort was a clean sheet re-write of API 581 Risk-BasedInspection and the development of a new version of the API RBIsoftware. He is currently working on the next generation of RBItechnology where Fitness-For-Service assessment procedures willbe used to compute the Probability of Failure for Risk-BasedInspection.

As an Adjunct Visiting Assistant Professor at Stevens Instituteof Technology, Mr. Osage has taught graduate level courses instrength of materials and elasticity, structural analysis and finiteelement methods, and structural optimization.

OSWEILLER, FRANCIS

Francis Osweiller got international recogni-tion for his expertise in French, Europeanand ASME Pressure Vessel Codes &Standards. He has been the head of theFrench delegation to CEN/TC 54 (EuropeanTechnical Committee for Unfired PressureVessels) for several years and has chairedseveral committees such as Simple PressureVessels, Testing & Inspection, Tubesheets

and Bellows. Mr. Osweiller has been actively involved in Europewith the development of the Pressure Equipment Directive and thenew CEN Standard for Unfired Pressure Vessels. He gave severalcourses on these issues in France UK and USA. As member of theMain Committee of CODAP, he developed several design rules forthe French Pressure Vessel Code (CODAP). His main contribution

was the development of Tubesheet Heat-exchanger rules to replacethe existing (TEMA) rules.

Francis Osweiller obtained a Mechanical Engineering degree inParis, France. He started his career at CETIM-France with FEManalysis applied to pressure vessels. He has published more than 40 papers in France, UK, Germany and US on European Codes,ASME Code and Pressure Equipment Directive and gave lecturesat AFIAP, ICPVT (International Conference of Pressure VesselTechnology) and ASME-PVP (Pressure Vessel & Piping Con-ference). He has been the representative for France at ICPVT andISO/TC11.

Since 1985 Osweiller has been actively involved in ASMEBoiler and Pressure Vessel Code organization where he is mem-ber of SCII/International Material Specifications, SCSVIII/SWGon Heat Transfer Equipment, Post Construction Main Com-mittee, Board on Pressure Vessel Technology and Council onCodes and Standards. His principal accomplishment is his rolefor the publication of common rules in ASME Code, EuropeanCode and French Code for the design of tube-sheets and expan-sion bellows. Osweiller is the recipient of several awards andcertificates from ASME and PVP and was elevated to the gradeof Fellow by ASME in 2001 and is listed in the Who’s Who inthe World.

PASTOR, THOMAS P.

Mr. Pastor has over thirty five years expe-rience working in the areas of stressanalysis and pressure vessel design. Heholds a Bachelors and Masters degree inCivil Engineering from the University ofConnecticut, with emphasis on structuraldesign and analysis.

Mr. Pastor began his career with Com-bustion Engineering in 1977, where he was

a member of the structural analysis group, responsible for perform-ing load analyses of nuclear reactor internals subject to significantexpertise in performing finite element analyses and scientificprogramming.

In 1986 Mr. Pastor joined the Hartford Steam Boiler Inspectionand Insurance Co. (HSB) working in the Codes and StandardsGroup in Hartford, Ct. During his 26 year tenure at HSB, Mr. Pastorrose from staff engineer, to Manager Codes & Standards, Director,and presently Vice-President Code Services. He has managed theCodes & Standards (C&S) Group for over 20 years, and led thedevelopment of several knowledge based databases which are usedtoday to provide Code technical support to over 3000 ASMECertificate Holders and Inspectors worldwide. Mr. Pastor’s ASMEcode expertise is in pressure vessels, and he has taught basic toadvanced seminars on Section VIII, Division 1 over 100 times toaudiences around the world. He has authored numerous technicalpapers on the subject of stress analysis and ASME Code develop-ments, Mr. Pastor is a licensed Professional Engineer in the states ofConnecticut and Indiana. He is currently serves on several ASMECommittees such as the Council on Standards and Certification,Board on Hearings and Appeals, Board on Pressure TechnologyCodes & Standards, BPV Technical Oversight ManagementCommittee (Vice-Chairman), Standards Committee on PressureVessels - BPV VIII, and the Subgroup Design – BPV VIII.


COMPANION GUIDE TO THE ASME BOILER & PRESSURE VESSEL CODE • xxv

PILLOW, JAMES T.

Mr. James (Jim) Pillow has over 35 yearsexperience as a quality assurance and qual-ity control specialist in installation, repairand maintenance of ASME power boilers,pressure vessels and ancillary equipment inutility and industrial power plants. Beforejoining Common Arc in 2007 as Chair ofthe Operating Committee, Jim worked forover 30 years with APComPower, a wholly

owned subsidiary of Alstom Power Inc., in Windsor, Connecticut.While there he managed the company’s quality, welding, NDEand construction engineering groups.

Jim has been a member of the American Society of MechanicalEngineers for nearly 25 years, during which he has been activelyinvolved in numerous committees, subgroups and task groups,including: BPV I, Standards Committee – Power Boilers (Member1997–present); BPV I - Subgroup General Requirements (Member1988–present); BPV I – Subgroup Fabrication & Examination(Member 1988–present, Secretary 2001–2004, Chair 2004–pre-sent); and the Board on Conformity Assessment (Member2003–2011). Jim has also been an active participant on theCommittee on National Board Inspection Code (NBIC–2000 topresent), the NBIC Subcommittee -Repairs and Alterations(2002–present), and is currently Chair, NBIC Repairs andAlterations Subgroup – Specific.

Jim is a recipient of the ASME Dedicated Service Award and isco-author with Mr. John R. MacKay of the second edition of“Power Boilers: A Guide to Section I of the ASME Boiler andPressure Vessel Code”.

RAHOI, DENNIS

D. W (Dennis) Rahoi is an authority onmaterials used in the pharmaceutical/biotechnology, chemical process, fossil fuel,and nuclear power industries. The author ofmore than 50 papers on materials, corrosionand oxidation, he received the PrimeMovers Award in Thermal Electric Gene-rating Equipment and Practice by EdisonElectric Institute for work published on

solving problems in high pressure feedwater heaters. He currentlyconsults in material selections, failure analysis and does otherforensic metallurgical work. Mr. Rahoi is also the current editor ofAlloy Digest (an ASM International, Inc. publication) and is anactive consultant to the Nickel Institute. Mr. Rahoi was the firstchairman of NACE’s Power Committee and is active on manystainless steel ASTM and ASME (including B31) materials com-mittees. He is the current chairman of the ASME Sub-Group Non-Ferrous Materials for Section II and holds a master’s degree in met-allurgical engineering from Michigan Technological University.

Mr. Rahoi’s work on writing many new ASTM specifications,his active sponsoring of 10 pipe and tube specifications and hisactive involvement in Welding Research Council and EPRIresearch proposals on welding and repair keep him in constanttouch with the needs of industry. This, combined with his other

experiences and consulting, allow him to contribute to the currentchapter in this book with authority.

RANA, MAHENDRA D.

Mahendra, an ASME Fellow has a bache-lor’s degree in mechanical engineeringfrom M.S. University in Baroda, India, anda master’s degree in mechanical engineer-ing from the Illinois Institute of Tech-nology, Chicago, Illinois. He is a registeredprofessional engineer in New York State.He is an Engineering Fellow working inthe Engineering Department of Praxair,

Inc. for the last 38 years. He is involved in the areas of fracturemechanics, pressure vessel design, pressure vessel development,and materials testing. He is also involved in the structural inte-grity assessment, and fracture control programs of pressure ves-sels. He is the Chairman of ASME Section XII Transport TanksStandards Committee. He is a member of several other ASMEBoiler and Pressure Vessel Code committees: member of SectionVIII Standards Committee, member of joint API/ASME Fitness-for Service Committee, member of the Technical OversightManagement Committee of the Boiler and Pressure Vessel Codeand the member of Board on Pressure Technology, Codes andStandards. Mahendra is also a member of several ISO, ASTM andCGA (Compress Gas Association) standards committees. He hasreceived several awards from the Pressure Vessel and PipingDivision for his contribution in organizing Codes and Standardssessions in Pressure Vessel and Piping Conferences. He is also therecipient of ASME J. Hall Taylor Medal. He has given severallectures in the pressure vessel technology topics in the USA andabroad. He has taught a course on ASME Section VIII, Division 1to ASME section of Buffalo New York. He is the co-recipient oftwo patents and the co-author of over 30 technical papers. He alsohas written several technical reports for his company.

RANGANATH, SAM

Dr. Sam Ranganath is the Founder andPricipal at XGEN engineering, SamJose, CA. XGEN, founded in 2003, pro-vides consulting services in fracturemechanics, materials, ASME Codeapplications and structural analysis tothe power plant industry. Before that heheld various leadership positions atGeneral Electric for 28 years. Dr.

Ranganath is a Fellow of the ASME and has been active inthe development of Section III and Section XI, ASME Coderules for the evaluation and inspection of nuclear pressurevessel components. Sam has a Ph.D. in Engineering fromBrown University, Providence, RI and an MBA from SantaClara University, Santa Clara, CA. He has also taughtGraduate Courses in Mechanical Engineering at Santa ClaraUniversity and Cal State University, San Jose for over 15years.


xxvi • Contributor Biographies

RAO, K. R.

KR Rao retired as a Senior Staff Engineerwith Entergy Operations Inc. and was pre-viously with Westinghouse Electric Cor-poration at Pittsburgh, PA and PullmanSwindell Inc., Pittsburgh, PA. KR got hisBachelors in Engineering from BanarasUniversity, India with a Masters Diploma inPlanning from School of Planning & Arc-hitecture, New Delhi, India. He completed

Post Graduate Engineering courses in Seismic Engineering, FiniteElement and Stress Analysis, and other engineering subjects atCarnegie Mellon University, Pittsburgh, PA. He earned his Ph.D.,from University of Pittsburgh, PA. He is a Registered ProfessionalEngineer in Pennsylvania and Texas. He is past Member of Ope-rations Research Society of America, (ORSA).

KR was Vice President, Southeastern Region, ASME Inter-national. He is a Fellow of ASME, active in National, Regional,Section and Technical Divisions of ASME. He has been the Chair,Director and Founder of ASME EXPO(s) at Mississippi Section.He was a member of General Awards Committee of ASME Inter-national. He was Chair of Codes & Standards Technical Com-mittee, ASME PV&PD. He developed an ASME Tutorial for PVPDivision covering select aspects of Code. KR is a Member, SpecialWorking Group on Editing and Review (ASME B&PV CodeSection XI) for September 2007 – June 2012 term.

Dr. Rao is a recipient of several Cash, Recognition and ServiceAwards from Entergy Operations, Inc., and Westinghouse ElectricCorporation. He is also the recipient of several awards, Certificatesand Plaques from ASME PV&P Division including OutstandingService Award (2001) and Certificate for “Vision and Leadership”in Mississippi and Dick Duncan Award, Southeastern Region,ASME. Dr. Rao is the recipient of the prestigious ASME SocietyLevel Dedicated Service Award.

Dr. Rao edited “Energy and Power Generation Handbook:Established and Emerging Technologies” published by ASMEPress in 2011. Dr. Rao who founded the annual “Early CareerTechnical Conference (ECTC)” organized the Eleventh ECTC atGeorgia Tech, Atlanta, GA on Nov. 4–5, 2011.

Dr. Rao is a Fellow of American Society of Mechanical Engi-neers, Fellow of Institution of Engineers, India and a CharteredEngineer, India. Dr. Rao was recognized as a ‘Life Time Member’for inclusion in the Cambridge “Who’s Who” registry of execu-tives and professionals. Dr. Rao was listed in the Marquis 25thSilver Anniversary Edition of “Who’s Who in the World” as ‘oneof the leading achievers from around the globe’.

REEDY, ROGER F.

Roger F. Reedy has a B.S. Civil Engi-neering from Illinois Institute of Techno-logy (1953). His professional career in-cludes the US Navy Civil EngineeringCorps, Chicago Bridge and Iron Company(1956–1976). Then he established himselfas a consultant and is an acknowledgedexpert in design of pressure vessels andnuclear components meeting the require-

ments of the ASME B&PV Code. His experience includes design,stress analysis, fabrication, and erection of pressure vessels and

piping components for nuclear reactors and containment vessels.He has expertise in the design, construction of pressure vesselsand piping components for fossil fuel power plants, chemicalplants and refineries. Mr. Reedy has been involved in licensing,engineering reviews, welding evaluations, quality programs, pro-ject coordination and ASME Code training of personnel. He tes-tified as an expert witness in numerous litigations involvingpressure vessels, piping, and quick-actuating closures and beforedifferent regulatory groups.

Mr. Reedy has written an important article regarding unsafepressure vessels on cement trucks that was published by theNational Board of Boiler and Pressure Vessel Inspectors in 2011,and another NBBPVI article on quick actuating closures for 2012.He also writes a summary of all changes made to the ASMEB&PV Code in each Addenda published since 1950 to the pre-sent, that is maintained in a computer database, RA-search. Mr.Reedy has served on ASME BP&V Code Committees for morethan 45 years being Chair of several of them, including Section IIIfor 15 years. He is still active on Section III and Section VIII.

Mr. Reedy was one of the founding members of the ASMEPressure Vessel & Piping Division. Mr. Reedy is registeredEngineer in seven states. He is a recipient of the ASME BernardF. Langer Award and the ASME Centennial Medal and is a LifeFellow Member of ASME.

Mr. Reedy has consulted with clients in Europe, Asia, Africa, andSouth America. Recently, he helped a European client with anASME Code Case that permits the use of a unique system of pipingsupports designed to significantly reduce the time of construction.

RODERY, CLAY D.

Clay Rodery is Technical Authority/ FixedEquipment for BP North American Pro-ducts. He has over 27 years of experienceconsulting in the areas of pressure vesselsand piping to Amoco and BP refining,chemicals, and upstream facilities and pro-jects worldwide. After receiving his BSCEfrom Purdue University in 1981, he joinedAmoco Oil Company’s Texas City Refi-

nery, where he was involved in project, maintenance, and inspec-tion engineering. In 1990, he moved to Amoco Oil’s Refining &Transportation Engineering Department as pressure vessel spe-cialist. In 1995, he became the principal vessel specialist withinAmoco Corporation’s Worldwide Engineering & ConstructionDepartment. In 1999, he moved to BP Chemicals’ Technology &Engineering Department as pressure vessel and piping specialist.He became BP Chemicals’ Pressure Vessel and Piping Advisor in2004, until moving to his current role in 2006.

Clay began participating in ASME Boiler and Pressure VesselCode activity in 1993. He joined the Subgroup on Fabrication &Inspection (Section VIII) in 1997, and the Subgroup on Design in1999. In May 2000, he was appointed Chairman of the Subgroupon Fabrication & Inspection and member of the Subcommittee onPressure Vessels. Clay is a member of the ASME Post Cons-truction Standards Committee, and Vice Chair of the Subcom-mittee on Repair and Testing. He is also a member of the SpecialWorking Group on Flange Joint Assembly.

As a member of the Design & Analysis Technical Committeeof the ASME Pressure Vessels and Piping Division, Clay hasserved as an Author, Session Developer/Chair, Editor, Technical


COMPANION GUIDE TO THE ASME BOILER & PRESSURE VESSEL CODE • xxvii

Program Representative, and Tutorial Presenter. Clay is a memberof the API Subcommittee on Inspection and the Task Group onInspection Codes. He is former Team Leader of the ProcessIndustry Practices (PIP) Vessel Function Team.

ROSENFELD, MICHAEL J.

Michael J. Rosenfeld, PE is Vice Presidentand General Manager of Kiefner/Applus-RTD (dba Kiefner & Associates) in Worth-ington, Ohio. He holds a BS in mechanicalengineering from the University of Michigan(1979) and a MS in mechanical engineeringfrom Carnegie-Mellon University (1981).He began his career at Westinghouse Elec-tric where he worked on finite element ana-

lyses of power plant generator stator structures. He then worked atEDS Nuclear (later Impel Corporation) performing stress analysesof piping systems, equipment, and site structures for nuclear powerstations. He then joined Battelle Memorial Institute- ColumbusLaboratories where he performed design and analysis work onindustrial and defense equipment, and became involved withresearch in areas concerning natural gas pipeline integrity.

The focus of Mr. Rosenfeld’s career has been on oil and gaspipeline integrity since joining Kiefner & Associates, Inc. (KAI)as Senior Structural Engineer in 1991. He then served asPresident from 2001 to 2011. While at KAI, he has performednumerous pipeline failure investigations, stress analyses of buriedpipelines subjected to geotechnical and live loadings, fitness forservice evaluations for pipelines affected by various types ofdegraded conditions, technical procedure development for integ-rity management planning, and has carried out industry-fundedresearch on pipeline damage mechanisms. Mr. Rosenfeld is a cur-rent member of the ASME B31.8 Gas Transmission & Dis-tribution Piping Section Committee, the ASME B31 MechanicalDesign Technical Committee, the ASME B31 Standards Com-mittee, and the ASME Board of Pressure Technology Codes &Standards. He is also ASME Professional Development’s desig-nated instructor for the B31.8 Code seminar, and was the primaryauthor of the recent major revision to ASME B31G. He is a pastmember of the API RP-1117 Task Group on Pipeline In-ServiceRelocation, and the ASCE-ASME Joint Task Group that devel-oped the American Lifelines Alliance “Guidelines for the Designof Buried Steel Pipe”. He has authored or co-authored over 40technical papers on various pipeline-related subjects.

ROWLEY, C. WESLEY

C. Wesley Rowley is Vice President, Engi-neering & Technical Services, with TheWesley Corporation in Tucson, AZ. He hasbeen with TWC since 1985. Mr. Rowleymanages engineering and non-metallic struc-tural repair activities for nuclear powerplants. He has published numerous reportsand technical papers for EPRI, ASME,ICONE Conferences, Pump & Valve Sym-posiums, and other nuclear industry events.

He is a recognized expert on risk-informed Inservice Testing, as wellas non-metallic materials and non-metallic structural repairs.

Mr. Rowley has been a member of the ASME Board onNuclear Codes and Standards for over fifteen years. He is also amember of the ASME Post Construction Committee, the Sub-committee on Repair & Testing, and the Chairman of the Non-metallic Repair Project Team. Additionally he has been theChairman of the ASME BPV/Subcommittee II, Materials/Special Working Group, Nonmetallic Material since 2002. Heis the past Chairman of the ASME BPV Joint SubcommitteeIII/XI Project Team for Plastic Pipe. ASME past VicePresident, Nuclear Codes & Standards and past Chairman,Board on Nuclear Codes & Standards. He is currently a mem-ber of the ASME BPV/ Subcommittee III/Special WorkingGroup on Polyethylene Pipe. ASME, Member, Operations &Maintenance Committee (and Sub-group ISTE, Risk-InformedInservice Testing).

Mr. Rowley is a retired Submarine Captain in the U. S. NavalReserve. He has a M.A. degree in International Relations andStrategic Studies from the Naval War College (1986). He also hasa B.S. in General Engineering (1965) and M.S. in NuclearEngineering from the University of Illinois (1967). Mr. Rowley isa Registered Professional Engineer.

SAMMATARO, ROBERT F.

The late Mr. Sammataro was Proto-Power’sProgram Manager — ISI/IST Projects. Hewas responsible for Proto-Power’s InserviceInspection (ISI) and Inservice Testing (IST)programs. These programs included devel-opment and implementation of programsinvolving ISI, IST, design integrity, designreconciliation, 10CFR50, Appendix J, inte-grated leakage rate testing, and in-plant and

out-plant training and consulting services.Mr. Sammataro was also responsible for Proto-Power’s ISI and

IST Training Programs has developed Proto-Power’s three-dayWorkshop on Containment Inservice Inspection, Repair, Testing,and Aging Management. He was recognized as an expert in con-tainment inservice inspection and testing.

Mr. Sammataro was the past Chair of the ASME PV&P Di-vision (1999–2000), General Chair of PVP Conference (1999)and was the Technical Program Chair (1998).

He was a member and chair of an ASME Section XI Subgroupand a member of an ASME Section XI Subgroup Subcommittee.He was a past member of the ASME BP&V Code Main Com-mittee (1989-1994). Mr. Sammataro was an ASME Fellow. Mr.Sammataro earned BSCE and MSCE from Rensselaer Poly-technic Institute.

SCOTT, BARRY

Barry Scott is currently Director of QualityAssurance Department (Power) with res-ponsibility to provide QA/QC support forthe engineering, procurement and con-struction phases of Power projects. Barryhas experience in the development, imple-mentation and auditing of Quality Pro-grams. He has considerable knowledge ofindustry Quality Standards, including ISO


xxviii • Contributor Biographies

9000, 10CFR50 Appendix B, NQA 1 and Government (DOE,DOD) requirements. Barry has extensive experience with projectsand project engineering management with special expertise in thestructural design of Nuclear Power Plant structures includingdesign of reinforced concrete Containment structures. Barry hasbeen a Member of various ASME Section III committees in-cluding Subgroup on General Requirements, Subcommittee onNuclear Power and Joint ASME-ACI Committee on ConcreteComponents for Nuclear Service for more than 30 years.

Barry has a Master of Science in Civil Engineering fromDrexel University and is a licensed PE (Civil Engineering) in thestates of Pennsylvania, California and Washington. He is a certi-fied Lead Auditor in accordance with the requirements of ASMENQA-1 and previously held certification as an ACI Level IIIConcrete Inspector as required by the ASME Section III Division2 Code.

SHELLEY, BERNARD F.

Bernard F. Shelley has a B.S. in Mech-anical Engineering for West Virginia Ins-titute of Technology and a Masters ofMechanical and Aerospace Engineeringfrom the University of Delaware. He has43 years experience in applying engineer-ing principles, computers, and Codes andStandards to solving design of processingequipment and vessels in the chemical

industry. Mr. Shelley spent the first three years of his career work-ing for DuPont designing textile processing equipment beforejoining the Franklin Institute Research Labs and designing equip-ment for the bakery industry. He then spent about 2 years atHercules beginning his career in chemical equipment design andthen moved to ICI Americas in 1975 where he worked for almost18 years designing all types of chemical processing equipment.He then left ICI to join BE&K and continued designing chemicalprocessing equipment primarily for DuPont before rejoiningDuPont in 1995 to the present time where he designs vesselstanks and heat exchangers both metallic and non-metallic. Mr.Shelley participated in the writing of the MTI /SPI Quality assur-ance report published in 1978 and has participated in the ASMERTP-1 committee since its first meeting in 1980 having served asDesign and Fabrication Subcommittee Chairman for almost 15years and contributing heavily to several sections of the RTP-1standard. He also serves on the RTP-1 Certification Subcom-mittee. In 1995 he became a member of ASME Section X and isresponsible for the recent addition of Class III vessels into thisCode. He also serves on the ASME Boiler Code Technical Over-sight Management Committee, the Hydrogen Project Team, theSection VIII Subgroup on Fabrication and Inspection and theStructures for Bulk Solids committees. In addition he is chairmanof the NBIC FRP Subgroup where he helped developed inspec-tion and repair procedures in the NBIC for FRP tanks and vessels.He is also the leader of the PIP Vessel Function teams where hedeveloped the current FRP practice based on RTP-1 and Section X.With his various Code committee memberships Mr. Shelley hasassisted in many projects to further the usefulness and safety ofthe design of vessels and tanks.

Mr. Shelley is a registered professional engineer in the State ofWest Virginia.

SIMS, J. ROBERT

Mr. Sims has over 45 years experience indesign, analysis, troubleshooting, designaudit, mechanical integrity evaluation, lead-ing risk based reviews and failure analysis.He is a recognized authority in risk-basedtechnologies for optimizing inspection andmaintenance decisions, high pressure equip-ment and mechanical integrity evaluation ofexisting equipment.

Bob is currently a member of the ASME Board of Governors, acurrent Contributing Member and past Chairman and ViceChairman of the ASME Post Construction Committee and a cur-rent member of the Subcommittee on Inspection Planning res-ponsible for developing standards for assuring the mechanicalintegrity of pressure equipment.

Bob is a current member and past Vice Chairman of theASME/API Joint Fitness-For-Service Committee. He is also a pastASME Senior Vice President of Codes and Standards, past ASMEVice President of Pressure Technology Codes and Standards, a cur-rent member and past Chairman of the ASME Subgroup on High Pressure Vessels, Section VIII, Div. 3, and past Chairman of the ASME Task Group on Risk Analysis for the Critical AssetsProtection Initiative plus other committee involvement such asB31.3 Subgroup on High Pressure Piping.

Bob was previously employed by Exxon Research and Engi-neering Company as a Pressure Equipment Specialist. He has a BSin Mechanical Engineering from Vanderbilt University and is anASME Fellow with more than 20 publications and two patents.

SMITH, CLAYTON T.

Clayton T. Smith is a Technical ServicesDirector and Fluor Fellow, Fluor NuclearPower division of Fluor Enterprises, Inc.

Mr. Smith's over 26 years of experienceincludes extensive 10 CFR Part 50,Appendix B, ACI, ASME Section III,ASME Section XI, and NQA-1 QualityAssurance program creation. He special-izes in Nuclear Safety Related, ASME

Section III, Division 1 & 2 design, construction, and procurement;Section XI nuclear power plant repair and replacements, coupledwith traditional non-nuclear ACI, ASME and AWS Code design,construction, fabrication & installation; and National BoardInspection Code (NBIC) alteration and repair activities.

Mr. Smith received his Bachelor of Science degree in NuclearEngineering Technology from TESC, and holds a Commissionfrom the National Board of Boiler and Pressure Vessels (NBBI)with the following endorsements A, B, C, I, N, IS, & NS. He rou-tinely authors and presents technical papers, participates in indus-try and technical panels, is a Member of the American Society ofMechanical Engineers, American Society of Quality, and is anASME NQA-1 Qualified Lead Auditor.

Mr. Smith is a multidiscipline NDE and QC Level III, and holdsvarious ACI certifications. He serves on the ASME Board ofNuclear Codes and Standards, ASME Section III StandardsCommittee, and as chair/vice-chair, as well as being an active mem-ber, in many ACI and ASME Standards Development Organization


COMPANION GUIDE TO THE ASME BOILER & PRESSURE VESSEL CODE • xxix

Committees. Finally, Mr. Smith is the Secretary of the ASMENuclear Engineering Division (NED) Technical Committee 4,“Safety, Codes, Standards and Regulation,” member of the NuclearPower International Technical Program Committee, and partici-pates on the Nuclear Energy Institute's CAP & QA Task Forces.

SOWINSKI, JAMES C.

Mr. Sowinski is a Consulting Engineer forThe Equity Engineering Group, Inc. inShaker Heights, Ohio. He has experiencein the refining and petrochemical industriesas an owner-user and as a consultant pro-viding engineering support. He providesplant engineering support to maintenanceand inspection personnel and performsdesign/analysis/re-rate calculations of pres-

sure containing equipment to evaluate mechanical integrity andimprove reliability. Mr. Sowinski is responsible for Equity’s “R”Certificate of Authorization issued by The National Board ofBoiler and Pressure Vessel Inspectors.

Mr. Sowinski was involved in the development of the newASME, Section VIII, Division 2, Boiler and Pressure Vessel Codeand was a contributing author of the ASME Section VIII,Division 2, Criteria and Commentary. He is Vice-Chair of theASME Boiler and Pressure Vessel VIII Subgroup on Design andalso serves on the Subgroup on General Requirements.

Mr. Sowinski is a Registered Professional Engineer in theStates of Ohio and Texas.

STAFFIERA, JIM E.

Jim E. Staffiera earned a BS in MechanicalEngineering from Drexel University in1971 and a Masters in Business from OldDominion University in 1975. He has beeninvolved with nuclear power plant contain-ment vessel and steel structure design, fab-rication, construction, and operation since1971. Originally employed by NewportNews Industrial Corporation (a subsidiary

of Newport News Shipbuilding), he assisted with development ofcommercial nuclear fabrication programs for ASME Code N-typeCertificate authorization. This progressed into nuclear componentfabrication and construction activities, resulting in his currentemployment with FirstEnergy Corporation at the Perry NuclearPower Plant, where he works in the Structural Mechanics Unitand is frequently involved with ASME Code Section XI-relatedissues.

Jim has been a member of ASME since 1972 and is involved innumerous ASME Boiler and Pressure Vessel Code Committeeactivities, including holding positions as Chair, Secretary, andMember of various Section XI committees on inservice require-ments for operating nuclear power plants. He currently chairs theWorking Group on Containment and is also a member of theSection XI Subcommittee, the Subgroup on Water-CooledSystems, and the Special Working Group on Editing and Review.

Jim is an active member of the ASME Pressure Vessels andPiping Division, having chaired the Codes and Standards (C&S)

Technical Committee and been C&S Technical Program Rep-resentative for the annual ASME Pressure Vessels and PipingConference. He has also been a member of the American Societyfor Quality (ASQ) since 1975.

Jim has been involved in several nuclear industry initiatives, themost recent of which was as a member of the Expert Panel for theEPRI Containment Integrated Leak-Rate Test (ILRT) IntervalExtension Project.

STANISZEWSKI, STANLEY (STAN)

Stanley Staniszewski is a senior MechanicalEngineer with the U.S. Department ofTransportation, Pipelines and HazardousMaterials Safety Administration. He is a ‘76Alumni of the Fenn College of Engineering,from Cleveland State University of Ohio andhas completed graduate level course work inBusiness Administration at Johns HopkinsUniversity and advanced engineering degree

work at the University of Virginia. Mr. Staniszewski has been amember of the American Society of Mechanical Engineers, sincejoining as a student. He currently serves on the ASME Section XIISubCommittee on Transport Tanks, Vice Chairs the Sub Group onGeneral Requirements, and is a member of the ASME HydrogenSteering Committee, and various taskgroups. Mr. Staniszewski isalso a member of the National Board Inspection Code, MainCommittee, Subgroups RB, and Nonmandatory Appendices. He hasexperience in the international standards arena through membershipand participation as a governmental technical expert to the UnitedNations and International Standards Organizations on variousTechnical Committees, Sub-Committees and Work-Groups on gascylinders, cryogenic vessels and Hydrogen technologies.

He has 10 years of varied experience in the private sector span-ning tool & die, manufacturing, research and product develop-ment, design, construction and inspection. Within the federalgovernment he has spent 20 years in the areas of mechanical/electrical/chemical project engineering, management, inspectionand enforcement issues that affect hazardous materials/dangerousgoods in national and international commerce.

STEVENSON, JOHN D.

Dr. John D. Stevenson is a SeniorConsultant for J.D. Stevenson, ConsultingEngineer Co. He has extensive experienceworldwide in the nuclear power fieldwhere he served as a consultant to theIAEA and several non U.S. utilities andconsulting firms. He holds a Ph.D. in CivilEngineering from Case Western ReserveUniversity. He has provided structural-

mechanical consulting services to the nuclear power industry inthe U.S. and abroad for the past 35 years and has been a memberof various committees of ASME and B&PVC Section III for thepast 35 years. He is currently also a member of several ofAmerican Society of Civil Engineers, American Nuclear Society,and American Concrete Institute committees and consultant togovernment agencies dealing with the structural-mechanical safetyof nuclear facilities.


xxx • Contributor Biographies

SUTHERLIN, RICHARD C.

Richard Sutherlin is the Manager ofTechnical Services for ATI Wah Chang inAlbany, Oregon. He has over 35 years ofexperience in reactive and refractory met-als (titanium, zirconium, niobium and tan-talum) in corrosion, welding, melting,R&D, Outside Fabrication, failure analysisand applications engineering. Mr. Sutherlinholds a B.Sc. in Metallurgical Engineering

from the Montana School of Mines, University of Montana. Hehas authored numerous technical papers and well as several hand-book chapters. He has performed many reactive metal failureanalyses and also holds several patents the production of reactivemetal products.

Mr. Sutherlin is a Registered Professional Engineer in the Stateof Oregon. He serves on the ASME Boiler and Pressure codecommittees, Member of BPV II, BPV II Sub-group Non-ferrousalloys and BPV VIII, Sub-group Materials. He is a member ofNACE (National Association of Corrosion Engineers). Richardserves as Chairman of the American Welding Society A5KSubcommittee of Titanium and Zirconium Filler Metals,Chairman of the G2D Subcommittee on Reactive Alloys and amember of the AWS G2 - Committee on Joining Metals andAlloys and a member of the A5 - Committee on Filler MetalsMaterials.

SWAYNE, RICHARD W.

Mr. Swayne has worked as a metallurgist,welding engineer, quality assurance man-ager, and consultant, in the pressure ves-sel and piping industry, since 1975. Hehas experience in design, fabrication, andoperation of various power and refineryplant components, including valve designand application, welding and materialsengineering, and quality assurance pro-

gram management for construction and operation. He is anexpert and well-known instructor in inservice inspection, inser-vice testing, and repair/replacement programs in operatingpower plants. He has assisted many organizations in preparationfor new and renewal ASME Certificates of ccreditation and hasparticipated in many ASME National Board AccreditationSurveys. Mr. Swayne has been an active participant since 1977as a member of ASME and ASTM Codes and StandardsCommittees. He is the ASME Vice President of Nuclear Codesand Standards and Chair of the ASME Board on Nuclear Codesand Standards (2011–2014), member of the ASME TechnicalOversight Management Committee, and Vice Chair of theASME Standards Committee on Nuclear Inservice Inspection.Mr. Swayne is also a past member of the Boiler and PressureVessel Standards Committee, the Subcommittee on Materials,

and several working groups under the Subcommittee on NuclearPower.

He has served as a consultant to utilities, architect/engineers,manufacturers, and material manufacturers and suppliers. He is aQualified Lead Auditor, and was a Qualified Level II Examiner inseveral nondestructive examination methods. He has been in-volved in engineering reviews, material selection and application,and quality assurance auditing.

UPITIS, ELMAR

Elmar Upitis received a B.S. degree in CivilEngineering from University of Illinois in1955 and did postgraduate studies at theIllinois Institute of Technology. He served inthe US Army and was employed by ChicagoBridge & Iron Company from 1955 to 1995in various capacities, including Chief DesignEngineer, Manager of Metals Engineering,and Senior Principal Engineer–Materials.

He was also responsible for oversight of CBI engineering inSouth America, Europe and Africa and Middle East. Mr. Upitisprovides engineering consulting services in the areas of codes andstandards (ASME, API, ASTM, etc.), design of plate structures,fitness-for-service evaluation, and materials related issues. He is alicensed professional and structural engineer in the State ofIllinois, ASME Fellow and a member of various technical com-mittees in the ASME B&P Vessel Code, ASTM Fellow and amember of several ASTM technical committees, former Chair ofPressure Vessel Research Council (PVRC) and an active partici-pant in the PVRC, and a member of AWS and WRC. He isinvolved in the development of the new B&PV Code to replacethe present Section VIII, Division 2 and several other projectsrelated to the ASME B & PV Code.

Mr. Upitis is a co-author of WRC Bulletin 435 on design mar-gins in ASME Section VIII, Divisions 1 and 2, WRC Bulletin 447on evaluation of operating margins for in-service pressure equip-ment, WRC Bulletin 453 on minimum weld spacing requirementsfor API Standard 653, PVRC report on the European PressureEquipment Directive, and several other published papers on Cr-Mo steel pressure vessels.

VOLLMER, RICHARD O.

Mr. Vollmer graduated with honors fromLehigh University in Bethlehem, PA (BSME1989), and was elected to Tau Beta Pi and PiTau Sigma. He has been a member of ASMEsince 1989, and is a Registered ProfessionalEngineer in the Commonwealths of Penn-sylvania and Virginia. He is an active con-tributor to the ASME Working Group forCore Support Structures.


COMPANION GUIDE TO THE ASME BOILER & PRESSURE VESSEL CODE • xxxi

Mr. Vollmer has worked in the electric power industry since1989, with expertise in the design and analysis of pressure ves-sels, valves, reactor internals, and power plant structures. He hasbroad experience with nuclear industry codes & standards, includ-ing the ASME B&PV Code and U.S. naval nuclear design codes.He is currently a Fellow Engineer specializing in advanced reac-tor internals at Westinghouse Electric Corporation. Prior to join-ing Westinghouse, Mr. Vollmer was a senior engineer at MPRAssociates, providing consulting services to fossil and nuclearpower utilities and equipment vendors.

VOORHEES, STEPHEN V.

Employed in the Authorized InspectionAgency sector since 1976 with FactoryMutual, Commercial Union Insurance Com-pany, Hartford Steam Boiler I and I, andOneBeacon America Insurance Company.Duties have included inspection of all typesof boilers, pressure vessels, heat exchang-ers, nuclear components as well as supervi-sion of these activities and finally manage-ment of same.

Currently serves on Section IV Heating Boilers as Vice Chair,Section XII, Transport Tanks as a member and Chair of Sub-Group Fabrication and Inspection, and serve as member of theStandards Committee.

From 1970 to 1974 served in the US Navy in the WesternPacific on destroyers as a boiler technician.

Married to Louise for 25 years with two sons. Reside inAllentown, PA. Hobbies include hunting, shooting and golf.

WOODWORTH, JOHN I.

John I. Woodworth has BSME from Univ.of Buffalo, 1948. He is engaged in consult-ing on Steam and Hot Water (hydronic)heating systems and Codes and Standards.He provides information for legal proceed-ings of hydronic heating systems and equip-ment. He was previously with FeddersCorp. (1948–1959), as Technical Director ofHydronics Institute (predecessor Institute of

Boiler and Radiator Manufacturers.), 1959–1990. Woodworth’sprofessional activities 1990 to date are supported by HydronicsInstitute Division, GAMA.

He is a member of ASME, and a member of several ASMECode Committees such as Section IV, (1967–date), Cast-IronSubgroup; Chair, ASME Section VI; Vice-Chair Controls andSafety Devices for Automatically-Fired Boilers StandardsCommittee (1973–2000). He was a consultant with the NationalInstitute of Science and Technology (formerly the NationalBureau of Standards). Woodworth is a Life Member of ASHRAE,Member of several of its Technical Committees, Secretary, ViceChair and Chair of SPC. He has written numerous technicalarticles for trade magazines.

John received ASME Distinguished Service Award (1991),Dedicated Service Award (2000) and ASHRAE StandardsAchievement Award (1996). He was a Member, National FuelGas Code Committee, VP, Uniform Boiler and Pressure VesselLaws Society and Liaison to Building Energy Codes &Standards Committee. He was a Member of technical advisorycommittees for Brook-haven National Laboratories.


CONTENTS

Dedication to the First EditionRobert E. Nickell and William E. Cooper . . . . . . . . . . . . . . iii

Acknowledgements (to the First Edition). . . . . . . . . . . . v

Acknowledgements (to the Second Edition) . . . . . . . . . v

Acknowledgements (to the Third Edition) . . . . . . . . . . . vi

Acknowledgements (to the Fourth Edition) . . . . . . . . . vii

Contributor Biographies . . . . . . . . . . . . . . . . . . . . . . . . . ix

Preface (to the First Edition) K. R. Rao and Robert E. Nickell . . . . . . . . . . . . . . . . . xxxvii

Preface (to the Second Edition)K. R. Rao. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . xxxviii

Preface (to the Third Edition)K. R. Rao. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . xxxix

Preface (to the Fourth Edition)K. R. Rao . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . xl

Introduction. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . xliii

Organization and Operation of the ASME Boiler and Pressure Vessel Committee . . . . . . . . . . . . lvii

PART 6: SECTION VIII – RULES FOR CONSTRUCTIONOF PRESSURE VESSELS

CHAPTER 21 Section VIII–Division 1: Rules forConstruction of Pressure VesselsThomas P. Pastor. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21-1

21.1 Introduction 21-121.2 Section VIII, Division 1, Foreword 21-121.3 Section VIII, Division 1, Introduction 21-221.4 Subsection A: General Requirements for

All Methods of Construction and All Materials 21-721.5 Subsection B–Requirements Pertaining to

Methods of Fabrication of Pressure Vessels 21-28

21.6 Subsection C: Requirements Pertaining to Classes of Materials 21-45

21.7 Mandatory Appendices 21-6621.8 Nonmandatory Appendices 21-9321.9 References 21-110

CHAPTER 22 Section VIII–Division 2:Alternative RulesDavid A. Osage, Clay D. Rodery, Thomas P. PastorRobert G. Brown, Philip A. Henry, and James C. Sowinski. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22-1

22.1 Introduction 22-122.2 Organization of VIII–2 22-222.3 Part 1 – General Requirements 22-222.4 Part 2 – Responsibilities and Duties 22-422.5 Part 3 – Materials Requirements 22-822.6 Part 4 – Design-By-Rule 22-1322.7 Part 5 – Design-By-Analysis 22-3122.8 Part 6 – Fabrication Requirements 22-4022.9 Part 7 – Inspection and Examination

Requirements 22-4622.10 Part 8 – Pressure Testing Requirements 22-5522.11 Part 9 – Pressure Vessel Overpressure

Protection 22-5622.12 References 22-58

CHAPTER 23 Section VIII, Division 3–Alternative Rulesfor Construction of High-Pressure VesselsJ. Roberts Sims Jr . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23-1

23.1 Introduction 23-123.2 Foreword and Policy Statements 23-123.3 Part KG–General Requirements 23-123.4 Part KM–Material Requirements 23-423.5 Part KD–Design Requirements 23-623.6 Part KF–Fabrication Requirements 23-2023.7 Part KR–Pressure-Relief Devices 23-2223.8 Part KE–Examination Requirements 23-2323.9 Part KT–Testing Requirements 23-2323.10 Part KS–Marking, Stamping,

Reports, and Records 23-2323.11 Mandatory and Nonmandatory Appendices 23-2323.12 Recommendations for Further Development

of Division 3 23-24


xxxiv • Contents

CHAPTER 24 Safety of Personnel Using Quick-Actuating Closures on Pressure Vessels and Associated Litigation IssuesRoger F. Reedy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 24-1

24.1 Introduction 24-124.2 Background 24-124.3 History of the Rules Governing

Quick-Actuating Closures 24-224.4 The Future 24-924.5 Conclusion 24-924.6 References 24-10

PART 7: SECTION IX OF B&PV CODE – WELDING ANDBRAZING QUALIFICATIONS

CHAPTER 25 Welding and Brazing QualificationsJoel G. Feldstein . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25-1

25.1 Introduction 25-125.2 History of Section IX 25-125.3 Organization of Section IX 25-125.4 Welding Processes 25-125.5 Classification of Materials 25-625.6 Qualification of Welding Procedures 25-725.7 Qualification of Welders and

Welding Operators 25-1625.8 Impact Tested Weld Procedures 25-2125.9 Testing and Examination Requirements 25-2525.10 Corrosion-Resistant and Hardfacing Overlay 25-3125.11 Brazing 25-3625.12 Future Actions for Section IX’s Consideration 25-37

PART 8: SECTION X OF B&PV CODE

CHAPTER 26 Fiber-Reinforced Plastic PressureVessels and ASME RTP-1 – Reinforced ThermosetPlastic Corrosion-Resistance EquipmentPeter Conlisk and Bernard F. Shelley . . . . . . . . . . . . . . 26-1

26.1 Introduction 26-126.2 FRP Technology 26-126.3 Fabrication Methods 26-626.4 Stress Analysis of FRP Vessels 26-1026.5 Scopes of Section X and RTP-1 26-1426.6 Design Qualifications of Section X and

RTP-1 Vessels 26-1626.7 Section X: Example Design Specification 26-2026.8 Section X: Example Design Calculations 26-2226.9 RTP-1: Example 1 Design Specification 26-2826.10 RTP-1: Design Example 2 26-3626.11 Quality Assurance of Section X and

RTP-1 Vessels 26-4226.12 References 26-45

PART 9: SECTION XI OF B&PV CODE – RULES FORINSERVICE INSPECTION OF NUCLEAR POWER

PLANT COMPONENTS

CHAPTER 27 Overview of Section XI StipulationsOwen Hedden . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27-1

27.1 Introduction 27-127.2 Development of Scope and Content

of Section XI 27-327.3 Future Issues 27-2127.4 Applicability of Code Editions and Addenda,

and the Use and Content of Code Cases and Interpretations 27-21

27.5 Efforts That Did Not Reach Publications 27-2227.6 Acknowledgments 27-2227.7 References 27-2327.8 Bibliography 27-2327.9 Appendix A: Code Cases 27-2427.10 Appendix B: Interpretations 27-27

CHAPTER 28 Repair/Replacement Activities forNuclear Power Plant ItemsRichard E. Gimple and Richard W. Swayne. . . . . . . . . . 28-1

28.1 Introduction 28-128.2 Background of Repair/Replacement Activity

Requirements 28-328.3 Scope and Applicability of Repair/

Replacement Activity Requirements 28-528.4 Alternative Requirements 28-1028.5 Responsibilities 28-1528.6 Repair/Replacement Program and Plan 28-1928.7 Additional General Requirements 28-2228.8 Requirements for Items Used in a

Repair/Replacement Activity 28-2628.9 Design Associated with Repair/Replacement

Activities 28-3228.10 Welding, Brazing, Metal Removal,

Fabrication and Installation 28-3628.11 Examination and Testing Requirements 28-4528.12 Alternatives to Construction Code Welding 28-5328.13 Plugging and Sleeving of Heat

Exchanger Tubing 28-5528.14 Code Cases 28-5628.15 Future Considerations 28-5728.16 References 28-59

CHAPTER 29 Section XI: Rules for InserviceInspection and Tests of Nuclear Power PlantComponentsRichard W. Swayne . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29-1

29.1 Introduction 29-129.2 Preface 29-129.3 Organization 29-129.4 Article IWA-1000: Scope and Responsibility 29-229.5 Article IWA-2000: Examination and Inspection 29-429.6 IWA-2000: Qualifications of Nondestructive

Examination Personnel 29-529.7 Mandatory Appendix VII: Qualification of

Nondestructive Examination Personnel for UT 29-729.8 IWA 2420: Inspection Program 29-729.9 IWA 2420: Inspection Plans and Schedules 29-829.10 IWA 2430: Inspection Intervals 29-829.11 IWA 2440: Application of Code Cases 29-929.12 IWA 2500: Extent of Examination 29-1029.13 IWA 2600: Weld Reference System 29-10


COMPANION GUIDE TO THE ASME BOILER & PRESSURE VESSEL CODE • xxxv

29.14 Subsections IWB/IWC/IWD/IWE/IWF/IWL:Requirements for Class 1, 2, 3, MC, and CC Components and Supports 29-10

29.15 Exemptions from the Examination Requirements 29-1029.16 Class 1, 2, and 3 Components and Their

Supports Exempt from Examination 29-1129.17 Class MC Components and Liners of Class

CC Components Exempt from Examination 29-1129.18 Portions of Reinforced Concrete Containment

Vessels and Their Posttensioning Systems Exempt from Examination 29-12

29.19 IWF-1300: Component Support ExaminationBoundaries 29-12

29.20 IWB/IWC/IWD/IWE/IWF-2000: Examination and Inspection 29-12

29.21 Combining Preservice Examinations withConstruction Code Shop and Field Examinations 29-12

29.22 IWE-2300: Visual Examination, PersonnelQualification, and the Responsible Individual 29-13

29.23 IWL-2300: Visual Examination, PersonnelQualification, and the Responsible Engineer 29-13

29.24 IWB/IWC/IWD/IWE/IWF/IWL-2400:Inspection Schedule 29-13

29.25 IWL-2400: Inspection Schedule 29-1429.26 IWB/IWC/IWD/IWE/IWF-2420: Successive

Inspections 29-1429.27 IWB/IWC/IWD/IWE/IWF-2430: Additional

Examinations 29-1429.28 IWB/IWC/IWD/IWE/IWF-2500: Examination

and Pressure Test Requirements 29-1529.29 Unique Aspects of Containment Vessel

Examination 29-1729.30 IWL-2500: Examination Requirements 29-1729.31 Unique Aspects of the Component Support

Examination 29-1829.32 IWA-5000: System Pressure Tests 29-1829.33 IWA-5110: Periodic System Pressure Tests 29-1929.34 IWA-5120: System Pressure Tests for

Repair/Replacement Activities 29-1929.35 IWA-5200: System Test Requirements 29-1929.36 IWA/IWB/IWC/IWD-5220: Test Pressurization

Boundaries 29-2029.37 IWA-5240: Visual Examination 29-2029.38 IWA-5250: Corrective Action 29-2129.39 IWA-5260: Instruments for System

Hydrostatic Tests 29-2229.40 IWA-5300: Test Records 29-2229.41 IWA-6000: Records and Reports 29-2229.42 IWA-6300: Retention 29-2229.43 Risk-Informed Inservice Inspection 29-2229.44 High-Temperature Gas-Cooled Reactors 29-23

CHAPTER 30 Section XI Flaw Acceptance Criteria and Evaluation Using Code ProceduresRussell C. Cipolla . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 30-1

30.1 Introduction 30-130.2 Evaluation of Examination Results (IWA-3000) 30-230.3 Acceptance of Flaws (IWB-3500) 30-830.4 Evaluation of Flaws in Components

(IWB-3600) 30-13

30.5 Evaluation of Flaws in Reactor Head Penetrations Components (IWB-3660) 30-20

30.6 Evaluation of Flaws in Piping (IWB-3640) 30-2330.7 Evaluation of Pipe Wall Thinning 30-3030.8 Temporary Acceptance of Flaws 30-3530.9 Evaluation of Plant Operating Events

(IWB-3700) 30-4230.10 Evaluation of Class 2, 3, MC, and

NF Components 30-5530.11 Recent and Future Developments in

Flaw Evaluation 30-5630.12 References 30-58

CHAPTER 31 IWE and IWLJim E. Staffiera . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31-1

31.1 Introduction 31-131.2 Regulatory Requirements for Containments 31-531.3 ASME Code Requirements for Containments 31-631.4 General Requirements 31-831.5 Requirements for Metal (Class MC)

Containments 31-831.6 Requirements for Concrete (Class CC)

Containments 31-831.7 Later Code Editions and Addenda 31-831.8 Code Cases and Interpretations 31-831.9 Advance Nuclear Power Plant Designs 31-931.10 References 31-9

CHAPTER 32 Fatigue Crack Growth, Fatigue and Stress Corrosion Crack Growth:Section XI EvaluationWarren H. Bamford . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32-1

32.1 Fatigue Crack Growth Analyses 32-132.2 Stress Corrosion Crack Growth 32-1332.3 Operating Plant Fatigue Assessment:

Section XI, Appendix L 32-2732.4 References 32-30

CHAPTER 33 Applications of Elastic-Plastic FractureMechanics in Section XI, ASME Code EvaluationsHardayal S. Mehta . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 33-1

33.1 Introduction 33-133.2 Early Progress in the Development of EPFM 33-133.3 Engineering Approach to EPFM and

Piping Applications 33-233.4 Application to RPV Evaluation 33-933.5 References 33-21

PART 10: SECTION XII OF B&PV CODE

CHAPTER 34 Description of Rules of Section XIITransport Tank CodeMahendra D. Rana and Stanley Staniszewski . . . . . . . . 34-1

34.1 Introduction 34-134.2 Rules on General Requirements, Pressure,

Relief Devices, Stamping, Marking Certification, Reports and Records 34-2


xxxvi • Contents

34.3 Rules for Materials and Design 34-334.4 Rules on Fabrication and Inspection 34-834.5 Additional Rules in Modal Appendix I on

Categories 406, 407, 412, 331 and 338 Cargo Tanks 34-11

34.6 New Appendix on Rules on Cold Stretched Vessels 34-14

34.7 Conclusions 34-1534.8 Acknowledgment 34-1534.9 References 34-15

PART 11: ASME B31 CODES

CHAPTER 35 ASME Piping Code: B31.1,Power PipingJimmy E. Meyer and Joe Frey . . . . . . . . . . . . . . . . . . . . 35-1

35.1 Introduction 35-135.2 Scope and Definitions 35-235.3 Design 35-235.4 Materials 35-1035.5 Dimensional Requirements 35-1035.6 Fabrication, Assembly and Erection 35-1035.7 Inspection, Examination, and Testing 35-1835.8 Operations and Maintenance 35-1935.9 Appendices in the Code 35-1935.10 References 35-22

CHAPTER 36 ASME Piping Codes: B31.3 Process,B31.5 Refrigeration, B31.9 Building Services and ASME Standards for Piping: B31E Seismic Design,B31J Stress I-Factors, B31T Toughness RequirementsJimmy E. Meyer . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36-1

36.1 Coverage 36-136.2 References 36-26

CHAPTER 37 Transportation Pipelines, IncludingASME B31.4, B31.8, B31.8S, B31.11, B31G,and B31Q CodesMichael J. Rosenfeld . . . . . . . . . . . . . . . . . . . . . . . . . . . 37-1

37.1 Introduction 37-137.2 ASME B31.4 “Transportation Systems for

Liquid Hydrocarbons and other Liquids” 37-337.3 ASME B31.8 “Gas Transmission and

Distribution Piping Systems” 37-1637.4 ASME B31.8S “Managing System Integrity

of Gas Pipelines”, Supplement to B31.8 37-3337.5 ASME B31.11 “Slurry Transportation

Piping Systems” 37-3737.6 ASME B31G “Manual for Determining the

Remaining Strength of Corroded Pipelines” 37-3837.7 ASME B31Q “Pipeline Personnel

Qualification” 37-4137.8 Acknowledgements 37-4337.9 References 37-43

CHAPTER 38 Hydrogen Piping and Pipe LinesLouis E. Hayden . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 38-1

38.1 Background and General Information 38-138.2 Organization of B31.12 38-338.3 Part GR-General Requirements 38-338.4 Part GR; Materials 38-438.5 GR-3 Welding, Brazing, Heat Treating,

Forming, and Testing 38-438.6 GR-4 Inspection, Examination and Testing 38-438.7 GR-5 Operation and Maintenance 38-438.8 GR-6 Quality System Program for Hydrogen

Piping and Pipeline Systems 38-938.9 Part IP-2 Design Conditions and Criteria 38-938.10 IP-3 Pressure Design of Piping Components 38-1038.11 IP-7 Specific Piping Systems 38-1338.12 IP-8.1 Dimensional Requirements 38-1438.13 IP-8.2 Ratings of Components 38-1438.14 IP10 Inspection, Examination, and Testing 38-1438.15 PL Pipelines 38-1438.16 Chapter PL-2 Pipeline Systems Components

and Fabrication Details 38-1738.17 Mandatory Appendix III Safeguarding 38-2738.18 References 38-28


This book provides “The Criteria and Commentary on SelectAspects of ASME Boiler and Pressure Vessel and Piping Codes”in two volumes. The intent of this book is to serve as a “Primer”to help the user weave through varied aspects of the ASME Codesand B31.1 and B31.3 Piping Codes and present a summary ofspecific aspects of interest to users. In essence, this Primer willenable users to understand the basic rationale of the Codes asdeliberated and disseminated by the ASME Code Committees.This book is different from the Code Cases or Interpretations ofthe Code, issued periodically by these ASME Code Committees,although these are referred in the book. It is meant for a variedspectrum of users of Boiler and Pressure Vessel (B&PV) andB31.1 and B31.3 Piping Codes in United States and elsewhere inthe world. This book should be considered as a comprehensiveguide for ASME B&PV Code Sections I through XI, B31.1 andB31.3 Piping Codes. The contents of these two volumes can beconsidered as a companion book—a criteria document—for thelatest editions of the Code, written by thirty-six professionals withexpertise in its preparation and use.

ASME and the industry volunteers have invested immenseresources in developing Codes and Standards for the Power andPetrochemical Industry, including nuclear, non-nuclear, fossil,and related. The industry has been relying on these documents,collectively referred to as the ASME Code, on a day-todaybasis, and regulators consult them for enforcing the rules.Research and development, in both the material science and ana-lytical areas, find their results in the revisions and updates of theCodes. Over a period of time, these B&PV and Piping Codes,encompassing several disciplines and topics, have become volu-minous Standards that belie the intent and expectations of theauthors of the Codes. In a word, the B&PV Codes can become a“labyrinth” for an occasional user not conversant with the infor-mation contained in the Code. Thus, given the wealth of infor-mation contained in the Code, these cannot be easily discerned.For example, the B&PV Code, even though it is literally anencyclopedia of rules and standards to be followed by engineersin the nuclear or fossil or related industries, is not easy to com-prehend and conform to. Alphanumeric text and graphics areloaded with information, arrived at by a consensus process fromthe deliberations of practicing engineers, professionals, acade-mia, and regulators meeting several times a year. A lack ofunderstanding of the Code, therefore, can cause not only profes-sional errors but also misplaced confidence and reliance on theengineer’s interpretation that could lead to serious public safetyhazards. Spread over several volumes and thousands of pages of

text, tables, and graphics, it is not easy to decipher the criteriaand the basis of these Codes.

Thus, given the importance of these ASME Codes related tothe industry and the attendant technological advances, it becomesa professional expediency to assimilate and appropriately applythe wealth of information contained in the Codes. The first step,then, is to ask, “Where is what?” The Code is spread over elevenSections; attending the tutorials is one way to understand first-hand the various Sections of the Code. However, this is not withinthe reach of all of the engineers in the industry. The next bestsolution is to have expert authors, versatile in the individualSections and Subsections, to make the subject matter understand-able to the practicing engineers in a book format such as “APRIMER.”

In this book, all of the Sections I through XI of the B&PV andB31.1 and B31.3 Piping Codes are summarily addressed withexamples, explanatory text, tables, graphics, references, and anno-tated bibliographical notes. This permits engineers to more easilyrefer to the material requirements and the acceptance criteriawhether they are in the design basis or in an operability situationof a nuclear plant or process piping. In addition, certain specialtopics of interest to engineers are explicitly addressed. Theseinclude Rules for Accreditation and Certification; Perspective onCyclic, Impact, and Dynamic Loads; Functionality andOperability Criteria; Fluids; Pipe Vibration; Stress IntensificationFactors, Stress Indices, and Flexibility Factors; Code Design andEvaluation for Cyclic Loading; and Bolted-Flange Joints andConnections. Important is the inclusion of unique Sections suchas Sections I, II, IV through VII, IX, and X that enriches the valueof the book as a comprehensive companion guide for B&PV andPiping Codes. Of considerable value is the inclusion of an in-depth treatment of Sections III, VIII, and XI. A unique aspect ofthe book chapters related to the Codes is the treatment of the ori-gins and the historical background unraveling the original intentof the writers of the Criteria of the Codes and Standards. Thus,the current users of these Codes and Standards can apply theirengineering knowledge and judgment intelligently in their use ofthese Codes and Standards.

Although these two volumes cannot be considered to be a per-fect symphony, the subject matter orchestrates around a centraltheme, that is, “The Use of B&PV and Piping Codes andStandards.” Special effort is made by the contributors, who areexperts in their respective fields, to cross-reference other Sections;this facilitates identifying the interconnection between variousB&PV Code Sections, as well as the B31.1 and B31.3 Piping

PREFACE TO THE FIRST EDITION


This edition continues to address the purpose of the first editionto serve as a “Primer” to help the user weave through varied aspectsof the ASME Codes and B31.1 and B31.3 Piping Codes and pres-ent a summary of specific aspects of interest to users. In providingthe “end user” all of these aspects, the first edition has been revisedappropriately to be consistent with the current 2004 Codes.

Contributors of the first and second volumes had takenimmense pains to carefully update their write-ups to include asmuch of the details that they could provide. Significant changescan be seen in Sections II, III, VIII and XI with repercussions onSections I, IV, V, VII, IX and X. Thus, these consequences had beenpicked up by the contributors to bring their write-up up-to-date.Similarly changes of Power Piping (B31.1 Code) and B31.3(Process Piping) have also been updated.

Included in this edition is a third volume that addresses the crit-ical issues faced by the BWR and PWR Nuclear facilities such asBWR Internals, PWR Reactor Integrity, and Alloy 600 relatedissues. With the aging of the Nuclear Plants, the regulators per-spective can be meaningful, and this has been addressed byexperts in this area. In today’s industrial spectrum the role ofProbabilistic Risk Analysis has taken an important role and this

volume has a chapter contributed by recognized authorities. Withthe increased use of computer–related analytical tools and withASME Codes explicitly addressing them, a chapter has beendevoted to the Applications of Elastic Plastic Fracture Mechanicsin ASME Section XI Code.

ASME Codes are literally used around the world. More impor-tantly the European Community, Canada, Japan and UK havebeen increasingly sensitive to the relevance of ASME Codes. Inthis second edition, experts conversant with these country Codeshad been invited to detail the specifics of their Codes and cross-reference these to the ASME Codes.

Public Safety, more so than ever before, has become extremelyrelevant in today’s power generation. Experts hade been invited toprovide a perspective of the regulations as they emerged as wellas discuss the salient points of their current use. These include thetransportation of radioactive materials and the new ASMESection XII Code, Pipe Line Integrity and pertinent topicsinvolved in decommissioning of nuclear facilities.

K. R. Rao, Ph.D., P.E. Editor

xxxviii • Preface

Codes. The Table of Contents, indexing, and annotated notes forindividual Chapters are provided to identify the connectionbetween varied topics. It is worth mentioning that despite thechapters not being of equal length, comprehensive coverage isensured. The coverage of some sections is intentionally increased

to provide in-depth discussion, with examples to elucidate thepoints citing the Code Subsections and Articles.

K. R. Rao, Ph.D., P. E. Robert E. Nickell, Ph.D. Editor 1999–2000 President

ASME International

PREFACE TO THE SECOND EDITION


PREFACE TO THE THIRD EDITION

This edition continues to address the purpose of the previous edi-tions to serve as a “Primer” to help the user weave through variedaspects of the ASME Codes and B31.1 and B31.3 Piping Codes,in addition to a discussion of “The Criteria and Commentary onSelect Aspects of ASME Boiler and Pressure Vessel and PipingCodes” of interest to “end users”. This publication has beenrevised in providing all of the aspects of the previous editions,while updating to the current 2007 Codes, unless otherwise men-tioned. This book in three volumes strives to be a comprehensive‘Companion Guide to the ASME Boiler and Pressure VesselCode’.

Since the first edition, a total of 140 authors have contributedto this publication, and in this edition there are 107 contributorsof which 51 are new authors. Several of the new contributors arefrom countries around the world that use ASME B&PV Codes,with knowledge of ASME Codes, in addition to expertise oftheir own countries’ B&PV Codes. All of these authors whocontributed to this third edition considerably updated, revised oradded to the content matter covered in the second edition toaddress the current and futuristic trend as well as dramaticchanges in the industry.

The first two volumes covering Code Sections I through XIaddress organizational changes of B&PV Code Committees andSpecial topics relating to the application of the Code. Consideringsignificant organizational changes are taking place in ASME thatreflect the industry’s demands both in USA and internationally, thesalient points of these have been captured in this publication byexperts who have first hand information about these.

Volume 1 covers ASME Code Sections I through VII, B31.1and B31.3 Piping Codes. Continuing authors have considerablyupdated the text, tables, and figures of the previous edition to bein line with the 2007 Code, bringing the insight knowledge ofthese experts in updating this Volume. Fresh look has been pro-vided by new authors, who in replacing previous contributors offew chapters, have provided an added perspectives rendered in theearlier editions. In one case, the chapter had been entirely rewrit-ten by new experts, with a new title but addressing the same sub-ject matter while updating the information to the 2007 ASMECode Edition.

ASME Code Committees have spent time and considerableresources to update Section VIII Division 2 that was completelyrewritten in the 2007 Code Edition, and this effort has been cap-tured in Volume 2 by several experts conversant with this effort.Volume 2 has chapters addressing Code Sections VIII through XI,

refurbished with additional code material consistent with the cur-rent 2007 Code edition. Notable updates included in this Volumerelate to maintenance rule; accreditation and certification; per-spectives on cyclic, impact and dynamic loads; functionality andoperability criteria; fluids; pipe vibration testing and analysis;stress intensification factors, stress indices and flexibility factors;Code design and evaluation for cyclic loading; and bolted-flangejoints, connections, code design and evaluation for cyclic loadingfor Code Sections III, VIII and a new chapter that discussesSafety of Personnel using Quick-actuating Closures on PressureVessels and associated litigation issues. While few chapters havebeen addressed by new authors who added fresh perspective, theefforts of continuing authors have provided their insights withadditional equations, figures and tables in addition to extensivetextual matter.

The third volume of this edition is considerably enlarged toexpand the items addressing changing priorities of Codes andStandards. Continuing authors who addressed these topics in theprevious edition have discussed these with respect to the ASME2007 Code Edition. The discussions include chapters on BWRand PWR Reactor Internals; License Renewal and AgingManagement; Alloy 600 Issues; PRA and Risk-InformedAnalysis; Elastic-Plastic Fracture Mechanics; and ASME CodeRules of Section XII Transport Tank Code. Chapters covering‘U.S. Transportation Regulations for Radioactive Materials’;‘Pipeline Integrity and Security’, and ‘Decommissioning ofNuclear Facilities’ have been considerably revised.

In Volume 3 experts around the world capture ‘Issues Criticalfor the Next Generation of Nuclear Facilities’ such asManagement of Spent Nuclear Fuel, Generation III1 PWRs, NewGeneration of BWRs and VERY High Temperature GenerationIV Reactors.

The impact of globalization and inter-dependency of ASMEB&PV Codes had been examined in the previous edition inEuropean Community, Canada, France, Japan and UnitedKingdom. Contributors who authored these country chaptersrevisited their write-up and updated to capture the currentscenario.

Significant contribution in the third volume is the inclusion ofadditional countries with changing priorities of their NuclearFacilities. In-depth discussions cover the international experts ofthese countries which own and operate nuclear reactors or havenuclear steam supply vendors and fabricators that use ASMEB&PV Code Sections I through XII. This information is meant to


benefit international users of ASME Codes in Finland, Belgium,Germany, Spain, Czech and Slovakia, Russia, South Africa, India,Korea and Taiwan that have been added in this third edition.

A unique feature of this publication is once again, as in the pre-vious editions, the inclusion of all author biographies and an

introduction that synthesizes every chapter, along with an alpha-betical listing of indexed terms

K. R. Rao, Ph.D., P.E.Editor

xl • Preface

This edition continues to address the purpose of the previous edi-tions to serve as a “Primer” to help the user weave through variedaspects of the ASME Codes and B31 Piping Codes, in addition to adiscussion of “The Criteria and Commentary on Select Aspects ofASME Boiler and Pressure Vessel and Piping Codes” of interest to“end users”. This publication has been revised in providing all ofthe aspects of the previous editions, while updating to the current2010 Codes, unless otherwise mentioned. This book strives to be acomprehensive ‘Companion Guide to the ASME Boiler andPressure Vessel Code’.

All of the 48 authors who contributed to 38 Chapters in thisfourth edition considerably updated, revised or added to the contentmatter covered in the third edition to address the current and futuretrends as well as dramatic changes in the industry. Unlike the previ-ous third edition, this edition has two volumes dedicated entirely tothe ASME Boiler and Pressure Vessel Code Sections I through XII.

Not only have chapters of the third edition altered but the restruc-turing of chapters made it possible for a smoother flow of chaptersrelating to Sections I through XII that proceed B31 Piping Codesappearing in Volume 2. Chapters not covering Code Section Ithrough XII which were in Volume 2 of third edition have beendropped from this fourth edition, and consequently chapters of thirdedition have been renumbered. In this edition pagination of chap-ters is different from the previous editions, starting from page 1 andending with the last page of the chapter.

Considering significant organizational changes taking place inASME that reflect the industry’s demands both in USA and interna-tionally, the salient points of these have been captured in both thevolumes by experts who have first hand information about these.Each of the volumes 1 and 2 have Index provided at the end of eachvolume as a quick reference to topics occurring in different CodeSections of that volume.

Volume 1 covers ASME Code Sections I through VII, andVolume 2 addresses ASME Code Sections VIII through XII. In sev-

eral instances continuing authors, in some cases replacementauthors have considerably updated the text, tables, and figures ofthe previous edition to be in line with the 2010 Code, bringing theinsight knowledge of these experts in updating the previous edition.Fresh look has been provided by new authors, who in replacingprevious contributors of few chapters, have provided an added per-spectives rendered in the earlier editions. In certain cases, the chap-ters had been entirely rewritten by replacement experts, with newtitles but addressing the same topics while revising in its entiretyand updating the information to the 2010 ASME Code Edition.

Volume 1 has chapters 3 and 15 covering Code Sections II andSection III Division 2, respectively that have additional experts toaddress topics which had not been covered in the third edition. Anadditional chapter to cover Code Section III Division 5 has beenincluded in this third edition by experts conversant with CodeCommittee activity. Other chapters covering the updates of CodeSections I, III Divisions 1, 2 and 3, Section IV, V and VI have beencompletely updated to ASME 2010 Code.

Volume 2 has chapters addressing Code Sections VIII throughXII with additional code material consistent with the current 2010Code edition. Notable updates relating to Section VIII are chapterscovering Divisions 1, 2 and 3 and chapter dealing with “Safety ofPersonnel”. ASME Section IX has been updated by a Code expertsince the initial rendering in the first edition. Code Section X hasbeen addressed by an expert replacing the original author withconsiderable changes. Code Section XI that is perhaps crucial foroperating nuclear plants has been reorganized consistent with thecurrent trends with expert authors who are members of the respec-tive committees who updated the chapters with 2010 Code. A sig-nificant addition in this edition is the retention of a chapter from thethird edition pertaining to Elastic-Plastic Mechanics in Section XI.

Unique for this fourth edition is the addition of several B31Piping Codes and Standards in Part 11 dealt by new authors cover-ing B31.9 Building Services and ASME Standards For Piping;

PREFACE TO THE FOURTH EDITION


COMPANION GUIDE TO THE ASME BOILER & PRESSURE VESSEL CODE • xli

B31T Standard For Toughness Requirements For Piping; B31.5:Refrigeration Piping and Heat Transfer Components; B31EStandard for Seismic Design and Current ASME Edition Retrofit ofabove Ground Piping Systems; B31J Standard for Test Method forDetermining Stress I- Factors for Metallic Piping Components;B31.4 Standard for Pipeline Transportation Systems for LiquidHydrocarbons and Other Liquids; B31.11 Standard for Slurry

Transportation Piping; B31G: Manual for Determining theRemaining Strength of Corroded Pipelines and B31Q: Qualificationof Pipeline Operators; and B31.12: Hydrogen Piping and Pipelines.

K. R. Rao, Ph.D., P.E. Editor


This fourth edition is in two volumes composed of 11 Parts,with Parts 1–5 in Volume 1, Parts 6–11 in Volume 2. Common toboth volumes is the front matter, including the Organization of theCode. Organization and Operation of the ASME Boiler andPressure Vessel (B&PV) Committee has been initially authoredby Martin D. Bernstein for the first edition, appropriately updatedin the second and third editions by Guido G. Karcher capturingthe dramatic changes in the ASME B&PV organization. The cur-rent fourth edition is updated by Joel G. Feldstein and Thomas P.Pastor who hold positions of responsibility in the Boiler andPressure Vessel Code Committees.

An index is provided at the end of each volume as a quick refer-ence to topics occurring in different Code Sections of that volume.In addition to indexing several topics covered in this publication, itis also meant to assist in reviewing the overlaps of the ASMEBoilers & Pressure Vessel Code Sections/Subsections/Paragraphsoccurring in the particular volume. In each chapter, all discussionsgenerally pertain to the latest 2010 Code Edition unless noted oth-erwise by the chapter author(s).

In the preceding three editions, a total of 140 authors con-tributed to this publication that had three volumes for the thirdedition. Unique for this edition with two volumes, is the inclusionof Code Sections I through XII, in addition to several ASME B31Piping Codes. Each of the 49 contributors covering 38 chapters ofthe current fourth edition captured ‘up-to-date’ Boiler andPressure Vessel Codes and Standards, making this publicationonce again a comprehensive “Companion Guide Book”.

The ASME Code is generally accepted in the United States(and in many foreign countries) as recognized minimum safetystandard for the construction of pressure vessels and piping.Toward that end, these two volumes can be considered “a primer.”Although this primer is authored by several Code Committeemembers who are considered experts in their respective fields, thecomments and interpretations of the rules contained in this publi-cation are strictly the opinions of the individual authors; they arenot to be considered official ASME Code Committee positions.

Volume 1 has five Parts, each addressing a unique aspect of theCode. Part 1 covers Power Boilers (Code Sections I and VII); Part2 covers Materials and Specifications (Code Section II). Scope ofPart 2 has been considerably enlarged to address the “sub-topics”of “material specifications” which are the essence of the B&PVCodes and Standards. Basis for Acceptance of B&PV Codes for“International Material Specifications” are also addressed.

Part 3 provides an in-depth commentary on Rules for Constructionof Nuclear Power Plant Components (Code Section III, Division 1).Previously, “Pumps” and “Valves” were addressed in a single chapter,which are now separately dealt in two chapters. As in the previouseditions, Section III Division 2 continues to be included in Part 3,addressed by several additional contributors with expertise in theirrespective areas. Section III Divisions 3 and 5 are included in Part 3,

with Division 5 addressing the “Generation IV Nuclear Reactors”,which is an add-on-aspect of this edition.

Part 4 covers Sections IV and VI of B&PV Code. Part 5 cover-ing Nondestructive Examination (NDE), Code Section V ofB&PV Code is now included in Volume 1.

Volume 2 covers Parts 6–11, with Part 6 covering Section VIII–Rules for Construction of Pressure Vessels. In Part 6, experts deal-ing with Divisions 1, 2, and 3 provide in-depth criteria andcommentary of Code Section VIII with the latest of the code stip-ulations. In addition there is a chapter by an expert of the B&PVCode who discusses safety and litigation issues.

Part 7 addresses welding and brazing qualifications of CodeSection IX by the contributor with expertise at the helm of CodeCommittee deliberations.

Part 8 covering Code Section X pertains to fiber-reinforcedplastic pressure vessels has been considerably revised by the cur-rent contributor for this edition.

Part 9 providing in-depth discussions of Code Section XI inchapters 27 through 34 is updated by authors associated with thespecific subgroups and subcommittees dealing with the topicsaddressed in the previous editions. A chapter from the third vol-ume of the third edition dealing with Applications of Elastic-Plastic Fracture Mechanics is included in this volume.

Part 10 covering Code Section XII dealing with Transport TankCode which was in the third volume of the third edition is nowincluded in this part.

Part 11 has coverage of ASME B31 Codes and Standards inchapters 35 through 38. Code for B31.1 Power Piping and B31.3Process Piping which were in chapters 16 and 17, respectively, ofvolume 1 of the third edition are now completely revised and cov-ered by Code Committee experts in Chapters 35 and 36 in thisPart 11. For the first time since the first edition, in Part 11 of thecurrent fourth edition, additional experts cover ASME StandardsB31.9, B31.T, B31.5, B31E, B31J, B31.4, B31.8, B31.11, B31Gand B31.12.

VOLUME 1

Chapter 1 of the 1st edition was authored by the late Martin D.Bernstein. It discussed Power Boilers, Section I of the ASMECode. His objective was to provide an overview of the intent,application and enforcement of Section I rules for the construc-tion of power boilers. This chapter is an abbreviated version ofthe book Power boilers, A Guide to Section I of the ASME Boilerand Pressure Vessel Code, used as the textbook for a two dayASME professional developement course on Section I developedand taught for many years by Martin D. Bernstein and Lloyd W.Yoder. Mr. Yoder has reviewed and updated the 1st editionChapter 1 for this 2nd edition to commemorate his close friendand associate. In doing so, he found that only minor changes and

INTRODUCTION


xliv • Introduction

updating were required because the 1st edition Chapter 1 was sowell crafted by Mr. Bernstein, like all of the many things he wasknown to have written.

Chapter 1 was reviewed and updated for the third edition byJohn R. MacKay, long-time member and past chairman ofStandards Committee I (BPVI), formerly Subcommittee I. Mr.MacKay also reviewed and updated the current edition of thischapter which covers revisions to Section I, Power Boilersthrough the 2010 Edition, 2011 Addenda. Significant additionsare included in this update that pertains to Code changes to PG-26Weld Strength Reduction Factor, PG-58 Boiler External Pipingand Boiler Proper Connections, and PG-105 Certification Marks.Standards Committee I (BPVI) has recently added two newSubgroups, SG Locomotive Boilers (BPVI) and SG Solar Boilers(BPVI). Additions to Section I from both these new Subgroupsare expected to be published in the 2013 Edition of the Code.

Chapter 1 covers some of the more important aspects ofSection I construction, including the history and philosophy ofSection I: how the ASME Code works; the organization andscope of Section I; the distinction between boiler proper pipingand boiler external piping; how and where Section I is enforced;and the fundamentals of Section I construction. These fundamen-tals include permitted materials; design; fabrication; welding andpostweld heat treatment; NDE; hydrostatic testing; third-partyinspection; and certification by stamping and the use of datareports. A number of design examples also have been included inthis chapter.

The design and construction of power boiler involves the use ofother sections of the ASME Code besides Section I, such asSection II, Materials; Section V, Nondestructive Examination; andSection IX, Welding and Brazing Qualifications. In a ratherunusual arrangement, the construction rules for boiler piping arefound partly in Section I and partly in the B31.1 Power PipingCode. This arrangement has led to considerable misunderstandingand confusion, as explained in Chapter 1, Section 1.5, where thedistinction between boiler proper piping and boiler external pip-ing is discussed.

In the 1st edition Mr. Bernstein stated “The ASME B&PV Codechanges very slowly but continuously. Thus, although this chapterprovides a substantial body of information and explanation of therules as they now exist, it can never provide the last word.Nevertheless, the chapter should provide the User with a veryuseful introduction and guide to Section I and its application.”His words are still true for the reason that Chapter 1, as updated,retains the philosophy and intent of the original author, Martin D.Bernstein.

Chapter 2, authored by James T. Pillow in the current update,covers ASME Boiler & Pressure Vessel Code Section VII,Recommended Guidelines for the Care of Power Boilers. ThisSection is very useful for operators of power boilers, as stated inthe Introduction of Section VII, “The purpose of these recom-mended guidelines is to promote safety in the use of power boil-ers. These guidelines are intended for use by those directlyresponsible for operating, maintaining, and inspecting power boil-ers.” In line with the other Code Sections, the nine Subsections,C1–C9, are addressed by the authors, including Fundamentalssuch as Boilers Types, Combustion, and Boiler Efficiency; BoilerOperation; Boiler Auxiliaries; Appurtenances; Instrumentation,Controls, and Interlocks; Inspection; Repairs, Alterations, andMaintenance; Control of Internal Chemical Conditions;Preventing Boiler Failures; and Guidelines for Safe and ReliableOperation of the Power Boilers.

The authors present the commentary in Chapter 2 from theperspective of Installer and Owner–Operator personnel with expe-rience in operating, maintaining, and inspecting industrial andutility power boilers. In some instances, although certain para-graphs are reiterations of Section VII, they, combined with addi-tional information, stress the importance of the aspects covered. Itis suggested that the reader review existing literature, such asmanufacturer’s instructions or existing company procedures, foradditional details. Section VII is a Nonmandatory Standard, andit, along with Section VI (Chapter 19 of Volume 1) provides rec-ommended practices and serves as a guideline. However, SectionVII touches on many activities that the Owner–Operator person-nel must be aware of before a power boiler is commissioned. Newpersonnel who are not familiar with boiler operation, mainte-nance, and inspection can use Section VII as an introduction tothese activities. Experienced personnel will find Chapter 2 to be agood review of the essentials of operation, maintenance, andinspection, with useful figures and references. In the “Summaryof Changes” of the 2010 Edition, it was written that “No revisionsare contained in Section VII, 2011a Addenda, of this Edition.”However, there were a few minor corrections made that were notlisted. It is the authors’ opinion that more effort should be madeby the committee to update and expand Section VII, as recom-mended in the Chapter 2 commentary. Like the other Sections,Section VII should also be a living document providing the latestinformation in this everchanging world. If the committee does notput in any effort in revising Section VII, they should at least alertprospective purchasers that no changes were made so that holdersof the previous Edition do not have to buy it.

Chapter 3 has multiple authors, and in Chapter 3.1, History ofMaterials in the ASME Boiler and Pressure Vessel Code,Domenic Canonico traces the chronological evolution of materi-als and associated technologies, from the need for materials toaccommodate riveted construction to the acceptance of fusionwelding as a fabrication process. Included in this discussion arethe application of advanced materials, the revisions to the basisfor setting allowable stress values, and the acceptance of MaterialSpecifications other than those approved by ASTM. Also coveredis the evolution of materials, from their humble beginning as a 35-page inclusion in the 1914 Edition of the Boiler Code to the 3994-page, four-Part 2001 Edition of Section II of the ASME B&PVCode. Chapter 3.1 provides some insight not only into the materi-als needed for the design and fabrication of power boilers but alsointo the determination of the Maximum Allowable WorkingPressure. With the aid of tables, Domenic discusses the MaterialSpecifications from the 1914 through the present Code Editions.

Chapter 3.2, authored by John Grubb in the current update, dis-cusses Code Section II, Part A—Ferrous Material Specifications,adopted by ASME for the construction of boiler, pressure vessel,and nuclear power plant components. He notes that all materialsaccepted by the various Code Sections and used for constructionwithin the scope of the Code Sections’ rules must be furnished inaccordance with the Material Specifications contained in SectionII, Parts A, B, or C, or referenced in Appendix A of Part A—except where otherwise provided in the ASME Code Cases or inthe applicable Code Section. Discussions in Chapter 3.2 includeThe Organization of Section II, Part A, Guideline on the Approvalof New Materials, Appendices, and Interpretations.

In Chapter 3.3, Richard C. Sutherlin provides the basis of acommentary on Section II, Part B – Nonferrous MaterialSpecifications, adopted by ASME for the construction of boiler,pressure vessel and nuclear power plant components. He notes


COMPANION GUIDE TO THE ASME BOILER & PRESSURE VESSEL CODE • xlv

that all materials allowed by the various Code Sections and usedfor construction within the scope of the Code Sections’ rules mustbe furnished in accordance with the Material Specifications con-tained in Section II, Part B or referenced in Appendix A of Part B,except where otherwise provided in the ASME Code Cases or inthe applicable Code Section. Richard discusses Alloy Definitions;Organization of Section II, Part B; Material Specifications includ-ed in Section II, Part B: Guidelines for Approval and Use ofMaterials for ASME Code Construction; Submittal of TechnicalInquiries to the Boiler and Pressure Vessel committee; AcceptableASTM and non-ASTM Editions; Guidelines on Multiple Markingof Materials; Appendices; ASME Code Cases; Interpretations;and the use of Nonferrous Material Specification in the PipingCodes 31.1 and 31.3. Richard also provides cross references toweldability; the ASME Code Section I, III, IV, VIII and IX; andPiping Codes B31.1 and B31.3.

Chapter 3.4, authored by Marvin Carpenter, discusses SectionII, Part C—Specification for Welding Rods, Electrodes, and FillerMetals. Welding plays a major role in the fabrication of pressurevessels and related components to the requirements of the ASMEB&PV Code. Marvin provides the basis for the Specifications andStandards enveloped by Section II, Part C and their relations tothe ANSI/AWS specifications. Marvin indicates that Section II,Part C does not include all the welding and brazing materialsavailable to the industry—only those Specifications applicable toASME Code Construction. Discussions also include Code Casespertinent to this chapter. Chapter 3.4 highlights the major featuresof the Welding Material Specifications contained in Section II,Part C and the relationship of these Specifications to otherSections of the Code, including Section IX. Included are the elec-trode classification system, material descriptions, welding materi-al applications, welding material procurement, and filler-metalcertification. Chapter 3.4 should prove useful for one to gain abasic understanding of ASME/AWS Welding Material Classifi-cation and Specification.

Chapter 3.5 has been revised by John Grubb and Jeff Henrywho reviewed important aspects of Section II, Part D – Properties.The discussion includes the properties of ferrous and nonferrousalloys used in the design of components for the B&PV andNuclear Construction Codes. Explanations are provided for theuse of tables within Section II, Part D, including the tables ofmaximum allowable stresses and design stress intensity values forthe alloys adopted by the Construction Codes, as well as thetables of yield strength and ultimate tensile strength values at arange of temperatures. The discussion also addresses the use ofthe external pressure charts as well as the values collected in thePhysical Properties tables that are required for Code design.Explanations are provided for how the allowable stresses for thedifferent Construction Codes are developed and the data require-ments for new materials briefly are reviewed. The chapter is auseful overview to understanding how the compendium of infor-mation on relevant material properties that is collected in SectionII, Part D can be successfully exploited by Code users.

Sub-chapter 3.6 is a new sub-covering non-metallic materialsused in structural applications by C. Wesley Rowley. Wesley cov-ered three broad categories of nonmetallic materials that are usedin structural applications: (A) Thermoplastic Materials, (B)Thermoset Plastic Materials, and (C) Graphite Materials.

Thermoplastic Materials include Polythylenes, Poly VinylChlorides, Polyphenylenes Chlorinated Poly Vinyl Chlorides, andPolybutylene. Thermoset Plastic Materials include Epoxies, Furan,Phenolics, Polyesters, Polyurethanes, and Vinyl Esters. Graphite

Materials include Thermoset Polymer Impregnated And Non-Impregnated Forms.

Thermoset plastic materials and thermoplastic materials may bereinforced with fibers to substantially change the engineeringproperties of the composite material. Reinforcing fibers includecarbon, glass, and aramid materials. Author covered key defini-tions, nonmetallic material fundamentals, engineering materialproperties, physical material properties, published ASME codesand standards using nonmetallic materials; published ASME codecases using nonmetallic materials; ASME strategic plan; interna-tional liaison; BPV code section II materials; initial publication ofpart e, and included pertinent references and common acronyms.

Chapter 3.7, authored by Anne Chaudouet and Elmar Upitis,discusses Section II, Part A and Part B — International MaterialSpecifications adopted by ASME for the construction of boiler,pressure vessel, and nuclear power plant components. MostASME material specifications are based on ASTM specifications.ASME Section II also includes guidelines for acceptance of mate-rial specifications of recognized National or International organi-zations other than ASTM. ASME does not have permission topublish such specifications. Section II includes cover sheets giv-ing the additional ASME requirements for specifications whichASME has adopted for ASME Code construction. Chapter 3.7also discusses the process of adoption of the CEN specificationsin Europe with consequences on the corresponding ASME speci-fications. The EN material specifications are restricted to Europeanspecifications themselves with no national endorsement, forewordand annexes and dated as the year of approval by CEN.

Section 3.7 describes the following international specificationsthat are adopted by ASME and included in Section II: AustralianStandard basis of SA/AS 1548 Specification for Steel Plates forPressure Equipment; Canadian Standard basis of SA/CSA-G40.21Structural quality steel; European Standards bases of SA/EN10028 Flat products made of steels for pressure purposes - Part 2Non-alloy and alloy steels with specified elevated temperatureproperties, Part 3 Weldable fine grain steels, normalized and Part 7Stainless steels, and of SB/EN 1706 Aluminum and AluminumAlloys - Castings - Chemical Composition and Mechanical Pro-perties; Chinese Standard basis of SA/GB 6654 Steel Plates forPressure vessels; and Japanese Standards bases of SA/JIS G3118Carbon steel plates for pressure vessels for intermediate andmoderate temperature services, and of SA/JIS G4303 Stainlesssteel bars. Some grades of international material specifications areapproved for Code construction by use of Code Cases. Chapter 3.7also includes a brief discussion of these materials.

In Chapter 4, Roger Reedy provides commentary for under-standing the principles of the ASME B&PV Code. Roger tracesthe history of the Code, from its initial publication in 1914 to thepresent. He also identifies the role of the volunteers who write theCode and the process used to establish Code with the outstandingsafety record that has been achieved by the current consensusprocess. Roger suggests that Code Users apply common sensewhen using and interpreting the Code He emphasizes that “theCode is not a handbook and cannot substitute for the use of engi-neering judgment.” Also, Roger emphasizes the need for a betterunderstanding of the basic principles of the Code. It is necessaryto understand the application of design factors for each SectionASME Boiler and Pressure Vessel Code, recognizing there are anumber of different design factors and stress theories in the differ-ent Code Sections and Divisions. Roger states that the term “safe-ty factor” is both incorrect and misleading, because a reduction inthe factor seems to indicate a reduction in safety. In fact, when the


xlvi • Introduction

Code Committee considers a reduction in design factor, it allowsthe reduction only after it determines that other changes in Coderequirements have compensated for the resulting increase inallowable stress values. There have been very significant reduc-tions in design factors in the past few years, and more will comein the near future.

Chapter 5, authored by Richard W. Swayne, describes the gen-eral requirements of Section III applicable to all ConstructionClasses, including concrete structures and steel vessels, piping,pumps, and valves. It identifies how to classify components anddescribes how the jurisdictional boundaries of Section III definewhat is within and what is outside the scope of the Code. Thischapter includes coverage of Subsection NCA, which pertains togeneral requirements for Divisions 1, 2, and 3 of Section III.Division 1 includes steel items such as vessels, storage tanks, pip-ing systems, pumps, valves, supports, and core support structuresfor use at commercial nuclear power plants; Division 2 includesconcrete reactor vessels and concrete containment vessels; andDivision 3 includes requirements for the construction of contain-ment vessels for transportation of spent nuclear fuel. The scope ofDivision 3 now also includes recently-published requirements forconstruction of storage canisters and transportation containmentsfor spent nuclear fuel.

Chapter 5 also explains the use of Code Editions, Addenda, andCode Cases. The requirements for design basis, design and con-struction specifications, and design reports are described, and theresponsibilities and quality assurance program requirements ofthe different entities involved in nuclear power plant con-struction—from the Material Manufacturer to the Owner—areaddressed. Requirements for ASME accreditation, application ofthe ASME Code Symbol Stamp, and use of Code Data Reportsare described. With in-depth information, Mr. Swayne outlines thebasis for exemptions, component classification, load combina-tions, responsibilities, Certificate of Authorization Holders andQuality System Certificate Holders. Also, Mr. Swayne providescross-referencing to other Code Sections and Subsections, such asSections III and XI, as well as to pertinent Regulatory Guides,such as the U.S. Code of Federal Regulations (CFR).

Chapter 6 has been updated by Chakrapani Basavaraju andDavid Jones to 2010 version of the Code. The major highlightsinclude discussion on Code Cases N-761, N-792 pertaining to theevaluation of the fatigue effects for components exposed to LWRenvironments, and discussion on changes to the rules on temperbead welding.

Authors cover Subsection NB, Class 1 Components. In present-ing the rules and requirements for Section III, Subsection NB, theauthors discuss the theories, on which the rules and requirementsare based, the appropriate application for applying the rules andrequirements, and the interfaces for design, analysis, and con-struction. The chapter emphasizes the analytical rules and require-ments, and makes reference to the Criteria of the ASME Boilerand Pressure Vessel Code for Design by Analysis in Sections IIIand VIII, Division 2, 1968 that is considered the basis documentfor Sections III and VIII. John provided the design theory andramifications of the key considerations, with cross-references toother Code Sections discussing the subtle differences between theSection III design criteria and the Section I and Section VIII,Division 1 design criteria.

In addition, commentary is provided on the Code requirementsof Class 1 for design by analysis “because of the prominent roleplayed by stress analysis in designing vessels by the rules ofSection III . . . and because of the necessity to integrate the design

and analysis efforts.”—The authors emphasize against the designby analysis theme of NB is to provide high assurance that the fail-ure modes of burst, plastic collapse, excessive plastic deformation, fatigue, ratcheting, brittle fracture, elastic instability (buckling),stress corrosion, and corrosion fatigue. The intent of the rules ofNB is to provide assurance that high quality is reached; therefore,stress analysis is added to the “NB rules for all of the disciplinesand their interaction” in an effort to reach high quality. Chapter 6has been updated by Greg Hollinger and David Jones to the 2007version of the Code including discussions of the differencesbetween Section VIII Division 2 and Section III NB. Discussionshave been added on the Section VIII Division 2 rules dealing withLimit Analysis, Finite Element Analysis and EnvironmentalFatigue, and new methods for fatigue of weldments.

Chapter 7 has been updated by Chakrapani Basavaraju to 2010version of the Code. The major highlights include a discussionregarding the NRC approval of new seismic rules for the designof piping, and alternate rules for axial compressive membranestress in the design of cylindrical storage tanks. This addressespressure atmospheric tanks, and 0–15 psig tanks as presented inthe ASME B&PV Code, Section III, Division 1, Subsection NC,Class 2 Components and Subsection ND, Class 3 Components.This chapter does not address piping, pumps, and valves; theseare addressed in Chapter 8 for Class 2 and Class 3 Piping, and inChapter 13 for Nuclear Pumps and Valves. This chapter discusses,in order, each of the eight major Code Articles: Introduction;Materials; Design, Fabrication and Installation; Examination;Testing; Overpressure Protection and Name Plates; and Stampingand Reports. In the 1971 Edition, Subsection NB was fully devel-oped in the evolution of the Nuclear Codes; all other were writtenby using the outline established for NB. Consequently, many ofthe basic paragraphs contained in Subsection NB and other refer-ence documents were included verbatim in both Subsections NCand ND, when the subsections were published as separate vol-umes in the 1974 Edition.

Subsections NC and ND are a combination of rules andrequirements taken from Section III, Subsection NB and SectionVIII. In Chapter 7, Thomas has referenced all of these Codes and meticulously identified both obvious and subtle differencesbetween Subsection NB, the parent Code, and Subsections NC and ND. Thus, because Thomas addresses the Articles ofSubsections NC and ND in this part of the commentary, he pre-sents comparisons, the most probable source of origin of the Coderequirements, certain insights as well as contradictions that seemto exist, and the specific source document and some of theunderlying theory. He provides cross-references to other CodeSections/Subsections/Paragraphs where applicable. Marcus hastaken this work and simplified it where possible, and updated it tothe 2007 Edition.

Chapter 8, was authored by Don Landers for the first throughthird Editions, and now is updated in the fourth Edition by JackCole. This update covers the changes in place and underway for the2010 Edition with 2011a Addenda of Section III, Division 1(Piping). Chapter 7 indicates that the requirements of Section III,Division 1 provide for three classes of components. Chapter 8 indi-cates that each Class can be considered a quality level, with Class 1the highest and Class 3 the lowest. These quality levels exist becauseof the various requirements for each Class in Section III related tomaterials, fabrication, installation, examination and design. Designwas placed last on the list because sufficient evidence exists to indi-cate that the other considerations listed are more important than thedesign requirements in constructing an acceptable piping system.


COMPANION GUIDE TO THE ASME BOILER & PRESSURE VESSEL CODE • xlvii

In Chapter 8, Don and now Jack develop the above list of con-siderations in the commentary regarding the criteria and basis forrequirements of the Subsections NB, NC, and ND for Piping.They provide the stress requirements for Nuclear Classes 1, 2, and3 piping and the corresponding design processes and DesignSpecifications, with pertinent references, tables, and figures. Theircommentary provides insight into load classifications and theresponsibility of Owners. The Code rules ensure that violation ofthe pressure boundary will not occur if the Design Specificationsatisfactorily addresses all issues necessary for Code compliance.In the commentary, Donald and Jack show the subtle differencesbetween the piping rules and design by analysis, and they explainwhat items the analyst should be concerned with in satisfyingCode requirements. They provide cross-references to B31.7 Codetechniques and discuss the recent regulatory acceptance of theseismic design requirements for piping in Section III, Division 1.In the fourth edition, Jack has provided updates that discussrecent Code changes to piping rules that include the adaption ofCode Cases for evaluation reactor coolant environmental fatigueevaluation, update of the Code Case for construction of Class 3HDPE pipe, alternate rules for simplified elastic plastic analysisusing Ke, and upcoming changes for buried Class 2 and 3 pipedesign rules.

Chapter 9, has been authored by Kamran Mokhtarian for theFirst two editions and updated for the 3rd edition by Roger F.Reedy who continues the discussion of Subsection NE, Class MCComponents. This chapter summarizes some of the more signifi-cant requirements of Section III, Subsection NE and provides acommentary on such requirements. Kamran’s comments and inter-pretations of the rules are based on his several years of experiencein design, analysis, and construction of containment vessels, as wellas his participation in various ASME Code Committees. Somecomparisons of the rules of Section VIII are included for informa-tion. The analysis procedures are not dealt with in any great detail,for they are similar to those of Subsection NB and the old SectionVIII, Division 2. However, more emphasis is placed on the uniquefeatures of Subsection NE. Further, the stress analysis proceduresdo not in any way compare with the stress analysis procedures inthe current Section VIII, Division 2 Code for pressure vessels. Anumber of Code Cases and references regarding the rules ofSubsection NE are cited, with cross-references to other CodeSections and Subsections. This chapter is based on the 2010 Editionof the Section III Code. The items covered in Chapter 9 includeScope of Subsection NE; Boundaries of Jurisdiction of SubsectionNE; General Material Requirements; Certified Material Test Reports;Material Toughness Requirements; General Design Requirements;Qualifications of Professional Engineers; Owner’s Design Speci-fications; Certified Design Report; Design by Analysis; Appendix F;Fatigue Analysis; Buckling; Reinforcement of Cone-to-CylinderJunctions; Plastic Analysis; Design by Formula; Openings; BoltedFlange Connections; Welded Connections; General Fabrication Re-quirements; Tolerances; Requirements for Weld Joints; WeldingQualifications; Rules for Making, Examining, and Repairing Welds;Heat Treatment; Examination; Qualification and Certification of NDEPersonnel; Testing; Overpressure Protection; and Nameplates, Stamp-ing, and Reports.

Because of the new nuclear power plants soon to be constructed,the rules of Subsection NE should be modified to address the needsof the industry for the new plants. There are many changes that canbe made without sacrificing safety.

Chapter 10 was authored for the first edition by Robert J.Masterson, who covered Subsection NF (Supports). The second,

third and fourth editions had been updated by Uma S.Bandyopadhyay with the current third edition addressing thechanges of the 2010 Code Edition. Robert traced the historicalbackground of this Subsection, which provides a single source ofrules for the design, construction, fabrication, and examination ofsupports for the nuclear industry. Section III, Division 1, Sub-section NF was developed to provide rules for the estimated10,000 piping and component supports existing in a typicalnuclear power plant. The criteria and commentary of Chapter 10provides information on the origin and evolution of design rulesand is intended to allow designers, engineers, and fabricators tomake better use of Subsection NF. Topics of greatest interest arediscussed from both a technical and a historical viewpoint.However, it is not the intent to address every detail associatedwith the use of Subsection NF.

Subsection NF rules have evolved dramatically over the past 30years so that today’s support rules seldom resemble the originalrules of 1973. In Chapter 10, commentary is provided to explainhow the criteria are used, the source and technical basis for equa-tions and rationale, and the reasons for change. Robert covers thescope and classification of the types of supports and attachments.Subsection NF contains rules for the material, design, fabrication,examination, testing, and stamping of supports for Classes 1, 2, 3,and MC construction. Robert provides cross-referencing to Subs-ections NB, NC, ND, NE, and NG, as well as to the B31.1 andB31.3 Codes, and he also addresses Code Cases and Inter-pretations. Discussions include Subsection NF Appendices andwith the help of figures, tables, and references, it is anticipated thatthe reader will develop a better understanding of Subsection NFand appreciate its complexities and usefulness.

Chapter 11, authored by Richard O. Vollmer, deals withSubsection NG (Core-Support Structures). This chapter providescommentary and practical examples on the materials, design,fabrication, installation, and examination requirements for core-support structures in Section III, Division 1, Subsection NG. Inaddition, commentary on Section XI as it applies to core-supportstructure repair, replacement, examination, and inspectionrequirements is presented. The objective of the Subsection NGrules is to provide a Code for the design and manufacture of struc-tures that support the core in pressurized water reactors (PWRs)and boiling water reactors (BWRs). These rules are similar to theSubsection NB rules, though there are important differences dueto differences in basic requirements between pressure boundaryand reactor internals structures. With the aid of figures, tables,and examples, important considerations in the design of core-sup-port structures, the Owner’s Design Specification, and the juris-dictional boundaries between core-support structures and reactorpressure vessels (RPVs) are discussed. The differences betweencore-support structures, internal structures, threaded structuralfasteners, and temporary attachments are explained. Discussionsalso include unique conditions of service; construction materials;special materials; fabrication and installation rules; examinationand repair; general design rules; design by analysis; testing andoverpressure protection; and examples of load combinations forcore-support structures.

The first edition was written based on the 1998 Edition ASMEB&PV Code. In the second edition, the 2001 Edition of the Codeup to and including July 2003 Addenda was used for examplesand discussion points. The third edition was updated to the 2007Edition of the Code, with new or additional commentary cover-ing: Background on Subsection NG Development; Discussion ofTypical Materials Used in CSS, IS, and TSFs; Owner’s Design


xlviii • Introduction

Specification, and Design Reports; Environmental Effects; CSSCode Cases; Improvements in Subsection NG; Material Degrada-tion Issues; Compatibility of Subsection NG with Other Interna-tional Codes; Trends Towards Realistics Design Loads in ReactorInternals; and a summary of changes to the Code through the2007 Edition. The fourth edition has been updated to the 2010Edition of the Code with 2011 Addenda, and expanded to provideadditional discussion on stress classification, special stress limits,Code Cases and Interpretations, and potential additions and im-provements to the NG rules.

Chapter 12, authored by Robert I. Jetter, discusses SubsectionNH, (Class 1 Components in Elevated Temperature Service). Thepurpose of this chapter is to provide background information onthe development and application of the rules for construction ofelevated temperature components for nuclear service. Also dis-cussed are the rules for Class 2 and 3 components and core-support structures that are contained in a series of Code Cases.Robert covers all aspects of construction: materials, design, fabri-cation, inspection, overpressure protection, testing, and markingfor Class 1 components in elevated temperature service. In Sec-tion III, elevated temperature is defined as 700°F for ferritic steelsand 800°F for austenitic stainless steels and nickel-base alloys.Elevated temperature behavior and associated failure modes arediscussed to provide background for the unique features of theSubsection NH rules. Robert presumes that readers have a basicfamiliarity with the rules for construction of Classes 1, 2, and 3components and core-support structures contained in SubsectionsNB, NC, ND, and NG, respectively, that are discussed in otherchapters of this book. Thus Robert provides crossreferencing tothese Code Subsections. Based on 40-plus years in the develop-ment and implementation of elevated temperature design andconstruction rules, Robert, with the aid of figures, tables, and ref-erences, provides a historical perspective to establish the criteriafor the rules contained in Subsection NH. Also discussed arecurrent and future needs.

Chapter 13 was authored for the first edition by the late DouglasB. Nickerson. The late Marcus Bressler updated this chapter forthe second edition. The third edition of this chapter has beenupdated considerably by Robert E. Cornman, Jr, who is employedby Flowserve Corporation and has many years of experience indesign, analysis, construction, and testing of the many pumpdesigns used in nuclear power plants as well as his participation invarious ASME Code Committees. This chapter discusses thoseitems that are the driving and controlling forces in hydraulic sys-tems for nuclear power plants. The pump in each system drives theflow through the piping to provide the transfer of energy from onecomponent to another. The fluid systems have varying degrees ofcriticality, depending on their function. This chapter explains therelevancy of the ASME Code requirements for safety-relatednuclear pumps using the latest edition of the Code. Since the Codeis limited to pressure-boundary requirements, most of the condi-tions necessary for the satisfactory design of a nuclear pump arenot subjected to Code rules. The design Specification defines theoperational requirements of the pump and is the most importantelement in the function and approval. This chapter not only definesthe applicable Code, but it also explains how these componentsfunction in their applications.

Chapter 13 also discusses the role of the system and componentdesign engineers, as well as the integrity of the Manufacturer. Thechapter provides a historical perspective for the Code rules, cross-referencing other Subsections of the Code. The Owners Res-ponsibilities for the system design plays an important part in

establishing the rules applicable to the Design Specification foreach safety-related pump. A satisfactory pump is a team effort.The authors have drawn upon considerable practical experience intheir discussion on operational and qualification requirements forthe procurement of these pumps from the Manufacturer. They dis-cuss these items for different service conditions with the aide ofschematics and references. Because safety-related Class 1, 2, or 3nuclear pumps often cost from 5 to 15 times as much as theequivalent commercial pump, the system designer should be verycareful not to classify a pump as safety related unless it truly per-forms a safety function. Non-mandatory Appendix U dividespump internal parts into various categories and sets up require-ments for appropriate quality levels. Currently the Working Groupfor Pumps of Section III is in the process of proposing a revisionto Appendix U in order to make it more useful.

Chapter 13 covering both pump and valves was authored forthe first edition by the late Douglas B. Nickerson, who held sev-eral memberships on Code Committees spread over severaldecades. He was associated with the design and qualification ofpumps and valves, a topic that was covered in Chapter 13 for thefirst 3 Editions of the Companion Guide. Marcus Bressler agreedto undertake the updating of Chapter 13 for the Second and ThirdEditions.

The 4th Edition has been reorganized with the pumps nowcovered under Chapter 13 and valves under Chapter 14. Guy A.Jolly volunteered to update Chapter 14 specific to valves for the4th Edition. Much of the commentary in Chapter 14 has beenretained from the Nickerson and Bressler input related to valvesfrom the Chapter 13, 3rd Edition. Douglas discusses those itemsthat are the driving and controlling forces in hydraulic systemsfor nuclear power plants. The valves control the flow throughthese fluid systems and thus the operation of the systems. Fluidsystems have varying degrees of criticality, depending on theirfunction. This commentary explains the relevancy of the ASMECode requirements for safety-related nuclear valves using the lat-est issue of the Code. The Code is limited to pressure-boundaryrequirements. Douglas states that because of this limitation of thescope of the Code, most conditions necessary to the satisfactorydesign of a nuclear valve are not subjected to Code rules. TheDesign Specification specifies operational requirements and thusis the most important element in their function and approval.This commentary not only defines the applicable Code but alsoexplains how these components function in their applications.Chapter 14 also discusses the role of system design and com-ponent design engineers, as well as the integrity of theManufacturer. Douglas provides a historical perspective for theCode rules, cross-referencing other Subsections of the Code. Henotes that Owner’s Responsibilities for system design plays animportant part in establishing the rules applicable to the DesignSpecification for each safety-related valve. Drawing upon consid-erable practical experience, Douglas covers operational and qual-ification requirements for the procurement of these items fromthe Manufacturer. He discusses these items for different serviceconditions with the aid of schematics and references. MarcusBressler, a member of the subgroup on Design since 1974, andChairman of the working group on Valves from 1974 to 1977,provides the background to the development of the design rulesfor valves, and updates the Chapter to the 2007 Edition of theCode. Jolly provides details of the ASME B16.34 historicaldevelopment and provides the current reference dimensionalstandards from the 2010 Code for use in the construction of “N”stamped valves based on the Code’s B16.34 reference. He also


COMPANION GUIDE TO THE ASME BOILER & PRESSURE VESSEL CODE • xlix

provides a list of widely used Valve Standards referenced inASME B31 piping codes. Valves constructed under the scope ofthese standards normally are required to meet the wall thicknessand pressure temperature requirements of ASME B16.34 butinclude other requirements (stem and seat size, stem retentionstructures, packing chamber details, etc.), which have producedvalves that have a successful operational history in the chemical,petroleum and power industries. Imposing the design rules of aselected standard from this group on the non-pressure retainingnuclear valve items could go far in validated the nuclear valvesuccessful functioning in service. These standards could be usedas reference for the writing of a valve Design Specification andconstruction of an “N” stamped valve.

Chapter 15 describes the bases and provisions of the Code forConcrete Reactor Vessels and Containments updating to 2011a CodeEdition. After a short description of the provisions for ConcreteReactor Vessels, the Chapter describes the concrete containment gen-eral environment, types of existing containments, future containmentconfigurations, and background development including the regulatorybases of concrete containment construction code requirements. Thedescription covers sequentially the following topics: Introduction,Concrete Reactor Vessels, Concrete Reactor Containments, Types ofContainments, Future Containments, Regulatory Bases for the CodeDevelopment, Background Development of the Code, ReinforcedConcrete Containment Behavior, Containment Design Analysis andRelated Testing, Code Design Requirements, Fabrication andConstruction, Construction Testing and Examination, ContainmentStructural Integrity Testing, Containment Overpressure Protection,Stamping and Reports, Containment Structure and Aircraft Impact,Containment and Severe Accident Considerations, Other RelevantInformation, Summary and Conclusion.

The basic format of this chapter is kept the same as in the pre-vious editions. The initial edition of this chapter was developedby John D. Stevenson. For this 4th Edition, the updates and addi-tional information relating to the regulatory bases for the coderequirements, future containment designs and considerations forfuture revisions of the Code are based upon contributions fromJoseph F. Artuso, Arthur C. Eberhardt, Michael F. Hessheimer,Ola Jovall and Clayton T. Smith.

In Chapter 16, authored by D. Keith Morton and D. WayneLewis, a commentary is provided regarding the containments usedfor the transportation and storage packaging of spent fuel andhigh-level radioactive material and waste.

In 1997, ASME issued the initial version of Division 3 ofSection III. Before the publication of Division 3, Section III, the Section applicable to the construction of nuclear pressure-retaining components and supports had only two divisions:Division 1, for metal construction, and Division 2, for concreteconstruction. Division 3 was added to cover the containments ofpackaging for nuclear materials. Currently, the scope for Division3 is limited to transportation and storage containments for onlythe most hazardous radioactive materials—namely, spent fuel andother highly radioactive materials, such as high-level waste.Division 3 contains three published subssections: Subsection WAproviding general requirements, Subsection WB addressing rulesfor transportation containments, and Subsection WC addressingstorage containment rules. Under active development is Sub-section WD, which will provide the construction rules applicableto internal support structures (baskets) for the transportation andstorage containments covered by Subsections WB and WC.Consistent with current Code practice, the primary concern ofDivision 3 is the integrity of these containments under design,

operating conditions (including normal, off-normal, and acci-dent), and test conditions. In particular, the structural and leak-integrity of these containments is the focus of the ASME B&PVCode rules. Division 3 is also concerned with certain aspects ofcontainment-closure functionality because of the potential forleakage, which is a key consideration in the containment function.Division 3 covers all construction aspects of the containment,including administrative requirements, material selection, materi-al qualification, design, fabrication, examination, inspection, test-ing, quality assurance, and documentation.

In Chapter 17, authored by D. Keith Morton and Robert I.Jetter, a commentary is provided regarding the development andfirst publication of Section III, Division 5. This new Division wasfirst issued in November 2011. Currently, the scope for Division 5is High Temperature Reactors, addressing both high temperaturegas-cooled reactors and liquid metal reactors. Division 5 identifiesrules based on only two classifications, Class A for safety-relatedcomponents and Class B for non-safety related but with specialtreatment components. Division 5 contains general requirementsfor both metals and graphite in Subsection HA, Subpart A andSubpart B, respectively. Rules for Class A metallic pressureboundary components, Class B metallic pressure boundary com-ponents, and Class A core support structures at both low tempera-ture conditions (under Subpart A) and elevated temperatureconditions (under Subpart B) are contained in Subsections HB,HC, and HG, respectively. Rules for Class A and B metallic sup-ports are contained in Subsection NF, Subpart A. Finally, newrules for non-metallic core support structures (graphite) are con-tained in Subsection HH, Subpart A. Consistent with currentCode practice, the primary concern of Division 5 is the integrityof these components under design, operating conditions (includ-ing normal, upset, emergency, and faulted), and test conditions.Division 5 covers all construction aspects of these components,including administrative requirements, material selection andqualification, design, fabrication, examination, inspection, testing,quality assurance, and documentation.

Chapter 18, was authored by M. A. Malek and John I.Woodworth for the first edition, and co-authored by Geoffrey M.Halley for the Second edition. The third and current fourth editionhas been revised by Edwin A. Nordstrom. In the first edition, thechapter covered Section IV, Rules for Construction of HeatingBoilers, using the 1998 Edition, 1999 Addenda, and Interpre-tations and has now been updated to the 2010 edition. To assistthe reader in understanding and using the Code, this chapter ispresented in a simplified manner, with the understanding that it isnot a Code book and is not written to replace the Code book pub-lished by ASME. A historical perspective of Section IV is provid-ed to trace the criteria covered by the Code. The authors definethe boilers that fall within the jurisdiction of this Section and pro-vide a detailed discussion of the minimum requirements for thesafe design, construction, installation, and inspection of low-pressure-steam boilers and hot-water boilers, which are directlyfired with oil, gas, electricity, or other solid or liquid fuels.However, the authors do not cover the operation, repair, alteration,rerating, and maintenance of such boilers, but they do coverpotable-water heaters and water-storage tanks for operation atpressures not exceeding 160 psi and water temperatures notexceeding 210°F.

In the first edition, Chapter 18 addressed the Code Inter-pretations, the Addenda, and the Code Inquiry procedure as theyrelate to Section IV. The authors mentioned that the format usedfor this chapter is compatible with the format used in Section IV


l • Introduction

(1998 Edition, 1999 Addenda, and Interpretations). For the cur-rent edition using the 2007 Code, this is still valid. For easy iden-tification, the exact numbers of paragraphs, figures, and tablesfrom the Code book have been used in the running text. Theappendices include Method of Checking Safety Valve and SafetyRelief Valve Capacity; Examples of Methods of Calculating aWelded Ring Reinforced Furnace; Examples of Methods ofComputation of Openings in Boiler Shells; Glossary; and twoexamples of Manufacturer’s Data Report Forms.

Chapter 19 provides criteria and commentary for ASME SectionVI, Recommended Rules for the Care and Operation of HeatingBoilers. This chapter that had been initially authored by M. A.Malek was updated for the second edition by Geoffrey M. Halleywith Edwin A. Nordstrom as the author of the current edition.While heating boilers are designed and constructed safely underSection IV, the rules of this Section are nonmandatory guidelinesfor the safe and efficient operation of steam-heating boilers, hot-water-supply boilers, and hot-water-heating boilers after installa-tion. These rules, however, are not applicable to potable-waterheaters. This chapter is divided into nine parts, along with the nec-essary figures and tables for each part: General, covering thescope, use of illustrations, manufacturer’s information, referencesto Section IV, and glossary of terms; Types of Boilers; Accessoriesand Installation; Fuels; Fuel-Burning Equipment and Fuel-BurningControls; Boiler-Room Facilities; Operation, Maintenance, andRepair of Steam Boilers and Hot-Water Boilers; and WaterTreatment. The authors have several years of professional fieldexperience in overseeing Code implementation and are conversantwith regulatory practice; as such, they discuss the jurisdictionalresponsibilities and role of licensing agencies.

The authors note that the format used for this chapter is compati-ble with the format used in Section VI 2007 Code Edition. For easyidentification, the exact numbers of paragraphs, figures, and tablesfrom the Code book have been used in the running text. TheExhibits include the maintenance, testing, and inspection log forsteam-heating boilers and the maintenance, testing, and inspectionlog for hot-water-heating boilers and tests. Bibliographical refer-ences and notes are also provided.

The first edition of Chapter 20, was authored by Harold C.Graber, and the subsequent second edition as well as the currentthird edition have been revised by Jon Batey. The authors discussSection V, Nondestructive Examination (NDE). The purpose ofthis chapter is to provide Users of Section V insight into the sig-nificant requirements, the NDE methods, the NDE methodology,the relationship of Section V with other Code Sections, and theuse of ASTM Standards. The information provided is based onthe 2010 Edition of Section V with 2011 addenda, dated July,2011. The charter and scope of this Section is to develop andmaintain Code rules for NDE methodology and equipmentinvolved with the performance of surface and volumetric testingmethods. These test methods are used for the detection and sizingof defects, discontinuities, and flaws in materials and weldmentsduring the manufacture, fabrication and construction of parts,components, and vessels in accordance with the ASME B&PVCode and other ASME Codes, such as B31.1 (Power Piping).

Harold and Jon provide commentary on the contents of Section V,including Subsection A, which contains Articles and both Mandatoryand Nonmandatory Appendices that address general requirements,test methods, and specific Code requirements and acceptance criteria;and Subsection B, which contains the ASTM Standards adopted bythe ASME B&PV Code. This chapter addresses an audience thatincludes manufacturers (including equipment manufacturers), insur-

ance companies, architect-engineers, research organizations, utilities,consultants, and the National Board. The authors address additions,revisions, inquires, interpretations, and Code Cases relevant toSection V. An important aspect of this chapter is its coverage of theinter-connection of Section V with other Code Sections and Subs-ections. This coverage provides insight into how the relationships ofthe Code Sections are integrated.

VOLUME 2

Chapter 21 initially authored by Urey R. Miller has beenrevised by Thomas P. Pastor for the current fourth edition. Thischapter covers Section VIII—Division 1, Rules for Constructionof Pressure Vessels. The author discusses the historical back-ground of this Section in relation to the construction and safeoperation of boilers and pressure vessels.

Section VIII Division 1 is written to cover a wide range of indus-trial and commercial pressure vessel applications. This Section isapplicable to small compressed air receivers as well as to very largepressure vessels needed by the petrochemical and refining industry.Section VIII Division 1 is intended for the construction of new pres-sure vessels. Miller discusses the applicability of Code and Codejurisdictions, as well as situations of the inapplicability and exemp-tions from this Section. This chapter provides an overview to each of the parts of Section VIII Division 1 Code. The commentaryincludes Subsection A—General Requirements for All Methods ofConstruction and Materials; Subsection B—Requirements Pertainingto Methods of Fabrication of Pressure Vessels; Subsection C—Requirements Pertaining to Classes of Material; Mandatory Appen-dices; Non-Mandatory Appendices; and Bibliography. The intent ofthe author is to provide a broad perspective for the reader to have bet-ter understanding of the Code’s intent, and to point out, by example,some of the subtleties that may not be evident. It is not the objectiveof this Chapter to provide the reader with a detailed “how to” hand-book. The user of the equipment must define the requirements thatare needed for a specific application. With the help of equations,tables, figures and examples Miller provides detailed commentary ofSection VIII, Division 1. He comments about several pertinent CodeInterpretations and Code Cases pertaining to this Section.

There have been a number of significant changes to SectionVIII Division 1 since the First Edition of this Guidebook. Themost significant is that the previously non-mandatory rules fortubesheets (Appendix AA) and flanged and flued expansion joints(Appendix CC) are now mandatory and are in Part UHX andAppendix 5 respectively. Also, a new mandatory appendix (Appendix32) has been added to the Code to allow consideration of localthin spots in shells and heads, and Appendix 33 has been added todefine the standard units to be used in Code equations.

The 2nd Edition of the Guidebook was updated to cover the ongoing Code revisions that affect shell-to-tubesheet joints,Appendix 26 expansion joints, and Appendix M.

The Third Edition of the Guidebook covers revisions to SectionVIII, Division 1 from the 2004 Edition through the 2007 Edition.Included are detailed descriptions of several new NonmandatoryAppendices, including Appendix FF: Guide for the Design andOperation of Quick-Actuating (Quick Opening) Closures, andAppendix GG: “Guidance for the Use of U. S. Customary and SIUnits in the ASME Boiler and Pressure Vessel Code”. ThisChapter also includes extensive updating of referenced figuresand tables from the 2007 Edition of Section VIII, Division 1.

The Fourth Edition of the Guidebook covers revisions toSection VIII, Division 1 from the 2007 Edition, 2008 Addenda


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through the 2010 Edition, 2011 Addenda. Included is a detaileddescription of Code Case 2695 which will allow a Section VIII,Division 1 Certificate Holder to use the design rules of SectionVIII, Division 2 Part 4 for the design of VIII-1 vessel. This CodeCase is groundbreaking in that it represents the first step in along-range plan by the Section VIII Committee to encouragepressure vessel manufacturers to consider using Section VIII,Division 2 for the design of custom engineered vessels. Also cov-ered is the move by ASME to utilize a single mark in place of thecurrent 28 stamps that are used with the different pressure equip-ment accreditation programs. A detailed description of the newPart UIG, Requirements for Pressure Vessels Constructed ofImpregnated Graphite, is provided, as well as the expanded set ofrequirements covering mass production of pressure vessels inAppendix 35. Similar to the Third Edition, numerous Figures andTables have also been updated.

Chapter 22, has been revised by David A. Osage, Clay D.Rodery, Thomas P. Pastor, Robert G. Brown, Philip A. Henry andJames C. Sowinski. The prior edition was completely reviseddetailing the updated technologies and modernization of the 2007Edition of Section VIII, Division 2. This revision covers theupdates made through the 2011 addenda of the 2010 Edition ofSection VIII, Division 2.

Mr. David A. Osage was the lead author for the new standard,and he made significant contributions to the design by rule anddesign by analysis chapters (Parts 4 and 5). He also had responsibil-ity for the assembly of all material that ultimately made up the 9 parts of the new standard: 1. General Requirements, 2. Respon-sibility and Duties, 3. Materials Requirements, 4. Design by RuleRequirements, 5. Design by Analysis Requirements, 6. FabricationRequirements 7. Inspection and Examination Requirements, 8. Pre-ssure Testing Requirements, 9. Pressure Vessel OverpressureProtection.

This chapter provides an overview of the development of thenew standard, its organization, and a detailed description of eachof the nine parts. Emphasis is given to those areas of the standardwhere new technology was introduced.

Chapter 23, authored by J. Robert (Bob) Sims, Jr., discussesSection VIII, Division 3 (Alternative Rules for the Construction ofHigh-Pressure Vessels). It is intended to be used as a companionto the Code by Manufacturers and Users of high-pressure vesselsand also provides guidance to Inspectors, materials suppliers, andothers. The chapter’s text is generally presented in the same orderin which it appears in the Code. Comments are not given abouteach Paragraph, but Paragraph numbers are referenced as appro-priate. The comments apply to the 2010 Edition including the2011 Addenda. The ASME Subgroup on High- Pressure Vessels(SG-HPV) of Subcommittee VIII developed the Code. The com-ments herein are Bob’s opinions; they should not be consideredCode Interpretations or the opinions of the Subgroup on High-Pressure Vessels or any other ASME Committee.

This chapter provides commentary that is intended to aid indi-viduals involved in the construction of high-pressure vessels, butit cannot substitute for experience and judgment. Bob covers gen-eral, material, and design requirements; supplementary require-ments for bolting; special design requirements for layered vessels;design requirements for attachments, supports, and heating andcooling jackets; fracture mechanics evaluation; design using auto-frettage; special design requirements for wirewound vessels andframes; design requirements for openings, closures, heads, bolt-ing, and seals; scope, jurisdiction and organization of Division 3;fatigue evaluation; pressure-relief devices; examination, fabrica-

tion, and testing requirements; marking, stamping, reports, andrecords; and Mandatory and Nonmandatory appendices.

Chapter 24 was previously an Appendix to Part 7, has beenauthored by Roger Reedy. This Chapter written by Roger F.Reedy deals with the Safety of Personnel Using Quick-ActuatingClosures on Pressure Vessels and Associated Litigation Issues.

Chapter 24 was written because of the number of lawsuitsagainst manufacturers of quick-actuating closures on pressurevessels. Often manufacturers are sued even though the closureshad been operating with no accidents for 20 or 30 years. Becauseof Worker’s Compensation rules, the owner of the equipmentoften cannot be sued, so the lawyers search for “deep pockets” tocompensate their clients and themselves. In order to bring forthlitigation, these lawyers would skillfully take words in the Codecompletely out of context. The Appendix is based on Roger’s per-sonal experience in a number of litigations involving quick-actuating closures during the last 25 years. He identifies each ofthe changes made to the Code rules in Section VIII, Division 1,from 1952 to the 2007 Edition of the ASME Code. In every casewhere Roger has testified as an expert witness, the manufacturerof the quick-actuating closure was not at fault, and the ASMECode rules had been properly followed. However, the attorneysfor the injured party often misinterpret the Code rules to accusethe manufacturer of not having complied with the Code when theclosure was made. Based on experience, Roger warns the writersof the ASME Code to assure that the rules are clear, concise andunderstandable to the common man. The most important pointhowever, is for everyone to understand that in order to avoidsevere accidents, users of quick-actuating closures must maintainthe equipment and ensure that inferior components are not used asreplacement parts, and that the design is not modified or changedin any way. The other key element for safety is that owners ofpressure vessels that have quick-actuating closures are responsiblefor training all employees regarding the proper care and use of theequipment. This training has been neglected by the employer inmost accidents.

Further, it is extremely important that the closure and all theequipment associated with the closure be continually maintainedby the user. In almost every litigation associated with quick-actuating closures, the user (company) failed in training employeesand maintaining equipment. In an important New Jersey lawsuit in2011, the jury cleared the manufacturer from any liability for thecause of a worker’s severe injuries, when he improperly forced theclosure open by hammering it with a small sledge hammer.

Chapter 25, authored by Joel G. Feldstein, discusses SectionIX, Welding and Brazing Qualifications. As the title indicates, thischapter deals with the qualification of welding and brazing proce-dures as well as the qualification of individuals performing thoseprocedures as required by the Construction Codes of the ASMEB&PV and Piping Codes. Joel discusses the two-Part organizationof the 2010 Edition of Section IX: Part QW, covering welding,and Part QB, covering brazing. Each Part is divided into fourArticles. The coverage for Part QW includes general requirementsfor both welding procedure and welder performance qualificationand the variables applicable to welding procedure and welder per-formance qualification. Part QB has a similar format: generalrequirements for brazing procedure and brazer performance quali-fication and the variables applicable to brazing procedure andbrazer performance qualification. Commentary is provided on allof the Articles with aid of figures and tables, and Code Inter-pretations are used to provide the Code User with some insightinto the requirements of Section IX. Joel provides a description of


lii • Introduction

the more common welding processes used in Code construction,reviews the qualification rules, provides commentary on thoserequirements, and covers the historical background leading to theincreased use of welding in manufacturing operations. Wherecomments are provided, they represent Joel’s opinions and shouldnot be regarded as the positions of the ASME Code or itsStandard Committee on Welding.

In Chapter 26 Bernard Shelley covers Section X, Fiber-Reinforced Plastic Pressure Vessels, and ASME RTP-1, Rein-forced Thermoset Plastic Corrosion-Resistant Equipment. Theauthor mentions that this chapter is tailored for engineers anddesigners whose experience with vessels is primarily with metalequipment, although he adds that those with experience usingfiberglass equipment but not using Section X or RTP-1 will alsofind this chapter useful, especially its discussions on fiber-reinforced plastic (FRP) technology. Section X has been enactedinto law in 37 jurisdictions in the United States and Canada,whereas RTP-1, although usable as a Code, has been enacted intolaw in only one state (Delaware), and; therefore, at present, it is avoluntary Standard in most jurisdictions. Both Standards governvessels constructed of thermosetting resin reinforced with glassfibers, but Section X addresses vessels reinforced with carbon oraramid fibers as well. The pressure scope of Section X is 15 psiginternal pressure up to 15,000 psig. RTP-1 covers tanks and ves-sels with design pressures of 0 to 15 psig. Both Standards haveprovisions for vessels with external pressures of 0 to 15 psig.

Neither RTP-1 nor Section X is meant to be handbook ortextbook on FRP vessel design. Chapter 27 is intended to be amanual on the use of these documents. An engineer who specifiesan FRP vessel does not need to understand FRP to the sameextent that a vessel designer does; however, in specifying the ves-sel, an engineer necessarily makes many design choices. Berniediscusses the basics of FRP technology; the fabrication methodsand stress analysis of FRP vessels; the scope of Section X andRTP-1; the design qualification of Section X, Class I, Class II,Class III, and RTP-1 vessels; the design qualification overview;Section X example of a Design Specification and its calculations;RTP-1 design examples; and quality assurance of Section X andRTP-1. He provides equations, tables, and figures as well as anno-tated bibliographical notes indicating the relevance of the citedreferences.

In Chapter 27, Owen F. Hedden provides an overview of thestipulations of Section XI, Rules for Inservice Inspection ofNuclear Power Plant Components. A chronological overview ofthe development of Section XI is presented, from its inception in1968 up to the 2010 Edition including 2011a Addenda. Thechapter traces the development, Edition-by-Edition, of importantelements of the Code, including the philosophy behind many ofthe revisions. Emphasis is placed on the 1989 through 2004Editions, for they apply to the majority of plants in the UnitedStates and elsewhere. Through an extensive tabulation of CodeInterpretations, this chapter also attempts to give the Code Usersome insight into clarification of many Section XI requirements.

In the current revisions of Section XI, feedback from operatingplants has resulted in new requirements to address stress corro-sion cracking mechanisms, weld overlay piping repair techniques,and a program for risk-informed piping inspections.

Owen notes that subsequent chapters of this book address themajor areas of Section XI: inservice inspection examination andtest programs, repairs and replacements, acceptance and evaluationcriteria, containment programs, and fatigue crack growth. Non-destructive examination (NDE) is addressed in this chapter, as its

requirements evolve. Owen mentions that Section XI initially hadonly 24 pages in 1970 but that it now has over 700 pages. Althoughoriginally it covered only light-water reactor Class 1 componentsand piping, now it includes Class 2 and Class 3 systems, metal andconcrete containment, and liquid metalcooled reactor plants. Withhis association with Section XI Code Committee activities sincetheir beginning, Owen is in a good position to comment on impor-tant areas that should not be overlooked as well as unimportantareas that should not distract attention.

In Chapter 28, Richard W. Swayne addresses the requirementsof IWA-4000 for repair/replacement (R/R) activities for nuclearpower plant items. Rick examines the background of these R/Ractivities and the changes in R/R activity requirements since theoriginal 1970 Edition, and reviews in detail the requirements inIWA-4000 in the 2011 Addenda of Section XI. This informationis beneficial to personnel performing R/R activities (e.g., design-ing plant modifications, obtaining replacement items, and perform-ing welding, brazing, defect removal, installation, examination, andpressure-testing activities). Although the 2011 Addenda is used todiscuss IWA-4000 requirements, discussions involving earlier edi-tions and addenda of Section XI have been retained from previouseditions of the Companion Guide. The thorough discussion ofchanges from earlier editions and addenda will be very beneficialto personnel using earlier editions and addenda, especially thoseupdating their Repair/Replacement Programs.

In Chapter 28, Mr. Swayne uses his unique professional exper-tise to discuss R/R activity requirements and provides the basisand pertinent explanations for the requirements. The discussion ofthe scope and applicability of Section XI R/R activities is infor-mative to both new and longtime users. Rick notes that Section XIis used in many countries, that it is often recognized as an interna-tional Standard, and has written Chapter 27 such that it appliesregardless of the country where the Section is used. To benefit thereader, numerous Code Interpretations and Code Cases areincluded in this chapter to help clarify and implement R/R activi-ties. Commentary is provided regarding Interpretations that mightbe of great benefit in understanding the Code. With over 25 yearsof association with Code Committee activities, Mr. Swayne pro-vides clarity and in-depth understanding of Section XI.

Chapter 29, authored by Richard W. Swayne, discusses theSection XI rules for inservice inspection and testing of nuclearpower plant components. This chapter covers the general require-ments of Section XI applicable to all Classes of components,including concrete structures and steel vessels, piping, pumps,and valves. It identifies the limits of applicability of Section XI,that is, what is within and outside the scope of the Code.Interfaces with applicable regulatory requirements are addressed,and use of Code Editions, Addenda, and Cases is explained. Mr.Swayne comments on the periodic NDE and pressure testingrequired to ensure integrity of components, other than contain-ment vessels, within the scope of jurisdiction of this Code. Theserequirements include NDE, from personnel qualification to con-duct of the NDE. They also include the type and frequency ofNDE required, including sample expansion and increased fre-quency required because of defect detection.

Mr. Swayne also addresses periodic pressure testing and pres-sure testing following R/R activities. Responsibilities and qualityassurance program requirements of the different entities involvedin examination and testing of a nuclear power plant are discussed.

This chapter addresses many controversial issues and topics ofcurrent concern, including the applicability of recent U.S. NuclearRegulatory Commission (NRC) Generic Letters and Information


COMPANION GUIDE TO THE ASME BOILER & PRESSURE VESSEL CODE • liii

Notices, and describes ways in which readers can use recent revi-sions of Section XI to their advantage. References to ASMEInterpretations are included to explain how the Code requirementscan be applied to common problems. This Edition contains newinformation from Mr. Swayne on risk-informed inservice inspec-tion and reliability integrity management programs for non-light-water reactors.

In Chapter 30, which was originally written by Arthur F.Deardorff, and updated and expanded by Russell C. Cipolla, theflaw acceptance criteria and evaluation methods specified in the2007 Edition through 2010 Edition, 2011 addenda of ASMESection XI Code are discussed. Coverage includes the evaluationof flaws in nuclear power plant components and piping usingASME Section XI procedures. The authors discuss flaw accep-tance criteria based on the use of predefined acceptance standardsand of detailed fracture-mechanics evaluations of flaws. Com-mentary is provided on flaw characterization and acceptance stan-dards, Class 1 vessel flaw evaluation, piping flaw evaluation (foraustenitic and ferritic materials), and evaluation of piping thinnedby flow-assisted corrosion. The authors discuss the backgroundand philosophy of the Section XI approach for evaluating inser-vice degradation, including the rules for inservice inspection ofnuclear power plant components and piping as they relate to thecriteria, to determine if flaws are acceptable for continued opera-tion without the need for repair.

Drawing upon their participation in Code Committees and pro-fessional experience with both domestic and international nuclearplants, the authors discuss step-by-step procedures for the evalua-tion of flaws in austenitic and ferritic components and piping. Theunderlying philosophy of Section XI evaluation of degraded com-ponents is to provide a structural margin consistent with thatwhich existed in the original design and construction code. Russhas expanded the chapter to describe the updated flaw evaluationprocedures for piping, which were added to Section XI in 2002.Also discussed are revised flaw acceptance criteria for Class 1 fer-ritic vessels in IWB-3610, updated structural factors for austeniticand ferritic piping in Appendix C, and revised fatigue crackgrowth reference curves, along with the technical basis for thesechanges.

Russ has also added the historical development and technicalbasis for Appendices E, G and K, which deal with evaluations forfracture prevention during operating plant events/conditions in thefracture-toughness transition temperature region, and at uppershelf. Further, recent Code Cases N-513 and N-705 to Section XIare described, which cover the requirements and procedures fortemporary acceptance of service induced degradation in pipingand vessels in moderate energy Class 2 and 3 systems. The degra-dation can be associated with various mechanisms (cracking, pit-ting, general wall thinning, etc.) and can include through-walldegradation where leakage can be adequately managed via moni-toring. These Cases provide the basis for continued operationuntil repair can be implemented at a later time. In addition, thischapter has been updated to discuss very recent and future devel-opments in flaw evaluation methodologies for components andpiping to include improvements in calculations techniques, mate-rial reference curves, and flaw acceptance criteria.

Wherever possible, the authors cite references to publisheddocuments and papers to aid the reader in understanding thetechnical bases of the specified Code flaw evaluation methods andacceptance criteria. The authors also cite related Section XIrequirements that are discussed in other chapters of the Com-panion Guide.

Chapter 31 originally authored by the late Robert F. Sammataro(a well-known and respected colleague well-versed in ASME Codesand Standards) and now updated by Jim E. Staffiera, addressesSubsections IWE and IWL for nuclear containment vessels.Subsection IWE, Requirements for Class MC and Metallic Linersof Class CC Components of Light-Water Cooled Plants, specifiesrequirements for preservice and inservice examination/inspection,repair/replacement activities, and testing of Class MC (metal con-tainment) pressure-retaining components and their integral attach-ments and repair/replacement activities and testing of Class CC(concrete containment) pressure-retaining components and theirintegral attachments for BWRs and PWRs. Similarly, SubsectionIWL, Requirements for Class CC Concrete Components of Light-Water Cooled Plants, specifies requirements for preservice andinservice examination/inspection, repair/replacement activities, andtesting of the reinforced concrete and the post-tensioning systems ofClass CC (concrete containment) components for BWRs and PWRs.Together with Subsection IWA, General Requirements, a compre-hensive basis is provided for ensuring the continued structural andleak-tight integrity of containments in nuclear power facilities.

Subsections IWE and IWL also provide requirements to ensurethat critical areas of primary containment structures/componentsare inspected to detect degradation that could compromise struc-tural integrity. These two Subsections have received significantattention in recent years since the Nuclear Regulatory Com-mission (NRC) mandated nuclear-industry compliance with thesetwo Subsections of the Code through publication of revisedParagraph 55(a) of Title 10, Part 50, of the Code of FederalRegulations [10 CFR 50.55(a)] in September, 1996. In incorporat-ing these two Subsections into the Regulations, the NRC identi-fied its concern with the increasing extent and rate of occurrenceof containment corrosion and degradation. Since that time,numerous additional changes have taken place in all aspects ofnuclear power plant inservice inspection requirements, not theleast of which have been those for nuclear containment vessels.With increasing emphasis in the nuclear industry on plant life-extension, these changes have resulted in several initiatives cur-rently moving through the ASME Code ‘consensus-committee’process, including action items addressing the need for moreappropriate and effective examinations/inspections and theexpanded use of risk-informed inservice inspection activities.

This updated Chapter 31 introduces the latest Commentariesfor Subsections IWE and IWL, important documents for users ofthe Code because of the background information and technicaljustification provided regarding the reasons for changes made tothese two subsections over the years. As noted in the Introductionto this book, the user is cautioned that these documents are theopinions of individuals only. These documents are not products ofthe ASME Code Committee consensus process, and thus do notrepresent ASME Code Committee positions.

In Chapter 32, Warren H. Bamford discusses the Code evalua-tion of fatigue crack growth, consistent with the evaluation meth-ods of Section XI. Fatigue has often been described as the mostcommon cause of failure in engineering structures, and designersof pressure vessels and piping have incorporated fatigue considera-tions since the first Edition of Section III in 1963. The develop-ment of this technology and its application in Section III isdiscussed in Chapter 39 of third edition; its application in SectionXI is discussed in Chapter 32. With the advancement of the stateof the art has come the capability for allowing the presence of acrack, for predicting crack growth, and for calculating the cracksize that could lead to failure. This capability has been a key aspect


liv • Introduction

of the Section XI flaw evaluation procedures since the 1974 edi-tion of Section XI; it is discussed thoroughly in Chapter 32.

Warren discusses the background of the criteria for fatiguecrack growth analyses and crack growth evaluation methods.Drawing upon his considerable experience in formulating thesecriteria and his professional expertise in these analyses andevaluations, Warren provides commentary on the calculation ofcrack shape changes; calculation of elastic–plastic crack growthwith the aid of crack growth rate reference curves for ferriticand austenitic steels in air environments; and crack growth ratecurves for ferritic and austenitic steels in water environments.He also discusses operating plant fatigue assessment with theaid of Appendix L of Section XI. Also included are discussionspertaining to Appendix A, fatigue evaluation, and flaw toler-ance evaluation. He provides extensive bibliographical notesand references.

Chapter 33, authored by Hardayal Mehta and SampathRanganath, recognized authorities on the Elastic-Plastic FractureMechanics (EPFM), are providing in this chapter a review ofEPFM applications in ASME Section XI Code. The early ASMESection XI flaw evaluation procedures have been typically basedon LEFM. Early progress in the development of EPFM methodol-ogy is first reviewed. A key element in the application of EPFMto flaw evaluation is the estimation of the fracture parameter J-Integral. Therefore, the applied J-Integral estimation methodsdeveloped by EPRI/GE are first reviewed. Basics of the J-T stabil-ity evaluation are then discussed. The first application of EPFMmethodology to flaw evaluation of austenitic piping welds is dis-cussed. The extension of EPFM techniques to flaw evaluations inferritic piping is then covered. Technical background and evolu-tion of Section XI Code Cases (N-463, N-494) and non-mandatoryAppendices (C and H) related to pipe flaw evaluation is thenprovided. Another EPFM based pipe flaw evaluation procedureusing the so-called DPFAD approach is also covered.

Drs. Mehta and Ranganath then describe the application ofEPFM methods to the flaw evaluations of reactor pressure vessel.An early application has been the evaluation of RPVs with pro-jected upper shelf energy less than that required by 10CFR50. Thetechnical background of Section XI Code Case N-512 and non-mandatory Appendix K is provided. Finally, a proposed Code Casecurrently under consideration by appropriate Section XI WorkingGroups, is discussed in detail that would permit the use of EPFMmethodology for RPV flaw evaluations per IWB-3610. The up-dated chapter considers the developments up to 2010 ASME Codeas they relate to EPFM flaw evaluation methods discussed.

The authors have included extensive bibliographical referencesfrom their own publications, research publications, internationaljournals and related EPRI and ASME publications.

Chapter 34, initially authored by Mahendra D. Rana, StanleyStaniszewski provide a Description of Rules of ASME SectionXII covering Transport Tank Code of the 2007 edition.

This chapter was revised by Mahendra D. Rana and StanleyStaniszewski to incorporate the latest Code changes in 2010 edi-tion. This Code provides rules for construction and continued ser-vice of pressure vessels used in transportation of dangerous goodsvia highway, rail, air or water.

The authors provide an overview of Section XII while coveringspecific topics such as the scope and general requirements, mate-rials and design, fabrication, inspection and testing requirements.

The need for a pressure vessel code dealing with the whole spec-trum of tanks to transport dangerous goods was a result of thereview of USDOT (U.S. Department of Transportation) regulations.

The regulations had become cumbersome to use, and in aglobal market without compromising safety the need to make therules for transport tanks acceptable internationally becameurgent. Hence the inaugural edition of ASME’s Section XII focuswas Portable Tanks. The subcommittee prepared the Code to betransparent with existing ASME Code requirements such asSection VIII, Div. 1, while including the existing DOT require-ments that impacted the scope of the charter to prepare theSection XII Code.

This chapter had been coordinated by Mahendra Rana with thehelp of experts covering topics in their respective fields. StanStaniszewski dealt with the scope and general requirements of theCode including rules on pressure relief devices, stamping, markingcertification, reports and records. The scope of the Code applies topressure vessels 450L and above, including additional componentsand criteria addressed in Modal Appendices that are to be usedalong with applicable regulations and laws. Mahendra Rana revisedthe sections on fabrication, inspection and testing requirements ofSection XII 2010 edition. From the perspective of fabrication andinspection, Section XII is a mixture of familiar and new concepts tothe Section VIII Division 1 Boiler and Pressure Vessel Code.Mahendra Rana covered the sections on materials and design rules.The coverage included Design Conditions and Allowable Stresses,Design Temperatures, Design and Allowable Working Pressures,Loadings, Design of Formed Heads, Torispherical Heads, ExternalPressure Design, Flat Heads and Covers, Openings and Rein-forcements, Design of Welded Joints, and Articles covering Por-table Cryogenic Tanks including Materials and Design. The rulesfor fatigue design are also given in the article covering PortableCryogenic Tanks. Information on new coldstreched vessel technol-ogy has been incorporated in this chapter.

Chapter 35 authored by Jimmy Meyer and Joe Frey covers thePower Piping Code. The chapter is based on the 2010 edition ofthe ASME B31.1 Power Piping Code. The chapter is written withthe assumption the reader has the 2010 edition of the PowerPiping Code at hand. The intention of the chapter is to supple-ment and provide additional insight to the proper use of the code.Frequently referenced is how the Power Piping Code interfaceswith other codes and standards, both in the B31 series as well asother ASME, API, AWWA, ASTM, et cetera.

Chapter 36 also authored by Jimmy Meyer covers the ASMEB31.3 Process Piping Code as well as the ASME B31.5Refrigeration, B31.9 Building Services. Also addressed are afew new standards in the ASME B31 series including ASMEB31E Seismic Design, B31J Stress Intensification Factors andB31.T Toughness Requirements. The chapters are written basedon the assumption the various codes are at hand, however forsome of the newer standards, enough information is given toprovide the user a good idea if they are required for theirspecific activities.

Chapter 36A is the largest of the subchapters and it primarilyaddresses the Process Piping Code, however it does give insightinto how the other documents are related and used to supplementthe requirements in ASME B31.3. The object of the chapter is notto repeat the Process Piping Code, but rather to provide additionalinsight into why it is organized the way it is and provide thereader a better understanding of why some of the chapters andrequirements are there. Frequent references are provided for thereader who would like to explore a topic in more depth, likewise anumber of simplified approaches are also provided to help thereader understand the general principles associated with therequirements of the Code(s).


COMPANION GUIDE TO THE ASME BOILER & PRESSURE VESSEL CODE • lv

Chapter 37, new for this Edition and prepared by MichaelRosenfeld, discusses several standards developed for oil, gas, orslurry transportation pipelines. Standards for the design, construc-tion, operation, and maintenance of pipelines are represented byB31.4, B31.8, and B31.11; standards associated with integritymanagement are represented by B31.8-S, B31G, and B31Q. Thetechnical basis for important differences in design principles andpractices between buried transmission pipelines and above-ground piping (embodied in B31.1 and B31.3) is examined inChapter 37. These differences, which arise from the unique needsof pipelines and the environment they operate in, are profoundand include allowable stress levels, material selection, and fabri-cation or installation requirements. It is also noted that the threepipeline standards (B31.4/8/11) address operation and mainte-nance through the full life-cycle of the facility, an importantdistinction from B31.1/3. Each of the pipeline standards(B31.4/8/11), in turn, is tailored to suit the particular needs andattributes of their respective services. They share many similari-ties among each other, but carry important differences as well,which are reviewed.

Finally, pipelines operate in the public. Failures can affect pub-lic safety and the environment, and are not readily tolerated. Aneed and desire by the industry to manage risk in an aging infra-structure has pushed the development of technical standards thatpromote pipeline integrity management. Historically this startedwith B31G, a manual for evaluate the remaining strength of cor-

roded pipelines. More recently, regulatory pressure led to thedevelopment of B31.8-S, a standard for managing gas pipelineintegrity, and B31Q, a standard for pipeline operating personnelqualifications. These standards have gained wide acceptance inthe US and worldwide.

Chapter 38 provides an insight to ASME B31.12 HydrogenPiping and Pipeline Code. This piping/pipeline code is ASME’sfirst design code to be written for a specific fluid service. As suchit provides information about hydrogen system design along withgeneral piping and pipeline system design requirements.

Hydrogen interacts with carbon steel piping and pipeline sys-tems in ways that can result in premature system failure. Thiscode has taken a conservative approach to system design thatwill provide a safe design. Material performance factors havebeen utilized to take into account the effects of hydrogenembrittlement within the range lowest service recommendedservice temperature up to 300°F (150°C) for carbon and lowalloy steels. Currently stainless steels do not have any materialperformance factors provided for their use in hydrogen sys-tems. For service temperatures above 300°F (150°C), API 941should be consulted for assistance in material selection.Engineers are cautioned that hydrogen embrittlement crackingmay occur during shutdown conditions for systems with servicetemperatures above the embrittlement range. The only require-ment for hydrogen embrittlement cracking is tensile stress,hydrogen and time.


ORGANIZATION AND RESPONSIBILITY

In 1911 the ASME set up a committee for the purpose of formu-lating standard rules for the construction of steam boilers and otherpressure vessels. The committee is now known as the ASMEBoiler and Pressure Vessel Committee. From one small group ofseven members in 1911, the Boiler and Pressure Vessel Committeehas grown to a 2011 membership of about 800 volunteers in theoverall committee structure. This consists of the TechnicalOversight Management Committee, ten Standards Committees,anAdministrative Committee, and various subtier committees calledsubcommittees, subgroups, working groups, and special commit-tees. Recent figures show a membership breakdown as follows:there are 31 members of the Technical Oversight ManagementCommittee, about 230 on Standard Committees, and over 1300 onrelated subordinate committees. (The total number of committeepositions is larger than the volunteer membership of 800 becausemany individuals serve on more than one committee.)

At the foundation of the committee structure are the standardcommittees, subcommittees, subgroups and working groups.Typically, these groups are responsible for a specific technicalfield or a specific part of a section of the Code, for example, theSubgroup on Radiography (a Section V subgroup) or theSubgroup on Design (a Section I subgroup). At the StandardsCommittee level, the responsibilities broaden to include a com-plete section of the Code, such as Section I, Power Boilers, or acomplete technical field, such as Section V, NondestructiveExamination. The Standard Committees satisfies the ANSIrequirements as the official “consensus committee”, and areresponsible for every technical action taken by the Boiler andPressure Vessel Committee. They deal with all sections of the

Code, Code Cases, and Interpretations. They also hear appealsarising from technical activities when these matters cannot beresolved at the subcommittee level.

There are four other groups that act in an advisory capacity tothe ten Standards Committees. These are called the ConferenceCommittee, the Marine Conference Group, and the recently intro-duced International Interest Review Group (IIRG) and the ASMEDelegate program described below. These advisory committeesrepresent legal jurisdictions or other authorities that have madethe Code a legal requirement. Each state in the U.S., eachprovince in Canada, and certain large cities that have adopted oneor more sections of the ASME Code and maintain a departmentthat enforces the Code is invited to appoint a representative to acton the Conference Committee. There are about 60 such represen-tatives on the Conference committee. An analogous committee isthe Marine Conference Group, composed of representatives ofmarine interests who promulgate and enforce regulations based onthe ASME Code. All these advisory functions have direct accessto the Standards Committees, and can bring to them any problemswith respect to implementation of Code requirements. They areall entitled to participate in discussion at the Standards Committeeand in voting by letter ballot for items that are receiving first con-sideration (explained below under Voting by the StandardsCommittees). On items receiving reconsideration, such advisoryCommittee members’ participation is limited to discussion, with-out vote. This participation by the regulatory authorities fosterstheir willingness to accept Code rules in their jurisdictions andassists in uniform administration of the Code.

As noted above both the International Interest Review Group(IIRG) and the ASME Delegate programs are recent additions tothe Boiler and pressure Vessel Code Committee. The principalobjectives of these new additions is improved international com-munications and to reduce the barriers to participation in ASMEstandards development activities by people living outside the U.S.and Canada. A delegate is an individual appointed to a committeeor subtier group who represents an organization that is outside theU.S. and Canada, and that is recognized within its country.Members of the group could work in their native language, anddesignate an English-speaking representative as a voting member

ORGANIZATION AND OPERATION OF THE

ASME BOILER AND PRESSURE VESSEL

COMMITTEE

Joel G. Feldstein and Thomas P. Pastor1

1In the initial first edition of this publication this chapter appearing inthe “front matter” was authored by the late Martin D. Bernstein and thesecond edition was updated by Guido G. Karcher. In the third editionGuido Karcher updated this chapter of the “front matter”. Current contribu-tors who updated this chapter of the “front matter” are Joel G. Feldsteinand Thomas P. Pastor.


lviii • Organization and Operation of the ASME Boiler and Pressure Vessel Committee

of an ASME codes and standards committee. These groups couldbe trade organizations such as manufacturers’ associations or usergroups, national standards committees, or organizations responsi-blefor oversight of a particular industry. Delegates may beappointed to any committee, group, or project team needed tosupport the development, update and maintenance of ASMEcodes and standards. The IIRG consists of appointed representa-tives from any national agency that accepts one or more Sectionsof the ASME Boiler and Pressure Vessel Code as a means ofmeeting regulatory requirements for which they have responsibili-ty. Not only does participation give national jurisdictional authori-ties knowledge of proposed changes to the ASME Code, it alsogives them an opportunity to contribute to the process based onthe needs of their industry and their organization’s responsibilityto protect the safety of the public. The balloting and advisoryprivileges of a Delegate and the members of the IIRG are essen-tially identical to the members of the Conference Committee andthe Marine Conference Group.

Many members of ASME and Code Users may not have a clearpicture of its overall organizational structure and just how andwhere the Boiler and Pressure Vessel Committee fit in. In thisregard, the top ASME level of authority is the Board of Governors(BOG). The ASME Council on Standards & Certification reportsdirectly to the BOG. The ASME Boiler and Pressure Vessel Codereports to the Council on Standards & Certification via the Boardon Pressure Technology Codes and Standards and the Board onNuclear Codes & Standards. Major policy and organizationaldecisions and directions are developed at the Board level and theyalso serve as the highest levels for appeals. However the majorityof the technical development and balloting occurs at theStandards Committee level.

The personnel of the Boiler and Pressure Standards Committees,subcommittees, subgroups, and working groups are listed in thefront of all book sections. The Standards Committeesare made upof a cross section of members from each of the subcommittees,subgroups and working groups that report to it. Usually the chair-man and vice chairman of the subordinate groups will be membersof the Standards Committee as well as some other senior membersof the subtier committees. This arrangement of overlapping mem-bership facilitates the work of the Standards Committees since cer-tain members of the Standards Committees are quite familiar withitems originating in their respective subtier committees, and canthus explain and answer questions about the items when theStandards Committees considers them.

A BALANCE OF INTERESTS

Since its inception in 1911 when the Boiler and Pressure VesselCommittee was established, it has been ASME policy that themembers should represent a balance of interests to avoid domina-tion by any one interest group. This is one of the ways by whichthe ASME tries to ensure that actions of a Standards Committeerepresent a valid Technical consensus, fair to all and free of anycommercial bias. Above all, the goal of the Committee is to pro-mote the welfare and safety of the public. In furtherance of thisgoal, each committee member must sign an agreement to adhereto the ASME policy on avoidance of conflict of interest and toconform to the ASME Canon of Ethics. The ASME has alsoestablished procedures to provide for due process in Committeeoperation (e.g. hearings and appeals), thus safeguarding the mem-bers and the ASME against any charges of unfairness.

Members of a Standards Committee are categorized accordingto the interests they represent. ASME has designated 24 cate-gories of interest involved in BPV codes and standards activities.Seventeen of these categories are represented on the ten Boilerand Pressure Vessel Standard Committees:

1 Constructor2 Design/Engineering Organization3 Designer/Constructor 4 General Interest, such as consulting engineers and educators5 Insurance/Inspection6 Laboratories7 Manufacturer 8 Material Manufacturer9 Owner

10 Oil Refining/Production 11 Regulatory, e.g., representatives of local, state, or federal

jurisdictions 12 User, i.e., a user/owner of the products to which the Code

applies 13 Utility, e.g., power plant user/operator14 Wrought Boiler Manufacturer 15 Cast Boiler Manufacturer 16 Water Heater Manufacturer17 Pressure relief Device Manufacturer

Individuals typically become members of a Boiler and PressureVessel Standards Committee by attending committee meetings asguests (meetings are open to the public), by indicating their desireto join, by participating in discussions, and assisting in the techni-cal activities of the committee. There is a practical limit to the sizeof these various active committees, and as openings arise, thechairman chooses members to maintain a balance of interests onthe committees and, also, seeks out individuals with particularexpertise. New members usually start by joining a subgroup orworking group, and as they gain experience in committee opera-tions and demonstrate their ability by contributing their own exper-tise, they eventually move up within the committee organization.Prospective members should be aware that they need employer orpersonal support for committee participation, to cover the traveland time expenses required to participate and attend meetings.

In addition to the many volunteer members of the committee,who are supported in these activities by their companies, theASME maintains a staff of directors and secretaries who facilitatethe work of the committees by managing meeting arrangements,preparation of meeting agenda and minutes, arrangements for pub-lication of the Code, scheduling, record keeping, correspondence,and telephone inquiries from the public. Staff secretaries preparethe agenda and take minutes at the Standards Committee level. Atthe subcommittee, subgroup and working group level, one of thevolunteer members of the committee usually serves as secretary.

THE CODE SECTIONS AND THEIR RELATEDSTANDARD COMMITTEES

The formulation of “standard rules for the construction ofsteam boilers and other pressure vessels” on which the committeestarted in 1911 eventually became the first edition of Section I ofthe ASME Boiler and Pressure Vessel Code, in 1915. That firstedition actually dealt only with boilers. Section VIII, coveringpressure vessels for other than steam, was added later, in 1925, as


COMPANION GUIDE TO THE ASME BOILER & PRESSURE VESSEL CODE • lix

part of the expanding coverage of the Code. (Section VIII nowcovers all kinds of vessels, including those containing steam.)There are now twelve sections of the Code, designated by RomanNumerals I through XII. Section XII is the most recent with theinitial publication issue in 2004 and it covers the design, con-struction, and continued operation of tanks used to carry danger-ous materials by all means of transport. The twelve Sections ofthe Code can be divided into two basic categories which are“product Sections” (i.e., components are constructed to therules), and “reference Sections” (i.e., the rules are used via refer-ence by the product Sections) as shown in Table 1. The varioussections of the ASME Code (sometimes called the book sections)and the committees directly responsible for each are shown inTable 1.

THE SERVICE COMMITTEES

In addition to the ten Standard Committees governing the vari-ous book sections, there is one service committees under the

Technical Oversight Management Committee, called a servicecommittee because it serves the book sections.

The Subcommittee on Safety Valve Requirements (SC-SVR)deals with the design, construction, testing, and certification of thepressure relief devices. There is no separate book section on safetyvalves; each of the product Sections provide appropriate rules forthese devices. Inquiries that pertain to safety valves are usuallyreferred by these book committees to the Subcommittee on SafetyValve Requirements. Actions approved by that committee arereturned to the book committees for further approval and action.

Until 1989, a service committee known as the Subcommitteeon Properties of Metals (SC-P) established the allowable stressfor all the materials used throughout the Code. In 1989, this com-mittee was merged with Subcommittee on Material Specifications(SC II) into a new committee called the Standards Committee onMaterials (SC II), which carries out all the duties formerly han-dled by the two separate committees.

The reference Sections are also used by other pressure equip-ment Codes and Standards such as the B31 Piping Code, B16Components Standards and Bioprocessing Equipment Code.

TABLE 1 THE BOOK SECTIONS MAKING UP THE ASME B&PV CODE

Code Section Governing CommitteeSection I, P Standards Committee on Power Boilers (BPV I)Rules for the Construction of Power Boilers

Section II, R Standards Committee on Materials (BPV II)Materials

Section III, P Standards Committee on Construction of NuclearRules for the Construction of Nuclear Facility Components Facility Components (BPV III)

Section IV, P Standards Committee on Heating Boilers (BPV IV)Heating Boilers

Section V, R Standard Committee on Nondestructive ExaminationNondestructive Examination (BPV V)

Section VI, R Subgroup on Care and Operation of Heating BoilersRecommended Rules for the Care and Operation (of BPV IV)

of Heating Boilers

Section VII, R Subgroup General Requirements (of BPV I)Recommended Guidelines for the Care of Power

Boilers

Section VIII, P Standards Committee on Pressure Vessels (BPV VIII)Rules for the Construction of Pressure Vessels

Section IX, R Standards Committee on Welding and BrazingWelding and Brazing Qualifications (BPV IX)

Section X, P Standards Committee on Fiber-Reinforced PlasticFiber-Reinforced Plastic Pressure Vessels Pressure Vessels (BPV X)

Section XI, P Standards Committee on Nuclear Inservice InspectionRules for Inservice Inspection of Nuclear Power (BPV XI)

Plant Components

Section XII, P Standards Committee on Transport Tanks (BPV XII)Rules for the Construction of and Continued Service

of Transport Tanks

* P denotes a product Code * R denotes a reference Code


lx • Organization and Operation of the ASME Boiler and Pressure Vessel Committee

THE ACCREDITATION COMMITTEES

As explained in the discussion of the various Code symbolstamps in section 1.7.8.3, no organization may do Code workwithout first receiving from the ASME a Certificate ofAuthorization to use one of the Code symbol stamps. The accredi-tation committees issue these certificates to applicants found to bequalified by ASME review teams. The Committee on Boiler &Pressure Vessel Conformity Assessment (CBPVCA) handles thiswork for boiler and pressure vessel activities. The Committee onNuclear Certification (CNC) does the same for nuclear activities.Any disagreements as to the qualifications of applicants and anyallegations of Code violations are dealt with by one or the otherof these two accreditation committees, in deliberations that arenot open to the general public. An ASME Certificate ofAuthorization can be revoked by cause, following hearing andappeal procedures.

COMMITTEE OPERATIONS

Since 1986, the Boiler and Pressure Vessel Committee has hadfour major meetings a year, during four weeks known as Code-weeks. The Committee used to meet six times a year, but decidedto reduce the number of meetings as an economy measure. Thefour meetings are scheduled to result in approximately equal timeintervals between meetings (i.e., February, May, August andNovember). The May meeting (sometimes called the out-of-townmeeting) is held jointly with the annual meeting of the NationalBoard of Boiler and Pressure Vessel Inspectors. The chief inspec-tors of the various states and provinces of Canada who comprisethe membership of the National Board are the top officials whoenforce those sections of the Code that are adopted into the lawsof their jurisdictions. This meeting also provides an opportunityfor them to observe and participate as guests or conference com-mittee members at the various Code committee meetings. TheTechnical Oversight Management Committee always meets onFriday; the Standard Committees meet earlier in the week.Section II, IX, XII and the Accreditation Committees meet onTuesday, Section IV on Wednesday, and Sections I, III, VIII, andXI meet on Thursdays of a Code week. Subgroups and workinggroups usually meet earlier in the week than their parent StandardCommittees. This arrangement facilitates an orderly and timelyflow of information from the subtier committees upward to theStandard Committees.

HOW THE COMMITTEE DOES ITS WORK

The ten Boiler and Pressure Vessel Standard Committeesadminister the Code. The major technical work of the Committeefalls into four categories; providing interpretations of the Code inresponse to inquiries, developing Code Cases, revising the Code,and adding new provisions to it. This work usually starts at thesub-tier levels of the committee structure (i.e., the subgroups andworking groups). Many items (Code changes for instance) requireconsideration by the Standards Committee. Actions of theStandards Committee are subject to approval by one or the otherof the two Boards above the Standards Committee (one fornuclear and the other for non-nuclear items). All proposed,revised or withdrawn standards shall be announced on the ASMEWeb site for public review. A notification shall also be included in

Mechanical Engineering that, at a minimum, directs interestedparties to the ASME Web site for public review announcements,and provides instructions on obtaining hard copies of the publicreview proposals. Since all proposed Code revisions also requireANSI approval, they are also announced in ANSI StandardsAction.

These approval actions by the Supervisory Boards as well asthe public review are conducted concurrently with the StandardsCommittee voting following the respective Standards Committeemeetings. Thus these items have received very careful technicalconsideration within the Committee and are also open to reviewby the public to avoid any inequity, hardship, or other problemthat might result from a Committee action. Any commentsreceived during public review delay an item until the originatingcommittee considers those comments. The several categories ofthe committee work are now described.

CODE INQUIRES AND INTERPRETATIONS

Anyone who has used the Code knows the aptness of the sec-ond paragraph of the preamble to Section I and similar statementsin Sections IV and VIII, Div. 1 & Div. 2: “The Code does not con-tain rules to cover all details of design and construction.” What itcontains rather are many rules for what might be called standardconstruction covering most typical and common constructiondetails. This has evolved over the past 90 plus years as modernboiler and pressure vessel construction have evolved, presentingnew situations, new arrangements, and new equipment. It is thusnot surprising that so many inquiries are received by theCommittee, asking for guidance in the application of specific pro-visions of the Code.

The ASME has established procedures and controls onresponding to inquiries and publishes the questions and replies forthe guidance of all users of the Code. These procedures areintended to protect the committee members and the ASME fromany inference that a specific industry or company has an undueinfluence in the formulation of the questions or replies, or maybenefit to the detriment of others. Sometimes inquirers ask ques-tions that the Committee can’t answer, for various reasons. TheCommittee is not in the business of consulting engineering. Itdoes not have the resources to study plans and details sent in byinquirers and pass judgment on those designs. It also is in no posi-tion to undertake the potential liability for making such judg-ments. Accordingly, the ASME Secretaries use one of four formletters for responding to the most common types of questions con-sidered inappropriate: Indefinite questions that don’t addresssome particular Code requirement; semi-commercial questions;questions that would involve review or approval of a specificdesign; and questions that ask for the basis or rationale of Coderules. These form letters explain that the Committee cannot ordoes not answer such questions and advises the inquirer to poseonly questions that pertain to existing wording and addressingparticular Code requirements, or to make specific recommenda-tions for any proposed Code changes with supporting technicalreasons or data. The committee also issues “intent interpretations”as described below.

In 1983, to reduce the work involved in replying to inquiries,mandatory appendices that give instructions on how to preparetechnical inquiries were added to the various book sections. (See,for example, Appendix I of Section I). Inquiries are supposed tobe sent to the Secretary of the Standards Committee who gives


COMPANION GUIDE TO THE ASME BOILER & PRESSURE VESSEL CODE • lxi

the inquiry an item number and usually reviews the files of previ-ous inquiries to see if the same question or a similar one has pre-viously been answered. If such a reply is found, it is sent to thenew inquirer. If not, there are three ways to handle an interpreta-tion of an inquiry as follows:

• Standards Committee: Interpretations are approved by a voteof the Standards Committee. No member interest categoryshall have a majority on the committee.

• Special Committee: Interpretations may be approved by theunanimous vote of a special committee. Members of the spe-cial committee shall be members of the Standards Committeeresponsible for the standard. No member interest categoryshall have a majority on the special committee. The specialcommittee shall have at least five members, one of whichshall be the ASME staff secretary responsible for the subjectstandard. Special committee members shall be appointed bythe Chair of the Standards Committee.

• Intent Interpretations: The basic objective of an interpretationis to clarify words or requirements that exist in the Code.However in some cases technical inquiries that cannot beanswered on the basis of existing wording of the pertinentstandard may be answered by an “intent” interpretation. Intentinterpretations can answer questions about subjects thataddress industry construction practices not specifically cov-ered in the Code or clarify conflicting or incorrect wording.An intent interpretation shall be submitted to theStandardsCommittee for approval along with a proposed revi-sion(s) to the standard that support the intent interpretation.Both the intent interpretation and the revision(s) to the stan-dard must be approved for the interpretation to be issued.

ASME staff may also offer informal responses to inquiries, as ameans of providing guidance. Such individual responses are notpublished and are accompanied by a statement making it clear thatthey are the opinion of the individual, and not an official interpre-tation. These responses may be either verbal or written. If written,the response shall not be on ASME interpretation letterhead. Afterapproval, all inquiries and replies are published, twice a year, asfurther explained in section 1.3.2 in Chapter 1 of this volume.

ADDITIONS AND REVISIONS OF THE CODE

The Code is subject to continuous change-some provisions arerevised, others deleted, still others added. Although some changesoriginate high in the committee structure (e.g., the mandatoryappendices in each book section on preparation of technicalinquiries), most start at the subtier level, in response to an inquir-er’s request for a change or a request by members of theStandards Committee to clarify, update, or expand existing Codeprovisions.

The development of a Code change follows a path similar tothat of a technical inquiry. Depending on the nature of the work,the cognizant subtier chairman either assigns a Project Manageror a task group to do the work. In appointing the task group, thechairman tries to maintain a balance of interests while makingsure to include members with the specific expertise appropriatefor the task. If and when the subgroup approves the change proposed by the Project Manager or task group, the proposal isforwarded to the Standards Committee for consideration, withdocumentation giving the background of the proposed change.

At this stage consideration of the proposed revision is handleda couple of different ways by the BPV Standard Committees.Some Standard Committees (e.g. BPV I and BPV IV) will reviewa proposal during their open meeting prior to placing the itemonto a ballot for a formal vote. This gives the StandardCommittee members an opportunity to hear from the ProjectManager or Task Group concerning the background for thechange, and gives members the opportunity to ask questions, andin many cases offer both editorial as well as technical improve-ments to the item prior to placing it on the Standards Committeefirst consideration ballot.

For other Standards Committees, such as BPV VIII, proposalsfor revision from subtier committees are immediately placed onfirst consideration ballot by the Standards Committee, ConferenceCommittee and Supervisory Board. The reason BPV-VIII handlestheir work in this manner is that the volume of proposals generat-ed by subtier committees each meeting is so large that it wouldnot be possible to consider presentations on all these items in aone-day meeting during Code week. By having all of the propos-als initially submitted directly to a ballot, many of the simpleritems are approved, and only those items that receive one or morenegatives or significant technical comments are held over to thenext meeting of the Standards Committee for consideration and/orresolution of the negatives. Although all of the BPV StandardsCommittees operate according to a common set of ANSI accredit-ed procedures, there is enough flexibility within these proceduresto allow each committee to manage their workload in a mannerthat assures a high quality technical review as well as efficient useof available resources.

In preparing an item for consideration by the StandardsCommittee, the Project Manager writes a paragraph of back-ground explanation that accompanies each item on the StandardsCommittee letter ballot, in what is called “an action box” for theitem. This explanation may include other technical informationsupporting the proposed action, such as a paper from an ASMEconference describing a new or improved design method. Thisexplanation is very helpful since the first time a StandardsCommittee member sees an item that hasn’t come from his ownsubtier committee is when it appears on the Standards Committeeletter ballot.

Code Cases are issued to clarify the intent of existing require-ments or provide, when the need is urgent, rules for materials orconstructions not covered by existing Code rules. It is a commonpractice to issue a Code Case for new or enhanced materials, test-ing practices, or design methods and then after a trial period theCode Case requirements are incorporated into the Code bookrequirements and the Code Case annulled. Code Cases and theiruse are explained in more detail in section 1.3.3 of Chapter 1 ofthis volume.

ASME WEB SITE TOOLS AND “CODES &STANDARDS CONNECT”

About eleven years ago ASME started an intensive program touse the Internet for managing and coordination C&S activitiesand balloting. This started very basically with what was called theWBPMS (Web-Based Project Management System). TheWBPMS began by supporting Standards Committee balloting andhas since grown into a major tool in the development, coordina-tion and balloting of C&S actions. In September 2004 theWBPMS was changed to “Codes & Standards Connect” and is an


lxii • Organization and Operation of the ASME Boiler and Pressure Vessel Committee

electronic tool used by both Staff and Volunteers to process manycommittee functions.

C&S Connect is currently made up of 12 sections or Tabs, sixof which form the backbone of this system.

1. My Committee Page Tab – Enables access to StandardsCommittee and any subtier group pages. Future meetingdates, minutes, agendas, rosters, etc. can be retrieved fromthis. The charter of the committee and the contact informa-tion of the secretary (ASME staff member) and other inter-esting information are posted on this page.

2. My Items Tab – the “My Items” tab lists all records forwhich the logged-in member is the Project Manager, eitherTechnical or Administrative. Updates can be performedexcept when the item is out for ballot. Responses can be post-ed through this page to comments or negatives during theballot.

3. Ballots Tab – the “Ballots” tab lists all open ballots for thelogged in member. This would include ballots for approvaland also review and comment. Closed ballots may beaccessed through the Search Tab.

4. Search Tab – The “Search” tab is used to locate records, bal-lots and cases by their number or by other criteria such askeyword, project manager name, level, committee, Standard,etc.

5. VCC Tab – The Volunteer Contact Center (VCC) tab pro-vides a method for sending e-mails to other volunteers, com-mittees, or a stored distribution list. So long as volunteersaccurately maintained their profiles, including their currente-mail address, the VCC provides the most efficient, directmethod for sending e-mails concerning committee business.

6. AS-11 Tab – The AS-11 tab allows a volunteer to query theASME membership database and locate contact informationand committee assignments for all volunteers and ASMEstaff.

The C&S Connect has greatly streamlined the standard devel-opment process and allows hundreds of volunteers to more efficiently carry out the work of updating and maintaining the dif-ferent ASME standards. Only Codes & Standards members haveaccess to C&S Connect which can be reached at: www.asme.org/kb/standards/boards-and-committees.

VOTING BY THE STANDARDS COMMITTEE

The Standards Committee letter ballot contains all itemsapproved by the subtier committees that require further approvalby the Standards Committee. This letter ballot is also distributedto the Conference Committee for technical comment. The boilerand pressure vessel items are sent to the Board on PressureTechnology Codes and Standards (BPTCS) and the nuclear itemsare sent to the Board on Nuclear Codes and Standards (BNCS) fortechnical comment. Typical B&PV Standards Committee ballotsare open for thirty days.

All voting on ballots is carried out electronically on C&SConnect, including those committees that are included in the bal-lot for Review and Comment. Members who register a disap-proved vote, must support their negative in writing. The ProjectManager for an item must respond to any comments or negativevotes within the C&S Connect record.

At the close of the letter ballot, the C&S Connect system auto-matically generates a tally of the vote, and determines whether or

not the item is approved based on the voting procedures adoptedby the particular Standards Committee. Items that are notapproved during this first consideration ballot are carried over forconsideration at the next meeting of the Standards Committee.

Items coming before the Standards Committee are consideredwithin two categories: first consideration and reconsideration,usually called second consideration. A new item appearing for thefirst time on a letter ballot is given “first consideration” by theCommittee. Items that did not receive negatives from members ofthe Standards Committee or objections from the advisory commit-tees, BPTCS and BNCS are reported as “approved” at theStandards Committee meeting and require no further action. Asingle negative vote is sufficient to stop a first consideration itemand return it to the originating subtier committee for reconsidera-tion. Technical objections from the advisory committees, BPTCS,and BNCS are treated like negative votes received from membersof the Standards Committee and responses must be provided tothose objections. When a negatively voted item is returned to asubtier committee, several different actions maybe taken. Theitem may be held in abeyance for the time being, with no actiontaken at the subtier committee level, pending further work.

Another possibility is that the subtier committee is not persuad-ed by the reasons given by the negative voter, and at its meetingduring the Code week following the letter ballot the subtier com-mittee responds to that effect, perhaps with rebuttal arguments,and reaffirms its earlier action. In that case the item proceeds tothe Standards Committee meeting , where it is then given what isconsidered “second consideration” (since this is the second timethe Standards Committee has seen the item). During second con-sideration, four negative ballots are required to stop and, in effect,“kill the item”. If the originating subtier committee wants to pur-sue the matter further, it must start all over, usually by makingsufficient revision to satisfy the objections raised. A subsequentappearance of the item would be a new first consideration. On theother hand, if on second consideration an item receives less thanfour negative votes, it is considered approved by the StandardsCommittee, and it proceeds to the next two approval levels, theBPTCS for boiler and pressure vessel items and the BNCS fornuclear items, and public review. At this stage, the only basis for anegative vote at the Board is an assertion that proper procedureshad not been followed by the lower committees.

Most of the items considered by the Standards Committee areproposed changes in the various book sections of the Code. Fairlyregularly, some items fail to pass because of strong objections byother Standards Committee members who perceive the change ashaving negative consequences to safety or representing anunworkable situation when applied to other comparable circum-stances. This is part of the give-and-take of committee actions,which are intended to achieve a technical consensus of the mem-bership, but with concern for safety always being paramount.

DUE PROCESS

Persons who consider themselves injured by an action of theCommittee regarding a technical revision, response to an inquiry,or the refusal to issue a certificate of authorization, can request ahearing to present their side of the story. Such hearings start at theStandards Committee that originated the item. If the StandardsCommittee can’t reach a mutually acceptable solution, the appealmay be submitted to the appropriate supervisory board and, ifnecessary, to the Board on Hearings and Appeals of the Council


COMPANION GUIDE TO THE ASME BOILER & PRESSURE VESSEL CODE • lxiii

on Standards and Certification. This careful attention to dueprocess is the result of an unfortunate event that happened in1971, the infamous Hydrolevel Corporation case. Here is theessence of that case.

Section IV stipulates that boilers must have an automatic low-water fuel cutoff that stops the fuel supply when the surface of thewater falls to the lowest visible part of the water gage glass.Hydrolevel had developed a new probe-type low-water fuel cutoffthat relied on an electrode on the probe. Water covering the elec-trode completed a circuit that maintained fuel flow. When thewater level fell below the electrode and uncovered it, the circuitwas broken and the fuel was stopped.

At that time, another manufacturer dominated the low-waterfuel cutoff market with a float-operated device. That rival manu-facturer happened to have a representative serving as vice-chairmanof the Section IV committee. Court records subsequently showedthat three officers of the rival manufacturer, including that vice-chairman, met with the chairman of the committee to draft aninquiry to the committee. The inquiry asked whether a low-watercutoff with a time-delay feature met the Code. The Section IVchairman at that time had the authority to respond to the inquiryon the ASME’s behalf without the endorsement of the full com-mittee. His letter of response implied that the device did not meetSection IV requirements and would not provide adequate safety.Hydrolevel subsequently alleged that the inquiry was deliberatelyintended to put the probe-type of device in a bad light and thatcopies of the ASME response were used by the rival manufactur-er’s sales force to discredit Hydrolevel’s device. When a formerHydrolevel customer reported this to Hydrolevel in 1972,Hydrolevel complained to the ASME and asked for a clarificationof the ruling. This time the ruling was put before the entireSection IV subcommittee (the vice president of the rival manufac-turer had by this time become chairman of the committee), whereit was reconfirmed, perhaps because of the committee’s belief thatthe Code required the fuel to be cut off as soon as the water levelwas no longer visible in the water gage glass (and not after a timedelay). However, the Standards Committee reversed the rulingand issued an official communication to Hydrolevel saying thatthe Section IV paragraph in question did not prohibit the use oflow-water cutoff with a time delay.

In 1975 Hydrolevel sued the parties, including the ASME,alleging conspiracy in restraint of trade. The other parties settled,but the ASME contested the charge, in the understandable beliefthat it had done no wrong. A district court judge awardedHydrolevel $7.5 million in damages. The ASME appealed, lostthat appeal, and then appealed to the U.S. Supreme Court, whichaffirmed the appellate court’s decision. The essence of the court’sfinding was that the ASME had put certain committee members inpositions where they appeared to represent the ASME and hadthereby conferred on those agents the ASME’s so-called apparentauthority. Even though the ASME is a nonprofit professionalorganization, it was found liable for the willful, anticompetitive,wrongful conduct of its agents. With interest on the triple dam-ages called for by the antitrust act, ASME had to pay almost 10million dollars (in addition, of course, to legal fees). This was aheavy price for an educational nonprofit organization that getsmuch of its financial support from the dues of its members. In anironic twist of fate, the principal owner of Hydrolevel died of aheart attack shortly after hearing the news of the Supreme Courtdecision.

Following that decision, the ASME developed improved proce-dures in an attempt to ensure the fairness of interpretations and to

provide for hearings and appeals for anyone who considers him-self injured by an action of the Code committee, such as anInterpretation or a proposed Code change. These proceduresshould prevent any further cases like the Hydrolevel case.

RESEARCH PROJECTS FOR THEMAINTENANCE AND DEVELOPMENT OFCODES AND STANDARDS

ASME formed the Codes and Standards Technology Institute(CSTI) in November 2001 to ensure that ASME codes and stan-dards committees are provided with a continuing source ofresearch in the technologies that they cover. In August 2004 theASME Standards Technology, LLC (ASME ST-LLC) wasformed, replacing CSTI. ASME ST-LLC is a not-for-profitLimited Liability Company with ASME as the sole member,formed to carry out work related to newly commercialized tech-nology. The ASME ST-LLC mission includes meeting the needsof industry and government by providing new standards-relatedproducts and services, which advance the application of emergingand newly commercialized science and technology and providingthe research and technology development needed to establish andmaintain the technical relevance of codes and standards. Visitwww.stllc.asme.org for more information.

Historically, ASME has periodically identified needs for specif-ic research projects to support the codes and standards develop-ment process. This research was previously performed by outsideorganizations with ASME support. ASME ST-LLC has helpedenhanced the coordination and long range planning and manage-ment of codes and standards development activities whilestrengthening volunteer participation in developing the technolo-gy for codes and standards.

ASME’s approach to standards development for emerging tech-nologies recognizes the important role of technically relevantstandards in advancing the commercialization, enhancing con-sumer confidence, and protecting public health and safety. ASMEST-LLC research and development (R&D) projects strive tobridge the gaps between technology advancement and standardsdevelopment. ASME’s involvement in R&D projects helps pro-duce results that respond to the needs of voluntary consensuscommittees in developing technically relevant codes and stan-dards. ASME identifies and prioritizes R&D needs to help focusthe use of limited resources in these priority areas. Collaborationin R&D projects helps to minimize individual investment whilemaximizing benefits.

As of early 2011, ASME ST-LLC was managing over 40 sepa-rate development projects. Some examples of ASME ST-LLCprojects include the rewrite of ASME Pressure Vessel Code,Section VIII, Division 2, hydrogen infrastructure standards devel-opment, high temperature materials for Generation IV reactors,probabilistic risk assessment (PRA) training development, andfusion magnet code development. Projects can be initiated byanyone, but require a clear scope definition, a legitimate businessneed, establishment of any funding requirements, and identifica-tion of applicable code, standard or committee. Project InitiationRequests can be submitted online at http://stllc.asme.org/Initiate_Project.cfm.

ASME ST-LLC publishes project deliverables as StandardsTechnology Publications (STPs), which are available through theASME Catalog and Digital Store. (http://catalog.asme.org/).


lxiv • Organization and Operation of the ASME Boiler and Pressure Vessel Committee

REALIGNMENT ACTIVITIES OF THE ASMEBOILER AND PRESSURE VESSEL CODECOMMITTEE STRUCTURE

In February 2007 the BNCS and BPTCS approved motions tomove forward with the concept of realigning the ten BPV sub-committees and one B&PV Standards Committees that theyreported to. The need for such realignment was based on theobservations that the organization was strained considering thecurrent climate and projected future workloads in both the nuclearand non-nuclear areas and the need to prepare for the future.Considering this the following Code and Standards vision andmission statements were developed for guidance:

Vision: ASME aims to be the essential resource for mechanicalengineers and other technical professionals throughout the worldfor solutions that benefit humankind.

Mission: ASME’s mission is to serve diverse global com-munities by advancing, disseminating and applying engineeringknowledge for improving the quality of life; and communicatingthe excitement of engineering.

In addition to these global guidance statements the followingspecific categories were also addressed:

• Volunteer work loads • Responsiveness to Industry-Specific Needs • Global Acceptance • Integrity/Credibility of Standards • Turnaround/Cycle Time • Volunteer Recruitment and Retention

Using the above as metrics a facilitated workshop meeting washeld in January 2008 with the participation of a broad cross-section of Volunteer, Regulatory, ASME Staff and Internationalparticipation. The outcome of that workshop and subsequentdeliberations by the BPTCS, BNCS and Council Standards &Certification resulted in the formulation of a plan that would tran-sition the ten BPV Subcommittees that promulgated rules in theASME BPV Code book sections into separate StandardsCommittees each reporting to their respective Boards (BPTCS orBNCS). Between the ten new Standards Committees and theBoards would be a new Technical Oversight ManagementCommittee (see Figure X). This new committee would be respon-sible for:

1) Overseeing technical adequacy and consistency across theBPV Standards Committees,

FIGURE X BOILER AND PRESSURE VESSEL ORGANIZATION

BCA

CNC CBPVCA

BNCS

Sec�on III Sec�on XI

Technical Oversight Management Commi�ee

Joint Project Teams

BPTCS

Safety Valve Requirements

New BPTCS Standards Commi�ees

Service Related

Sec�on II

Sec�on V

Sec�on IX

New BPTCS Standards Commi�eesConstruc�on Related

Sec�on IV

Sec�on I

Sec�on VIII

Sec�on X

Sec�on XII

New BNCS Standards Commi�ees

New BCA Commi�ees


COMPANION GUIDE TO THE ASME BOILER & PRESSURE VESSEL CODE • lxv

2) Provide advice and recommendations to the Boards onstrategic issues and R&D initiatives,

3) Supervise subordinate groups responsible for specializedareas or activity (e.g., Safety Valve requirements)

4) Maintain the Foreword which was common to all the BookSections.

Shortly after the realignment plan was approved a Task Groupwas established to implement the proposed changes with a targetdate of February 2009 (the first meeting date for consideration ofchanges to the next Edition of the Boiler and Pressure VesselCode). The time was needed for development and approval ofcharters for each of the new Standards Committees and TOMC, to

assure that the committees met the required interest-balance of itsmembership and, most importantly, each new StandardsCommittee member understood their voting responsibility as amember of a Standards Committee.

The realignment of the Boiler and Pressure Vessel Committeewas introduced in February 2009 and has been operating success-fully since then. It is felt that this realigned organization structurehas meet the objectives above while continuing to assure safepressure containing structures via ASME C&S and ANSI consen-sus requirements for Codes and Standards. In addition, technicalinterchanges and liaisons between the nuclear and non-nuclearCodes and regulatory organizations (e.g., NRC, National Board,Jurisdictions, etc.) have continued without disruption.


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