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Online Companion Guide to the ASME Boiler & Pressure Vessel CodesAvailable to Purchase
Publisher:
ASME Press
Publication date:
2020

This chapter provides a chronological overview of the development of Section XI, “The Rules for Inservice Inspection of Nuclear Power Plant Components,” from its 1968 inception to the 2019 edition. It traces the development, edition-by-edition, of important Code elements including the philosophy behind many of the revisions. Emphasis is placed on the 2003 Addenda through 2008 Addenda because they apply to a majority of nuclear plants in the United States and in other countries. Through an extensive tabulation of Code Interpretations, this chapter also attempts to give the Code user some insights into clarification of many Section XI requirements. Further insight into the philosophy and technical basis behind Section XI may be gained from review of papers cited in the Bibliography of this chapter.

Subsequent chapters of this book address the major areas of Section XI, including inservice inspection (ISI) examination and test programs, repairs and replacements, acceptance and evaluation criteria, containment programs, and fatigue crack growth. Reference to specific chapters is included as changes to their topics are introduced. Their specific discussions may be easier to follow and will be more complete than the brief chronological development in this chapter. Nondestructive examination is addressed in this chapter as its requirements evolve.

The 2017 and 2019 Editions of the Code provides the basis for changes and additions to this Chapter.

History

The current online edition was updated by Gary Park and Douglas Scarth

1.
WRC 252
,
Adamonis
,
D. C.
, and
Hughes
,
E. T.
(
1979
). “
Ultrasonic Evaluation and Sectioning of PVRC Flat Weld Specimen 201
,”
Welding Research Council, Bulletin 252
,
New York
.
2.
WRC 257
,
Buchanan
,
R. A.
, and
Hedden
,
O. F.
(
1980
). “
Analysis of the Ultrasonic Examinations of PVRC Weld Specimens 155, 202, and 203 by Standard and Two-Point Coincidence Methods
,”
Welding Research Council, Bulletin 257
,
New York
.
3.
Bush
,
S. H.
, “
Reliability of Nondestructive Examination
,”
Chapters 3–5, NUREG CR-3110, NRC
,
1983
.
4.
PISC-II Report No. 5, “Evaluation of the PISC-II Trials Results,”
Programme for the Inspection of Steel Components
,
OECD Nuclear Energy Agency
,
CSNI No. 121
,
Sept.
1986
.
5.
WRC 343
, (
1989
). “
Destructive Examination of PVRC Weld Specimens 202, 203, and 251J
,”
Welding Research Council, Bulletin 343
,
New York
.
6.
Cowfer
,
C. D.
, and
Hedden
,
O. F.
, “
Overview of the ASME Section XI Code Relating to NDE and Ultrasonic Examination Performance Demonstration
,”
Journal of Pressure Vessel Technology
, Vol.
113
,
The American Society of Mechanical Engineers
,
1991
, pp.
170
173
.
7.
Maccary
,
R. R.
,
EPRI NP-1406-SR
, “
Nondestructive Examination Acceptance Standards Technical Basis and Development for ASME Boiler and Pressure Vessel Code Section XI, Division 1
,”
Special Report
,
May
1980
.
8.
WRC 413
, (
1996
). “
Development of Criteria for Assessment of Reactor Vessels with Low Upper-Shelf Fracture Toughness
,”
Welding Research Council, Bulletin 413
,
New York
.
9.
ASME Boiler and Pressure Vessel Code Section XI, Division 1, Code Case N-560
,
Alternative Examination Requirements for Class 1, Category B-J Piping Welds
;
The American Society of Mechanical Engineers
,
New York
,
1996
.
10.
ASME Section XI Working Group on Implementation of Risk-Based Examination, White Paper in Support of Code Case N-716, Report No. 2002-02A-01 Revision 0
, dated
October
2005
.
11.
WRC 382
, (
1993
). “
Nuclear Piping Criteria for Advanced Light Water Reactors, Volume 1—Failure Mechanisms and Corrective Actions
,”
Welding Research Council, Bulletin 382
,
New York
.
12.
API 579-1/ASME FFS-1
,
Fitness-For-Service
; Third Edition,
The American Petroleum Institute and The American Society of Mechanical Engineers
,
June
2016
.
13.
EPRI NP-719-SR, Flaw Evaluation Procedures—ASME Section XI, Special Report
,
Aug.
1978
.
14.
Xu
,
X.S.
,
Lee
,
D.R.
,
Scarth
,
D.A.
and
Cipolla
,
R.C.
, “
Closed-Form Relations for Stress Intensity Factor Influence Coefficients for Axial ID Surface Flaws in Cylinders for Appendix A of ASME Section XI,
Proceedings of the ASME 2014 Pressure Vessels & Piping Division Conference, July 20-24, 2014, Anaheim, California, USA, PVP2014-28222.
15.
Xu
,
X.S.
,
Lee
,
D.R.
,
Scarth
,
D.A.
and
Cipolla
,
R.C.
, “
Update on Stress Intensity Factor Influence Coefficients for Axial ID Surface Flaws in Cylinders for Appendix A of ASME Section XI,
Proceedings of the ASME 2015 Pressure Vessels & Piping Division Conference, July 19-23, 2015, Boston, Massachusetts, USA, PVP2015-46009
.
16.
Xu
,
X.S.
,
Lee
,
D.R.
,
Scarth
,
D.A.
and
Cipolla
,
R.C.
, “
Closed-Form Relations for Stress Intensity Factor Influence Coefficients for Axial Outside Surface Flaws in Cylinders for Appendix A of ASME Section XI,
Proceedings of the ASME 2016 Pressure Vessels & Piping Division Conference, July 17-21, 2016, Vancouver, BC, Canada, PVP2016-64023
.
17.
Lee
,
D.R.
,
Cipolla
,
R.C.
and
Liu
,
M.C.
, “
Stress Intensity Factor Coefficients for Circumferential OD Surface Flaws in Cylinders for Appendix A of ASME Section XI,
Proceedings of the ASME 2018 Pressure Vessels & Piping Division Conference, July 15-20, 2018, Prague, Czech Republic, PVP2018-84381
.
18.
Hojo
,
K.
and
Xu
,
S.X.
, “
Revision to Stress Intensity Factor Equations for ASME Section XI Appendix C-4000, Determination of Failure Mode,
Proceedings of the ASME 2018 Pressure Vessels & Piping Division Conference, July 15-20, 2018, Prague, Czech Republic, PVP2018-85051
.
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