Proposed Rule Draft Regulatory Guide-1342 (RG 1.147, Rev. 19)

U.S. NUCLEAR REGULATORY COMMISSION
DRAFT REGULATORY GUIDE DG-1342
Proposed Revision 19 to Regulatory Guide RG 1.147
Issue Date: August 2018
Technical Lead: Giovanni Facco

INSERVICE INSPECTION CODE CASE ACCEPTABILITY,
ASME SECTION XI, DIVISION 1
A. INTRODUCTION
Purpose
This regulatory guide (RG) lists the American Society of Mechanical Engineers (ASME)
Section XI Code Cases that the U.S. Nuclear Regulatory Commission (NRC) has approved for use as
voluntary alternatives to the mandatory ASME Boiler and Pressure Vessel (BPV) Code provisions that
are incorporated by reference into Title 10, Part 50, of the Code of Federal Regulations (10 CFR Part 50),
“Domestic Licensing of Production and Utilization Facilities” (Ref. 1).
Applicable Rules and Regulations
•

General Design Criterion (GDC) 1, “Quality Standards and Records,” of Appendix A, “General
Design Criteria for Nuclear Power Plants,” to 10 CFR Part 50 requires, in part, that structures,
systems, and components important to safety be designed, fabricated, erected, and tested to
quality standards commensurate with the importance of the safety function to be performed.
Where generally recognized codes and standards are used, Criterion 1 requires that they be
identified and evaluated to determine their applicability, adequacy, and sufficiency and be
supplemented or modified as necessary to ensure a quality product in keeping with the required
safety function.

•

Criterion 30, “Quality of Reactor Coolant Pressure Boundary,” of Appendix A to 10 CFR Part 50
requires, in part, that components that are part of the reactor coolant pressure boundary be
designed, fabricated, erected, and tested to the highest practical quality standards.

•

Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Processing Plants,”
to 10 CFR Part 50 requires, in part, a program for inspection of activities affecting quality to

This RG is being issued in draft form to involve the public in the development of regulatory guidance in this area. It has not received final staff
review or approval and does not represent an NRC final staff position. Public comments are being solicited on this DG and its associated
regulatory analysis. Comments should be accompanied by appropriate supporting data. Comments may be submitted through the Federal
rulemaking Web site, http://www.regulations.gov, by searching for draft regulatory guide DG-1342. Alternatively, comments may be submitted
to the Rules, Announcements, and Directives Branch, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 205550001. Comments must be submitted by the date indicated in the Federal Register notice.
Electronic copies of this DG, previous versions of this guide, and other recently issued guides are available through the NRC’s public Web site
under the Regulatory Guides document collection of the NRC Library at http://www.nrc.gov/reading-rm/doc-collections/reg-guides/. The DG is
also available through the NRC’s Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/readingrm/adams.html, under Accession No. ML18114A225. The regulatory analysis may be found in ADAMS under Accession No. ML18099A041.

verify conformance with documented instructions and procedures.
•

The regulation in 10 CFR 50.55a(g), “Inservice Inspection Requirements,” requires, in part, that
Classes 1, 2, 3, MC, and CC components and their supports meet the requirements of Section XI,
“Rules for Inservice Inspection of Nuclear Power Plant Components,” of the ASME BPV Code
(Ref. 2) or equivalent quality standards.

•

10 CFR 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants” (Ref. 3), Section
10 CFR 52.79(a)(11) requires that, “[The final safety analysis report shall include the following
information:] A description of the program(s), and their implementation, necessary to ensure that
the systems and components meet the requirements of the ASME Boiler and Pressure Vessel
Code and the ASME Code for Operation and Maintenance of Nuclear Power Plants in accordance
with 50.55a of this chapter.”

Related Guidance
•

Regulatory Guide 1.84, “Design, Fabrication, and Materials Code Case Acceptability, ASME
Section III” (Ref. 4), lists the ASME Section III Code Cases that the NRC has approved for use as
voluntary alternatives to the mandatory ASME BPV Code provisions that are incorporated into
10 CFR 50.55a.

•

Regulatory Guide 1.192, “Operation and Maintenance Code Case Acceptability, ASME OM
Code” (Ref. 5), lists the ASME Operation and Maintenance Code (OM Code) Code Cases that
the NRC has approved for use as voluntary alternatives to the mandatory ASME OM Code
provisions that are incorporated into 10 CFR 50.55a.

•

Regulatory Guide 1.193, “ASME Code Cases Not Approved for Use” (Ref. 6), lists the ASME
Section III and Section XI, and ASME OM Code, Code Cases that the NRC has not approved for
generic use.

Purpose of This Regulatory Guide
This RG is incorporated into 10 CFR 50.55a by reference. The RG contains new Code Cases and
revisions to existing Code Cases that the staff has approved for use, as listed in Tables 1 and 2 of this
guide. The rule also states the requirements governing the use of Code Cases. Code Cases approved by
the NRC may be used voluntarily by licensees as an alternative to compliance with ASME Code
provisions that have been incorporated by reference into 10 CFR 50.55a. Because of continuing change
in the status of Code Cases, the staff plans periodic updates to 10 CFR 50.55a and this guide to
accommodate new Code Cases and any revisions of existing Code Cases.

DG-1342, Page 2

Paperwork Reduction Act
This RG provides guidance for implementing the mandatory information collections in 10 CFR
Parts 50 and 52 that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et. seq.). These
information collections were approved by the Office of Management and Budget (OMB), under control
numbers 3150-0011 and 3150-0151. Send comments regarding this information collection to the
Information Services Branch, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by
e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory
Affairs, NEOB-10202 (3150-0011, 3150-0151), Office of Management and Budget, Washington, DC
20503.
Office of the Chief Information Officer (OCIO) will review this paragraph to ensure that the
correct control number is being used. The list of OCIO control numbers are located here:
http://fusion.nrc.gov/ois/team/CSD/FPIB/ICT/Shared Documents/Clearance List.xlsx
Public Protection Notification
The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of
information unless the document requesting or requiring the collection displays a currently valid OMB
control number.

DG-1342, Page 3

B. DISCUSSION
Reason of Revision
Revision 19 of RG 1.147 includes new information reviewed by the NRC that is provided in
Section XI Code Cases listed in Supplement 11 to the 2010 Edition and Supplements 0 through 7 to the
2013 Edition. In addition, there are 6 Code Cases selected from supplements to the 2015 Edition and 2
Code Cases selected from supplements to the 2017 Edition of the ASME BPV Code. This is an update to
RG 1.147, Revision 18, which included information from Supplement 11 to the 2007 Edition and
Supplements 0 through 10 to the 2010 Edition.
Background
Provisions of the ASME BPV Code have been used since 1971 as one part of the framework
to establish the necessary design, fabrication, construction, testing, and performance requirements for
structures, systems, and components important to safety in nuclear power plants. Among other things,
ASME standards committees develop improved methods for the construction and inservice inspection
(ISI) of ASME Class 1, 2, 3, MC (metal containment), and CC (concrete containment) nuclear power
plant components. A broad spectrum of stakeholders participates in the ASME process, which helps to
ensure that the various interests are considered.
The ASME publishes a new edition of the BPV Code, which includes Section XI, every 2 years.
The latest edition of Section XI that the NRC has approved for use is referenced in 10 CFR
50.55a(a)(1)(ii). The ASME also publishes Code Cases quarterly. Code Cases provide alternatives
developed and approved by ASME. This regulatory guide identifies the Code Cases that have been
determined by the NRC to be acceptable alternatives to applicable parts of Section XI. Section XI Code
Cases not yet endorsed by the NRC may be used by a licensee or applicant through 10 CFR 50.55a(z).
That section permits the use of alternatives to the Code requirements referenced in 10 CFR 50.55a
provided that the proposed alternatives result in an acceptable level of quality and safety, and that their
use is authorized by the Director of the Office of Nuclear Reactor Regulation.
The ASME Code is incorporated by reference into 10 CFR 50.55a. Code Cases approved by the
NRC provide an acceptable voluntary alternative to the mandatory ASME Code provisions.
Requirements related to Code Case implementation are provided in 10 CFR 50.55a(b). When a licensee
initially applies a Code Case listed in Tables 1 or 2, the licensee must implement the most recent version
of that Code Case incorporated by reference in 10 CFR 50.55a.

DG-1342, Page 4

Code Cases may be annulled because the provisions have been incorporated into the Code, the
application for which it was specifically developed no longer exists, or experience has shown that an
examination or testing method is no longer adequate. After the ASME annuls a Code Case and the NRC
amends 10 CFR 50.55a and this guide, licensees may not implement that Code Case for the first time.
However, a licensee who implemented the Code Case prior to annulment may continue to use that Code
Case through the end of the present ISI interval. An annulled Code Case cannot be used in the subsequent
ISI interval unless implemented as an approved alternative under 10 CFR 50.55a(z). If a Code Case is
incorporated by reference into 10 CFR 50.55a and later annulled by the ASME because experience has
shown that an examination or testing method is inadequate, the NRC will amend 10 CFR 50.55a and this
guide to remove the approval of the annulled Code Case. Licensees should not begin to implement such
annulled Code Cases in advance of the rulemaking. Notwithstanding these requirements, the Commission
may impose new or revised Code requirements, including implementation schedules, which it determines
are consistent with the Backfit Rule (10 CFR 50.109).
A Code Case may be revised, for example, to incorporate user experience. The older or
superseded version of the Code Case cannot be applied by the licensee or applicant for the first time. If
an applicant or a licensee applied a Code Case before it was listed as superseded, the applicant or the
licensee may continue to use the Code Case until the applicant or the licensee updates its construction
Code of Record (in the case of an applicant, updates its application) or until the licensee’s 120-month
ISI/IST update interval expires, after which the continued use of the Code Case is prohibited unless NRC
approval is granted under 10 CFR Part 50.55a(z). If a Code Case is incorporated by reference into 10
CFR Part 50.55a and later a revised version is issued by the ASME because experience has shown that the
design analysis, construction method, examination method, or testing method is inadequate; the NRC will
amend 10 CFR Part 50.55a and the relevant RG to remove the approval of the superseded Code Case.
Applicants and licensees should not begin to implement such superseded Code Cases in advance of the
rulemaking.
With regard to the use of any Code Case, it is the responsibility of the user to make certain that
the provisions of the Code Case do not conflict with licensee commitments or regulatory requirements.

DG-1342, Page 5

C. REGULATORY POSITION
For Revision 19 of Regulatory Guide 1.147, the NRC reviewed the Section XI Code Cases listed
in Supplement 11 to the 2010 Edition, Supplements 0 through 7 to the 2013. Additionally, there are 6
Code Cases selected from supplements to the 2015 Edition and 2 Code Cases selected from supplements
to the 2017 Edition of the ASME BPV Code. Appendix A to this guide lists the supplements reviewed,
the edition, the supplement number, and the date on which the supplement was approved by the ASME
Board on Nuclear Codes and Standards. Appendix B is a list of the Section XI Code Cases in the 9
supplements and 8 selected Code Cases from the 2015 and 2017 Editions. Finally, Appendix C is a
current list of all Section XI Code Cases. The Code Cases addressed by this regulatory guide are listed in
five tables:
(1)

Table 1, “Acceptable Section XI Code Cases,” lists the Code Cases that are acceptable to the
NRC for implementation in the ISI of light-water-cooled nuclear power plants.

(2)

Table 2, “Conditionally Acceptable Section XI Code Cases,” lists the Code Cases that are
acceptable, provided that they are used with the identified conditions (i.e., the Code Case is
generally acceptable but the NRC has determined that the requirements in the Code Case, which
are an alternative to requirements in the BPV Code, must be supplemented in order to provide an
acceptable level of quality and safety).

(3)

Table 3, “Annulled Unconditionally Approved Section XI Code Cases,” lists Code Cases annulled
by the ASME that the NRC previously determined to be fully acceptable.

(4)

Table 4, “Annulled Conditionally Acceptable Section XI Code Cases,” lists Code Cases that the
NRC determined to be acceptable, provided that they were used with the identified conditions,
but were subsequently annulled by the ASME.

(5)

Table 5, “Section XI Code Cases That Have Been Superseded by Revised Code Cases,” lists
Code Cases that have been superseded through revision.

DG-1342, Page 6

1.

Acceptable Section XI Code Cases

The Code Cases listed in Table 1 are acceptable to the NRC for application in licensee’s
Section XI inservice inspection programs. The 2010 Edition of the ASME BPV Code was published on
July 1, 2010. An addenda was issued in 2011; no addenda was issued in 2012. Beginning with 2013,
new editions of the BPV Code will be issued every two years. Code Cases will continue to be published
quarterly in supplements to each edition. To assist users, new and revised Code Cases are shaded to
distinguish them from those approved in previous versions of this guide. For Code Cases previously
listed in this guide, the third column of Table 1 lists the date of ASME approval. For new or revised
Code Cases, the third column of Table 1 lists the supplement and edition in which each Code Case
was published (e.g., “5/13E” means Code Case Supplement 5 to the 2013 Edition).
Code Cases that the NRC determined to be unacceptable are listed in Regulatory Guide 1.193,
“ASME Code Cases Not Approved for Use.”
Table 1. Acceptable Section XI Code Cases
Code Case
Number

Table 1
Acceptable Section XI Code Cases

Date or
Supplement/
Edition

N-432-1

Repair Welding Using Automatic or Machine Gas Tungsten-Arc Welding
(GTAW) Temper Bead Technique, Section XI, Division 1

3/28/01

N-460

Alternative Examination Coverage for Class 1 and Class 2 Welds,
Section XI, Division 1

2/14/03

N-491-2

Rules for Examination of Class 1, 2, 3, and MC Component Supports of LightWater Cooled Power Plants, Section XI, Division 1

2/14/03

N-494-4

Pipe Specific Evaluation Procedures and Acceptance Criteria for Flaws in
Class 1 Ferritic Piping that Exceed the Acceptance Standards of IWB-3514.2
and in Class 1 Austenitic Piping that Exceed the Acceptance Standards of
IWB-3514.3, Section XI, Division

1/12/05

N-496-2

Helical-Coil Threaded Inserts, Section XI, Division 1

8/04/04

N-513-4

Evaluation of Criteria for Temporary Acceptance of Flaws in Moderate
Energy Class 2 or 3 Piping, Section XI, Division 1

N-517-1

Quality Assurance Program Requirements for Owners, Section XI, Division 1

3/28/01

N-526

Alternative Requirements for Successive Inspections of Class 1 and 2 Vessels,
Section XI, Division 1

8/20/02

N-528-1

Purchase, Exchange, or Transfer of Material Between Nuclear Plant Sites,
Section XI, Division 1

4/19/02

N-532-5

Alternative Requirements to Repair and Replacement Documentation
Requirements and Inservice Summary Report Preparation and Submission as
Required by IWA-4000 and IWA-6000, Section XI, Division 1

1/04/11

DG-1342, Page 7

6/13E

Code Case
Number

Table 1
Acceptable Section XI Code Cases

Date or
Supplement/
Edition

N-537

Location of Ultrasonic Depth-Sizing Flaws, Section XI, Division 1

3/28/01

N-554-3

Alternative Requirements for Reconciliation of Replacement Items and
Addition of New Systems, Section XI, Division 1

2/14/03

N-566-2

Corrective Action for Leakage Identified at Bolted Connections, Section XI,
Division 1

3/28/01

N-567-1

Alternative Requirements for Class 1, 2, and 3 Replacement Components,
Section XI, Division 1

4/19/02

N-573

Transfer of Procedure Qualification Records Between Owners, Section XI,
Division 1

2/14/03

N-586-1

Alternative Additional Examination Requirements for Classes 1, 2, and 3
Piping, Components, and Supports, Section XI, Division 1

5/04/04

N-600

Transfer of Welder, Welding Operator, Brazer, and Brazing Operator
Qualifications Between Owners, Section XI, Division 1

9/18/01

N-609-1

Alternative Requirements to Stress-Based Selection Criteria for Category B-J
Welds, Section XI, Division 1

9/17/10

N-613-2

Ultrasonic Examination of Full Penetration Nozzles in Vessels, Examination
Category B-D, Reactor Nozzle-To-Vessel Welds, and Nozzle Inside Radius
Section Figs. IWB-2500-7(a), (b), (c), and (d), Section XI, Division 1

12/10/10

N-624

Successive Inspections, Section XI, Division 1

4/19/02

N-629

Use of Fracture Toughness Test Data to Establish Reference Temperature for
Pressure Retaining Materials, Section XI, Division 1

8/20/02

N-641

Alternative Pressure-Temperature Relationship and Low Temperature
Overpressure Protection System Requirements, Section XI, Division 1

2/03/03

N-643-2

Fatigue Crack Growth Rate Curves for Ferritic Steels in PWR Water
Environment, Section XI, Division 1

5/04/04

N-649

Alternative Requirements for IWE-5240 Visual Examination, Section XI,
Division 1

3/28/01

N-651

Ferritic and Dissimilar Metal Welding Using SMAW Temper Bead Technique
Without Removing the Weld Bead Crown for the First Layer, Section XI,
Division 1

8/14/01

N-652-2

Alternative Requirements to Categorize B-G-1, B-G-2, and C-D Bolting
Examination Methods and Selection Criteria, Section XI, Division 1

9/3/10

N-653-1

Qualification Requirements for Full Structural Overlaid Wrought Austenitic
Piping Welds, Section XI, Division 1

4/4/12

DG-1342, Page 8

Code Case
Number

Table 1
Acceptable Section XI Code Cases

Date or
Supplement/
Edition

N-658

Qualification Requirements for Ultrasonic Examination of Wrought Austenitic
Piping Welds, Section XI, Division 1

4/4/02

N-661-3

Alternative Requirements for Wall Thickness Restoration of Class 2 and 3
Carbon Steel Piping for Raw Water Service Section XI, Division 1

0/15E

N-663

Alternative Requirements for Classes 1 and 2 Surface Examinations,
Section XI, Division 1

9/17/02

N-664

Performance Demonstration Requirements for Examination of Unclad Reactor
Pressure Vessel Welds, Excluding Flange Welds, Section XI, Division 1

8/20/02

N-665

Alternative Requirements for Beam Angle Measurements Using Refracted
Longitudinal Wave Search Units, Section XI, Division 1

2/28/03

N-683

Method for Determining Maximum Allowable False Calls When Performing
Single-Sided Access Performance Demonstration in Accordance with
Appendix VIII, Supplements 4 and 6, Section XI, Division 1

2/28/03

N-685

Lighting Requirements for Surface Examination, Section XI, Division 1

2/28/03

N-686-1

Alternative Requirements for Visual Examinations, VT-1, VT-2, and VT-3,
Section XI, Division

1/10/07

N-694-2

Evaluation Procedure and Acceptance Criteria for PWR Reactor Vessel Head
Penetration Nozzles, Section XI, Division 1

1/16/13

N-697

Pressurized Water Reactor (PWR) Examination and Alternative Examination
Requirements for Pressure Retaining Welds in Control Rod Drive and
Instrument Nozzle Housings, Section XI, Division 1

11/18/03

N-700

Alternative Rules for Selection of Classes 1, 2, and 3 Vessel Welded
Attachments for Examination, Section XI, Division 1

11/18/03

N-706-1

Alternative Examination Requirements of Table IWB-2500-1 and Table
IWC-2500-1 for PWR Stainless Steel Residual and Regenerative Heat
Exchangers, Section XI, Division 1

1/10/07

N-712

Class 1 Socket Weld Examinations, Section XI, Division 1

5/12/04

N-716-1

Alternative Piping Classification and Examination Requirements, Section XI,
Division 1

1/27/13

N-730-1

Roll Expansion of Class 1 Control Rod Drive Bottom Head Penetrations in
BWRs, Section XI, Division 1

7/16/12

N-731

Alternative Class 1 System Leakage Test Pressure Requirements, Section XI,
Division 1

2/22/05

DG-1342, Page 9

Code Case
Number

Table 1
Acceptable Section XI Code Cases

Date or
Supplement/
Edition

N-733

Mitigation of Flaws in NPS 2 (DN 50) and Smaller Nozzles and Nozzle Partial
Penetration Welds in Vessels and Piping by Use of a Mechanical Connection
Modification, Section XI, Division 1

7/01/05

N-735

Successive Inspection of Class 1 and 2 Piping Welds, Section XI, Division 1

10/12/06

N-739-1

Alternative Qualification Requirements for Personnel Performing Class CC
Concrete and Post-Tensioning System Visual Examinations, Section XI,
Division 1

1/21/07

N-747

Reactor Vessel Head-to-Flange Weld Examinations, Section XI, Division 1

1/13/06

N-753

Vision Tests, Section XI, Division 1

7/14/06

N-762-1

Temper Bead Procedure Qualification Requirements for Repair/Replacement
Activities Without Postweld Heat Treatment, Section XI, Division 1.

N-765

Alternative to Inspection Interval Scheduling Requirements of IWA-2430,
Section XI, Division 1

1/26/09

N-769-2

Roll Expansion of Class 1 In-Core Housing Bottom Head Penetrations in
BWRs, Section XI, Division 1

7/16/12

N-771

Alternative Requirements for Additional Examinations of Class 2 or 3 Items,
Section XI, Division 1

9/8/11

N-773

Alternative Qualification Criteria for Eddy Current Examinations of Piping
Inside Surfaces, Section XI, Division 1

1/26/09

N-775

Alternative Requirements for Bolting Affected by Borated Water Leakage,
Section XI, Division 1

6/24/10

N-776

Alternative to IWA-5244 Requirements for Buried Piping, Section XI,
Division 1

4/9/10

N-786-1

Alternative Requirements for Sleeve Reinforcement of Class 2 and 3
Moderate-Energy Carbon Steel Piping, Section XI, Division 1

4/24/11

N-789-2

Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate
Energy Carbon Steel Piping for Raw Water Service Section XI, Division 1

3/13E

5/15E

N-798

Alternative Pressure Testing Requirements for Class 1 Piping Between the
First and Second Vent, Drain, and Test Isolation Devices, Section XI,
Division 1

12/20/10

N-800

Alternative Pressure Testing Requirements for Class 1 Piping Between the
First and Second Injection Valves, Section XI, Division 1

12/20/10

DG-1342, Page 10

Code Case
Number

Table 1
Acceptable Section XI Code Cases

Date or
Supplement/
Edition

N-803

Similar and Dissimilar Metal Welding Using Ambient Temperature
Automatic or Machine Dry Underwater Laser Beam Welding (ULBW)
Temper Bead Technique, Section XI, Division 1

2/25/11

N-805

Alternative to Class 1 Extended Boundary End of Interval or Class 2 System
Leakage Testing of the Reactor Vessel Head Flange O-Ring Leak-Detection
System, Section XI, Division 1

2/25/11

N-823-1

Visual Examination, Section XI, Division 1

N-825

Alternative Requirements for Examination of Control Rod Drive Housing
Welds, Section XI, Division 1

N-839

Similar and Dissimilar Metal Welding Using Ambient Temperature SMAW
Temper Bead Technique Section XI, Division 1

7/13E

N-842

Alternative Inspection Program for Longer Fuel Cycles Section XI,
Division 1

4/13E

N-845

Qualification Requirements for Bolts and Studs, Section XI, Division 1

5/7/14

N-853

PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection
Weld Metal Buildup for Material Susceptible to Primary Water Stress
Corrosion Cracking Section XI, Division 1

6/15E

N-854

Alternative Pressure Testing Requirements for Class 2 and 3 Components
Connected to the Class 1 Boundary Section XI, Division 1

1/15E

DG-1342, Page 11

4/13E
10/2/13

2.

Conditionally Acceptable Section XI Code Cases

The Code Cases listed in Table 2 are acceptable to the NRC for application in licensee’s
Section XI inservice inspection programs within the limitations imposed by the NRC staff. Unless
otherwise stated, limitations imposed by the NRC are in addition to the conditions specified in the Code
Case. The 2010 Edition of the ASME BPV Code was published on July 1, 2010. An addenda was issued
in 2011; no addenda was issued in 2012. Beginning with 2013, new editions of the BPV Code will be
issued every two years. Code Cases will continue to be published quarterly in supplements to each
edition. To assist users, new and revised Code Cases are shaded to distinguish them from those approved
in previous versions of this guide. The shading will assist in focusing attention during the public
comment period on the changes to the guide. For Code Cases previously listed in this guide, the third
column of Table 1 lists the date of ASME approval. For new or revised Code Cases, the third column of
Table 1 lists the supplement and edition in which each Code Case was published (e.g., “5/10E” means
Code Case Supplement 5 to the 2010 Edition).
Table 2. Conditionally Acceptable Section XI Code Cases
Code Case
Number

Table 2
Conditionally Acceptable Section XI Code Cases
Condition

N-416-4

Alternative Pressure Test Requirement for Welded or Brazed Repairs, Fabrication
Welds or Brazed Joints for Replacement Parts and Piping Subassemblies, or
Installation of Replacement Items by Welding or Brazing, Classes 1, 2, and 3,
Section XI, Division 1

Date or
Supplement/
Edition
1/12/05

Nondestructive examination shall be performed on welded or brazed repairs and
fabrication and installation joints in accordance with the methods and acceptance
criteria of the applicable subsection of the 1992 Edition of Section III.
N-498-4

Alternative Requirements for 10-Year System Hydrostatic Testing for Class 1, 2,
and 3 Systems, Section XI, Division 1
Prior to conducting the VT-2 examination of Class 2 and Class 3 components not
required to operate during normal plant operation, a 10-minute holding time is
required after attaining test pressure. Prior to conducting the VT-2 examination of
Class 2 and Class 3 components required to operate during normal plant
operation, no holding time is required, provided the system has been in operation
for at least 4 hours for insulated components or 10 minutes for non-insulated
components.

DG-1342, Page 12

4/08/02

Code Case
Number

Table 2
Conditionally Acceptable Section XI Code Cases
Condition

N-504-4

Alternative Rules for Repair of Class 1, 2, and 3 Austenitic Stainless Steel Piping,
Section XI, Division 1

Date or
Supplement/
Edition
7/14/06

The provisions of Section XI, Nonmandatory Appendix Q, “Weld Overlay Repair
of Class 1, 2, and 3 Austenitic Stainless Steel Piping Weldments,” must also be
met. In addition, the following conditions shall be met: (a) the sum of laminar
flaw length in any direction shall be less than 10% of the overlay with a total
reduction in area equal to or less than Table IWB-3514-3; (b) the finished overlay
surface shall be 250 micro-in (6.3 micrometers) root mean square or smoother; (c)
the surface flatness shall be adequate for ultrasonic examination; and (d)
radiography shall not be used to detect planar flaws under or masked by laminar
flaws.
N-508-4

Rotation of Serviced Snubbers and Pressure Retaining Items for the Purpose of
Testing, Section XI, Division 1

1/26/09

When Section XI requirements are used to govern the examination and testing of
snubbers and the ISI Code of Record is earlier than Section XI, 2006 Addenda,
Footnote 1 shall not be applied.
N-516-4

Underwater Welding, Section XI, Division 1
(1) Licensees must obtain NRC approval in accordance with 10 CFR 50.55a(z)
regarding the welding technique to be used prior to performing welding on
ferritic material exposed to fast neutron fluence greater than 1 x 1017 n/cm2 (E
> 1 MeV).
(2) Licensees must obtain NRC approval in accordance with 10 CFR 50.55a(z)
regarding the welding technique to be used prior to performing welding on
austenitic material other than P-No. 8 material exposed to thermal neutron
fluence greater than 1 x 1017 n/cm2 (E < 0.5 eV).
(3) Licensees must obtain NRC approval in accordance with 10 CFR 50.55a(z)
regarding the welding technique to be used prior to performing welding on PNo. 8 austenitic material exposed to thermal neutron fluence greater than 1 x
1017 n/cm2 (E < 0.5 eV) and measured or calculated helium concentration of
the material greater than 0.1 atomic parts per million.

DG-1342, Page 13

7/13E

Code Case
Number

Table 2
Conditionally Acceptable Section XI Code Cases
Condition

N-533-1

Alternative Requirements for VT-2 Visual Examination of Class 1, 2, and 3
Insulated Pressure-Retaining Bolted Connections, Section XI, Division 1

Date or
Supplement/
Edition
4/08/02

Prior to conducting the VT-2 examination of Class 2 and Class 3 components not
required to operate during normal plant operation, a 10 minute holding time is
required after attaining test pressure. Prior to conducting the VT-2 examination of
Class 2 and Class 3 components required to operate during normal plant
operation, no holding time is required, provided the system has been in operation
for at least 4 hours for insulated components or 10 minutes for non-insulated
components.
N-552-1

Alternative Methods - Qualification for Nozzle Inside Radius Section from the
Outside Surface, Section XI, Division 1

6/22/12

To achieve consistency with the 10 CFR 50.55a rule change published
September 22, 1999 (64 FR 51370), incorporating Appendix VIII, “Performance
Demonstration for Ultrasonic Examination Systems,” to Section XI, add the
following to the specimen requirements:
“At least 50 percent of the flaws in the demonstration test set must be cracks and
the maximum misorientation must be demonstrated with cracks. Flaws in nozzles
with bore diameters equal to or less than 4 inches may be notches.”
Add to detection criteria, “The number of false calls must not exceed three.”
Note: The above conditions are identical to those imposed on Code Case N-552,
Rev. 16, RG 1.147
N-557-1

In-Place Dry Annealing of a PWR Nuclear Reactor Vessel, Section XI,
Division 1

8/20/02

The secondary stress allowable of 3Sm, shown in Figure 1 of the Code Case, must
be applied to the entire primary plus secondary stress range during the anneal.
N-561-2

Alternative Requirements for Wall Thickness Restoration of Class 2 and High
Energy Class 3 Carbon Steel Piping, Section XI, Division 1
(1) Paragraph 5(b): for repairs performed on a wet surface, the overlay is only
acceptable until the next refueling outage.
(2) Paragraph 7(c): if the cause of the degradation has not been determined, the
repair is only acceptable until the next refueling outage.
(3) The area where the weld overlay is to be applied must be examined using
ultrasonic methods to demonstrate that no crack-like defects exist.
(4) Piping with wall thickness less than the diameter of the electrode shall be
depressurized before welding.

DG-1342, Page 14

1/22/07

Code Case
Number

Table 2
Conditionally Acceptable Section XI Code Cases
Condition

N-562-2

Alternative Requirements for Wall Thickness Restoration of Class 3 Moderate
Energy Carbon Steel Piping, Section XI, Division 1

Date or
Supplement/
Edition
1/22/07

(1) Paragraph 5(b): for repairs performed on a wet surface, the overlay is only
acceptable until the next refueling outage.
(2) Paragraph 7(c): if the cause of the degradation has not been determined, the
repair is only acceptable until the next refueling outage.
(3) The area where the weld overlay is to be applied must be examined using
ultrasonic methods to demonstrate that no crack-like defects exist.
(4) Piping with wall thickness less than the diameter of the electrode shall be
depressurized before welding.
N-569-1

Alternative Rules for Repair by Electrochemical Deposition of Class 1 and 2
Steam Generator Tubing, Section XI, Division 1

4/19/02

NOTES: Steam generator tube repair methods require prior NRC approval
through the Technical Specifications. This Code Case does not address certain
aspects of this repair, e.g., the qualification of the inspection and plugging criteria
necessary for staff approval of the repair method. In addition, if the user plans to
“reconcile,” as described in Footnote 2, the reconciliation is to be performed
in accordance with IWA-4200 in the 1995 Edition, 1996 Addenda of ASME
Section XI.
N-576-2

Repair of Class 1 and 2 SB-163, UNS N06600 Steam Generator Tubing,
Section XI, Division 1

3/16/12

NOTES: Steam generator tube repair methods require prior NRC approval
through the Technical Specifications. This Code Case does not address certain
aspects of this repair, e.g., the qualification of the inspection and plugging criteria
necessary for staff approval of the repair method.
N-583

Annual Training Alternative, Section XI, Division 1

2/14/03

(1) Supplemental practice shall be performed on material or welds that contain
cracks, or by analyzing prerecorded data from material or welds that contain
cracks.
(2) The training must be completed no earlier than 6 months prior to performing
ultrasonic examinations at a licensee’s facility.
N-593-2

Alternative Examination Requirements for Steam Generator Nozzle to Vessel
Welds, Section XI, Division 1
(1) Essentially 100 percent (not less than 90 percent) of the examination volume
A-B-C-D-E-F-G-H must be inspected.
(Note: the above condition is identical to condition on the use of Code Case
N-593, RG 1.147, Rev. 16)
(2) The examination volume specified in Section XI, Table IWB-2500-1,
Examination Category B-D, must be used for the examination of steam
generator nozzle-to-vessel welds at least once prior to using the reduced
examination volume allowed by Code Case N-593-2.
DG-1342, Page 15

11/8/11

Code Case
Number

Table 2
Conditionally Acceptable Section XI Code Cases
Condition

N-597-3

Requirements for Analytical Evaluation of Pipe Wall Thinning, Section XI

Date or
Supplement/
Edition
5/13E

(1) The use of N-597-3 for any degradation mechanisms other than flow
accelerated corrosion is not authorized unless an alternative is proposed and
approved in accordance with 10 CFR 50.55a(z).
(2) Use of Code Case N-597-3 to mitigate Flow Accelerated Corrosion is
authorized subject to the following conditions.
(a) Code Case must be supplemented by the provisions of EPRI Nuclear
Safety Analysis Center Report 202L- 2,“Recommendations for an
Effective Flow Accelerated Corrosion Program” (Ref. 7), April 1999, for
developing the inspection requirements, the method of predicting the rate
of wall thickness loss, and the value of the predicted remaining wall
thickness. As used in NSAC-202L-R2, the term “should” is to be applied
as “shall” (i.e., a requirement).
(b) Components affected by flow-accelerated corrosion to which this Code
Case are applied must be repaired or replaced in accordance with the
construction code of record and Owner’s requirements or a later NRC
approved edition of Section III, “Rules for Construction of Nuclear
Power Plant Components,” of the ASME Code prior to the value of tp
reaching the allowable minimum wall thickness, tmin, as specified
in -3622.1(a)(1) of this Code Case. Alternatively, use of the Code Case is
subject to NRC review and approval per 10 CFR 50.55a(z).
(3) For those components that do not require immediate repair or replacement,
the rate of wall thickness loss is to be used to determine a suitable inspection
frequency so that repair or replacement occurs prior to reaching allowable
minimum wall thickness, tmin.
(4) The evaluation criteria in Code Case N-513-4 may be applied to Code Case
N-597-3 for the temporary acceptance of wall thinning (until the next
refueling outage) for moderate-energy Class 2 and 3 piping.
(5) Code Case N-597-3 shall not be used to evaluate through-wall leakage
conditions.
N-606-2

Similar and Dissimilar Metal Welding Using Ambient Temperature Machine
GTAW Temper Bead Technique for BWR CRD Housing/Stub Tube Repairs,
Section XI, Division 1
Prior to welding, an examination or verification must be performed to ensure
proper preparation of the base metal, and that the surface is properly contoured
so that an acceptable weld can be produced. This verification is to be required in
the welding procedure.

DG-1342, Page 16

2/13E

Code Case
Number

Table 2
Conditionally Acceptable Section XI Code Cases
Condition

N-616

Alternative Requirements for VT-2 Visual Examination of Classes 1, 2, 3
Insulated Pressure Retaining Bolted Connections, Section XI, Division 1

Date or
Supplement/
Edition
4/08/02

(1) Insulation must be removed for VT-2 examination during the system
pressure test for any 17-4 PH stainless steel of 410 stainless steel stud or bolt
aged at a temperature below 1100 °F or with hardness above Rc 30.
(2) For A-286 stainless steel studs or bolts, the preload must be verified to be
below 100 Ksi or the thermal insulation must be removed and the joint
visually examined.
(3) Prior to conducting the VT-2 examination of Class 2 and Class 3 components
not required to operate during normal plant operation, a 10-minute holding
time is required after attaining test pressure. Prior to conducting the VT-2
examination of Class 2 and Class 3 components required to operate during
normal plant operation, no holding time is required, provided the system has
been in operation for at least 4 hours for insulated components or 10 minutes
for non-insulated components.
N-619

Alternative Requirements for Nozzle Inner Radius Inspections for Class 1
Pressurizer and Steam Generator Nozzles, Section XI, Division 1

4/08/02

In lieu of a UT examination, licensees may perform a VT-1 examination in
accordance with the code of record for the Inservice Inspection Program utilizing
the allowable flaw length criteria of Table IWB-3512-1 with limiting assumptions
on the flaw aspect ratio.
N-638-7

Similar and Dissimilar Metal Welding Using Ambient Temperature Machine
GTAW Temper Bead Technique, Section XI, Division 1

2/13E

Demonstration for ultrasonic examination of the repaired volume is required
using representative samples which contain construction type flaws.
N-639

Alternative Calibration Block Material, Section XI, Division 1

8/20/02

Chemical ranges of the calibration block may vary from the materials
specification if (1) it is within the chemical range of the component specification
to be inspected, and (2) the phase and grain shape are maintained in the same
ranges produced by the thermal process required by the material specification.
N-647

Alternative to Augmented Examination Requirements of IWE-2500, Section XI,
Division 1
A VT-1 examination is to be used in lieu of the “detailed visual examination.”
[Note: : Regulatory Guide 1.164, “DEDICATION OF COMMERCIAL-GRADE
ITEMS FOR USE IN NUCLEAR POWER PLANTS” (Ref. 8), which endorses in
part EPRI 3002002982, provides acceptable guidelines for sampling criteria.]

DG-1342, Page 17

11/18/03

Code Case
Number

Table 2
Conditionally Acceptable Section XI Code Cases
Condition

N-648-2

Alternative Requirements for Inner Radius Examination of Class 1 Reactor Vessel
Nozzles, Section XI Division 1

Date or
Supplement/
Edition
7/13E

This Code Case shall not be used to eliminate the preservice or inservice
volumetric examination of plants with a Combined Operating License pursuant to
10 CFR Part 52, or a plant that receives its operating license after October 22,
2015.
N-660

Risk-Informed Safety Classification for Use in Risk-Informed Repair/Replacement
Activities, Section XI, Division 1

7/23/02

The Code Case must be applied only to ASME Code Classes 2 and 3, and nonCode Class pressure retaining components and their associated supports.
N-662-1

Alternative Repair/Replacement Requirements for Items Classified
in Accordance with Risk-Informed Processes, Section XI, Division 1

7/15/11

The Code Case must be applied only to ASME Code Classes 2 and 3, and nonCode Class pressure retaining components and their associated supports.
(Note: this condition is identical to condition on the use of Code Case N-662,
RG 1.147, Rev. 16).
N-666-1

Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI,
Division 1

3/13/12

A surface examination (magnetic particle or liquid penetrant) must be performed
after installation of the weld overlay on Class 1 and 2 piping socket welds.
Fabrication defects, if detected, must be dispositioned using the surface
examination acceptance criteria of the Construction Code identified in the
Repair/Replacement Plan.
(Note: Code Case N-666 was unconditionally approved in Rev. 17, RG 1.147.)
N-695-1

Qualification Requirements for Dissimilar Metal Piping Welds Section XI,
Division 1

0/15E

Inspectors qualified using the 0.25 RMS error for measuring the depths of flaws
using N-695-1 are not qualified to depth-size inner diameter (ID) surface
breaking flaws greater than 50% through-wall in dissimilar metal welds 2.1
inches or greater in thickness. When an inspector qualified using N-695-1
measures a flaw as greater than 50% through-wall in a dissimilar metal weld
from the ID, the flaw shall be considered to have an indeterminate depth.
N-696-1

Qualification Requirements for Mandatory Appendix VIII Piping Examinations
Conducted from the Inside Surface Section XI, Division 1
Inspectors qualified using the 0.25 RMS error for measuring the depths of flaws
using N-696-1 are not qualified to depth-size inner diameter (ID) surface
breaking flaws greater than 50% through-wall in welds 2.1 inches or greater in
thickness. When an inspector qualified using N-696-1 measures a flaw as
greater than 50% through-wall in a weld from the ID, the flaw shall be
considered to have an indeterminate depth.
DG-1342, Page 18

6/13E

Code Case
Number

Table 2
Conditionally Acceptable Section XI Code Cases
Condition

N-702

Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius
and Nozzle-to-Shell Welds, Section XI, Division 1

Date or
Supplement/
Edition
2/20/04

The applicability of Code Case N-702 for the first 40 years of operation must be
demonstrated by satisfying the criteria in Section 5.0 of NRC Safety Evaluation
regarding BWRVIP-108 dated December 18, 2007 (ML073600374) or Section
5.0 of NRC Safety Evaluation regarding BWRVIP-241 dated April 19, 2013
(ML13071A240).
The use of Code Case N-702 in the period of extended operation is prohibited.
If VT-1 is used, it shall utilize ASME Code Case N-648-2, “Alternative
Requirements for Inner Radius Examination of Class 1 Reactor Vessel Nozzles,
Section XI Division 1,” with associated required conditions specified in
Regulatory Guide 1.147.
Note: This code case was previously approved with conditions, the conditions
have been revised for Revision 19 of Reg. Guide 1.147.
N-705

Evaluation Criteria for Temporary Acceptance of Degradation in
Moderate Energy Class 2 or 3 Vessels and Tanks Section XI, Division 1

11/10E

The ASME Code repair or replacement activity temporarily deferred under the
provisions of this Code Case shall be performed during the next scheduled
refueling outage. If a flaw is detected during a scheduled shutdown, an ASME
code repair is required before plant restart.
Note: This code case was previously approved with no conditions, this a new
condition for Revision 19 of Reg. Guide 1.147.
N-711-1

Alternative Examination Coverage Requirements for Examination Category BF, B-J, C-F-1, C-F-2, and R-A Piping Welds Section XI, Division 1
Code Case N-711-1 shall not be used to redefine the required examination
volume for preservice examinations or when the postulated degradation
mechanism for piping welds is PWSCC, Intergranular Stress Corrosion
Cracking (IGSCC) or crevice corrosion (CC) degradation mechanisms.

DG-1342, Page 19

0/17E

Code Case
Number

Table 2
Conditionally Acceptable Section XI Code Cases
Condition

N-749

Alternative Acceptance Criteria for Flaws in Ferritic Steel Components
Operating in the Upper Shelf Temperature Range, Section XI, Division 1

Date or
Supplement/
Edition
3/16/12

In lieu of the upper shelf transition temperature, Tc, as defined in the Code Case,
the following shall be used:
Tc = 154.8 °F + 0.82 × RTNDT (in U.S Customary Units), and
Tc = 82.8 °C + 0.82 × RTNDT (in SI Units).
Tc is the temperature above which the elastic plastic fracture mechanics (EPFM)
method must be applied. Additionally, the NRC defines temperature Tc1 below
which the linear elastic fracture mechanics (LEFM) method must be applied:
Tc1 = 95.36 °F + 0.703 × RTNDT (in U.S Customary Units), and
Tc1 = 47.7 °C + 0.703 × RTNDT (in SI Units).
Between Tc1 and Tc, while the fracture mode is in transition from LEFM to
EPFM, users should consider whether or not it is appropriate to apply the EPFM
method. Alternatively, the licensee may use a different Tc value if it can be
justified by plant specific Charpy curves.
N-751

Pressure Testing of Containment Penetration Piping, Section XI, Division 1

8/03/06

When a 10 CFR 50, Appendix J, Type C test is performed as an alternative to
the requirements of IWA-4540 (IWA-4700 in the 1989 edition through the 1995
edition) during repair and replacement activities, nondestructive examination
must be performed in accordance with IWA-4540(a)(2) of the 2002 Addenda of
Section XI.
N-754-1

Optimized Structural Dissimilar Metal Weld Overlay for Mitigation of PWR
Class 1 Items, Section XI, Division 1
(1) The conditions imposed on the optimized weld overlay design in NRC
safety evaluation for the topical report, “Materials Reliability Program
(MRP): Technical Basis for Preemptive Weld Overlays for Alloy 82/182
Butt Welds in PWRs (MRP-169),” Revision 1-A, Electric Power Research
Institute (ADAMS Accession Nos. ML101620010 and ML101660468)
must be satisfied.
(2) In lieu of the pre-service and inservice examinations as specified in Section
3(c) of the code case, the optimized weld overlay must be examined in
accordance with 10 CFR 50.55a(g)(6)(ii)(F).
(3) The optimized weld overlay in this code case can only be installed on an
Alloy 82/182 weld where the outer 25 percent of weld wall thickness does
not contain indications that are greater than 1/16 inch in length or depth.

DG-1342, Page 20

1/13E

Code Case
Number

Table 2
Conditionally Acceptable Section XI Code Cases
Condition

N-766-1

Nickel Alloy Reactor Coolant Inlay and Onlay for Mitigation of PWR Full
Penetration Circumferential Nickel Alloy Dissimilar Metal Welds in Class 1
Items, Section XI, Division 1

(2)
(3)

(4)
(5)

N-778

Date or
Supplement/
Edition
1/13E

(1) Credit cannot be taken to reduce preservice and inservice inspection
requirements specified by this Code Case on an inlay or onlay if an
inlay or onlay is applied to an Alloy 82/182 dissimilar metal weld which
contains an axial indication that has a depth of more than 25 percent of
the pipe wall thickness and a length of more than half axial width of the
dissimilar metal weld, or a circumferential indication that has a depth of
more than 25 percent of the pipe wall thickness and a length of more
than 20 percent of the circumference of the pipe.
In lieu of paragraph 2(e) of the code case, pipe with any thickness of inlay or
onlay must be evaluated for weld shrinkage, pipe system flexibility, and
additional weight of the inlay or onlay.
If an inlay or onlay is applied to an Alloy 82/182 dissimilar metal weld which
contains an indication that exceeds the acceptance standards of IWB-3514 and
is accepted for continued service in accordance with IWB-3132.3 or IWB3142.4, the subject weld must be inspected in three successive examinations
after inlay or onlay installation.
Any detectable subsurface indication discovered by eddy current testing in the
inlay or onlay during acceptance examinations is prohibited to remain in
service.
The flaw analysis of paragraph 2(d) of the case shall also consider primary
water stress corrosion cracking growth in the circumferential and axial
directions, in accordance with IWB-3640.

Alternative Requirements for Preparation and Submittal of Inservice Inspection
Plans, Schedules, and Preservice and Inservice Inspection Summary Reports,
Section XI, Division 1

12/29/05

Licensees must submit the following reports to the regulatory authority:
1) The preservice inspection summary report must be submitted prior to the
date of placement of the unit into commercial service.
2) The inservice inspection summary report must be submitted within 90
calendar days of the completion of each refueling outage.
N-795

Alternative Requirements for BWR Class 1 System Leakage Test Pressure
Following Repair/Replacement Activities, Section XI, Division 1
1) The use of nuclear heat to conduct the BWR Class 1 system leakage test is
prohibited (i.e., the reactor must be in a non-critical state), except during
refueling outages in which the ASME Section XI Category B-P pressure
test has already been performed, or at the end of mid-cycle maintenance
outages fourteen (14) days or less in duration.
2) The test condition holding time, after pressurization to test conditions, and
before the visual examinations commence, shall be 1 hour for non-insulated
components.

DG-1342, Page 21

9/17/10

Code Case
Number

Table 2
Conditionally Acceptable Section XI Code Cases
Condition

N-799

Dissimilar Metal Welds Joining Vessel Nozzles to Components, Section XI,
Division 1

Date or
Supplement/
Edition
12/20/10

1) The gap between the ultrasonic probe and component surface shall not
exceed 1/32 in. If the gap exceeds 1/32 in., the weld shall be considered to
be unexamined unless the examination technique is successfully
demonstrated on representative mockups.
2) The following requirements must be implemented when applying this Code
Case to ensure that welds are adequately inspected:
a. Examination requirements of Section XI, Mandatory Appendix I,
paragraph I-3200(c) must be applied.
b. Ultrasonic depth and sizing qualifications for cast austenitic stainless
steel components must follow Appendix VIII, Supplement 10, using
representative cast austenitic stainless steel mockups containing
representative cracks and be independent of other Supplement 10
qualifications.
c. Cracks detected and not depth sized to Appendix VIII type
performance-based procedures, equipment, and personnel qualifications
shall be repaired or removed.
N-824

Ultrasonic Examination of Cast Austenitic Piping Welds From the Outside
Surface, Section XI, Division 1
1.

2.

N-829

11/10E

Instead of Paragraph 1(c)(1)(–c)(–2), licensees shall use a phased array
search unit with a center frequency of 500 kHz with a tolerance of ± 20
percent.
Instead of Paragraph 1(c)(1)(–d), the phased array search unit must produce
angles including, but not limited to, 30 to 55 degrees with a maximum
increment of 5 degrees.

Austenitic Stainless Steel Cladding and Nickel Base Cladding Using Ambient
Temperature Machine GTAW Temper Bead Technique Section XI, Division 1

0/13E

The provisions of 3(e)(2) or 3(e)(3) may only be used when it is impractical to
use the interpass temperature measurement methods described in 3(e)(1), such
as in situations where the weldment area is inaccessible (e.g., internal bore
welding) or when there are extenuating radiological conditions.
N-830

Direct Use of Master Fracture Toughness Curve for Pressure Retaining
Materials of Class 1 Vessels Section XI

7/13E

Use of Code Case N-830 Paragraph (f), which provides an alternative to limiting
the lower shelf of the 95 percent lower tolerance bound Master Curve toughness,
KJC-lower 95%, to a value consistent with the current KIC curve, is prohibited.
N-831

Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic Pipe,
Section Xl, Division 1
Code Case N-831 is prohibited for use in new reactor construction.

DG-1342, Page 22

0/17E

Code Case
Number

Table 2
Conditionally Acceptable Section XI Code Cases
Condition

N-838

Flaw Tolerance Evaluation of Cast Austenitic Stainless Steel Piping Section XI,
Division 1

Date or
Supplement/
Edition
2/15E

Code Case N-838 shall not be used to evaluate flaws in cast austenitic stainless
steel piping where the delta ferrite content exceeds 25 percent.
N-843

Alternative Pressure Testing Requirements Following Repairs or Replacements
for Class 1 Piping between the First and Second Inspection Isolation Valves,
Section XI, Division 1

4/13E

If the portions of the system requiring pressure testing are associated with more
than one safety function, the pressure test and visual examination VT-2 shall be
performed during a test conducted at the higher of the operating pressures for
the respective system safety functions.
N-849

In-situ VT-3 Examination of Removable Core Support Structures Without
Removal Section XI
(1) The use of Code Case N-849 is limited to plants that are designed with
accessible core support structures to allow for in-situ inspection.
(2) Prior to initial plant start-up, the VT-3 examination shall be performed with
the core support structure removed, as required by ASME Section XI, IWB2500-1, and shall include all surfaces that are accessible when the core support
structure is removed, including all load bearing and contact surfaces.

DG-1342, Page 23

7/13E

3.

Annulled Unconditionally Approved Section XI Code Cases

The Code Cases listed in Table 3 were previously unconditionally approved by the NRC and have
been annulled by the ASME.
Table 3. Annulled Unconditionally Approved Section XI Code Cases
Code Case
Number

Table 3
Annulled Unconditionally Approved Section XI Code Cases

Annulment
Date

N-34
(1551)

Inservice Inspection of Welds of Nuclear Components, Section XI

N-72
(1646)

Partial Postponement of Category B-C Examination for Class 1 Components,
Section XI

1/1/81

N-73
(1647)

Partial Postponement of Category B-D Examination for Class 1 Components,
Section XI

1/1/81

N-98
(1705-1)

Ultrasonic Examination - Calibration Block Tolerances, Section XI, Division 1

8/9/96

N-112
(1730)

Acceptance Standards for Class 2 and 3 Components, Section XI, Division 1

7/1/79

N-113-1

Basic Calibration Block for Ultrasonic Examination of Weld 10 in. to 14 in.
Thick, Section XI, Division 1

8/9/96

N-167
(1804)

Minimum Section Thickness Requirements for Repair of Nozzles, Section XI,
Division 1

1/14/80

N-198-1

Exemption from Examination for ASME Class 1 and 2 Piping Located at
Containment Penetrations, Section XI, Division 1

3/28/01

N-211

Recalibration of Ultrasonic Equipment Upon Change of Personnel, Section XI,
Division 1
(The Code Case was annulled on 3/20/81 and reinstated on 7/13/81. There was
no change in the Code Case, and the NRC considers that the Code Case was in
effect during the period 3/20/81 through 7/13/81)

4/30/93

N-216

Alternative Rules for Reactor Vessel Closure Stud Examination, Section XI,
Division 1

5/7/90

N-234

Time Between Ultrasonic Calibration Checks, Section XI, Division 1

12/3/90

N-235

Ultrasonic Calibration Checks per Section V, Section XI,
Division 1

8/9/96

N-236-1

Repair and Replacement of Class MC Vessels, Section XI,
Division 1

8/5/97

N-288

Hydrostatic Test Requirements for Class 1 and Class 2 Components, Section
XI, Division 1

5/25/83

DG-1342, Page 24

11/20/81

Code Case
Number

Table 3
Annulled Unconditionally Approved Section XI Code Cases

Annulment
Date

N-306

Calibration Block Material Selection, Appendix 1, 1-3121,
Section XI, Division 1

5/7/90

N-307-3

Revised Ultrasonic Examination Volume for Class 1 Bolting, Table
IWB-2500-1, Examination Category B-G-1, When the Examinations Are
Conducted from the End of the Bolt or Stud or from the Center-Drilled Hole,
Section XI, Division 1

1/21/07

N-308

Documentation of Repairs and Replacements of Components in Nuclear Power
Plants, Section XI, Division 1

9/30/90

N-311

Alternative Examination of Outlet Nozzle on Secondary Side of Steam
Generators, Section XI, Division 1

11/18/03

N-322

Examination Requirements for Integrally Welded or Forged Attachments to
Class 1 Piping at Containment Penetrations,
Section XI, Division 1

2/14/03

N-323-1

Alternative Examination for Welded Attachments to Pressure Vessels, Section
XI, Division 1

1/21/07

N-334

Examination Requirements for Integrally Welded or Forged Attachments to
Class 2 Piping at Containment Penetrations, Section XI, Division 1

7/14/06

N-335-1

Rules for Ultrasonic Examination of Similar and Dissimilar Metal Piping
Welds, Section XI, Division 1

5/11/97

N-343

Alternative Scope of Examination of Attachment Welds for Examination
Categories B-H, B-K-1, and C-C, Section XI,
Division 1

12/3/90

N-355

Calibration Block for Angle Beam Ultrasonic Examination of Large Fittings in
Accordance with Appendix III-3410, Section XI,
Division 1

8/9/96

N-356

Certification Period for Level III NDE Personnel, Section XI,
Division 1
(Note: July 1, 1988, is the date that the provisions of the Code Case were
acceptable to the NRC.)

8/5/97

N-375-2

Rules for Ultrasonic Examination of Bolds and Studs, Section XI, Division 1

5/7/90

N-389-1

Alternative Rules for Repairs, Replacements, or Modifications,
Section XI, Division 1

4/19/02

N-401-1

Eddy Current Examination, Section XI, Division 1

5/11/97

N-402-1

Eddy Current Calibration Standards, Section XI, Division 1

5/11/97

N-406

Alternative Rules for Replacement, Section XI, Division 1

5/7/90

N-408-3

Alternative Rules for Examination of Class 2 Piping, Section XI, Division 1

4/19/02

DG-1342, Page 25

Code Case
Number

Table 3
Annulled Unconditionally Approved Section XI Code Cases

Annulment
Date

N-409-3

Procedure and Personnel Qualification Requirements for Ultrasonic Detection
and Sizing of Flaws in Piping Welds, Section XI,
Division 1

4/30/96

N-415

Alternative Rules for Testing Pressure Relief, Section XI, Division 1

8/14/94

N-419

Extent of VT-1 Examinations, Category B-G-1 of Table IWB-2500-1, Section
XI, Division 1

5/13/94

N-424

Qualification of Visual Examination Personnel, Section XI,
Division 1

7/18/88

N-426

Extent of VT-1 Examinations, Category B-G-2 of Table IWB-2500-1, Section
XI, Division 1

5/13/94

N-427

Code Cases in Inspection Plans, Section XI, Division 1

12/16/94

N-429-2

Alternative Rules for Ultrasonic Instrument Calibration, Section XI, Division 1

7/27/95

N-435-1

Alternative Examination Requirements for Vessels With Wall Thickness 2 in.
or Less, Section XI, Division 1

5/4/04

N-436-1

Alternative Methods for Evaluation of Flaws in Austenitic Piping, Section XI,
Division 1

12/3/90

N-437

Use of Digital Readout and Digital Measurement Devices for Performing
Pressure Tests, Section XI, Division 1

7/27/95

N-444

Preparation of Inspection Plans, Section XI, Division 1
(Valve stroke times may be documented outside of the IST program.
However, if included within the IST program and it becomes necessary to
revise the maximum stroke time required by “Supplement 4—Content of IWV
Valve Test Tables,” it is not necessary to submit a revised IST program to the
NRC solely to document a revision in valve stroke time.)

12/30/90

N-445

Use of Later Editions of SNT-TC-1A for Qualification of Nondestructive
Examination Personnel, Section XI, Division 1, 2 and 3

5/7/90

N-446

Recertification of Visual Examination Personnel, Section XI,
Division 1

5/7/90

N-448

Qualification of VT-2 and VT-3 Visual Examination Personnel, Section XI,
Division 1

4/30/96

N-449

Qualification of VT-4 Visual Examination Personnel, Section XI, Division 1

4/30/96

N-457

Qualification Specimen Notch Location for Ultrasonic Examination of Bolts
and Studs, Section XI, Division 1

4/19/02

N-458-1

Magnetic Particle Examination of Coated Materials, Section XI, Division 1

3/38/01

DG-1342, Page 26

Code Case
Number

Table 3
Annulled Unconditionally Approved Section XI Code Cases

Annulment
Date

N-461-1

Alternative Rules for Piping Calibration Block Thickness,
Section XI, Division 1

3/28/01

N-463-1

Evaluation Procedures and Acceptance Criteria for Flaws
in Class 1 Ferritic Piping That Exceed the Acceptance Standards of IWB3514.2, Section XI, Division 1

3/28/01

N-471

Acoustic Emission for Successive Inspections, Section XI, Division 1

4/19/02

N-472

Use of Digital Readout and Digital Measurement Devices
for Performing Pump Vibration Testing, Section XI, Division 1

8/14/97

N-478

Inservice Inspection for Class CC Concrete Components
Of Light-Water Cooled Power Plants, Section XI, Division 1

3/2/98

N-479-1

Boiling Water Reactor (BWR) Main Steam Hydrostatic Test,
Section XI, Division 1

4/19/02

N-481

Alternative Examination Requirements for Cast Austenitic Pump Casings,
Section XI, Division 1

3/28/04

N-485-1

Eddy Current Examination of Coated Ferritic Surfaces as an Alternative to
Surface Examination, Section XI, Division 1

2/14/03

N-489

Alternative Rules for Level III NDE Qualification Examinations, Section XI,
Divisions 1, 2, and 3

4/19/02

N-490-1

Alternative Vision Test Requirements for Nondestructive Examiners, Section
XI, Divisions 1, 2, and 3

2/14/03

N-495

Hydrostatic Testing of Relief Valves, Section XI, Division 1

4/19/02

N-496-1

Helical-Coil Threaded Inserts, Section XI, Division 1

5/11/97

N-503

Limited Certification of Nondestructive Examination Personnel, Section XI,
Division 1
(Note: Because of the statistical screening criteria used
for Appendix VIII to Section XI qualifications, this Code Case is not
applicable to Appendix VIII, “Performance Demonstration for Ultrasonic
Examination Systems.”)

2/14/03

N-514

Low Temperature Overpressure Protection, Section XI, Division 1

4/19/02

N-515

Class 1 Mechanical Joint Pressure Tests, Section XI, Division 1

4/19/02

N-521

Alternative Rules for Deferral of Inspections of Nozzle-to-Vessel Welds, Inside
Radius Sections, and Nozzle-to-Safe End Welds of a Pressurized Water
Reactor (PWR) Vessel, Section XI, Division 1

4/19/02

N-522

Pressure Testing of Containment Penetration Piping, Section XI, Division 1

4/8/02

N-523-2

Mechanical Clamping Devices for Class 2 and 3 Piping, Section XI, Division 1

3/28/04

DG-1342, Page 27

Code Case
Number

Table 3
Annulled Unconditionally Approved Section XI Code Cases

Annulment
Date

N-524

Alternative Examination Requirements for Longitudinal Welds in Class 1 and
2 Piping, Section XI, Division 1

4/19/02

N-534

Alternative Requirements for Pneumatic Pressure Testing, Section XI,
Division 1

5/09/03

N-535

Alternative Requirements for Inservice Inspection Intervals,
Section XI, Division 1

3/28/01

N-538

Alternative Requirements for Length Sizing Performance Demonstration in
Accordance with Appendix VIII, Supplements 2, 3, 10, 11, and 12,
Section XI, Division 1

4/19/02

N-541

Alternative Requirements for Performance Demonstration in Accordance with
Appendix VIII, Supplements 4 and 6, Section XI, Division 1

3/28/01

N-543

Alternative to Performing Periodic Calibration Checks, Section XI, Division 1

9/18/01

N-544

Repair/Replacement of Small Items, Section XI, Division 1

3/28/01

N-545

Alternative Requirements for Conduct of Performance Demonstration
Detection Test of Reactor Vessel, Section XI, Division 1

5/20/98

N-553-1

Inservice Eddy Current Surface Examination of Pressure Retaining Pipe
Welds and Nozzle-to-Safe End Welds, Section XI, Division 1

3/28/01

N-555

Use of Section II, V, and IX Code Cases, Section XI, Division 1

4/8/02

N-556

Alternative Requirements for Verification of Acceptability
Of Replacements, Section XI, Division 1

4/19/02

N-563

Grading of Examinations, IWA-2320, Section XI, Division 1

4/19/02

N-588

Attenuation to Reference Flaw Orientation of Appendix G
for Circumferential Welds in Reactor Vessels, Section XI, Division 1

3/28/04

N-592

ASNT Central Certification Program, Section XI, Division 1

3/28/04

N-598

Alternative Requirements to Required Percentages of Examinations, Section
XI, Division 1

3/28/04

N-601

Extent and Frequency of VT-3 Visual Examination for Inservice Inspection of
Metal Containments, Section XI, Division 1

3/28/04

N-603

Alternative to the Requirements of IWL-2421, Sites with Two Plants, Section
XI, Division 1

3/28/04

N-604

Alternative to Bolt Torque or Tension Test Requirements of Table IWE-25001, Category E-G, Item E8.20, Section XI, Division 1

9/18/04

N-605

Alternative to the Requirements of IWE-2500(c)
[sic, should state IWE-2500(b)] for Augmented Examination of Surface Areas,
Section XI, Division 1]

3/28/04

DG-1342, Page 28

Code Case
Number

Table 3
Annulled Unconditionally Approved Section XI Code Cases

Annulment
Date

N-617

Alternative Examination Distribution Requirements for Table
IWC-25001, Examination Category C-G, Pressure Retaining Welds in Pumps and
Valves, Section XI, Division 1

4/19/02

N-623

Deferral of Inspections of Shell-to-Flange and Head-to-Flange Welds of a
Reactor Vessel, Section XI, Division 1

4/19/02

N-627

VT-1 Visual Examination in Lieu of Surface Examination for RPV
Closure Nuts, Section XI, Division 1

5/7/02

N-640

Alternative Reference Fracture Toughness for Development of P-T Limit
Curves, Section XI, Division 1

4/19/02

DG-1342, Page 29

4.

Annulled Conditionally Acceptable Section XI Code Cases

The Code Cases listed in Table 4 were conditionally approved by the NRC but were subsequently
annulled by the ASME.
Table 4. Annulled Conditionally Acceptable Section XI Code Cases
Code Case
Number
N-118
(1738)

Table 4
Annulled Conditionally Acceptable Section XI Code Cases
Examination—Acceptance Standards for Surface Indications in Cladding,
Section XI

Annulment
Date
12/3/90

The last sentence of the “Reply” is to be replaced with the following: “The
provisions of this Code Case may not be applied for the examination of clad
surfaces of nozzles, including the inner surface of the nozzle-to-vessel insert
welds.”
N-210

Exemption to Hydrostatic Tests After Repairs, Section XI, Division 1

3/20/81

Paragraph (3) of the “Reply” is to be replaced with the following: “Repairs to
piping, pumps, and valves where the depth of the repaired cavity does not
exceed 25 percent of the wall thickness.”
N-252

Low Energy Capacitive Discharge Welding Method for Temporary
or Permanent Attachments to Components and Supports, Section III, Division
1, and Section XI

7/16/82

The applicant should indicate in the safety analysis report the application, the
material, and the thickness of the material to which the strain gage or
thermocouple will be attached by CD welding.
N-278

Alternative Ultrasonic Calibration Block Configuration I-3131 and
T-434.3, Section XI, Division 1
(Code Case N-278 was inadvertently allowed to expire because of an ASME
administrative error on 3/17/83. The Code Case was reinstated without
technical change on May 25, 1993. Thus, the NRC considered the Code Case
to be in effect during the period from March 17, 1983, through May 25, 1993.)

2/19/92

When a universal calibration block is used and some or all of the reference
holes are larger than the reflector holes at comparable depths recommended by
Article IV, Section V, 1980 Edition of the ASME Code, a correction factor
should be used to adjust the DAC level to compensate for the larger reflector
holes. Also, if the reactor pressure vessel was previously examined using a
conventional block, a ratio between the DAC curves obtained from the two
blocks should be noted (for reference) with the significant indication data.
N-509

Alternative Rules for the Selection and Examination of Class 1, 2, and 3
Integrally Welded Attachments, Section XI, Division 1
A minimum 10% sample of integrally welded attachments for each item in
each Code class per interval should be examined.

DG-1342, Page 30

5/20/01

Code Case
Number
N-512-1

Table 4
Annulled Conditionally Acceptable Section XI Code Cases
Assessment of Reactor Vessels With Low Upper Shelf Charpy Impact Energy
Levels, Section XI, Division 1

Annulment
Date
5/20/01

The material properties and transient selection must follow the guidance in
Regulatory Guide 1.161, “Evaluation of Reactor Pressure Vessels with Charpy
Upper-Shelf Energy Less Than 50 ft-lb” (Ref. 9), or an equivalent method
approved by the NRC staff.
N-546

Alternative Requirements for Qualification of VT-2 Examination Personnel,
Section XI, Division 1

9/18/04

This Code Case is applicable only to the performance of VT-2 examinations
and may not be applied to other VT-2 functions such as verifying the
adequacy of procedures and training VT-2 personnel.
N-568

Alternative Examination Requirements for Welded Attachments, Section XI,
Division 1

2/14/03

This Code Case may only be used for examination of the accessible portions
of lugs on piping where riser clamps (i.e., clamps on vertical runs of pipe)
obstruct access to welded surfaces.
N-599

Alternatives to Qualification of Nondestructive Examination Personnel for
Inservice Inspection of Metal (Class MC) and Concrete (Class CC)
Containments, Section XI, Division 1

9/18/04

This Code Case may not be used when a licensee updates to the 1992 or later
Edition of Section XI that requires the use of ANSI/ASNT CP-189, “Standard
for Qualification and Certification of Nondestructive Testing Personnel” (Ref.
10).
N-630

Alternatives to VT-1C and VT-3C Visual Examination for Inservice Inspection
of Concrete and VT-1 Visual Examination for Inservice Inspection of
Anchorage Hardware and Surrounding Concrete for Concrete Containments,
Section XI, Division 1
The Responsible Engineer’s written practice must define qualification
requirements for concrete and tendon hardware examination personnel in
accordance with IWA-2300 in lieu of the Owner defined qualification
requirements specified in Paragraph (c) of the Code Case. However, limited
certification in accordance with IWA-2350 is permitted.

DG-1342, Page 31

4/8/02

5.

Code Cases That Have Been Superseded

Table 5 lists Code Cases that have been superseded by revision. The third column of the table
indicates the date on which each Code Case was superseded. Note: Some of these Code Cases were not
approved for use by the NRC in previous versions of this guide.
Table 5. Section XI Code Cases That Have Been Superseded
Code Case
Number

Table 5
Section XI Code Cases That Have Been Superseded

Date

N-113
(1731)

Basic Calibration Block for Ultrasonic Examination of Weld 10 in. To 14 in.
Thick, Section XI, Division 1

N-113-1
Published on
12/31/82

N-236

Repair and Replacement of Class MC Vessels, Section XI,
Division 1

N-236-1
Published on
9/5/85

(a) In paragraph 1.0(a), second sentence, the phrase, “while the plant is not
in service,” refers to a refueling outage.
(b) In paragraph 1.0(a), third sentence, the phrase, “the next scheduled plant
outage,” refers to the next scheduled refueling outage.
For clarification, “Repair and Replacement of Class MC Vessels” means
Repair and Replacement of Class MC Vessels and Components (systems).
Acceptance of this Code Case in no way provides/constitutes NRC approval to
violate the technical specification or any NRC requirements with regard to
breach of containment during repair and replacement procedures while the
plant is in operation.
Where a numbered Code paragraph is not identified by a particular edition of
the Code, the Code in effect at the time of the ASME meeting (November 3,
1978) that approved the Code Case should be governing.
N-307
N-307-1
N-307-2

Revised Ultrasonic Examination Volume for Class 1 Bolting, Table IWB2500-1, Examination Category B-G-1, When the Examinations Are Conducted
from the Center-Drilled Hole, Section XI, Division 1

N-307-1
Published on
12/5/84
N-307-2
Published on
9/24/99
N-307-3
Published on
3/28/01

N-335

Rules for Ultrasonic Examination of Similar and Dissimilar Metal Piping
Welds, Section XI, Division 1

N-335-1
Published on
6/20/85

DG-1342, Page 32

Code Case
Number

Table 5
Section XI Code Cases That Have Been Superseded

Date

N-375
N-375-1

Rules for Ultrasonic Examination of Bolds and Studs,
Section XI, Division 1

N-375-1
Published on
4/14/83;
N-375-2
Published on
4/5/84

N-389

Alternative Rules for Repairs, Replacements, or Modifications, Section XI,
Division 1

N-389-1
Published on
12/9/93

The applicant should submit for approval the appropriate edition and addenda
of the Code that is to be used for the repair, replacement, or modification
before the start of the work.
N-401

Eddy Current Examination, Section XI, Division 1

N-401-1
Published on
5/4/88

N-402

Eddy Current Calibration Standards, Section XI, Division 1

N-402-1
Published on
3/14/91

N-408

Alternative Rules for Examination of Class 2 Piping, Section XI, Division 1

N-408-1
Published on
3/8/89

N-408-1
N-408-2

Alternative Rules for Examination of Class 2 Piping,
Section XI, Division 1
The applicant for an operating license should define the Class 2 piping subject
to volumetric and surface examination in the Preservice Inspection for
determination of acceptability by the NRC staff.

N-408-2
Published on
7/24/89
N-408-3
Published on
8/9/93

N-409

Procedure and Personnel Qualification Requirements for Ultrasonic
Detection and Sizing of Flaws in Piping Welds,
Section XI, Division 1

N-409-1
Published on
12/7/87

N-409-1
N-409-2

Procedure and Personnel Qualification Requirements for Ultrasonic
Detection and Sizing of Flaws in Piping Welds,
Section XI, Division 1

N-409-2
Published on
7/27/88;
N-409-3
Published on
4/30/93

The applicant should give prior notification to the NRC of the intention to use
the Code Case.

DG-1342, Page 33

Code Case
Number

Table 5
Section XI Code Cases That Have Been Superseded

Date

N-416
N-416-1
N-416-2
N-416-3

Alternative Pressure Test Requirements for Welded Repairs or Installation of
Replacement Items by Welding, Class 1, 2, and 3, Section XI, Division 1

N-416-1
Published on
2/15/94
N-416-2
Published on
5/5/00
N-416-3
Published on
09/07/01
N-416-4
Published on
1/12/05

N-429
N-429-1

Alternative Rules for Ultrasonic Instrument Calibration,
Section XI, Division 1

N-429-1
Published on
2/23/87;
N-429-2
Published on
7/27/92

N-432

Repair Welding Using Automatic or Machine Gas Tungsten-Arc Welding
(GTAW) Temper Bead Technique, Section XI, Division 1

N-432-1
Published on
3/28/01

N-435

Alternative Examination Requirements for Vessels With Wall Thickness 2 in.
Or Less, Section XI, Division 1

N-435-1
Published on
7/30/86

N-436

Alternative Methods for Evaluation of Flaws in Austenitic Piping, Section XI,
Division 1

N-436-1
Published on
12/7/87

N-458

Magnetic Particle Examination of Coated Materials,
Section XI, Division 1

N-458-1
Published on
3/14/95

N-461

Alternative Rules for Piping Calibration Block Thickness,
Section XI, Division 1

N-461-1
Published on
3/14/95

N-463

Evaluation Procedures and Acceptance Criteria for Flaws in
Class 1 Ferritic Piping That Exceed the Acceptance Standards of IWB-3514.2,
Section XI, Division 1

N-463-1
Published on
3/5/90

N-479

Boiling Water Reactor (BWR) Main Steam Hydrostatic Test, Section XI,
Division 1

N-479-1
Published on
12/3/90

N-485

Eddy Current Examination of Coated Ferritic Surfaces as an Alternative to
Surface Examination, Section XI, Division 1

N-485
Published on
8/14/91

DG-1342, Page 34

Code Case
Number

Table 5
Section XI Code Cases That Have Been Superseded

Date

N-490

Alternative Vision Test Requirements for Nondestructive Examiners, Section
XI, Divisions 1, 2, and 3

N-490-1
Published on
5/13/91

N-491
N-491-1

Alternative Rules for Examination of Class 1, 2, 3, and MC Component
Supports of Light-Water Cooled Power Plants,
Section XI, Division 1

N-491-1
Published on
4/30/93;
N-491-2
Published on
3/12/97

N-494
N-494-1
N-494-2
N-494-3

Pipe Specific Evaluation Procedures and Acceptance Criteria for Flaws in
Class 1 Ferritic Piping that Exceed the Acceptance Standards of IWB-3514.2,
Section XI, Division 1

N-494-1
Published on
7/27/92;
N-494-2
Published on
12/9/93
N-494-3
Published on
8/9/96
N-494-4
Published on
10/11/05

N-496
N-496-1

Helical-Coil Threaded Inserts, Section XI, Division 1

N-496-1
Published on
5/11/94;
N-496-1
Annulled on
5/11/97
N-496-2
Published on
9/18/01

N-498
N-498-1
N-498-2
N-498-3

Alternative Rules for 10-Year System Hydrostatic Testing for
Class 1, 2, and 3 Systems, Section XI, Division 1

N-498-1
Published on
5/11/94
N-498-2
Published on
6/9/95
N-498-3
Published on
5/20/98
N-498-4
Published on
2/15/99

DG-1342, Page 35

Code Case
Number

Table 5
Section XI Code Cases That Have Been Superseded

Date

N-504
N-504-1
N-504-2
N-504-3

Alternative Rules for Repair of Class 1, 2, and 3 Austenitic Stainless Steel
Piping, Section XI, Division 1

N-504-1
Published on
8/9/93
N-504-2
Published on
3/12/97
N-504-3
Published on
8/4/04
N-504-4
Published on
7/14/06

N-508
N-508-1
N-508-2
N-508-3

Rotation of Serviced Snubbers and Pressure Relief Valves for the Purpose of
Testing, Section XI, Division 1

N-508-1
Published on
5/11/94
N-508-2
Published on
3/28/01
N-508-3
Published on
11/18/03
N-508-4
Published on
1/26/09

N-512

Assessment of Reactor Vessels With Low Upper Shelf Charpy Impact Energy
Levels, Section XI, Division 1

N-512-1
Published on
8/24/95

N-513

Evaluation Criteria for Temporary Acceptance of Flaws
in Class 3 Piping, Section XI, Division 1

N-513-1
Published on
3/28/01

N-513-1

Evaluation Criteria for Temporary Acceptance of Flaws
in Class 3 Piping, Section XI, Division 1

N-513-2
Published on
2/20/04

N-513-2

(1)
(2)

N-513-3

Specific safety factors in paragraph 4.0 must be satisfied.
Code Case N-513 may not be applied to:
(a) Components other than pipe and tube.
(b) Leakage through a gasket.
(c) Threaded connections employing nonstructural seal welds for
leakage prevention (through seal weld leakage is nota structural
flaw; thread integrity must be maintained).
(d) Degraded socket welds

Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy
Class 2 or 3 Piping, Section XI, Division 1
The repair or replacement activity temporarily deferred under the provisions
of this Code Case shall be performed during the next scheduled outage.
DG-1342, Page 36

N-513-3
Published on
1/26/09

N-513-4
Published on
5/7/2014

Code Case
Number
N-516
N-516-1

N-516-2
N-516-3

Table 5
Section XI Code Cases That Have Been Superseded
Underwater Welding, Section XI, Division 1
When welding is to be performed on high neutron fluence Class 1 material,
then a mockup, using material with similar fluence levels, should be welded to
verify that adequate crack prevention measures were used.

Underwater Welding, Section XI, Division 1
Licensees must obtain NRC approval in accordance with 10 CFR 50.55a(z)
regarding the method to be used in the weld repair or replacement of irradiated
material underwater.

Date
N-516-1
Published on
12/31/96;
N-516-2
Published on
1/17/00
N-516-3
Published on
4/8/02
N-516-4
Published on
5/7/13

N-517

Quality Assurance Program Requirements for Owners, Section XI, Division 1

N-517-1
Published on
7/30/98

N-523
N-523-1

Mechanical Clamping Devices for Class 2 and 3 Piping,
Section XI, Division 1

N-523-1
Published on
8/24/95
N-523-2
Published on
10/2/00

N-528

Purchase, Exchange, or Transfer of Material Between Nuclear Plant Sites,
Section XI, Division 1

N-528-1
Published on
5/7/99

N-532
N-532-1
N-532-2
N-532-3
N-532-4

Alternative Requirements to Repair and Replacement Documentation
Requirements and Inservice Summary Report Preparation and Submission as
Required by
IWA-4000 and IWA-6000, Section XI, Division 1

N-532-1
Published on
3/28/01
N-532-2
Published on
7/23/02
N-532-3
Published on
2/20/04
N-532-4
Published on
4/19/06
N-532-5
Published on
1/04/11

N-533

Alternative Requirements for VT-2 Visual Examination of Class 1 Insulated
Pressure-Retaining Bolted Connections, Section XI, Division 1

N-552

Alternative Methods – Qualification for Nozzle Inside Radius Section from the
Outside Surface, Section XI, Division 1
DG-1342, Page 37

N-533-1
Published
2/26/99

Code Case
Number

Table 5
Section XI Code Cases That Have Been Superseded

Date

To achieve consistency with the 10 CFR 50.55a rule change published
September 22, 1999 (64 FR 51370), incorporating Appendix VIII,
“Performance Demonstration for Ultrasonic Examination Systems,” to
Section XI, add the following to the specimen requirements:
“At least 50 percent of the flaws in the demonstration test set must be cracks
and the maximum misorientation must be demonstrated with cracks. Flaws
in nozzles with bore diameters equal to or less than 4 inches may be notches.”
Add to detection criteria, “The number of false calls must not exceed three.”

N-552-1
Published on
6/22/12

N-553

Inservice Eddy Current Surface Examination of Pressure Retaining Pipe
Welds and Nozzle-to-Safe End Welds, Section XI, Division 1

N-553-1
Published on
3/28/01

N-554
N-554-1
N-554-2

Alternative Requirements for Reconciliation of Replacement Items, Section XI,
Division 1

N-554-1
Published on
7/98E;
N-554-2
Published on
2/25/00
N-554-3
Published on
2/14/03

N-557

In-Place Dry Annealing of a PWR Nuclear Reactor Vessel,
Section XI, Division 1

N-557-1
Published on
12/31/96

N-560
N-560-1

Alternative Examination Requirements for Class 1, Category B-J Piping
Welds, Section XI, Division 1

N-560-1
Published on
8/9/96;
N-560-2
Published on
3/28/00

N-561
N-561-1

Alternative Requirements for Wall Thickness Restoration of
Class 2 and High Energy Class 3 Carbon Steel Piping,
Section XI, Division 1

N-561-1
Published on
7/30/98
N-561-2
Published on
3/22/07

N-562
N-562-1

Alternative Requirements for Wall Thickness Restoration of
Class 3 Moderate Energy Carbon Steel Piping, Section XI, Division 1

N-562-1
Published on
7/30/98
N-562-2
Published on
3/22/07

DG-1342, Page 38

Code Case
Number

Table 5
Section XI Code Cases That Have Been Superseded

Date

N-566
N-566-1

Corrective Action for Leakage Identified at Bolted Connections, Section XI,
Division 1

N-566-1
Published on
2/15/99
N-566-2
Published on
3/28/01

N-567

Alternative Requirements for Class 1, 2, and 3 Replacement Components,
Section XI, Division 1

N-567-1
Published on
2/26/99

N-569

Alternative Rules for Repair by Electrochemical Deposition of Class 1 and 2
Steam Generator Tubing, Section XI, Division 1

N-569-1
Published on
5/7/99

N-576
N-576-1

Repair of Class 1 and 2 SB-163, UNS N06600 Steam Generator Tubing,
Section XI, Division 1

N-576-1
Published on
5/7/99
N-576-2
Published on
3/16/12

N-577

Risk-Informed Requirements for Class 1, 2, and 3 Piping,
Method A, Section XI, Division 1

N-577-1
Published on
3/28/00

N-578

Risk-Informed Requirements for Class 1, 2, and 3 Piping,
Method B, Section XI, Division 1

N-578-1
Published on
3/28/00

N-586

Alternative Additional Examination Requirements for Class 1, 2, and 3 Piping,
Components, and Supports, Section XI, Division 1

N-586-1
Published on
5/4/04

The engineering evaluations addressed under Item (a) and the additional
examinations addressed under Item (b) shall be performed during this outage.
If the additional examinations performed under Item (b) reveal indications
exceeding the applicable acceptance criteria of Section XI, the engineering
evaluations and the examinations shall be further extended to include
additional evaluations and examinations at this outage.
N-589

Class 3 Nonmetallic Cured-in-Place Piping, Section XI,
Division 1

N-589-1
Published on
7/23/02

N-593
N-593-1

Alternative Examination Requirements for Steam Generator Nozzle to Vessel
Welds, Section XI, Division 1

N-593-1
Published on
10/8/04
N-593-2
Published on
11/8/11

DG-1342, Page 39

Code Case
Number

Table 5
Section XI Code Cases That Have Been Superseded

Date

N-597
N-597-1

Requirements for Analytical Evaluation of Pipe Wall Thinning, Section XI,
Division 1

N-597-1
Published on
7/7/01
N-597-2
Published on
11/18/03

N-597-2

Requirements for Analytical Evaluation of Pipe Wall Thinning, Section XI,
Division 1

N-597-3
Published on
5/7/2014

(1) Code Case must be supplemented by the provisions of EPRI Nuclear
Safety Analysis Center Report 202L-R2,“Recommendations for an
Effective Flow Accelerated Corrosion Program,” April 1999, for
developing the inspection requirements, the method of predicting the rate
of wall thickness loss, and the value of the predicted remaining wall
thickness. As used in NSAC-202L-R2, the term “should” is to be applied
as “shall” (i.e., a requirement).
(2) Components affected by flow-accelerated corrosion to which this Code
Case are applied must be repaired or replaced in accordance with the
construction code of record and Owner’s requirements or a later NRC
approved edition of Section III, “Rules for Construction of Nuclear Power
Plant Components,” of the ASME Code (Ref. 11) prior to the value of tp
reaching the allowable minimum wall thickness, tmin, as specified in 3622.1(a)(1) of this Code Case. Alternatively, use of the Code Case is
subject to NRC review and approval per 10 CFR 50.55a(z).
(3) For Class 1 piping not meeting the criteria of -3221, the use of evaluation
methods and criteria is subject to NRC review and approval per 10 CFR
50.55a(z).
(4) For those components that do not require immediate repair or replacement,
the rate of wall thickness loss is to be used to determine a suitable
inspection frequency so that repair or replacement occurs prior to reaching
allowable minimum wall thickness, tmin.
(5) For corrosion phenomenon other than flow accelerated corrosion, use of
the Code Case is subject to NRC review and approval. Inspection plans
and wall thinning rates may be difficult to justify for certain degradation
mechanisms such as MIC and pitting.
(6) The evaluation criteria in Code Case N-513-2 may be applied to Code
Case N-597-2 for temporary acceptance of wall thinning (until the next
refueling outage) for moderate-energy Class 2 and 3 piping. Moderateenergy piping is defined as Class 2 and 3 piping whose maximum
operating temperature does not exceed 200 °F (93 °C) and whose
maximum operating pressure does not exceed 275 psig (1.9MPa). Code
Case N-597-2 shall not be used to evaluate through-wall leakage
conditions.
N-606

Similar and Dissimilar Metal Welding Using Ambient Temperature Machine
GTAW Temper Bead Technique, Section XI, Division 1

DG-1342, Page 40

N-606-1
Published on
9/24/99

Code Case
Number
N-606-1

Table 5
Section XI Code Cases That Have Been Superseded
Similar and Dissimilar Metal Welding Using Ambient Temperature Machine
GTAW Temper Bead Technique for BWR CRD Housing/Stub Tube Repairs,
Section XI, Division 1

Date
N-606-2
Published on
8/13/13

Prior to welding, an examination or verification must be performed to ensure
proper preparation of the base metal, and that the surface is properly contoured
so that an acceptable weld can be produced. This verification is to be required
in the welding procedures.
N-609

Alternative Requirements to Stress-Based Selection Criteria for Category B-J
Welds, Section XI, Division 1

N-609-1
Published on
9/17/10

N-613
N-613-1

Ultrasonic Examination of Penetration Nozzles in Vessels, Examination
Category B-D, Item Nos. B3.10 and B3.90, Reactor Nozzle-to-Vessel Welds,
Figs. IWB-2500-7(a), (b), and (c),
Section XI, Division 1

N-613-1
Published on
8/20/02
N-613-2
Published on
12/10/10

N-638
N-638-1
N-638-2
N-638-3

Similar and Dissimilar Metal Welding Using Ambient Temperature Machine
GTAW Temper Bead Technique, Section XI, Division 1

N-638-1
Published on
5/9/03
N-638-2
Published on
7/1/05
N-638-3
Published on
4/19/06
N-638-4
Published on
10/12/06

N-638-4
N-638-5

N-638-6

The Construction Code of Record acceptance criteria must be used for
volumetric examinations.

Similar and Dissimilar Metal Welding Using Ambient Temperature Machine
GTAW Temper Bead Technique, Section XI, Division 1
(1) Demonstration for ultrasonic examination of the repaired volume is
required using representative samples which contain construction type
flaws.
(2) The provisions of 3(e)(2) or 3(e)(3) may only be used when it is
impractical to use the interpass temperature measurement methods
described in 3(e)(1), such as in situations where the weldment area is
inaccessible (e.g., internal bore welding) or when there are extenuating
radiological conditions.
Similar and Dissimilar Metal Welding Using Ambient Temperature Machine
GTAW Temper Bead Technique, Section XI, Division 1
Demonstration for ultrasonic examination of the repaired volume is required
using representative samples which contain construction type flaws.
(Note: the above condition is identical to the condition on the use of Code
Case N-638-4, RG 1.147, Rev. 17)
DG-1342, Page 41

N-638-5
Published on
4/27/09
N-638-6
Published on
6/25/11

N-638-7
Published on
5/17/13

Code Case
Number

Table 5
Section XI Code Cases That Have Been Superseded

Date

N-643
N-643-1

Fatigue Crack Growth Rate Curves for Ferritic Steels in PWR Water
Environment, Section XI, Division 1

N-643-1
Published on
2/3/03
N-643-2
Published on
5/4/04

N-648

Alternative Requirements for Inner Radius Examination of Class 1 Reactor
Vessel Nozzles, Section XI, Division 1

N-648-1
Published on
7/7/01

N-648-1

Alternative Requirements for Inner Radius Examination of Class 1 Reactor
Vessel Nozzles, Section XI Division 1

N-648-2
Published on
9/4/14

In lieu of a UT examination, licensees may perform a VT-1 examination in
accordance with the code of record for the Inservice Inspection Program
utilizing the allowable flaw length criteria of Table IWB-3512-1 with limiting
assumptions on the flaw aspect ratio.
N-652
N-652-1

Alternative Requirements to Categorize B-G-1, B-G-2, and
C-D Bolting Examination Methods and Selection Criteria,
Section XI, Division 1

N-652-1
Published on
2/20/04
N-652-2
Published on
9/3/10

N-653

Qualification Requirements for Full Structural Overlaid Wrought Austenitic
Piping Welds, Section XI, Division 1

N-653-1
Published on
4/4/12

N-661

Alternative Requirements for Wall Thickness Restoration of Classes 2 and 3
Carbon Steel Piping for Raw Water Service, Section XI, Division 1

N-661-1
Published on
10/11/05

(a)

If the root cause of the degradation has not been determined, the repair
is only acceptable for one cycle.
(b) Weld overlay repair of an area can only be performed once in the same
location.
(c) When through-wall repairs are made by welding on surfaces that are wet
or exposed to water, the weld overlay repair is only acceptable until the
next refueling outage.

N-661-1

Alternative Requirements for Wall Thickness Restoration of Class 2 and 3
Carbon Steel Piping for Raw Water Service, Section XI, Division 1

DG-1342, Page 42

N-661-2
Published on
3/22/07

Code Case
Number
N-661-2

Table 5
Section XI Code Cases That Have Been Superseded

Date

Alternative Requirements for Wall Thickness Restoration of Classes 2 and 3
Carbon Steel Piping for Raw Water Service, Section XI, Division 1

N-661-3
Published on
4/25/16

(1) Paragraph 4(b): for repairs performed on a wet surface, the overlay is only
acceptable until the next refueling outage.
(2) Paragraph 7(c): if the cause of the degradation has not been determined,
the repair is only acceptable until the next refueling outage.
(3) The area where the weld overlay is to be applied must be examined using
ultrasonic methods to demonstrate that no crack-like defects exist.
(4) Piping with wall thickness less than the diameter of the electrode shall be
depressurized before welding.
N-662

Alternative Repair/Replacement Requirements for Items Classified in
Accordance with Risk-Informed Processes, Section XI, Division 1

N-662-1
Published on
6/25/11

N-666

Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI,
Division 1

N-666-1
Published on
3/12/12

A surface (magnetic particle or liquid penetrant) examination must be
performed after installing the seal weld and weld overlay on Class 1 and 2
piping socket welds. The fabrication defects, if detected, must be
dispositioned using the surface examination acceptance criteria of the
Construction Code identified in the Repair/Replacement Plan.
N-686

Alternative Requirements for Visual Examinations, VT-1, VT-2, and VT-3,
Section XI, Division 1

N-686-1
Published on
1/10/07

N-694

Evaluation Procedure and Acceptance Criteria for PWR Reactor Vessel
Upper Head Penetration, Section XI, Division 1

N-694-1
Published on
2/20/04

N-694-1

(a) The maximum instantaneous through-thickness stress distribution along
the crack front and in the crack-length path must be used to calculate the
crack driving force.
(b) The stress intensity factor expression Raju and Newman (Ref. 12), is
only applicable to cylindrical products having a ratio of wall thickness to
inside radius between 0.1 and 0.25.

N-694-2
Published on
1/16/13

N-695

Qualification Requirements for Dissimilar Metal Piping Welds Section XI,
Division 1

N-695-1
Published on
12/31/14

N-696

Qualification Requirements for Appendix VIII Piping Examinations
Conducted from the Inside Surface, Section XI, Division 1

N-696-1
Published on
5/7/14

N-706

Alternative Examination Requirements of Table IWB-2500-1 and Table IWC2500-1 for PWR Stainless Steel Residual and Regenerative Heat Exchangers,
Section XI, Division 1

N-706-1
Published on
1/10/07

DG-1342, Page 43

Code Case
Number

Table 5
Section XI Code Cases That Have Been Superseded

Date

N-711

Alternative Examination Coverage Requirements for Examination Category
B-F, B-J, C-F-1, C-F-2, and R-A Piping Welds

N-711-1
Published on
11/7/2016

N-716

Alternative Piping Classification and Examination Requirements, Section XI,
Division 1

N-716-1
Published on
1/27/13

N-730

Roll Expansion of Class 1 Control Rod Drive Bottom Head Penetrations in
BWRs, Section XI, Division 1

N-730-1
Published on
7/16/12

N-739

Alternative Qualification Requirements for Personnel Performing Class CC
Concrete and Post-Tensioning System Visual Examinations, Section XI,
Division 1

N-739-1
Published on
1/21/07

N-754

Optimized Structural Dissimilar Metal Weld Overlay for Mitigation of PWR
Class 1 Items, Section XI, Division 1

N-754-1
Published on
2/28/13

N-762

Temper Bead Procedure Qualification Requirements for Repair/Replacement
Activities Without Postweld Heat Treatment, Section XI, Division 1.

N-762-1
Published on
10/21/13

N-766

Nickel Alloy Reactor Coolant Inlay and Onlay for Mitigation of PWR Full
Penetration Circumferential Nickel Alloy Dissimilar Metal Welds in Class 1
Items, Section XI, Division 1

N-766-1
Published on
4/7/13

N-769

Roll Expansion of Class 1 In-Core Housing Bottom Head Penetrations in
BWRs, Section XI, Division 1

N-769-1
Published on
9/17/10
N-769-2
Published on
7/16/12

N-786

Alternative Requirements for Sleeve Reinforcement of Class 2 and 3
Moderate-Energy Carbon Steel Piping, Section XI, Division 1

N-786-1
Published on
4/24/11

N-789

Alternative Requirements for Pad Reinforcement of Class 2 and 3 ModerateEnergy Carbon Steel Piping, Section XI, Division 1

N-789-1
Published on
11/13/13

N-769-1

Areas containing pressure pads shall be visually observed at least once per
month to monitor for evidence of leakage. If the areas containing pressure
pads are not accessible for direct observation, then monitoring will be
accomplished by visual assessment of surrounding areas or ground surface
areas above pressure pads on buried piping, or monitoring of leakage
collection systems, if available.
DG-1342, Page 44

Code Case
Number

Table 5
Section XI Code Cases That Have Been Superseded

Date

N-789-1

Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate
Energy Carbon Steel Piping for Raw Water Service

N-789-2
Published on
6/23/15

N-823

Visual Examination, Section XI, Division 1

N-823-1
Published on
1/23/14

DG-1342, Page 45

D. IMPLEMENTATION
The purpose of this section is to provide information to applicants and licensees regarding the
NRC staff’s plans for using this regulatory guide. The requirements addressing implementation of
Section XI Code Cases are contained in 10 CFR 50.55a(b)(5). No backfitting is intended or approved in
connection with the issuance of this guide.

DG-1342, Page 46

REFERENCES1
1.

Code of Federal Regulations, Title 10, Energy, Part 50, “Domestic Licensing of Production and
Utilization Facilities,” U.S. Nuclear Regulatory Commission, Washington, DC.

2.

ASME Boiler and Pressure Vessel Code, Section XI, “Rules for Inservice Inspection of Nuclear
Power Plant Components,” American Society of Mechanical Engineers, New York, NY.2

3.

CFR, Title 10, Energy, Part 52, “Licenses, Certifications, and Approvals for Nuclear Power
Plants,” U.S. Nuclear Regulatory Commission, Washington, DC.

4.

Regulatory Guide 1.84, “Design, Fabrication, and Materials Code Case Acceptability, ASME
Section III,” U.S. Nuclear Regulatory Commission, Washington, DC.

5.

Regulatory Guide 1.192, Operation and Maintenance Code Case Acceptability, ASME OM
Code,” U.S. Nuclear Regulatory Commission, Washington, DC.

6.

Regulatory Guide 1.193, “ASME Code Cases Not Approved for Use,” U.S. Nuclear Regulatory
Commission, Washington, DC.

7.

EPRI Nuclear Safety Analysis Center Report 202L-R2, “Recommendations for an Effective
Flow Accelerated Corrosion Program,” Electric Power Research Institute, Palo Alto, California,
April 1999.3

8.

Regulatory Guide 1.64, “Dedication of Commercial-Grade Items for Use in Nuclear Power
Plants,” U.S. Nuclear Regulatory Commission, Washington, DC.

9.

Regulatory Guide 1.161, “Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf
Energy Less Than 50 ft-lb,” U.S. Nuclear Regulatory Commission, Washington, DC.

10.

ANSI/ASNT CP-189, “Standard for Qualification and Certification of Nondestructive Testing
Personnel,” American Society for Nondestructive Testing, Columbus, OH.4

1

Publicly available NRC published documents are available electronically through the NRC Library on the NRC’s public
Web site at http://www.nrc.gov/reading-rm/doc-collections/ and through the NRC’s Agencywide Documents Access and
Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html The documents can also be viewed online or
printed for a fee in the NRC’s Public Document Room (PDR) at 11555 Rockville Pike, Rockville, MD. For problems with
ADAMS, contact the PDR staff at 301-415-4737 or (800) 397-4209; fax (301) 415-3548; or e-mail pdr.resource@nrc.gov.

2

Copies may be purchased from the American Society of Mechanical Engineers, Three Park Avenue, NewYork, NY 100165990; phone (212) 591-8500; fax (212) 591-8501; www.asme.org.

3

Copies of the listed EPRI standards and reports may be purchased from the Electric Power Research Institute (EPRI), 3420
Hillview Ave., Palo Alto, California 94304; telephone (800) 313-3774; fax (925) 609-1310.

4

Copies may be obtained from the American Society for Nondestructive Testing, 1711 Arlingate Lane, Columbus, OH,
43228-0518; telephone (800) 222-2768 or (614) 274-6003; fax (614) 274-6899. Purchase information is available through
the ASNT Web-based store at http://www.asnt.org/publications/standards/cp-189/index.htm

DG-1342, Page 47

11.

ASME Boiler and Pressure Vessel Code, Section III, “Rules for Construction of Nuclear Power
Plant Components,” American Society of Mechanical Engineers, New York, NY.

12.

Raju, I. S. and J. C, Newman. Jr., Stress Intensity Factor Influence Coefficients for Internal and
External Surface Cracks in Cylindrical Vessels, ASME PVP 58, Aspects of Fracture Mechanics
in Pressure Vessel and Piping, pp, 35-41, 1982.

DG-1342, Page 2

APPENDIX A
SUPPLEMENTS ADDRESSED IN REVISION 19
OF REGULATORY GUIDE 1.147

1
2

Edition

Supplement Number

BNCS1 Approval Date of Code Cases in Supplement2

2010

11

December 17, 2012

2013

0

July 1, 2013

2013

1

April 7, 2013

2013

2

August 13, 2013

2013

3

October 22, 2013

2013

4

January 28, 2014

2013

5

May 7, 2014

2013

6

May 7, 2014

2013

7

October 28, 2014

BNCS = ASME Board on Nuclear Codes and Standards
Publication of supplements approximately 6 months after BNCS approval.

Appendix A to DG-1342, Page A-1

APPENDIX B
NUMERICAL LISTING OF SECTION XI CODE CASES IN
SUPPLEMENT 11 TO THE 2010 EDITION AND SUPPLEMENT 0
THROUGH SUPPLEMENT 7 TO THE 2013 EDITION, AND SELECTED
CODE CASES FROM THE 2015 AND 2017 EDITIONS
Legend
1

Code Case N-528-1 was approved with conditions in Revision 18 to Regulatory Guide 1.147,
Revision 19 removes these conditions

2

Code Case N-702 was approved with conditions in Revision 18 to Regulatory Guide 1.147,
Revision 19 revises the conditions

3

Code Case N-705 was unconditionally approved in Revision 18 to Regulatory Guide 1.147 with
no conditions, Revision 19 adds conditions

4

Code Case published in Supplement 0 to the 2015 Edition; included at request of ASME

5

Code Case published in Supplement 1 to the 2015 Edition; included at request of ASME

6

Code Case published in Supplement 2 to the 2015 Edition; included at request of ASME

7

Code Case published in Supplement 5 to the 2015 Edition; included at request of ASME

8

Code Case published in Supplement 6 to the 2015 Edition; included at request of ASME

9

Code Case published in Supplement 0 to the 2017 Edition; included at request of ASME

N-513-4
N-606-2
N-695-14
N-711-19
N-824
N-839
N-8538

N-516-4
N-638-7
N-696-1
N-754-1
N-830
N-842
N-8545

N-528-11
N-648-2
N-7022
N-762-1
N-8319
N-843

Appendix B to DG-1342, Page B-1

N-597-3
N-661-343
N-7053
N-789-27
N-8386
N-849

APPENDIX C
NUMERICAL LISTING OF SECTION XI CODE CASES
AND TABLE WHERE EACH CODE CASE IS LISTED
Legend
1

Code Case is unacceptable for use. See Revision 6 of Regulatory Guide 1.193.

2

Code Case is directly addressed in 10 CFR 50.55a.

N-34 [T3]
N-112 [T3]
N-167 [T3]
N-216 [T3]
N-236-1 [T3]
N-306 [T3]
N-307-3 [T3]
N-323-1 [T3]
N-343 [T3]
N-375-1 [T5]
N-401 [T5]
N-406 [T3]
N-408-3 [T3]
N-409-3 [T3]
N-416-2 [T5]
N-424 [T3]
N-429-1 [T5]
N-435 [T5]
N-437 [T3]
N-448 [T3]
N-458-1 [T3]
N-463 [T5]
N-471 [T3]
N-478 [T3]
N-481 [T3]
N-490 [T5]
N-491-2 [T1]
N-494-3 [T5]
N-496-1 [T3] [T5]
N-498-2 [T5]
N-504 [T5]
N-504-4 [T2]
N-508-3 [T5]
N-512-1 [T4]
N-513-3 [T5]

N-72 [T3]
N-113 [T5]
N-198-1 [T3]
N-234 [T3]
N-252 [T4]
N-307 [T5]
N-308 [T3]
N-334 [T3]
N-355 [T3]
N-375-2 [T3]
N-401-1 [T3]
N-408 [T5]
N-409 [T5]
N-415 [T3]
N-416-3 [T5]
N-426 [T3]
N-429-2 [T3]
N-435-1 [T3]
N-444 [T3]
N-449 [T3]
N-460 [T1]
N-463-1 [T3]
N-472 [T3]
N-479 [T5]
N-485 [T5]
N-490-1 [T3]
N-494 [T5]
N-494-4 [T1]
N-496-2 [T1]
N-498-3 [T5]
N-504-1 [T5]
N-508 [T5]
N-508-4 [T2]
N-513 [T5]
N-513-4[T1]

N-73 [T3]
N-113-1 [T3]
N-210 [T4]
N-235 [T3]
N-278 [T4]
N-307-1 [T5]
N-311 [T3]
N-335 [T5]
N-356 [T3]
N-389 [T5]
N-402 [T5]
N-408-1 [T5]
N-409-1 [T5]
N-416 [T5]
N-416-4 [T2]
N-427 [T3]
N-432 [T5]
N-436 [T5]
N-445 [T3]
N-457 [T3]
N-461 [T5]
N-4651
N-4731
N-479-1 [T3]
N-485-1 [T3]
N-491 [T5]
N-494-1 [T5]
N-495 [T3]
N-498 [T5]
N-498-4 [T2]
N-504-2 [T5]
N-508-1 [T5]
N-509 [T4]
N-513-1 [T5]
N-514 [T3]

Appendix C to DG-1342, Page C-1

N-98 [T3]
N-118 [T4]
N-211 [T3]
N-236 [T5]
N-288 [T3]
N-307-2 [T5]
N-322 [T3]
N-335-1 [T3]
N-375 [T5]
N-389-1 [T3]
N-402-1 [T3]
N-408-2 [T5]
N-409-2 [T5]
N-416-1 [T5]
N-419 [T3]
N-429 [T5]
N-432-1 [T1]
N-436-1 [T3]
N-446 [T3]
N-458 [T5]
N-461-1 [T3]
N-465-11
N-473-11
N-4801
N-489 [T3]
N-491-1 [T5]
N-494-2 [T5]
N-496 [T5]
N-498-1 [T5]
N-503 [T3]
N-504-3 [T5]
N-508-2 [T5]
N-512 [T5]
N-513-2 [T5]
N-515 [T3]

N-516 [T5]
N-516-4 [T2]
N-522 [T3]
N-524 [T3]
N-532 [T5]
N-532-4 [T5]
N-534 [T3]
N-541 [T3]
N-545 [T3]
N-552-1 [T2]
N-554-1 [T5]
N-556 [T3]
N-560-1 [T5]
N-561-2 [T2]
N-563 [T3]
N-567 [T5]
N-569-1 [T2]
N-576 [T5]
N-577-11
N-586 [T5]
N-5891 [T5]
N-592 [T3]
N-597 [T5]
N-598 [T3]
N-603 [T3]
N-606-1 [T5]
N-6131
N-616 [T2]
N-619 [T2]
N-627 [T3]
N-638-1 [T5]
N-638-5 [T5]
N-640 [T3]
N-643-2 [T1]
N-648-2 [T2]
N-652-1 [T5]
N-6541
N-661-1 [T5]
N-662-1 [T2]
N-666 [T5]
N-686 [T5]
N-694-1 [T5]
N-696 [T5]
N-702 [T2]
N-711[T5]
N-7161
N-722-21
N-729-32

N-516-1 [T5]
N-517 [T5]
N-523 [T5]
N-526 [T1]
N-532-1 [T5]
N-532-5 [T1]
N-535 [T3]
N-5421
N-546 [T4]
N-553 [T5]
N-554-2 [T5]
N-557 [T5]
N-560-21
N-562 [T5]
N-566 [T5]
N-567-1 [T1]
N-573 [T1]
N-576-1 [T5]
N-578 [T5]
N-586-1 [T1]
N-589-11
N-5931
N-597-1 [T5]
N-599 [T4]
N-604 [T3]
N-606-2 [T2]
N-613-1 [T5]
N-617 [T3]
N-6221
N-629 [T1]
N-638-2 [T5]
N-638-6 [T5]
N-641 [T1]
N-647 [T2]
N-649 [T1]
N-652-2 [T1]
N-658 [T1]
N-661-2 [T5]
N-663 [T1]
N-666-1 [T2]
N-686-1 [T1]
N-694-2 [T1]
N-696-1 [T2]
N-705 [T2]
N-711-1[T2]
N-716-1 [T1]
N-7291
N-729-42

N-516-2 [T5]
N-517-1 [T1]
N-523-1 [T5]
N-528 [T5]
N-532-2 [T5]
N-533 [T5]
N-537 [T1]
N-543 [T3]
N-5471
N-553-1 [T3]
N-554-3 [T1]
N-557-1 [T2]
N-561 [T5]
N-562-[T5]
N-566-1 [T5]
N-568 [T4]
N-5741
N-576-2 [T2]
N-578-11
N-5871
N-5901
N-593-1 [T5]
N-597-2 [T5]
N-600 [T1]
N-605 [T3]
N-609 [T5]
N-613-2 [T1]
N-6181
N-623 [T3]
N-630 [T4]
N-638-3 [T5]
N-638-7 [T2]
N-643 [T5]
N-648 [T5]
N-651 [T1]
N-6531
N-660 [T2]
N-661-3 [T1]
N-664 [T1]
N-683 [T1]
N-6911
N-695 [T5]
N-697 [T1]
N-706 [T5]
N-712 [T1]
N-7222
N-729-12
N-730 [T5]

Appendix C to DG-1342, Page C-2

N-516-3 [T5]
N-521 [T3]
N-523-2 [T3]
N-528-1 [T1]
N-532-3 [T5]
N-533-1 [T2]
N-538 [T3]
N-544 [T3]
N-552 [T5]
N-554 [T5]
N-555 [T3]
N-560 [T5]
N-561-1 [T5]
N-562-2 [T2]
N-566-2 [T1]
N-569 [T5]
N-5751
N-577 [T5]
N-583 [T2]
N-588 [T3]
N-5911
N-593-2 [T2]
N-597-3 [T2]
N-601 [T3]
N-606 [T5]
N-609-1 [T1]
N-6151
N-618-11
N-624 [T1]
N-638 [T5]
N-638-4 [T5]
N-639 [T2]
N-643-1 [T5]
N-648-1 [T5]
N-652 [T5]
N-653-1 [T1]
N-661 [T5]
N-662 [T5]
N-665 [T1]
N-685 [T1]
N-694 [T5]
N-695-1[T2]
N-700 [T1]
N-706-1 [T1]
N-7131
N-722-12
N-729-22
N-730-1 [T1]

N-731 [T1]
N-739-1 [T1]
N-747 [T1]
N-754 [T5]
N-762-1[T1]
N-769 [T5]
N-770-12
N-775 [T1]
N-7841
N-789-1 [T5]
N-798 [T1]
N-8061
N-824 [T2]
N-830 [T2]
N-842 [T1]
N-853 [T1]

N-733 [T1]
N-7401
N-749 [T2]
N-754-1 [T2]
N-765 [T1]
N-769-1 [T5]
N-770-22
N-776 [T1]
N-786 [T5]
N-789-2 [T1]
N-800 [T1]
N-8131
N-825 [T1]
N-831[T2]
N-843 [T2]
N-854 [T1]

N-735 [T1]
N-740-11
N-751 [T2]
N-7551
N-766 [T5]
N-769-2 [T1]
N-771 [T1]
N-778 [T2]
N-786-1 [T1]
N-795 [T2]
N-803 [T1]
N-823 [T5]
N-8261
N-838[T2]
N-845 [T1]

Appendix C to DG-1342, Page C-3

N-739 [T5]
N-740-21
N-753 [T1]
N-762 [T5]
N-766-1 [T2]
N-7702
N-773 [T1]
N-7801
N-789 [T5]
N-799 [T2]
N-805 [T1]
N-823-1 [T1]
N-829 [T2]
N-839 [T1]
N-849 [T2]