Draft Reg Guide DG-1231

Draft Reg Guide DG-1231.pdf

10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities

Draft Reg Guide DG-1231

OMB: 3150-0011

⚠️ Notice: This form may be outdated. More recent filings and information on OMB 3150-0011 can be found here:
Document [pdf]
Download: pdf | pdf
U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REGULATORY RESEARCH

June 2013
Division 1

DRAFT REGULATORY GUIDE
Contact: W. Norris
(301) 251-7650

DRAFT REGULATORY GUIDE DG-1231
(Proposed Revision 17 of Regulatory Guide 1.147, dated October 2010)

INSERVICE INSPECTION CODE CASE ACCEPTABILITY,
ASME SECTION XI, DIVISION 1
A. INTRODUCTION
General Design Criterion (GDC) 1, “Quality Standards and Records,” of Appendix A, “General
Design Criteria for Nuclear Power Plants,” to Title 10, Part 50, of the Code of Federal Regulations
(10 CFR Part 50), “Domestic Licensing of Production and Utilization Facilities” (Ref. 1), 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 functions 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.
Provisions of the ASME International Boiler and Pressure Vessel (B&PV) 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.
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.

This regulatory guide is being issued in draft form to involve the public in the early stages of the development of a regulatory
position in this area. It has not received final staff review or approval and does not represent an official NRC final staff position.
Public comments are being solicited on this draft guide (including any implementation schedule) and its associated regulatory
analysis or value/impact statement. Comments should be accompanied by appropriate supporting data. Written comments may be
submitted to the Rules, Announcements, and Directives Branch, Office of Administration, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001; submitted through the NRC’s interactive rulemaking Web page at http://www.nrc.gov; or faxed to
(301) 492-3446. Copies of comments received may be examined at the NRC’s Public Document Room, 11555 Rockville Pike,
Rockville, MD. Comments will be most helpful if received by September 9, 2013.
Electronic copies of this draft regulatory guide are available through the NRC’s interactive rulemaking Web page (see above); the
NRC’s public Web site under Draft Regulatory Guides in the Regulatory Guides document collection of the NRC Library at
http://www.nrc.gov/reading-rm/doc-collections/; and the NRC’s Agencywide Documents Access and Management System
(ADAMS) at http://www.nrc.gov/reading-rm/adams.html, under Accession No. ML102590004.

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. Every 3 years the ASME publishes a new edition of the BPV Code,
including Section XI, and new addenda are published every year. The latest editions and addenda of
Section XI that the U.S. Nuclear Regulatory Commission (NRC) has approved for use are referenced in
10 CFR 50.55a(a)(1)(ii). The ASME also publishes Code Cases quarterly. Code Cases provide
alternatives to existing Code requirements that the ASME developed and approved. This regulatory guide
identifies the Code Cases that the NRC has determined to be acceptable alternatives to applicable parts of
Section XI. Licenses may use these Code Cases without requesting authorization from the NRC,
provided that they are used with any identified limitations or modifications. 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, which the NRC will amend to
incorporate this guide by reference; 10 CFR 50.55a states the requirements governing the use of Code
Cases. 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. Code Cases approved by the NRC provide an acceptable voluntary alternative to the mandatory
ASME Code provisions.
Paperwork Reduction Act Statement
This regulatory guide does not contain new or amended information collection requirements
subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.) (Ref. 3). Existing information
collection requirements were approved by the Office of Management and Budget, control number 31500011.
Public Protection Notification
The NRC may not conduct or sponsor, and a person is not required to respond to, a request for
information or an information collection requirement unless the requesting document displays a currently
valid OMB control number.
This regulatory guide is a rule as designated in the Congressional Review Act (5 U.S.C. 801-808)
(Ref. 13). However, the NRC has determined this regulatory guide is not a major rule as designated by
the Congressional Review Act and has verified this determination with the OMB.

DG-1231, Page 2

B. DISCUSSION
For Revision 17 of Regulatory Guide 1.147, the NRC reviewed the Section XI Code Cases listed
in Supplements 1 through 10 to the 2007 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 published by the ASME in the seven supplements. 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.

Code Cases that the NRC has determined to be unacceptable are listed in Regulatory Guide
1.193, “ASME Code Cases Not Approved for Use” (Ref. 4).
Code Cases provide alternatives to existing Code requirements that the ASME developed and
approved. The new Code Cases and revisions to existing Code Cases listed as approved in Tables 1 and 2
of this guide will be incorporated by reference into 10 CFR 50.55a. Code Cases approved by the NRC
may be used voluntarily by licensees as an alternative to compliance with ASME Code provisions
incorporated by reference into 10 CFR 50.55a.
When a licensee initially implements a Code Case, 10 CFR 50.55a requires that the most recent
version of that Code Case as listed in Tables 1 and 2 be implemented. If a Code Case is implemented by
a licensee and a later version of the Code Case is incorporated by reference into 10 CFR 50.55a and listed
in Tables 1 and 2 during the licensee’s present 120-month ISI program interval, that licensee may use
either the later version or the previous version. An exception to this provision would be the inclusion
of a limitation or condition on the use of the Code Case that is necessary, for example, to enhance safety.
Licensees who choose to continue use of the Code Case during the subsequent 120-month ISI program
interval will be required to implement the latest version incorporated by reference into 10 CFR 50.55a
and listed in Tables 1 and 2.
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 a Code Case is annulled and 10 CFR 50.55a
and this guide are amended, licensees may not implement that Code Case for the first time. However, a
DG-1231, Page 3

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 prior to the rulemaking. Notwithstanding these requirements, the Commission may impose
new or revised Code requirements, including implementation schedules, that it determines are consistent
with the Backfit Rule (10 CFR 50.109).
Code Cases 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 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 regulatory requirements or licensee commitments.

DG-1231, Page 4

C. STAFF REGULATORY GUIDANCE
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. The ASME will issue a new edition of Section XI in 2011 and every two years thereafter.
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., “3/07E” means Code Case Supplement 3 to the
2007 Edition).
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-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-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

5/10E

N-534

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

5/09/03

N-537

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

3/28/01

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

DG-1231, Page 5

Code Case
Number

Table 1
Acceptable Section XI Code Cases

Date or
Supplement/
Edition

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

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

7/30/98

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

8/20/02

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-652-1

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

2/20/04

N-658

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

4/4/02

N-663

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

9/17/02

DG-1231, Page 6

Code Case
Number

Table 1
Acceptable Section XI Code Cases

Date or
Supplement/
Edition

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-666

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

4/18/06

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-695

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

5/21/03

N-696

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

5/21/03

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-705

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

10/12/06

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
(Note: Code Case N-706 was unconditionally approved in Revision 15 to
Regulatory Guide 1.147)

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

N-730

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

10/04/06

N-731

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

2/22/05

DG-1231, Page 7

1/13E

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-747

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

9/04E

N-753

Vision Tests, Section XI, Division 1

N-762

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

1/07E

N-765

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

8/07E

N-769

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

8/07E

N-773

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

8/07E

DG-1231, Page 8

7/14/06

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 ASME will issue a new edition of Section XI in 2011 and every two years thereafter. 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., “3/07E” means Code Case Supplement 3 to the
2007 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-1231, Page 9

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

8/07E

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-513-3

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

1/26/09

The repair or replacement activity temporarily deferred under the provisions of
this Code Case shall be performed during the next scheduled outage.
N-516-3

Underwater Welding, Section XI, Division 1

4/08/02

Licensees must obtain NRC approval in accordance with 10 CFR 50.55a(z)
regarding the technique to be used in the weld repair or replacement of irradiated
material underwater.
N-528-1

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

4/19/02

The requirements of 10 CFR Part 21, “Reporting of Defects and Noncompliance”
(Ref. 5), are to be applied to the nuclear plant site supplying the material as well
as to the nuclear plant site receiving the material that has been purchased,
exchanged, or transferred between sites.
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
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-1231, Page 10

4/08/02

Code Case
Number

Table 2
Conditionally Acceptable Section XI Code Cases
Condition

N-552

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

Date or
Supplement/
Edition
4/19/02

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-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

1/07E

(1) Paragraph 5(b): for repairs performed on a wet surface, the overlay is only
acceptable until the next refueling outage.
(2) Paragraph 6(c)(1): this exemption is not permitted.
(3) Paragraph 7(c): if the cause of the degradation has not been determined, the
repair is only acceptable until the next refueling outage.
(4) The area where the weld overlay is to be applied must be examined using
ultrasonic methods to demonstrate that no crack-like defects exist.
(5) Paragraph 4(b): All systems must be depressurized before welding.
Note: Previous versions of this Code Case were not approved for use.
N-562-2

Alternative Requirements for Wall Thickness Restoration of Class 3 Moderate
Energy 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 6(c)(1): this exemption is not permitted.
(3) Paragraph 7(c): if the cause of the degradation has not been determined, the
repair is only acceptable until the next refueling outage.
(4) The area where the weld overlay is to be applied must be examined using
ultrasonic methods to demonstrate that no crack-like defects exist.
(5) All systems must be depressurized before welding.
Note: Previous versions of this Code Case were not approved for use.

DG-1231, Page 11

1/07E

Code Case
Number

Table 2
Conditionally Acceptable Section XI Code Cases
Condition

N-569-1

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

Date or
Supplement/
Edition
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-576-1

Repair of Class 1 and 2 SB-163, UNS N06600 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-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

Alternative Examination Requirements for Steam Generator Nozzle to Vessel
Welds, Section XI, Division 1
Essentially 100 percent (not less than 90 percent) of the examination volume
A-B-C-D-E-F-G-H must be inspected.

DG-1231, Page 12

2/14/03

Code Case
Number

Table 2
Conditionally Acceptable Section XI Code Cases
Condition

N-597-2

Requirements for Analytical Evaluation of Pipe Wall Thinning, Section XI,
Division 1
(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” (Ref. 6), 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. 7) 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) For moderate-energy Class 2 and 3 piping, wall thinning acceptance criteria
may be determined on a temporary basis (until the next refueling outage)
based on the provisions of Code Case N-513-2. Moderate-energy 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.

DG-1231, Page 13

Date or
Supplement/
Edition
11/18/03

Code Case
Number

Table 2
Conditionally Acceptable Section XI Code Cases
Condition

N-606-1

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 or
Supplement/
Edition
8/20/02

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. The surfaces to be welded, and surfaces
adjacent to the weld, are to be free from contaminants, such as, rust, moisture,
grease, and other foreign material or any other condition that would prevent
proper welding and adversely affect the quality or strength of the weld. This
verification is to be required in the welding procedures.
N-616

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

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 10minute 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 visual examination with
enhanced magnification that has a resolution sensitivity to detect a 1-mil width
wire or crack, utilizing the allowable flaw length criteria of Table IWB-3512-1
with limiting assumptions on the flaw aspect ratio.
N-638-4

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.

DG-1231, Page 14

10/05/06

Code Case
Number

Table 2
Conditionally Acceptable Section XI Code Cases
Condition

N-639

Alternative Calibration Block Material, Section XI, Division 1

Date or
Supplement/
Edition
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

11/18/03

A VT-1 examination is to be used in lieu of the “detailed visual examination.”
[Note: Draft Regulatory Guide DG-1070, “Sampling Plans Used for Dedicating
Simple Metallic Commercial Grade Items for Use in Nuclear Power Plants”
(Ref. 8), is being developed to provide acceptable guidelines for sampling
criteria.]
N-648-1

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

9/18/01

In lieu of a UT examination, licensees may perform a visual examination with
enhanced magnification that has a resolution sensitivity to detect a 1-mil width
wire or crack, utilizing the allowable flaw length criteria of Table IWB-3512-1
with limiting assumptions on the flaw aspect ratio.
In place of a UT examination, licensees may perform a visual examination with
enhanced magnification that has a resolution sensitivity to detect a 1-mil wire or
crack, utilizing the allowable flaw length criteria of Table IWB-3512-1 with
limiting assumptions on the flaw aspect ratio. The provisions of Table IWB2500-1, Examination Category B-D, continue to apply except that, in place of
examination volumes, the surfaces to be examined are the external surfaces
shown in the figures applicable to the table (the external surface is from point M
to point N in the figure).
N-660

Risk-Informed Safety Classification for Use in Risk-Informed Repair/Replacement
Activities, Section XI, Division 1
The Code Case must be applied only to ASME Code Classes 2 and 3, and nonCode Class pressure retaining components and their associated supports.

DG-1231, Page 15

7/23/02

Code Case
Number

Table 2
Conditionally Acceptable Section XI Code Cases
Condition

N-661-2

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

Date or
Supplement/
Edition
1/07E

(1) Paragraph 4(b): for repairs performed on a wet surface, the overlay is only
acceptable until the next refueling outage.
(2) Paragraph 6(c)(1): this exemption is not permitted.
(3) Paragraph 7(c): if the cause of the degradation has not been determined, the
repair is only acceptable until the next refueling outage.
(4) The area where the weld overlay is to be applied must be examined using
ultrasonic methods to demonstrate that no crack-like defects exist.
(5) All systems must be depressurized before welding.
Note: Conditions (1) and (3) were listed in Revision 16 to RG 1.147 for Code
Case N-661-1.
N-662

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

8/20/02

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-694-1

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

2/20/04

(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 of Raju and Newman (Ref. 11) is only
applicable to cylindrical products having a ratio of wall thickness to inside
radius between 0.1 and 0.25.
N-702

Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius
and Nozzle-to-Shell Welds, Section XI, Division 1
The technical basis supporting the implementation of this Code Case is
addressed by BWRVIP-108: BWR Vessel and Internals Project, “Technical
Basis for the Reduction of Inspection Requirements for the Boiling Water
Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii,” EPRI
Technical Report 1003557, October 2002 (ML-023330203). The applicability
of Code Case N-702 must be shown by demonstrating that the criteria in Section
5.0 of NRC Safety Evaluation regarding BWRVIP-108 dated December 18,
2007 (ML073600374) are met. The evaluation demonstrating the applicability
of the Code Case shall be reviewed and approved by the NRC prior to the
application of the Code Case.

DG-1231, Page 16

12/01E

Code Case
Number

Table 2
Conditionally Acceptable Section XI Code Cases
Condition

N-739-1

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

Date or
Supplement/
Edition
1/07E

The ACI reference should be ACI 201.1.
Note: N-739 was not approved by the NRC.
N-751

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

DG-1231, Page 17

8/03/06

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

11/20/81

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

N-306

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

5/7/90

DG-1231, Page 18

Code Case
Number

Table 3
Annulled Unconditionally Approved Section XI Code Cases

Annulment Date

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-1231, Page 19

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-1231, Page 20

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
IWB-3514.2, 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-1231, Page 21

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

4/19/02

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-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-2500-1, 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
[Note: Draft Regulatory Guide DG-1070 (Ref. 8) is being developed to
provide acceptable guidelines for sampling criteria.]

3/28/04

N-617

Alternative Examination Distribution Requirements for Table
IWC-2500-1, Examination Category C-G, Pressure Retaining Welds in
Pumps and Valves, Section XI, Division 1

4/19/02

N-541

DG-1231, Page 22

3/28/01

Code Case
Number

Table 3
Annulled Unconditionally Approved Section XI Code Cases

Annulment Date

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-1231, Page 23

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.)
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.

DG-1231, Page 24

2/19/92

Code Case
Number
N-509

Table 4
Annulled Conditionally Acceptable Section XI Code Cases

Annulment Date

Alternative Rules for the Selection and Examination of Class 1, 2, and 3
Integrally Welded Attachments, Section XI, Division 1

5/20/01

A minimum 10% sample of integrally welded attachments for each
item in each Code class per interval should be examined.
N-512-1

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

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 CP189, “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-1231, Page 25

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
IWB-2500-1, 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

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

DG-1231, Page 26

Code Case
Number
N-389

Table 5
Section XI Code Cases That Have Been Superseded
Alternative Rules for Repairs, Replacements, or Modifications,
Section XI, Division 1

Date
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

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

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-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.
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
7/7/01
N-416-3 Published on
1/12/05
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

DG-1231, Page 27

Code Case
Number

Table 5
Section XI Code Cases That Have Been Superseded

Date

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

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

DG-1231, Page 28

Code Case
Number

Table 5
Section XI Code Cases That Have Been Superseded

Date

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

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

(1)
(2)

N-516
N-516-1

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

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.

DG-1231, Page 29

N-516-1 Published on
12/31/96;
N-516-2 Published on
1/17/00

Code Case
Number
N-516-2

Table 5
Section XI Code Cases That Have Been Superseded
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-516-3 Published on
4/8/02

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-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

DG-1231, Page 30

N-533-1 Published
2/26/99

Code Case
Number
N-561

Table 5
Section XI Code Cases That Have Been Superseded

Date

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

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-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

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-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

N-561-1
N-562
N-562-1

N-561-2 Published on
3/22/07

N-562-2 Published on
3/22/07

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-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-606

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

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

DG-1231, Page 31

Code Case
Number
N-638
N-638-1
N-638-2
N-638-3

Table 5
Section XI Code Cases That Have Been Superseded

Date

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

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

N-638-2 Published on
N-638-3 Published on
4/19/06
N-638-4 Published on
10/12/06

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-652

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-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

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

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
(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 is only
applicable to cylindrical products having a ratio of wall
thickness to inside radius between 0.1 and 0.25.

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

DG-1231, Page 32

Code Case
Number

Table 5
Section XI Code Cases That Have Been Superseded

Date

N-706

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

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

N-716

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

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

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

DG-1231, Page 33

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.

REGULATORY ANALYSIS
A separate regulatory analysis was not prepared for this regulatory guide. The regulatory basis
for this guide is the regulatory analysis prepared for the amendment to 10 CFR 50.55a, “Codes and
Standards.” The amendment to 10 CFR 50.55a incorporates this regulatory guide by reference.

DG-1231, Page 34

REFERENCES1
1.

Code of Federal Regulations, Title 10, Energy, Part 50, “Domestic Licensing of Production and
Utilization Facilities” (10 CFR Part 50), 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.

Paperwork Reduction Act of 1995 (Public Law 104-13), United States Code, Title 44,
“Public Printing and Documents,” Chapter 35, “Coordination of Federal Information Policy”
(44 U.S.C. 3501 et seq.), 104th Congress of the United States of America, Washington, DC.3

4.

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

5.

Code of Federal Regulations, Title 10, Energy, Part 21, “Reporting of Defects and
Noncompliance” (10 CFR Part 21), U.S. Nuclear Regulatory Commission, Washington, DC.

6.

EPRI Nuclear Safety Analysis Center Report 202L-R2, “Recommendations for an Effective
Flow Accelerated Corrosion Program,” Electric Power Research Institute, Palo Alto, California,
April 1999.4

7.

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

8.

Draft Regulatory Guide DG-1070, “Sampling Plans Used for Dedicating Simple Metallic
Commercial Grade Items for Use in Nuclear Power Plants,” U.S. Nuclear Regulatory
Commission, Washington, DC. [DG-1070 was issued in October 1997.]

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/. The documents can also be viewed on-line or
printed for a fee in the NRC’s Public Document Room (PDR) at 11555 Rockville Pike, Rockville, MD; the mailing
address is USNRC PDR, Washington, DC 20555; telephone 301-415-4737 or (800) 397-4209; fax (301) 415-3548; and
e-mail pdr.resource@nrc.gov.

2

Copies may be purchased from the American Society of Mechanical Engineers, Three Park Avenue, NewYork, NY
10016-5990; phone (212) 591-8500; fax (212) 591-8501; www.asme.org.

3

The Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.) is available electronically through the Federal Register
Web site administered by the U.S. National Archives and Records Administration, at http://www.archives.gov/ federalregister/laws/paperwork-reduction/.

4

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.

DG-1231, Page 35

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.5

11.

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

12.

ASME RA-S-2005, “Standard for Probabilistic Risk Assessment for Nuclear Power Plant
Applications,” American Society of Mechanical Engineers, New York, NY2

13.

The Congressional Review Act, a part of the Small Business Regulatory Enforcement Fairness
Act of 1996, is available through the Federal Register Web site administered by the U.S. National
Archives and Records Administration, at http://www.archives.gov/federalregister/laws/congressional-review

____________________________________
5

Copies may be obtained from the American Society for Nondestructive Testing, 1711 Arlingate Late, 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-1231, Page 36

APPENDIX A
SUPPLEMENTS ADDRESSED IN PROPOSED REVISION 17
OF REGULATORY GUIDE 1.147

1
2
3
4

Edition

Supplement Number

BNCS1 Approval Date of Code Cases in Supplement2

2007

1

March 22, 2007

2007

2

October 19, 2007

2007

3

October 19, 20073

2007

4

January 4, 2008

2007

5

February 12, 2008

2007

6

June 9, 2008

2007

7

November 10, 2008

2007

8

January 26, 2009

2007

9

April 27, 2009

2007

10

May 15, 20094

BNCS = ASME Board on Nuclear Codes and Standards
Publication of supplements approximately 6 months after BNCS approval.
No nuclear Code Cases were published in Supplement 3 to the 2007 Edition.
Only errata published in Supplement 10 to the 2007 Edition.

Appendix A to DG-1231, Page A-1

APPENDIX B
NUMERICAL LISTING OF SECTION XI CODE CASES IN
SUPPLEMENT 1 THROUGH SUPPLEMENT 10 TO THE 2007 EDITION
N-494-4
N-513-3
N-508-4
N-532-53
N-561-2

M-562-2
N-638-4
N-661-2
N-7131
N-716-14

N-722-12
N-739-1
N-740-11
N-740-21
N-7551

N-762
N-765
N-769
N-7702
N-773

_____________

1

Code Case in unacceptable for use. See Draft Regulatory Guide DG-1193, proposed Revision 4 of
Regulatory Guide 1.193.

2

Code Case is directly addressed in 10 CFR 50.55a.

3

Code Case published in Supplement 5 to the 2010 Edition.

4

Code Case published in Supplement 1 to the 2013 Edition.

Appendix B to DG-1231, Page B-1

APPENDIX C
NUMERICAL LISTING OF SECTION XI CODE CASES
AND TABLE WHERE EACH CODE CASE IS LISTED
N-34 [T3]
N-72 [T3]
N-73 [T3]
N-98 [T3]
N-112 [T3]
N-113 [T5]
N-113-1 [T3]
N-118 [T4]
N-167 [T3]
N-198-1 [T3]
N-210 [T4]
N-211 [T3]
N-216 [T3]
N-234 [T3]
N-235 [T3]
N-236 [T5]
N-236-1 [T3]
N-252 [T4]
N-278 [T4]
N-288 [T3]
N-306 [T3]
N-307 [T5]
N-307-1 [T5]
N-307-2 [T5]
N-307-3 [T3]
N-308 [T3]
N-311 [T3]
N-322 [T3]
N-323-1 [T3]
N-334 [T3]
N-335 [T5]
N-335-1 [T3]
N-343 [T3]
N-355 [T3]
N-356 [T3]
N-375 [T5]
N-375-1 [T5]
N-375-2 [T3]
N-389 [T5]
N-389-1 [T3]
N-401 [T5]

N-401-1 [T3]
N-402 [T5]
N-402-1 [T3]
N-406 [T3]
N-408 [T5]
N-408-1 [T5]
N-408-2 [T5]
N-408-3 [T3]
N-409 [T5]
N-409-1 [T5]
N-409-2 [T5]
N-409-3 [T3]
N-415 [T3]
N-416 [T5]
N-416-1 [T5]
N-416-2 [T5]
N-416-3 [T5]
N-416-4 [T2]
N-419 [T3]
N-424 [T3]
N-426 [T3]
N-427 [T3]
N-429 [T5]
N-429-1 [T5]
N-429-2 [T3]
N-432 [T5]
N-432-1 [T1]
N-435 [T5]
N-435-1 [T3]
N-436 [T5]
N-436-1 [T3]
N-437 [T3]
N-444 [T3]
N-445 [T3]
N-446 [T3]
N-448 [T3]
N-449 [T3]
N-457 [T3]
N-458 [T5]
N-458-1 [T3]
N-460 [T1]

N-461 [T5]
N-461-1 [T3]
N-463 [T5]
N-463-1 [T3]
N-4651
N-465-11
N-471 [T3]
N-472 [T3]
N-4731
N-473-11
N-478 [T3]
N-479 [T5]
N-479-1 [T3]
N-4801
N-481 [T3]
N-485 [T5]
N-485-1 [T3]
N-489 [T3]
N-490 [T5]
N-490-1 [T3]
N-491 [T5]
N-491-1 [T5]
N-491-2 [T1]
N-494 [T5]
N-494-1 [T5]
N-494-2 [T5]
N-494-3 [T5]
N-494-4 [T1]
N-495 [T3]
N-496 [T5]
N-496-1 [T3] [T5]
N-496-2 [T1]
N-498 [T5]
N-498-11 [T5]
N-498-21 [T5]
N-498-31 [T5]
N-498-4 [T2]
N-503 [T3]
N-504 [T5]
N-504-1 [T5]
N-504-2 [T5]

Appendix C to DG-1231, Page C-1

N-504-3 [T5]
N-504-4 [T2]
N-508 [T5]
N-508-1 [T5]
N-508-2 [T5]
N-508-3 [T5]
N-508-4 [T2]
N-509 [T4]
N-512 [T5]
N-512-1 [T4]
N-513 [T5]
N-513-1 [T5]
N-513-2 [T5]
N-513-3 [T2]
N-514 [T3]
N-515 [T3]
N-516 [T5]
N-516-1 [T5]
N-516-2 [T5]
N-516-3 [T2]
N-517 [T5]
N-517-1 [T1]
N-521 [T3]
N-522 [T3]
N-523 [T5]
N-523-1 [T5]
N-523-2 [T3]
N-524 [T3]
N-526 [T1]
N-528 [T5]
N-528-1 [T2]
N-532 [T5]
N-532-1 [T5]
N-532-2 [T5]
N-532-3 [T5]
N-532-4 [T5]
N-532-53 [T1]
N-533 [T5]
N-533-1 [T2]
N-534 [T1]
N-535 [T3]

N-537 [T1]
N-538 [T3]
N-541 [T3]
N-5421
N-543 [T3]
N-544 [T3]
N-545 [T3]
N-546 [T4]
N-5471
N-552 [T2]
N-553 [T5]
N-553-1 [T1]
N-554 [T5]
N-554-1 [T5]
N-554-2 [T5]
N-554-3 [T1]
N-555 [T3]
N-556 [T3]
N-557 [T5]
N-557-1 [T2]
N-560 [T5]
N-560-11 [T5]
N-560-21
N-5611 [T5]
N-561-11 [T5]
N-561-2 [T2]
N-5621 [T5]
N-562-11
N-562-2 [T2]
N-563 [T3]
N-566 [T5]
N-566-1 [T5]
N-566-2 [T1]
N-567 [T5]
N-567-1 [T1]
N-568 [T4]
N-569 [T5]
N-569-1 [T2]
N-573 [T1]
N-5741

N-5751
N-576 [T5]
N-576-1 [T2]
N-5771 [T5]
N-577-11
N-5781 [T5]
N-578-11
N-583 [T2]
N-586 [T5]
N-586-1 [T1]
N-5871
N-588 [T3]
N-5891 [T5]
N-589-11
N-5901
N-5911
N-592 [T3]
N-593 [T2]
N-593-11
N-597 [T5]
N-597-1 [T5]
N-597-2 [T2]
N-598 [T3]
N-599 [T4]
N-600 [T1]
N-601 [T3]
N-603 [T3]
N-604 [T3]
N-605 [T3]
N-606 [T5]
N-606-1 [T2]
N-609 [T1]
N-6131
N-613-1 [T1]
N-6151
N-616 [T2]
N-617 [T3]
N-6181
N-618-11
N-619 [T2]

N-6221
N-623 [T3]
N-624 [T1]
N-627 [T3]
N-629 [T1]
N-630 [T4]
N-638 [T5]
N-638-1 [T5]
N-638-3 [T3]
N-638-4 [T2]
N-639 [T2]
N-640 [T3]
N-641 [T1]
N-643 [T5]
N-643-1 [T5]
N-643-2 [T1]
N-647 [T2]
N-648 [T5]
N-648-1 [T2]
N-649 [T1]
N-651 [T5]
N-652 [T5]
N-652-1 [T1]
N-6531
N-6541
N-658 [T1]
N-660 [T2]
N-661 [T5]
N-661-1 [T1]
N-661-2 [T2]
N-662 [T2]
N-663 [T1]
N-664 [T1]
N-665 [T1]
N-666 [T1]
N-683 [T1]
N-685 [T1]
N-686 [T5]
N-686-1 [T1]
N-6911

N-694-1 [T5]
N-694-2 [T5]
N-694-2 [T2]
N-695 [T1]
N-696 [T1]
N-697 [T1]
N-700 [T1]
N-702 [T2]
N-705 [T1]
N-706 [T5]
N-706-1 [T1]
N-7111
N-712 [T1]
N-7131
N-7161
N-716-14 [T1]
N-7222
N-722-12
N-7291
N-729-12
N-730 [T1]
N-731 [T1]
N-733 [T1]
N-735 [T1]
N-739 [T5]
N-739-1 [T2]
N-7401
N-740-11
N-740-21
N-747 [T1]
N-751 [T2]
N-753 [T1]
N-7551
N-762 [T1]
N-765 [T1]
N-769 [T1]
N-7701
N-773 [T1]

———

1
2

3
4

Code Case is unacceptable for use. See Draft Regulatory Guide DG-1193, proposed Revision 4 of
Regulatory Guide 1.193.
Code Case is directly addressed in 10 CFR 50.55a.
Code Case N-532-5 was published in Supplement 5 to the 2010 Edition.
Code Case N-716-1 was published in Supplement 1 to the 2013 Edition.

Appendix C to DG-1231, Page C-2
File Type	application/pdf
File Modified	2013-06-21
File Created	2013-06-21