The U.S. Nuclear Regulatory Commission (NRC) issues regulatory guides to describe and make available to the public methods that the NRC staff considers acceptable for use in implementing specific parts of the agency’s regulations, techniques that the staff uses in evaluating specific problems or postulated accidents, and data that the staff needs in reviewing applications for permits and licenses.  Regulatory guides are not substitutes for regulations, and compliance with them is not required.  Methods and solutions that differ from those set forth in regulatory guides will be deemed acceptable if they provide a basis for the findings required for the issuance or continuance of a permit or license by the Commission.
This guide was issued after consideration of comments received from the public.
Regulatory guides are issued in 10 broad divisions:  1, Power Reactors; 2, Research and Test Reactors; 3, Fuels and Materials Facilities; 4, Environmental and Siting;5, Materials and Plant Protection; 6, Products; 7, Transportation; 8, Occupational Health; 9, Antitrust and Financial Review; and 10, General.
Electronic copies of this guide and other recently issued guides are available through the NRC’s public Web site under the Regulatory Guides document collection of
U.S. NUCLEAR REGULATORY COMMISSION  October 2007
Revision 15
REGULATORY GUIDE
OFFICE OF NUCLEAR REGULATORY RESEARCH
REGULATORY GUIDE 1.147
(Draft was issued as DG-1134, dated October 2006)
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 American Society of Mechanical Engineers (ASME) 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 co
mponents 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.
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(b).  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 the
y are used with any identified limitations or modifications.  Section XI Code Cases that the NRC has not yet endorsed may be implemented through 10 CFR 50.55a(a)(3), which 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.
B.  DISCUSSION
For Revision 15 of Regulatory Guide 1.147, the NRC staff reviewed the Section XI Code Cases listed in Supplements 7–12 to the 2001 Edition, and Supplement 1 to the 2004 Edition of the ASME BPV Co
de.  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 limitations or modifications (i.e., the
Code Case is generally acceptable but the NRC has determined that the alternative requirements 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 limitations or modifications, 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 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 are 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 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(a)(3).
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).
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.
C.  REGULATORY POSITION
1.Acceptable Section XI Code Cases
The Code Cases listed in Table 1 are acceptable to the NRC for application in licensees’Section XI inservice inspection programs.
Table 1.  Acceptable Section XI Code Cases
Code Case Number
Table 1
Acceptable Section XI Code Cases
ASME
Approval Date
N-307-3Revised 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
3/28/01
N-334Examination Requirements for Integrally Welded or Forged Attachments to
Class 2 Piping at Containment Penetrations, Section XI, Division 1
5/9/03
N-416-3Alternative Pressure Test Requirement for Welded Repairs or Installation of
Replacement Items by Welding, Class 1, 2, and 3, Section XI, Division 1
9/7/01
N-432-1Repair Welding Using Automatic or Machine Gas Tungsten-Arc Welding
(GTAW) Temper Bead Technique, Section XI, Division 1
3/28/01
N-460Alternative Examination Coverage for Class 1 and Class 2 Welds,
Section XI, Division 1
2/14/03
N-471Acoustic Emission for Successive Inspections, Section XI, Division 14/19/02 N-491-2Rules for Examination of Class 1, 2, 3, and MC Component Supports of Light-
Water Cooled Power Plants, Section XI, Division 1
2/14/03
N-494-3Pipe 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
4/19/02
N-496-2Helical-Coil Threaded Inserts, Section XI, Division 19/18/01 N-508-3Rotation of Serviced Snubbers and Pressure Relief Valves for the Purpose of
Testing, Section XI, Division 1
11/18/03
N-513-2Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy
Class 2 or 3 Piping, Section XI, Division 1
2/20/04 N-517-1Quality Assurance Program Requirements for Owners, Section XI, Division 13/28/01 N-522Pressure Testing of Containment Penetration Piping, Section XI, Division 14/8/02
N-526Alternative Requirements for Successive Inspections of Class 1 and 2 Vessels,
Section XI, Division 1
8/20/02
Code Case Number
Table 1
Acceptable Section XI Code Cases
ASME
Approval Date
N-532-4Alternative Requirements to Repair and Replacement Documentation
editor evaluating revision
Requirements and Inservice Summary Report Preparation and Submission as
Required by IWA-4000 and IWA-6000, Section XI, Division 1
4/19/06
N-534Alternative Requirements for Pneumatic Pressure Testing, Section XI,
Division 1
5/9/03 N-537Location of Ultrasonic Depth-Sizing Flaws, Section XI, Division 13/28/01
N-545Alternative Requirements for Conduct of Performance Demonstration
Detection Test of Reactor Vessel, Section XI, Division 1
5/20/98
N-553-1Inservice Eddy Current Surface Examination of Pressure Retaining Pipe Welds
and Nozzle-to-Safe End Welds, Section XI, Division 1
3/28/01
N-554-3Alternative Requirements for Reconciliation of Replacement Items and
Addition of New Systems, Section XI, Division 1
2/14/03
N-566-2Corrective Action for Leakage Identified at Bolted Connections, Section XI,
Division 1
3/28/01
N-567-1Alternative Requirements for Class 1, 2, and 3 Replacement Components,
Section XI, Division 1
4/19/02
N-573Transfer of Procedure Qualification Records Between Owners, Section XI,
Division 1
2/14/03
N-586-1Alternative Additional Examination Requirements for Classes 1, 2, and 3
Piping, Components, and Supports, Section XI, Division 1
5/04/04
N-600Transfer of Welder, Welding Operator, Brazer, and Brazing Operator
Qualifications Between Owners, Section XI, Division 1
9/18/01
N-609Alternative Requirements to Stress-Based Selection Criteria for Category B-J
Welds, Section XI, Division 1
7/30/98
N-613-1Ultrasonic 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-617Alternative 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-623Deferral of Inspections of Shell-to-Flange and Head-to-Flange Welds of a
Reactor Vessel, Section XI, Division 1
4/19/02
N-624Successive Inspections, Section XI, Division 14/19/02 N-629Use of Fracture Toughness Test Data to Establish Reference Temperature for
Pressure Retaining Materials, Section XI, Division 1
8/20/02
N-640Alternative Reference Fracture Toughness for Development of P-T Limit
Curves, Section XI, Division 1
4/19/02

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