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2024年8月26日发(作者：亓格格)

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 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.

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.

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

the NRC’s Electronic Reading Room at /reading-rm/doc-collections/

and through the NRC’s Agencywide Documents Access and Management

System (ADAMS) at /reading-rm/

, under Accession No. ML072070419.

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 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

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)

(2)

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.

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).

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.

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.

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).

(3)

(4)

(5)

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

RG 1.147, Rev. 15, Page 2

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.

RG 1.147, Rev. 15, Page 3

C. REGULATORY POSITION

able 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

N-307-3

Table 1

Acceptable Section XI Code Cases

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

Examination Requirements for Integrally Welded or Forged Attachments to

Class 2 Piping at Containment Penetrations, Section XI, Division 1

Alternative Pressure Test Requirement for Welded Repairs or Installation of

Replacement Items by Welding, Class 1, 2, and 3, Section XI, Division 1

Repair Welding Using Automatic or Machine Gas Tungsten-Arc Welding

(GTAW) Temper Bead Technique, Section XI, Division 1

Alternative Examination Coverage for Class 1 and Class 2 Welds,

Section XI, Division 1

Acoustic Emission for Successive Inspections, Section XI, Division 1

Rules for Examination of Class 1, 2, 3, and MC Component Supports of Light-

Water Cooled Power Plants, Section XI, Division 1

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

Helical-Coil Threaded Inserts, Section XI, Division 1

Rotation of Serviced Snubbers and Pressure Relief Valves for the Purpose of

Testing, Section XI, Division 1

Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy

Class 2 or 3 Piping, Section XI, Division 1

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

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

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

Section XI, Division 1

ASME

Approval Date

3/28/01

N-334

N-416-3

N-432-1

N-460

N-471

N-491-2

N-494-3

5/9/03

9/7/01

3/28/01

2/14/03

4/19/02

2/14/03

4/19/02

N-496-2

N-508-3

N-513-2

N-517-1

N-522

N-526

9/18/01

11/18/03

2/20/04

3/28/01

4/8/02

8/20/02

RG 1.147, Rev. 15, Page 4

Code Case

Number

N-532-4

Table 1

Acceptable Section XI Code Cases

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

Alternative Requirements for Pneumatic Pressure Testing, Section XI,

Division 1

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

Alternative Requirements for Conduct of Performance Demonstration

Detection Test of Reactor Vessel, Section XI, Division 1

Inservice Eddy Current Surface Examination of Pressure Retaining Pipe Welds

and Nozzle-to-Safe End Welds, Section XI, Division 1

Alternative Requirements for Reconciliation of Replacement Items and

Addition of New Systems, Section XI, Division 1

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

Division 1

Alternative Requirements for Class 1, 2, and 3 Replacement Components,

Section XI, Division 1

Transfer of Procedure Qualification Records Between Owners, Section XI,

Division 1

Alternative Additional Examination Requirements for Classes 1, 2, and 3

Piping, Components, and Supports, Section XI, Division 1

Transfer of Welder, Welding Operator, Brazer, and Brazing Operator

Qualifications Between Owners, Section XI, Division 1

Alternative Requirements to Stress-Based Selection Criteria for Category B-J

Welds, Section XI, Division 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

Alternative Examination Distribution Requirements for Table IWC-2500-1,

Examination Category C-G, Pressure Retaining Welds in Pumps and Valves,

Section XI, Division 1

Deferral of Inspections of Shell-to-Flange and Head-to-Flange Welds of a

Reactor Vessel, Section XI, Division 1

Successive Inspections, Section XI, Division 1

Use of Fracture Toughness Test Data to Establish Reference Temperature for

Pressure Retaining Materials, Section XI, Division 1

Alternative Reference Fracture Toughness for Development of P-T Limit

Curves, Section XI, Division 1

ASME

Approval Date

4/19/06

N-534

N-537

N-545

N-553-1

N-554-3

N-566-2

N-567-1

N-573

N-586-1

N-600

N-609

N-613-1

5/9/03

3/28/01

5/20/98

3/28/01

2/14/03

3/28/01

4/19/02

2/14/03

5/04/04

9/18/01

7/30/98

8/20/02

N-617

4/19/02

N-623

N-624

N-629

N-640

4/19/02

8/20/02

4/19/02

RG 1.147, Rev. 15, Page 5

Code Case

Number

N-641

N-643-2

N-649

Table 1

Acceptable Section XI Code Cases

Alternative Pressure-Temperature Relationship and Low Temperature

Overpressure Protection System Requirements, Section XI, Division 1

Fatigue Crack Growth Rate Curves for Ferritic Steels in PWR Water

Environment, Section XI, Division 1

Alternative Requirements for IWE-5240 Visual Examination,

Section XI, Division 1

Ferritic and Dissimilar Metal Welding Using SMAW Temper Bead Technique

Without Removing the Weld Bead Crown for the First Layer, Section XI,

Division 1

Alternative Requirements to Categorize B-G-1, B-G-2, and C-D Bolting

Examination Methods and Selection Criteria, Section XI, Division 1

Qualification Requirements for Ultrasonic Examination of Wrought Austenitic

Piping Welds, Section XI, Division 1

Alternative Requirements for Classes 1 and 2 Surface Examinations,

Section XI, Division 1

Performance Demonstration Requirements for Examination of Unclad Reactor

Pressure Vessel Welds, Excluding Flange Welds, Section XI, Division 1

Alternative Requirements for Beam Angle Measurements Using Refracted

Longitudinal Wave Search Units, Section XI, Division 1

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

Lighting Requirements for Surface Examination, Section XI, Division 1

Alternative Requirements for Visual Examinations, VT-1, VT-2,

and VT-3, Section XI, Division 1

Qualification Requirements for Dissimilar Metal Piping Welds,

Section XI, Division 1

Qualification Requirements for Appendix VIII Piping Examinations Conducted

from the Inside Surface, Section XI, Division 1

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

Alternative Rules for Selection of Classes 1, 2, and 3 Vessel Welded

Attachments for Examination, Section XI, Division 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

ASME

Approval Date

2/3/03

5/04/04

3/28/01

N-651

8/14/01

N-652-1

N-658

N-663

N-664

N-665

N-683

2/20/04

4/4/02

9/17/02

8/20/02

2/28/03

N-685

N-686

N-695

N-696

N-697

2/28/03

5/21/03

11/18/03

N-700

N-706

11/18/03

11/11/05

ionally Acceptable Section XI Code Cases

RG 1.147, Rev. 15, Page 6

The Code Cases listed in Table 2 are acceptable to the NRC for application in licensees’ 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.

Table 2. Conditionally Acceptable Section XI Code Cases

Code Case

Number

Table 2

Conditionally Acceptable Section XI Code Cases

Condition

N-498-4Alternative 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.

N-504-3Alternative Rules for Repair of Class 1, 2, and 3 Austenitic Stainless Steel

Piping, Section XI, Division 1

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.

N-516-3Underwater Welding, Section XI, Division 1

Licensees must obtain NRC approval in accordance with 10 CFR 50.55a(a)(3)

regarding the technique to be used in the weld repair or replacement of irradiated

material underwater.

N-528-1Purchase, Exchange, or Transfer of Material Between Nuclear Plant Sites,

Section XI, Division 1

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-533-1Alternative 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.

N-552Alternative Methods - Qualification for Nozzle Inside Radius Section from the

Outside Surface, Section XI, Division 1

4/19/02

4/8/02

4/19/02

4/8/02

8/4/04

4/8/02

ASME

Approval Date

RG 1.147, Rev. 15, Page 7

Code Case

Number

Table 2

Conditionally Acceptable Section XI Code Cases

Condition

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.”

ASME

Approval Date

N-557-1In-Place Dry Annealing of a PWR Nuclear Reactor Vessel, Section XI,

Division 1

The secondary stress allowable of 3S

, shown in Figure 1 of the Code Case,

must be applied to the entire primary plus secondary stress range during the

anneal.

8/20/02

N-569-1Alternative Rules for Repair by Electrochemical Deposition of Class 1 and 2

Steam Generator Tubing, Section XI, Division 1

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.

4/19/02

N-576-1Repair of Class 1 and 2 SB-163, UNS N06600 Steam Generator Tubing,

Section XI, Division 1

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.

4/19/02

RG 1.147, Rev. 15, Page 8

Code Case

Number

Table 2

Conditionally Acceptable Section XI Code Cases

Condition

ASME

Approval Date

N-583Annual Training Alternative, Section XI, Division 1

(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.

2/14/03

N-593Alternative 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.

2/14/03

N-597-2Requirements 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 t

reaching the allowable minimum wall thickness, t

min

, 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(a)(3).

(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(a)(3).

(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, t

min

(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.

11/18/03

RG 1.147, Rev. 15, Page 9

Code Case

Number

Table 2

Conditionally Acceptable Section XI Code Cases

Condition

ASME

Approval Date

N-606-1Similar and Dissimilar Metal Welding Using Ambient Temperature Machine

GTAW Temper Bead Technique for BWR CRD Housing/Stub Tube Repairs,

Section XI, Division 1

Prior to welding, an examination or verification must be performed to ensure

proper preparation of the base metal, and that the surface is properly contoured

so that an acceptable weld can be produced. 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.

8/20/02

N-616Alternative Requirements for VT-2 Visual Examination of Classes 1, 2, 3

Insulated Pressure Retaining Bolted Connections, Section XI, Division 1

(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 1100EF or with hardness above R

30.

(2)For A-286 stainless steel studs or bolts, the preload must be verified to be

below 100 Ksi or the thermal insulation must be removed and the joint

visually examined.

(3)Prior to conducting the VT-2 examination of Class 2 and Class 3

components not required to operate during normal plant operation, a 10-

minute holding time is required after attaining test pressure. Prior to

conducting the VT-2 examination of Class 2 and Class 3 components

required to operate during normal plant operation, no holding time is

required, provided the system has been in operation for at least 4 hours for

insulated components or 10 minutes for non-insulated components.

4/8/02

N-619Alternative Requirements for Nozzle Inner Radius Inspections for Class 1

Pressurizer and Steam Generator Nozzles, Section XI, Division 1

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. The provisions of Table

IWB-2500-1, 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 this table (the external surface is from point M

to point N in the figure).

4/8/02

N-638-1Similar and Dissimilar Metal Welding Using Ambient Temperature Machine

GTAW Temper Bead Technique, Section XI, Division 1

UT volumetric examinations shall be performed with personnel and procedures

qualified for the repaired volume and qualified by demonstration using

representative samples which contain construction type flaws. The acceptance

criteria of NB-5330 in the 1998 Edition through 2000 Addenda of Section III

(Ref. 7) apply to all flaws identified within the repaired volume.

2/13/03

RG 1.147, Rev. 15, Page 10

Code Case

Number

Table 2

Conditionally Acceptable Section XI Code Cases

Condition

ASME

Approval Date

N-639Alternative Calibration Block Material, Section XI, Division 1

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.

8/20/02

N-647Alternative to Augmented Examination Requirements of IWE-2500, Section XI,

Division 1

A VT-1 examination is to be used in lieu of the “detailed visual examination.”

[Note: 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.]

11/18/03

N-648-1Alternative Requirements for Inner Radius Examination of Class 1 Reactor

Vessel Nozzles, Section XI Division 1

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 width

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

IWB-2500-1, 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 this table (the external surface is from point M

to point N in the figure).

9/18/01

N-660Risk-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 non-

Code Class pressure retaining components and their associated supports.

7/23/02

N-661Alternative Requirements for Wall Thickness Restoration of Classes 2 and 3

Carbon Steel Piping for Raw Water Service, Section XI, Division 1

(a)

(b)

(c)

If the root cause of the degradation has not been determined, the repair

is only acceptable for one cycle.

Weld overlay repair of an area can only be performed once in the same

location.

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.

7/23/02

N-662Alternative Repair/Replacement Requirements for Items Classified

in Accordance with Risk-Informed Processes, Section XI, Division 1

The Code Case must be applied only to ASME Code Classes 2 and 3, and non-

Code Class pressure retaining components and their associated supports.

8/20/02

RG 1.147, Rev. 15, Page 11

Code Case

Number

Table 2

Conditionally Acceptable Section XI Code Cases

Condition

ASME

Approval Date

N-694-1Evaluation 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 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.

2/20/04

RG 1.147, Rev. 15, Page 12

ed 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. The third column of the table lists the date that the ASME annulled

the Code Case.

Table 3. Annulled Unconditionally Approved Section XI Code Cases

Code Case

Number

N-34

(1551)

N-72

(1646)

N-73

(1647)

N-98

(1705-1)

N-112

(1730)

N-113-1

N-167

(1804)

N-198-1

N-211

Table 3

Annulled Unconditionally Approved Section XI Code Cases

Inservice Inspection of Welds of Nuclear Components, Section XI

Partial Postponement of Category B-C Examination for Class 1

Components, Section XI

Partial Postponement of Category B-D Examination for Class 1

Components, Section XI

Ultrasonic Examination - Calibration Block Tolerances, Section XI,

Division 1

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

Division 1

Basic Calibration Block for Ultrasonic Examination of Weld 10 in.

to 14 in. Thick, Section XI, Division 1

Minimum Section Thickness Requirements for Repair of Nozzles,

Section XI, Division 1

Exemption from Examination for ASME Class 1 and 2 Piping

Located at Containment Penetrations, Section XI, Division 1

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)

Alternative Rules for Reactor Vessel Closure Stud Examination,

Section XI, Division 1

Time Between Ultrasonic Calibration Checks, Section XI, Division 1

Ultrasonic Calibration Checks per Section V, Section XI,

Division 1

Repair and Replacement of Class MC Vessels, Section XI,

Division 1

Hydrostatic Test Requirements for Class 1 and Class 2 Components,

Section XI, Division 1

Calibration Block Material Selection, Appendix 1, 1-3121,

Section XI, Division 1

Annulment Date

11/20/81

1/1/81

8/9/96

7/1/79

8/9/96

1/14/80

3/28/01

4/30/93

N-216

N-234

N-235

N-236-1

N-288

N-306

5/7/90

12/3/90

8/9/96

8/5/97

5/25/83

5/7/90

RG 1.147, Rev. 15, Page 13

Code Case

Number

N-308

N-311

N-322

Table 3

Annulled Unconditionally Approved Section XI Code Cases

Documentation of Repairs and Replacements of Components in

Nuclear Power Plants, Section XI, Division 1

Alternative Examination of Outlet Nozzle on Secondary Side of

Steam Generators, Section XI, Division 1

Examination Requirements for Integrally Welded or Forged

Attachments to Class 1 Piping at Containment Penetrations,

Section XI, Division 1

Rules for Ultrasonic Examination of Similar and Dissimilar Metal

Piping Welds, Section XI, Division 1

Alternative Scope of Examination of Attachment Welds for

Examination Categories B-H, B-K-1, and C-C, Section XI,

Division 1

Calibration Block for Angle Beam Ultrasonic Examination of Large

Fittings in Accordance with Appendix III-3410, Section XI,

Division 1

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.)

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

Division 1

Alternative Rules for Repairs, Replacements, or Modifications,

Section XI, Division 1

Eddy Current Examination, Section XI, Division 1

Eddy Current Calibration Standards, Section XI, Division 1

Alternative Rules for Replacement, Section XI, Division 1

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

Division 1

Procedure and Personnel Qualification Requirements for Ultrasonic

Detection and Sizing of Flaws in Piping Welds, Section XI,

Division 1

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

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

Section XI, Division 1

Qualification of Visual Examination Personnel, Section XI,

Division 1

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

Section XI, Division 1

Code Cases in Inspection Plans, Section XI, Division 1

Annulment Date

9/30/90

11/18/03

2/14/03

N-335-1

N-343

5/11/97

12/3/90

N-355

8/9/96

N-356

8/5/97

N-375-2

N-389-1

N-401-1

N-402-1

N-406

N-408-3

N-409-3

5/7/90

4/19/02

5/11/97

5/7/90

4/19/02

4/30/96

N-415

N-419

N-424

N-426

N-427

8/14/94

5/13/94

7/18/88

5/13/94

12/16/94

RG 1.147, Rev. 15, Page 14

Code Case

Number

N-429-2

N-435-1

N-436-1

N-437

N-444

Table 3

Annulled Unconditionally Approved Section XI Code Cases

Alternative Rules for Ultrasonic Instrument Calibration, Section XI,

Division 1

Alternative Examination Requirements for Vessels With Wall

Thickness 2 in. or Less, Section XI, Division 1

Alternative Methods for Evaluation of Flaws in Austenitic Piping,

Section XI, Division 1

Use of Digital Readout and Digital Measurement Devices for

Performing Pressure Tests, Section XI, Division 1

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.)

Use of Later Editions of SNT-TC-1A for Qualification of

Nondestructive Examination Personnel, Section XI, Division 1, 2

and 3

Recertification of Visual Examination Personnel, Section XI,

Division 1

Qualification of VT-2 and VT-3 Visual Examination Personnel,

Section XI, Division 1

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

Division 1

Qualification Specimen Notch Location for Ultrasonic Examination

of Bolts and Studs, Section XI, Division 1

Magnetic Particle Examination of Coated Materials, Section XI,

Division 1

Alternative Rules for Piping Calibration Block Thickness,

Section XI, Division 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

Use of Digital Readout and Digital Measurement Devices

for Performing Pump Vibration Testing, Section XI, Division 1

Inservice Inspection for Class CC Concrete Components

of Light-Water Cooled Power Plants, Section XI, Division 1

Boiling Water Reactor (BWR) Main Steam Hydrostatic Test,

Section XI, Division 1

Alternative Examination Requirements for Cast Austenitic Pump

Casings, Section XI, Division 1

Annulment Date

7/27/95

5/4/04

12/3/90

7/27/95

12/30/90

N-445

5/7/90

N-446

N-448

N-449

N-457

N-458-1

N-461-1

N-463-1

5/7/90

4/30/96

4/19/02

3/38/01

3/28/01

N-472

N-478

N-479-1

N-481

8/14/97

3/2/98

4/19/02

3/28/04

RG 1.147, Rev. 15, Page 15

Code Case

Number

N-485-1

N-489

N-490-1

N-495

N-496-1

N-503

Table 3

Annulled Unconditionally Approved Section XI Code Cases

Eddy Current Examination of Coated Ferritic Surfaces as an

Alternative to Surface Examination, Section XI, Division 1

Alternative Rules for Level III NDE Qualification Examinations,

Section XI, Divisions 1, 2, and 3

Alternative Vision Test Requirements for Nondestructive Examiners,

Section XI, Divisions 1, 2, and 3

Hydrostatic Testing of Relief Valves, Section XI, Division 1

Helical-Coil Threaded Inserts, Section XI, Division 1

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.”)

Low Temperature Overpressure Protection, Section XI, Division 1

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

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

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

Division 1

Alternative Examination Requirements for Longitudinal Welds in

Class 1 and 2 Piping, Section XI, Division 1

Alternative Requirements for Inservice Inspection Intervals,

Section XI, Division 1

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

Alternative to Performing Periodic Calibration Checks, Section XI,

Division 1

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

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

Alternative Requirements for Verification of Acceptability

of Replacements, Section XI, Division 1

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

Annulment Date

2/14/03

4/19/02

2/14/03

4/19/02

5/11/97

2/14/03

N-514

N-515

N-521

4/19/02

N-523-2

N-524

N-535

N-538

3/28/04

4/19/02

3/28/01

4/19/02

N-541

3/28/01

N-543

N-544

N-555

N-556

N-563

9/18/01

3/28/01

4/8/02

4/19/02

RG 1.147, Rev. 15, Page 16

Code Case

Number

N-588

N-592

N-598

N-601

N-603

N-604

N-605

Table 3

Annulled Unconditionally Approved Section XI Code Cases

Attenuation to Reference Flaw Orientation of Appendix G

for Circumferential Welds in Reactor Vessels, Section XI, Division 1

ASNT Central Certification Program, Section XI, Division 1

Alternative Requirements to Required Percentages of Examinations,

Section XI, Division 1

Extent and Frequency of VT-3 Visual Examination for Inservice

Inspection of Metal Containments, Section XI, Division 1

Alternative to the Requirements of IWL-2421, Sites with Two Plants,

Section XI, Division 1

Alternative to Bolt Torque or Tension Test Requirements of Table

IWE-2500-1, Category E-G, Item E8.20, Section XI, Division 1

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.]

VT-1 Visual Examination in Lieu of Surface Examination

for RPV Closure Nuts, Section XI, Division 1

Annulment Date

3/28/04

9/18/04

3/28/04

N-6275/7/02

RG 1.147, Rev. 15, Page 17

ed 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

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-210Exemption to Hydrostatic Tests After Repairs, Section XI, Division 1

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-252Low Energy Capacitive Discharge Welding Method

for Temporary or Permanent Attachments to Components and

Supports, Section III, Division 1, and Section XI

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-278Alternative 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.

2/19/92

7/16/82

3/20/81

Annulment Date;

Supplement/

Edition

12/3/90

RG 1.147, Rev. 15, Page 18

Code Case

Number

N-509

Table 4

Annulled Conditionally Acceptable Section XI Code Cases

Alternative Rules for the Selection and Examination of Class 1, 2,

and 3 Integrally Welded Attachments, Section XI, Division 1

A minimum 10% sample of integrally welded attachments for each

item in each Code class per interval should be examined.

Annulment Date;

Supplement/

Edition

5/20/01

N-512-1Assessment of Reactor Vessels With Low Upper Shelf Charpy Impact

Energy Levels, Section XI, Division 1

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.

5/20/01

N-546Alternative Requirements for Qualification of VT-2 Examination

Personnel, Section XI, Division 1

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.

9/18/04

N-568Alternative Examination Requirements for Welded Attachments,

Section XI, Division 1

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.

2/14/03

N-599Alternatives to Qualification of Nondestructive Examination

Personnel for Inservice Inspection of Metal (Class MC) and

Concrete (Class CC) Containments, Section XI, Division 1

This Code Case may not be used when a licensee updates to the

1992 or later Edition of Section XI that requires the use of

ANSI/ASNT CP-189, “Standard for Qualification and Certification

of Nondestructive Testing Personnel” (Ref. 10).

9/18/04

N-630Alternatives 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.

4/8/02

RG 1.147, Rev. 15, Page 19

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

N-113

(1731)

N-236

Table 5

Section XI Code Cases That Have Been Superseded

Basic Calibration Block for Ultrasonic Examination of Weld 10

in. To 14 in. Thick, Section XI, Division 1

Repair and Replacement of Class MC Vessels, Section XI,

Division 1

(a)

(b)

In paragraph 1.0(a), second sentence, the phrase, “while

the plant is not in service,” refers to a refueling outage.

In paragraph 1.0(a), third sentence, the phrase, “the next

scheduled plant outage,” refers to the next scheduled

refueling outage.

Date

N-113-1 Published on

12/31/82

N-236-1 Published on

9/5/85

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-335-1 Published on

6/20/85

N-375-1 Published on

4/14/83;

N-375-2 Published on

4/5/84

N-335

N-375

N-375-1

Rules for Ultrasonic Examination of Similar and Dissimilar

Metal Piping Welds, Section XI, Division 1

Rules for Ultrasonic Examination of Bolds and Studs,

Section XI, Division 1

RG 1.147, Rev. 15, Page 20

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

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.

Date

N-389-1 Published on

12/9/93

N-401

N-402

N-408

N-408-1

N-408-2

Eddy Current Examination, Section XI, Division 1

Eddy Current Calibration Standards, Section XI, Division 1

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

Division 1

Alternative Rules for Examination of Class 2 Piping,

Section XI, Division 1

The applicant for an operating license should define the Class 2

piping subject to volumetric and surface examination in the

Preservice Inspection for determination of acceptability by the

NRC staff.

N-401-1 Published on

5/4/88

N-402-1 Published on

3/14/91

N-408-1 Published on

3/8/89

N-408-2 Published on

7/24/89

N-408-3 Published on

8/9/93

N-409Procedure and Personnel Qualification Requirements for

Ultrasonic Detection and Sizing of Flaws in Piping Welds,

Section XI, Division 1

Procedure and Personnel Qualification Requirements for

Ultrasonic Detection and Sizing of Flaws in Piping Welds,

Section XI, Division 1

The applicant should give prior notification to the NRC of the

intention to use the Code Case.

N-409-1 Published on

12/7/87

N-409-2 Published on

7/27/88;

N-409-3 Published on

4/30/93

N-409-1

N-409-2

N-416

N-416-1

N-416-2

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-429-1 Published on

2/23/87;

N-429-2 Published on

7/27/92

N-432-1 Published on

3/28/01

N-435-1 Published on

7/30/86

N-436-1 Published on

12/7/87

N-429

N-429-1

Alternative Rules for Ultrasonic Instrument Calibration,

Section XI, Division 1

N-432

N-435

N-436

Repair Welding Using Automatic or Machine Gas Tungsten-Arc

Welding (GTAW) Temper Bead Technique, Section XI, Division 1

Alternative Examination Requirements for Vessels With Wall

Thickness 2 in. Or Less, Section XI, Division 1

Alternative Methods for Evaluation of Flaws in Austenitic

Piping, Section XI, Division 1

RG 1.147, Rev. 15, Page 21

Code Case

Number

N-458

N-461

N-463

Table 5

Section XI Code Cases That Have Been Superseded

Magnetic Particle Examination of Coated Materials,

Section XI, Division 1

Alternative Rules for Piping Calibration Block Thickness,

Section XI, Division 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

Boiling Water Reactor (BWR) Main Steam Hydrostatic Test,

Section XI, Division 1

Eddy Current Examination of Coated Ferritic Surfaces as an

Alternative to Surface Examination, Section XI, Division 1

Alternative Vision Test Requirements for Nondestructive

Examiners, Section XI, Divisions 1, 2, and 3

Alternative Rules for Examination of Class 1, 2, 3, and MC

Component Supports of Light-Water Cooled Power Plants,

Section XI, Division 1

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

Date

N-458-1 Published on

3/14/95

N-461-1 Published on

3/14/95

N-463-1 Published on

3/5/90

N-479-1 Published on

12/3/90

N-485 Published on

8/14/91

N-490-1 Published on

5/13/91

N-491-1 Published on

4/30/93;

N-491-2 Published on

3/12/97

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-496-1 Published on

5/11/94;

N-496-1 Annulled on

5/11/97

N-496-2 Published on

9/18/01

N-498-1 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-504-1 Published on

8/9/93

N-504-2 Published on

3/12/97

N-504-3 Published on

8/4/04

N-479

N-485

N-490

N-491

N-491-1

N-494

N-494-1

N-494-2

N-496

N-496-1

Helical-Coil Threaded Inserts, Section XI, Division 1

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-504

N-504-1

N-504-2

Alternative Rules for Repair of Class 1, 2, and 3 Austenitic

Stainless Steel Piping, Section XI, Division 1

RG 1.147, Rev. 15, Page 22

Code Case

Number

N-508

N-508-1

N-508-2

Table 5

Section XI Code Cases That Have Been Superseded

Rotation of Serviced Snubbers and Pressure Relief Valves for the

Purpose of Testing, Section XI, Division 1

Date

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-512-1 Published on

8/24/95

N-513-1 Published on

3/28/01

N-513-2 Published on

2/20/04

N-512

N-513

N-513-1

Assessment of Reactor Vessels With Low Upper Shelf Charpy

Impact Energy Levels, Section XI, Division 1

Evaluation Criteria for Temporary Acceptance of Flaws

in Class 3 Piping, Section XI, Division 1

Evaluation Criteria for Temporary Acceptance of Flaws

in Class 3 Piping, Section XI, Division 1

(1)

(2)

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

N-516

N-516-1

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.

N-516-1 Published on

12/31/96;

N-516-2 Published on

1/17/00

N-516-2Underwater Welding, Section XI, Division 1

Licensees must obtain NRC approval in accordance with 10 CFR

50.55a(a)(3) regarding the method to be used in the weld repair

or replacement of irradiated material underwater.

N-516-3 Published on

4/8/02

N-517

N-523

N-523-1

Quality Assurance Program Requirements for Owners, Section

XI, Division 1

Mechanical Clamping Devices for Class 2 and 3 Piping,

Section XI, Division 1

N-517-1 Published on

7/30/98

N-523-1 Published on

8/24/95

N-523-2 Published on

10/2/00

N-528-1 Published on

5/7/99

N-528Purchase, Exchange, or Transfer of Material Between Nuclear

Plant Sites, Section XI, Division 1

RG 1.147, Rev. 15, Page 23

Code Case

Number

N-532

N-532-1

N-532-2

N-532-3

Table 5

Section XI Code Cases That Have Been Superseded

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

Date

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-533-1 Published

2/26/99

N-553-1 Published on

3/28/01

N-554-1 Published on

7/98E;

N-554-2 Published on

2/25/00

N-554-3 Published on

2/14/03

N-557-1 Published on

12/31/96

N-560-1 Published on

8/9/96;

N-560-2 Published on

3/28/00

N-561-1 Published on

7/30/98

N-562-1 Published on

7/30/98

N-566-1 Published on

2/15/99

N-566-2 Published on

3/28/01

N-567-1 Published on

2/26/99

N-569-1 Published on

5/7/99

N-576-1 Published on

5/7/99

N-577-1 Published on

3/28/00

N-533Alternative Requirements for VT-2 Visual Examination of Class 1

Insulated Pressure-Retaining Bolted Connections, Section XI,

Division 1

Inservice Eddy Current Surface Examination of Pressure

Retaining Pipe Welds and Nozzle-to-Safe End Welds, Section XI,

Division 1

Alternative Requirements for Reconciliation of Replacement

Items, Section XI, Division 1

N-553

N-554

N-554-1

N-554-2

N-557

N-560

N-560-1

In-Place Dry Annealing of a PWR Nuclear Reactor Vessel,

Section XI, Division 1

Alternative Examination Requirements for Class 1, Category B-J

Piping Welds, Section XI, Division 1

N-561Alternative Requirements for Wall Thickness Restoration of

Class 2 and High Energy Class 3 Carbon Steel Piping,

Section XI, Division 1

Alternative Requirements for Wall Thickness Restoration of

Class 3 Moderate Energy Carbon Steel Piping, Section XI,

Division 1

Corrective Action for Leakage Identified at Bolted Connections,

Section XI, Division 1

N-562

N-566

N-566-1

N-567

N-569

N-576

N-577

Alternative Requirements for Class 1, 2, and 3 Replacement

Components, Section XI, Division 1

Alternative Rules for Repair by Electrochemical Deposition of

Class 1 and 2 Steam Generator Tubing, Section XI, Division 1

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

Tubing, Section XI, Division 1

Risk-Informed Requirements for Class 1, 2, and 3 Piping,

Method A, Section XI, Division 1

RG 1.147, Rev. 15, Page 24

Code Case

Number

N-578

N-586

Table 5

Section XI Code Cases That Have Been Superseded

Risk-Informed Requirements for Class 1, 2, and 3 Piping,

Method B, Section XI, Division 1

Alternative Additional Examination Requirements for Class 1, 2,

and 3 Piping, Components, and Supports, Section XI, Division 1

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.

Date

N-578-1 Published on

3/28/00

N-586-1 Published on

5/4/04

N-589

N-597

N-597-1

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

Division 1

Requirements for Analytical Evaluation of Pipe Wall Thinning,

Section XI, Division 1

N-589-1 Published on

7/23/02

N-597-1 Published on

7/7/01

N-597-2 Published on

11/18/03

N-606-1 Published on

9/24/99

N-638-1 Published on

5/9/03

N-606Similar and Dissimilar Metal Welding Using Ambient

Temperature Machine GTAW Temper Bead Technique, Section

XI, Division 1

Similar and Dissimilar Metal Welding Using Ambient

Temperature Machine GTAW Temper Bead Technique, Section

XI, Division 1

The Construction Code of Record acceptance criteria must used

for volumetric examinations.

N-638

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-648-1 Published on

7/7/01

N-652-1 Published on

2/20/04

N-694-1 Published on

2/20/04

N-648

N-652

Alternative Requirements for Inner Radius Examination of Class

1 Reactor Vessel Nozzles, Section XI, Division 1

Alternative Requirements to Categorize B-G-1, B-G-2, and

C-D Bolting Examination Methods and Selection Criteria,

Section XI, Division 1

Evaluation Procedure and Acceptance Criteria for PWR Reactor

Vessel Head Penetration Nozzles, Section XI, Division 1

N-694

RG 1.147, Rev. 15, Page 25

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)(4). No backfit is intended or approved in

connection with the issuance of this guide.

Except when an applicant or licensee proposes or has previously established an acceptable

alternative method for complying with specified portions of the NRC’s regulations, the methods

described in this guide will be used in evaluating (1) submittals in connection with applications

for construction permits, design approvals, design certifications, operating licenses, and combined

licenses, and (2) submittals from operating reactor licensees who voluntarily propose to initiate system

modifications that have a clear nexus with this guidance.

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” (Ref. 11), which incorporates this regulatory guide by reference.

RG 1.147, Rev. 15, Page 26

REFERENCES

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.

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.

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.), 104

Congress of the United States of America, Washington, DC.

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

Commission, Washington, DC.

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.

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.

ASME Boiler and Pressure Vessel Code, Section III, “Rules for Construction of Nuclear Power

Plant Components,” American Society of Mechanical Engineers, New York, NY.

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.]

All NRC regulations listed herein are available electronically through the Public Electronic Reading Room

on the NRC’s public Web site, at /reading-rm/doc-collections/cfr/. Copies are also available

for inspection or copying for a fee from the NRC’s Public Document Room at 11555 Rockville Pike, Rockville, MD;

the PDR’s mailing address is USNRC PDR, Washington, DC 20555; telephone (301) 415-4737 or (800) 397-4209;

fax (301) 415-3548; email PDR@

Copies may be purchased from the American Society of Mechanical Engineers, Three Park Avenue, New York, NY

10016-5990; phone (212) 591-8500; fax (212) 591-8501; .

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 /

federal-register/laws/paperwork-reduction/.

All regulatory guides listed herein are available electronically through the Electronic Reading Room on the NRC’s

public Web site at /reading-rm/doc-collections/reg-guides/. Active guides may be purchased from

the National Technical Information Service (NTIS). Details may be obtained by contacting NTIS at 5285 Port Royal

Road, Springfield, Virginia 22161, online at

, by telephone at (800) 553-NTIS (6847) or (703) 605-

6000, or by fax to (703) 605-6900. Copies are also available for inspection or copying for a fee from the NRC’s Public

Document Room (PDR), which is located at 11555 Rockville Pike, Rockville, Maryland; the PDR’s mailing address is

USNRC PDR, Washington, DC 20555-0001. The PDR can also be reached by telephone at (301) 415-4737

or (800) 397-4209, by fax at (301) 415-3548, and by email to PDR@

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.

RG 1.147, Rev. 15, Page 27

10.

11.

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.

ANSI/ASNT CP-189, “Standard for Qualification and Certification of Nondestructive Testing

Personnel,” American Society for Nondestructive Testing, Columbus, OH.

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

Regulatory Analysis for the Amendment to 10 CFR 50.55a, “Codes and Standards,” U.S. Nuclear

Regulatory Commission, Washington, DC.

12.

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 /publications/standards/cp-189/

Copies of this regulatory analysis are available for inspection and copying for a fee at the NRC’s Public Document

Room (PDR), which is located at 11555 Rockville Pike, Rockville, Maryland. The PDR’s mailing address is USNRC

PDR, Washington, DC 20555-0001. The PDR can also be reached by telephone at (301) 415-4737 or (800) 397-4209,

by fax at (301) 415-3548, and by email to PDR@

RG 1.147, Rev. 15, Page 28

APPENDIX A

SUPPLEMENTS ADDRESSED IN PROPOSED REVISION 15

OF REGULATORY GUIDE 1.147

Edition

2001

2004

Supplement Number

BNCS

Approval Date of Code Cases in Supplement

February 3, 2002

February 14, 2003

May 9, 2003

June 17, 2003

November 18, 2003

February 20, 2004

May 4, 2004

BNCS = ASME Board on Nuclear Codes and Standards

Publication of supplements approximately 6 months after BNCS approval.

Appendix A to DG-1134, Page A-1

APPENDIX B

NUMERICAL LISTING OF SECTION XI CODE CASES IN

SUPPLEMENT 7 THROUGH SUPPLEMENT 12 TO THE 2001 EDITION,

N-307-3

N-311

N-322

N-334

N-416-3

N-432-1

N-460

N-465-1

N-473-1

N-481

N-485-1

N-490-1

N-491-2

N-503

N-504-2

N-508-3

N-513-2

N-517-1

N-523-2

N-532-3

N-534

N-537

N-545

N-546

N-553-1

N-554-3

N-560-2

N-561-1

N-562-1

N-566-2

N-568

N-573

N-574

N-575

N-577-1

N-578-1

N-583

N-586-1

N-587

N-588

N-592

N-593

N-597-2

N-598

AND SUPPLEMENT 1 TO THE 2004 EDITION

N-599

N-600

N-601

N-603

N-604

N-605

N-609

N-615

N-618-1

N-638-1

N-641

N-643-1

N-643-2

N-647

N-648-1

N-649

N-651

N-652-1

N-653

N-665

N-683

N-685

N-686

N-691

N-694-1

N-695

N-696

N-697

N-700

N-702

Appendix B to DG-1134, Page B-1

APPENDIX C

NUMERICAL LISTING OF SECTION XI CODE CASES

AND TABLE WHERE EACH CODE CASE IS LISTED

N-34 [T3]

N-401 [T5]

N-460 [T1]

N-72 [T3]

N-401-1 [T3]

N-461 [T5]

N-73 [T3]

N-402 [T5]

N-461-1 [T3]

N-98 [T3]

N-402-1 [T3]

N-463 [T5]

N-112 [T3]

N-406 [T3]

N-463-1 [T3]

N-113 [T5]

N-408 [T5]

N-465

N-113-1 [T3]

N-408-1 [T5]

N-465-1

N-118 [T4]

N-408-2 ]T5]

N-471 [T1]

N-167 [T3]

N-408-3 [T3]

N-472 [T3]

N-198-1 [T3]

N-409 [T5]

N-473

N-210 [T4]

N-409-1 [T5]

N-473-1

N-211 [T3]

N-409-2 [T5]

N-478 [T3]

N-216 [T3]

N-409-3 [T3]

N-479 [T5]

N-234 [T3]

N-415 [T3]

N-479-1 [T3]

N-235 [T3]

N-416 [T5]

N-480

N-236 [T5]

N-416-1 [T5]

N-481 [T3]

N-236-1 [T3]

N-416-2 [T5]

N-485 [T5]

N-252 [T4]

N-416-3 [T1]

N-485-1 [T3]

N-278 [T4]

N-419 [T3]

N-489 [T3]

N-288 [T3]

N-424 [T3]

N-490 [T5]

N-306 [T3]

N-426 [T3]

N-490-1 [T3]

N-307 [T5]

N-427 [T3]

N-491 [T5]

N-307-1 [T5]

N-429 [T5]

N-491-1 [T5]

N-307-2 [T5]

N-429-1 [T5]

N-491-2 [T1]

N-307-3 [T1]

N-429-2 [T3]

N-494 [T5]

N-308 [T3]

N-432 [T5]

N-494-1 [T5]

N-311 [T3]

N-432-1 [T1]

N-494-2 [T5]

N-322 [T3]

N-435 [T5]

N-494-3 [T1]

N-323-1

N-435-1 [T3]

N-495 [T3]

N-334 [T1]

N-436 [T5]

N-496 [T5]

N-335 [T5]

N-436-1 [T3]

N-496-1 [T3] [T5]

N-335-1 [T3]

N-437 [T3]

N-496-2 [T1]

N-343 [T3]

N-444 [T3]

N-498 [T5]

N-355 [T3]

N-445 [T3]

N-498-1

[T5]

N-356 [T3]

N-446 [T3]

N-498-2

[T5]

N-375 [T5]

N-448 [T3]

N-498-3

[T5]

N-375-1 [T5]

N-449 [T3]

N-498-4 [T2]

N-375-2 [T3]

N-457 [T3]

N-503 [T3]

N-389 [T5]

N-458 [T5]

N-504 [T5]

N-389-1 [T3]

N-458-1 [T3]

N-504-1 [T5]

Code case is unacceptable for use. See Revision 2 of Regulatory Guide 1.193 (Ref. 4).

Supplement 9 to the 2004 Edition.

Supplement 5 to the 2004 Edition.

Supplement 7 to the 2004 Edition.

Appendix C to DG-1134, Page C-1

N-504-2 [T5]

N-504-3 [T1]

N-508 [T5]

N-508-1 [T5]

N-508-2 [T5]

N-508-3 [T1]

N-509 [T4]

N-512 [T5]

N-512-1 [T4]

N-513 [T5]

N-513-1 [T5]

N-513-2 [T1]

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 [T1]

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

T[5]

N-532-3 [T5]

N-532-4 [T1]

N-533 [T5]

N-533-1 [T2]

N-534 [T1]

N-535 [T3]

N-537 [T1]

N-538 [T3]

N-541 [T3]

N-542

N-543 [T3]

N-544 [T3]

N-545 [T1]

N-546 [T4]

N-547

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-560-1

[T5]

N-560-2

N-561

[T5]

N-561-1

N-562

[T5]

N-562-1

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-574

N-575

N-576 [T5]

N-576-1 [T2]

N-577

[T5]

N-577-1

N-578

[T5]

N-578-1

N-583 [T2]

N-586 [T5]

N-586-1 [T1]

N-587

N-588 [T3]

N-589

[T5]

N-589-1

N-590

N-591

N-663 [T1]

N-592 [T3]

N-664 [T1]

N-593 [T2]

N-665 [T1]

N-597 [T5]

N-683 [T1]

N-597-1 [T5]

N-685 [T1]

N-597-2 [T2]

N-686 [T1]

N-598 [T3]

N-691

N-599 [T4]

N-694-1 [T5]

N-600 [T1]

N-694-2 [T5]

N-601 [T3]

N-694-2 [T2]

N-603 [T3]

N-695 [T1]

N-604 [T3]

N-696 [T1]

N-605 [T3]

N-697 [T1]

N-606 [T5]

N-700 [T1]

N-606-1 [T2]

N-702

N-609 [T1]

N-706 [T1]

N-613

N-613-1 [T1]

N-615

N-616 [T2]

N-617 [T1]

N-618

N-618-1

N-619 [T2]

N-622

N-623 [T1]

N-624 [T1]

N-627 [T3]

N-629 [T1]

N-630 [T4]

N-638 [T5]

N-638-1 [T2]

N-639 [T2]

N-640 [T1]

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-653

N-654

N-658 [T1]

N-660 [T2]

N-661 [T2]

N-662 [T2]

Appendix C to DG-1134, Page C-2

Appendix C to DG-1134, Page C-3