Regulatory Guide 1.147

Inservice Inspection Code Case Acceptability ASME Section Xi Division 1

ML13350A192
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Issue date:	09/30/1985
From:	Office of Nuclear Regulatory Research
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RG-1.147, Rev. 4
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SRi.es1on498 September

1985 .U.S. NUCLEAR REGULATORY

COMMISSION'

REG ULATORY GUIDE OFFICE OF NUCLEAR REGULATORY

RESEARCH REGULATORY

GUIDE 1.147 INSERVICE

INSPECTION

CODE CASE ACCEPTABILITY

ASME SECTION Xl DIVISION 1

A. INTRODUCTION

Section50.55a, "Codes and Standards," of 10CFR Part 50, "Dom-stic licensing of Production and Utilization Facilities," requires, in part, that each operating license for a boiling or pressurized water-cooled nuclear power facility and each construction permit for a utilization facility be subject to the conditions in paragraph (g), "Inservice Inspec-tion Requirements," of §50.55a. Paragraph (g) requires, in part, that Classes 1, 2, and 3 components and their supports meet the requirements of Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," 1 of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code or equivalent quality standards.

Paragraph

50.SSa(b), in part, references the latest editions and addenda in effect of Section XI of the Code and any supplementary requirements to that section of the Code.Footnote 6 to §50.55a states that the use of specific Code Cases may be authorized by the Commission upon request pursuant to paragraph

50.S5a(aX2)(ii), which requires that proposed alternatives to the described requirements or portions thereof provide an acceptable level of quality and safety.General Design Criterion I, "Quality Standards and Re-cords," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50 requires, in part, that structures, systems, and components important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety function to be performed.

Where generally recognized codes and standards are used, Criterion

1 requires that they be identi-fied and evaluated to determine their applicability, adequacy, and sufficiency and be supplemented or modified as neces-sary to ensure a quality product in keeping with the required safety function.This regulatory guide lists those Section XI ASME Code.Cases that are generally acceptable to the NRC staff for Co t plu nay be obtained hom the American Society of Mechanical Enaimenr, United Englimeuing Center, 345 East 47th Street, New York, N.V. 10017.implementation in the inservice inspection of light-water- cooled nuclear power plants.Any information collection activities mentioned in this regu-latory guide are contained as requirements in 10 CFR Part 50, which provides the regulatory basis for this guide. The informa-tion collection requirements in 10 CFR Part 50 have been cleared under OMB Clearance No. 3150-0011.

B. DISCUSSION

The ASME Boiler and Pressure Vessel Committee pub-lishes a document entitled "Code Cases."' Generally, the individual Code Cases that make up this document explain the intent of Code rules or provide for alternative requirements under special circumstances.

Most Code Cases are eventually superseded by revision of the Code and tben are annulled by action of the ASME Council.In such instances, the intent of the annulled Code Case becomes part of the revised Code, and therefore continued use of the Code Case intent is sanctioned under the rules of the Code. In other instances, the Code Case is annulled because it is no longer acceptable or there is no further requirement for it. A Code Case that was approved for a particular situation and not for a generic application shuld be used only for the approved situation because annulment of such a Code Case could result in situations that would not meet Code requirements.

The ASME considers the use of Code Cases to be optional for the user and not a mandatory requirement.

The Code Cases listed in this guide are limited to those cases applicable to Section XI of the Code.All published Code Cases that are applicable to Section XI of the Code and were in effect on July 12, 1984, were reviewed for inclusion in this guide. Code Cases that are not listed herein are either not endorsed or will require supple-.mentary provisions on an individual plant basis to attain endorselnent status.*Lines indicate substanilve changes from Revision

3. USNRC REGULATORV

GUIDES Regulatory Guides are Issued to describe and make available to the public methods acceptable to the NRC staff of Implementing specfic -parts of the Commission's regulations, to delineate tech.niques ue by the staff In evaluating

$Pecific problems or postu-lated aUcidents, or to provide guidance to applicants.

Regulatory

-Guides are not substitutes for regulations, and compliance.

with the'l Is not required.

Methods and solutions different from those set*out, n the guid~es will! be acceptable If they. provide a basis for the findings.'requisite to the issuance or continuance of a permit or..license by the Commission.

This guide was Issued after consideration of comments received from the public. Comments and suggestions for Improvements In these guides are encouraged at all times, and guides will be revised, as appropriate, to accommodate comments and to reflect now Informo-tio0n1or experience.

l .e Comments should be sent-to the Secretary of the Commission, U.S. Nuclear Regulatory Commissionn, DC 20555,-Attontlons Docketing and Service 8rancnr--..I

The guides are Issued In the following ten broad dl¥visonsi..

1. Power Reactors 6. Products 2. Research and Test Reactors

7. Transportation

3. Fuels and Materials Facilities

8. Occupational Health.4. Environmental end Siting 9. Antitrust and Flnanclal Review 5.. Materials and Plant Protection

10. General -.............

Copies of Issued guides may be purchaseda t thecurrent Goverpment Prlntlna Office price. A subscription service for future uldes In wr.cific d vislons Is available through the Government PKnting Of C&information on the subscription servIce and current 0POrices mae be obtained by writing the Superintendent of ?ocument=

Un, Government Printing Office, Post Off0 e Box '3702, shlngton, DC 20013-7082.

F2 '.'~

The endorsement of a Code Case by this guide constitutes acceptance of its technical position for applications not precluded by regulatory or other requirements or by the recommendations in this or other regulatory guides. Con-tingent endorsement if applicable is indicated in regulatory position I for specific cases. However, it is the responsibil- ity of the user to make certain that no regulatory requirements are violated and that there are no conflicts with other recom-mended limitations resulting from Code Case usage.Acceptance or endorsement by the NRC staff applies only to those Code Cases or Code Case revisions with the date of "Council Approval" as shown in the regulatory position of this guide. Earlier or later revisions of a Code Case are not endorsed by this guide. New Code Cases will require evaluation by the NRC staff to determine if they qualify for inclusion in the approved list. Because of the con-tinuing change in the status of Code Cases, it is planned that this guide will require periodic updating to accommodate new Code Cases and any revision of existing Code Cases.C. REGULATORY

POSITION 1. The Section XI ASME Code Cases 2 listed below (by number, date of Council approval, 3 and title) are accept-able to the NRC staff for application in the inservice inspection of components and their supports for water-cooled nuclear power plants. Their use is acceptable within the limitations stated in the "Inquiry" and "Reply" sec-tions of each individual Code Case, within the limitations of such NRC or other requirements as may exist, and within the additional limitations recommended by the NRC staff and given with the individual Code Case in the list.1551 11/6/72 Inservice Inspection of Welds on N-34 11/20/78 Nuclear Components,Section X;the examination of clad surfaces of nozzles, including the inner surface of the nozzle-to-vessel insert welds.N-211 4 7/13/81 Recalibration of Ukrasonic Equip-ment Upon Change of Personnel,Section XI, Division I N-216 3/10/78 Alternate Rules for Reactor Vessel 7/13/81 Closure Stud Examination, Sco-Lion XI, Division 1 N-234 1/8/79 Time Between Ultrasonic Calibra-1/21/82 tion Checks,Section XI, Divi-sion I N-235 1/8/79 Ultrasonic Calibration Checks per 4/2/82 Section V, Section Xl, Division I N-236 1/8/79 Repair and Replacement of Class 1/21/82 MC Vessels,Section XI, Division I Code Case N-236 is acceptable subject to the following conditions in addition to those conditions specified in the Code Case:

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 infers NRC approval to violate the technical specification or any NRC require-ments 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 (11/3/78)

that approved the Code Case should be governing.

N-278 3/17/80 Alternative Ultrasonic Calibration

3/17/835 Block Configuration

1-3131 and 5/25/83' T-434.3I Section XI, Division I Code Case N-278 is acceptable subject to the following conditions in addition to those conditions specified in the Code Case: When a universal calibration block is 4 The Code Case was annulled on no081 (ASME mandatory annulment date). It was reinstated on 1/13151. Because there was no change In the Code Case, the NRC considers that the Case was in effect during the period 3120/81 through 7/13/81.SCode Case N-278 was inadvertently allowed to expire because of an ASME administrative error on 3/17/83, Its mandatory amendment date. The Code Case without any technical changes was reinstated on 5/25183. Because of these circumstances, the Code Case Is considered to be in effect during that period of time.1705-1 3/1/76 N-98 11/20/78 1/21/82 Ultrasonic Examination- Calibra-tion Block Tolerances,Section XI N-I 13-1 12/13/82 Basic Calibration Block for Ultra-sonic Examination of Welds 10 in. to 14 in. Thick,Section XI, Diviwsin I 1738 12/22/75 N-118 11/20/78 1/21/82 Examination

-Acceptance Stand-ards for Surface Indications in Cladding,Section XI Code Case 1738 (N-118) is acceptable subject to the following condition in addition to those conditions specified in the Code Case. The last sentence of the"Reply" should be replaced with the following:

The provisions of this Code Case may not be applied for 2A numerical listing of the Code Cases appears In the appendix.3When more than one date Is given, the earlier date Is that on which the Code Case was approved by the ASME Council, and the later date (or dates) Is that on which the Code Case was reaffirmed by the ASME Council.1.147-2 used and some or all of the reference holes are larger than the reflector holes at comparable depths recom-mended by Article IV,'Section V, 1980 edition of the ASM. 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 by using a conventional block, a ratio between the DAC curves obtained from the two blocks should be noted (for reference)

with the significant indication data.N-306 1/15/81 Calibration Block Material Selec-* 4/5/84 tion, Appendix 1, 1-3121, Sec-tion XlI Division 1 N-307 1/15/81 Revised Ultrasonic Examination

4/5/84 Volume for Class I Bolting, Examination Category B-G-I, Division i, When the Examina-tions Are Conducted from the Center-Drilled Hole N-308 9/30/81 Documentation of Repairs and Replacements of Components in Nuclear Power Plants,.Section Xl, Division I N-311 5/11/81 Alternate Examination of Outlet* I 4/5/84 Nozzle on Secondary Side of Steam Generators,Section XI, Division 1 Code Case N-311 is acceptable subject to the following condition in addition to those conditions specified in the Code Case: The applicant should indicate in the Safety Analysis Report that the stress analysis of the nozzle inside-comer region meets the Code Case stipulations for the state of stress in this region.N-335 4/2/82 Rules for Ultrasonic

)-Iamina-tion of Similar and Dissimilar Metal Piping Welds,Section XI, Division I N-343 4/2/82 Alternate Scope of Examination of Attachment Welds for Exami-nation Categories B-H, B-K-I, and C-C, Section Xl, Division I N-355 7/16/82 Calibration Block for Angi Beam Ultrasonic Examin, of Large Fittings in Accorda, with .Appendix iii-3410, Sec.tion XI, Division 1'N-375-2 4/5/84 Rules for UltrasonicExamination of Bolts and Studs, Section Xl, Division I Code Case N-389 is acceptable subject to the following condition in addition to those conditions specified in the Code Case: Theapplicant should submit for approv-al the appropriate'edition and addenda of the Code that is to. be used for the repair, replacement, or modification before start of the work.N-401 2120/84 Eddy Current Examination, Sec-tion Xl, Division I N-402 2/20/84 'Eddy Current Calibration Stan-dard Material,Section XI, Divi-sion I N-406 4/5/84 Alternate Rules for Replace-ment,Section XI, Division .1 N-408 7/12184 Alternate Rules for Examination of Class 2 Piping,. Section -XI, Division 1 Code Case N-408 is acceptable subject to the following condition in addition to those conditions specified in the Code Case: 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.2. Code Cases that were endorsed by the NRC in a prior version of this guide and were later annulled by action of the ASME Council should be considered as deleted from the list of acceptable Code Cases as of the date of the AS4E Council.action that approved the annulment.

Such Code Cases that were annulled on or after November 1, 1978, are listed below by number, effective dates, 6 and title.1646 8/12/74 N-72 11/20/78 1/1181 1647 8/12/74 N-73 11/20178/l1/81 Partial Postponement of Category B-C Examination for Class I Com-ponents,Section XI Partial Postponement of Category B-D Examination for Class: I Components, Section XU 1730 11/3/75 Acceptance Standards for Class 2 N-112 7/1/79 and 3 Components,Section XI, Division I 1804 1/14/77 N-167 1/14/80 Minimum. Section Thickness Requirements for 'Repair -of: Nozzles,Section XI, Division 1 N-210 3/20/78 Exemption to Hydrostatic Tests 3/20/81, After Repairs; Section Xl, Divi-sion I N-389 7/25/83 Alternative Rules .for 1 Replacements, or Modiflc Oection XI, Division I: Repairs,' "Earle date-date Coda Came.was roved by -ASME Cowute"l ..cations, later date"d Code Coswa aweuned.l

.mia than two dst__:a-.sr. the lat te date thaante Code n. = u. e. The n~iddle data (or dt) was thei te of reaffirma.tion of the Coe .Cas:.1.147-3! : ::'k I Code Case N-210 was acceptable subject to the follow.ing condition in addition to those conditions specified in the Code Cas

e. Paragraph

(3) of the "Reply"should 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-21 1 3/20/78 Recalibration of Ultrasonic Equip-3/20/81 ment Upon Change of Personnel,Section XI, Division I N-2S2 11/19/79 Low Energy Capacitive Discharge 7/16/82 Welding Method for Temporary or Permanent Attachments to Components and Supports, Sec-tion III, Division 1, and XI Code Case N-252 was acceptable subject to the following condition in addition to those conditions specified in the Code Case: 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-288 8/25/80 Hyrostatic lbst Requirements for 5/25/83 Class I and Class 2 Components,Section XI, Division I 3. Code Cases that were endorsed by the NRC in a prior version of this guide and were superseded by revised Code Cases on or after November 1, 1978, should be considered as not endorsed as of the date of the Council action that approv-ed the revised version of the Code Cases. These Code Cases that are no longer endorsed are listed in the following by number, effective dates, 7 and title.1731 11/3/75 Basic Calibration Block for Ultra-N- 113 11/20/78 sonic Examination of Welds 10in.1/21/82 to 13 in. Thick,Section XI, Divi-12/13/82 sion I 7 Earfler date-date Code Case was approved by ASME Council: later date-date revision of Code Case was appioved by ASMECouncil.

Where more than two dates atar, the tlat date Is the date on which the Code Case was revised.sTh middle date (or dates) was the date of reaffirmation of the Code Case.N-375s 8 2/14/83 Rules for Ultrasonic Examination

4/14/83 of Bolts and Studs,Section XI, Division I N-375-1 4/14/83 Rules for Ultrasonic Examina-4/5/84 tion of Bolts and Studs, Sec-tion XI, Division 1 4. Code Cases that are not on the approved list of this guide (paragraph C.I) or other regulatory guides, or for which authorization by the Commission has not been granted, are not acceptable on a generic basis.

D. IMPLEMENTATION

The purpose of this section is to provide information to applicants regarding the use of this regulatory guide.I. Except for those Code Cases that have been annulled by action of the ASME Council, the NRC staff will authorize appropriate use of the Code Cases listed in this guide under regulatory position 1 upon specific request by the applicant in accordance with footnote 6 to §50.55a, the Codes and Standards rule. Code Cases that are actually used are to be identified in the Inservice Inspection Program.2. Code Cases to be applied during an inspection interval or Code Cases for a preservice inspection need not be changed because a subsequent revision of the Code Case is listed as the approved version in this guide.3. Code Cases to be applied during an inspection interval or Code Cases fora preservice inspection that were previously approved for use need not be changed because the Code Case has been subsequently annulled.4. Code Cases on the approved list may be applied to procedures for an inspection interval and procedures for the inservice inspection that were established prior to the effective date of the Code Case within the limits specified in the Code Case and applicable regulations or recommended in other regulatory guides.8 Code Case N-375 was not liated in prior versions of this regulatory guide.0 1.147-4 APPENDIX Numerical Listing of Code Cases 1551 (N-34)1705-1 (N-98)N-1 13-1 1738 (N-118)N-211 N-216 N-234 N-235 N-236 N-278 N-306 N-307 1.147-5 N-308 N-3 11 N-335 N-343 N-355 N-375-2 N-389 N-40 1 N402 N-406 N-408