ML20137V412

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Rev 4 to Reg Guide 1.147, Inservice Insp Code Case Acceptability,Asme Section XI Div 1
ML20137V412
Person / Time
Issue date: 09/30/1985
From:
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:
References
REGGD-01.147, REGGD-1.147, NUDOCS 8510040019
Download: ML20137V412 (6)
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Revision 4

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U.S. NUCLEAR REGULATORY COMMISSION September 1985 4

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OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 1.147 INSERVICE INSPECTION CODE CASE ACCEPTABILITY ASME SECTION XI DIVISION 1 A. INTRODUCTION implementation in the inservice inspection of bght water-cooled nuclear power plants.

Ssction 50.55a, " Codes and Standards," of 10 CFR Part 50, " Domestic Licensing of Production and Utilization Any information collection activities nrntioned in this regu-Facilities." requires, in part, that each operating license for latory guile are contained as requirenrnts in 10 CFR Part 50, i

I a boiling or pressurized water-cooled nuclear power facility which povides the regulatory basis for this guide. The informa-and each construction permit for a utilization facihty be tion collection requirements in 10 GR Part 50 have been subject to the conditions in paragraph (g)," Inservice Inspec-cleared under OMB Clearance No. 3150-0011.

tion Requirements," of 50.55a. Paragraph (g) requires, in part, that Classes 1,2, and 3 components and their supports B. DISCUSSION mect the requirements of Section XI," Rules for Inservice Inspection of Nuclear Power Plant Ccmponents,"I of the The ASME Boiler and Pressure Vessel Committee pub-American Society of Mechanical Engineers (ASME) Boiler hshes a document entitled " Code Cases."I Generally, and Pressure Vessel Code or equivalent quality standards.

the individual Code Cases that make up this document Paragraph 50.55a(b), in part, references the latest editions explain the intent of Code rules or provide for alternative and addends in effect of Section XI of the Code and any requirements under special circumstances.

supplementary requirements to that section of the Code.

Footnote 6 to 50.55a states that the use of specific Code Most Code Cases are eventually superseded by revision of the Code and tirn are annulled by.ttion of the ASME Council.

b Cases may be authorized by the Commission upon request pursuant to paragraph 50.55a(a)(2)(ii), which requires that in suchinstances, the intent of the annulled Code Case irmmes proposed alternatives to the described requirements or portions part of the revised Code, and therefore contmued use of the thereof provide an acceptable level of quahty and safety.

Code Case intent is sanctioned under the rules of the Code. In other instances, the Code Case is annulled because it is no General Design Criterion 1," Quality Standards and Re-longer acceptable or there is no further requirement forit. A cords," of Appendix A " General Design Cnteria for Nuclear Code Case that was approved for a retticular situation and nd Power Plants," to 10 CFR Part 50 requires, in part, that for a gmeric application dould be med mly for the approved structures, systems, and components important to safety be situation tecause annulment of such a Code Case could result designed, fabricated, erected, and tested to quality standards in situations that would not meet Code requirements. The commen; urate with the importance of the safety function ASME considers the use of Code Cases to be optional for the to be performed. Where generally recognized codes and user and not a mandatory requirement.

standards are used, Criterion I requires that they he identi-fied and evaluat ed to determine their applicability, adequacy, The Code Cases listed in this guide are limited to those and sufficiency and be supplemented or modified as neces-cases applicable to Section XI of the Code.

sary to ensure a quality productin keeping with the required safety function.

All published Code Cases that are applicable to Section XI of the Code and were in effect on July 12,1984, were l This regulatory guide lists those Section XI ASME Code reviewed for inclusion in this guide. Code Cases that are not Cases that are generally acceptable to the NRC staff for listed herein are either not endorsed or will require supple-mentary provisions on an individual plant basis to attain I

endorsement status.

Copies may be obtained from the American Society of Mechanical Engirrers, United Engineering Center,34s East 47:h Street, New York, N.Y.10o 17.

' Lines indicate substantive changes from Revision 3.

USNRC REGULATORY GUiOES Comments should be sent to the Secretary of the Commission, pu c meth s a optab o he N st f of ir em tl L"u'e'sufe'fty 't4"*stf#*," Tat"M"s'e'c'Ec' ',2',','&,',0:

W 9ui M are issued in the following ten broad divisions:

t 0ted accidents, or to provide guidance to app cants. Regulatory

1. Power Reactors
6. Products Guides are not substitutes for regulations, and compilance w6th
2. Research and Test Reactors
7. Transportation them is not required. Methods and solutions different frorn those set
3. Fuels and Materials Facilities
8. Occupational Health out in the guides will be acceptable if they provide a basis for the
4. Environmental and Siting
9. Antitrust and Financial Review 1"e%"e't#ninm'",sii7n.'""'"" " """""*"" o'
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Copies of issued guides may be purchased at the current Government c fic d vi s is aval'labi th g

h ove ment i i tin f fl This guide was issued af ter consideration of coruments received from the pubHC. Comments and suggestions for improvements in these Informat6on on the subscription service and current GPO prfces may guides are encouraged at all times, and guides will be tsv6 sed, as be obtained b writin the Superintendent of Documents U.S r niing O f ace, Post Office Box 37082, Wasmngton" pero riat o commodate comments and to reflect new informa-rn nt 8510040019 850930 PDR RECCD 01.147 p pyg l

The endorsement of a Code Case by this guide constitutes the examination of clad surfaces of nozzles, including acceptance of its technical position for applications not the inner surface of the nozzle to-vesselinsert welds.

precluded by regubtory or other requirements or by the recommendations in this or other regulatory guides. Con-N-211 7/13/81 Recalibration of Ultrasonic Equip-l 4

tingent endorsement if applicable is indicated in regulatory ment Upon Change of Personnel, position 1 for specific cases. Ilowever, it is the responsibil-Section XI, Division 1 ity of the user to mak e certain that no regulatory requirements are violated and that there are no conflicts with other recom-N-216 3/10/78 Altermte Rules for Reactor Vessel mended limitations resulting from Code Case usage.

7/13/81 Closure Stud Examination, Sec-tion XI, Division 1 Acceptance or endorsement by the NRC staff applies only to those Code Cases or Code Case revisions with the N-234 1/8/79 Time Between Ultrasonic Cahbra-date of " Council Approval" as shown in the regulatory 1/21/82 tion Checks,Section XI, Divi-position of this guide. Earlier or later revisions of a Code sion !

Case are not endorsed by this guide. New Code Cases will require evaluation by the NRC staff to determine if they N-235 1/8/79 Ultrasonic Calibration Checks per qualify for inclusion in the approved list. Because of the con-4/2/82 Section V,Section XI, Division I tinuing change in the status of Code Cases, it is planned that this guide will require periodic updating to accommodate N-236 1/8/79 Repair and Replacement of Class new Code Cases and any revision of existing Code Cases.

1/21/82 MC Vessels,Section XI, Division 1 C. REGULATORY POSITION Code Case N-236is acceptable subject to the following conditions in addition to those conditions specified

1. The Section XI ASME Code Cases 2 listed below (by in the Code Case:

number, date of Council approval,3 and title) are accept-able to the NRC staff for appbcation in the inservice

a. In paragraph 1.0(a), second sentence - the phrase, inspection of components and their supports for water-

"while the plant is not m service," ufers to a cooled nuclear power plants. Their use is acceptable within refueling outage.

the limitations stated in the "laquiry" and " Reply" sec-tions of each individual Code Case, within the lirnitations of such NRC or other requirements as may cust, and within

o. In paragraph 1.0(a), third sentence - the phrase, t

"the next scheduled plant outage " refers to the the additional limitations recommended by the NRC staff next scheduled refueling outage.

k and giv.n with the individu.d Code Case in tne list.

For clarification, Repair and Replacement of Class MC i

1551 11/6/72 Inservice Inspection of Welds or-Vessels means Repair and Replacement of Class MC N-34 11/20/78 Nuclear Components,Section XI Vessels and Components (systems). Acceptance of this Code Case in no way infers NRC approvtl to 1705-1 3/1/76 Ultrasonic Examination-Calibra-violate the technicalspecificationor any NRC require-N-98 11/20/78 tion Block Tolerances,Section XI ments with regard to breach of containment during 1/21/82 repair and replacement procedures while the plaat is in operation.

N-113-1 12/13/82 Basic Calibration Block for Ultra-sonic Examination of Welds 10 Where a numbered Code paragraph is not identified in. to 14 in. Thick,Section XI, by a particular edition of the Code, the Code in elfect Division 1 at the time of the ASME meeting (11/3/78) that approved the Code Case should be governing.

1738 12/22/75 Examination - Acceptance Stand-N-118 11/20/78 ards for Surface Indications in N-278 3/17/80 Alternative Ultrasonic Cahbration 1/21/82 Cladding,Section XI 3/17/83 Block Configuration ! 3131 and 5

5 5/25/83 T-434.3,Section XI, Division !

Code Case 1738 (N-Il8) is acceptable subject to the following condition in addition to those conditions Code Case N-278 is acceptable subject to the following specified in the Code Case. The last sentence of the conditions in addition to those conditions specified in

" Reply" should be replaced with the following: The the Code Case: When a universal calibration block is provisions of this Code Case may not be applied for 4The Code Case was annulled on 3/20/81 (ASME mandatory annulment date). It was reinstated on 7/13/81. Because there was no change in the Code Case, the NRC considers that the Case was 2

n efrect during the period 3/20/81 through 7/13/81.

A numerical listing of the Code Cases appears in the appendix.

3 Code Case N-278 wasinadvertently allowed to expire because of l

When more than one date is given, the earlier date is that on which the Code Case was approved by the ASME Council, and the an ASME administrative error on 3/17/83,its mandatory amendment later date (or dates) is that on which the Code Case was reaffirmed date. The Code Case without any technical changes was reinstated on a

q by the ASME Council s/2 s/83. Because of these circu mstances, the Code Case is coraidered to be in erfect during that period of time.

1.147-2 l

used and some or all of the reference holes are larger Code Case N-389 is acceptable subject to the following than the reflector holes at comparable depths recom-condition in addition to those conditions specified in mended by Article IV,Section V,1980 edition of the the Code Case: The applicant should submit for approv-D ASME Code, a correction factor should be used to al the appropriate edition and addenda of the Code that adjust the DAC level to compensate for the larger is to be used f(r the repair, replacement.or modification reflector holes. Also,if the reactor pressure vessel was before start of the work, previously examined by using a conventional block, a ratio between the DAC curves obtained from the two N401 2/20/84 Eddy Current Examination, Sec-l blocks should be noted (for reference) with the tion XI, Division i significant indication data.

N402 2/20/84 Eddy Current Calibration Stan-N-306 1/15/81 Calibration Block Material Seier dard Material,Section XI, Divi-j l

4/5/84 tion, Appendix 1,1-3121, Se; sion I tion XI, Division I N406 4/5/84 Alternate Rules for Replace-N-307 1/15/81 Revised Ultrasonic Examination me r.t,Section XI, Division 1 l

4/5/84 Votr me for Class 1 Bolting, Examination Category B-G-1, N408 7/12/84 Alternate Rules for Examination Division 1, When the Examina-of Class 2 Piping,Section XI, tions Are Conducted from the Division 1 Center-Drilled IIole Code Case N-408 is acceptable subject to the following N-308 9/30/81 Documentation of.'tepairs and condition in addition to those conditions specified in Replacements of Components in the Code Case: The applicant for an operating license Nuclear Power Plants,Section XI, should define the Class 2 piping subject to volumetric Division I and surface examination in the Preservice Inspection for determination of acceptabihty by the NRC staff.

N-311 5/11/81 Alternate Examination of Outlet l

4/5/84 Nozzle on Secondary Side of

2. Code Cases that were endorsed by the NRC in a prior Steam Generators,Section XI, version of this guide and were later annulled by action of the Division 1 ASME Council should be considered as deleted from the list D

of acceptable Code Cases as of the date of the ASME Council Code Case N-311 is acceptable subject to the following action that approved the annulment. Such Code Cases that condition in addition to those conditions specified in were annulled on or after November 1,1978, are listed the Code Case: The applicant should indicate in the below by number, effective dates,6 and title.

Safety Analysis Report that the stress analysis of the nozzle inside-corner region meets the Code Case 1646 8/12/74 Partial Postpmenrnt of Category stipulations for the state of stress in this region.

N-7 2 11/20/78 BC Examination for Class 1 Com-1/1/81 ponents,Section XI N 335 4/2/82 Rules for Ultrasonic Examina-tion of Similar and Dissimilar 1647 8/12/74 Partial Postpmement of Category Metal Piping Welds,Section XI, N-73 11/20/78 B-D Examination for Class i Division 1 1/1/81 Components,Section XI N-343 4/2/82 Alternate Scope of Examination 1730 11/3/75 Acceptance Standards for Class 2 of Attachment Welds for Exami-N-ll2 7/1/79 and 3 Components,Section XI, nation Categories B-II, B-K 1,and Division 1 C-C,Section XI, Division 1 1804 1/14/77 Minimum Section 7hickness N-355 7/16/82 Calibration Block for Angle N-167 1/14/80 Requirements for Repair of Beam Ultrasonic Examination Nozzles,Section XI, Division 1 of Large Fittings in Accordance with Appendix 111-3410, Sec-N-210 3/20/78 Exemption to llydrostatic Tests tion XI, Division 1 3/20/81 After Repairs,Section XI, Divi-sion 1 l

N-375-2 4/5/84 Rules for Ultrasonic Examination of Bolts and Studs,Section XI, Division 1 N-389 7/25/83 Alternative Rules for Repairs, 6Earlier date-.date Code Case was a roved by ASME Council; later date@ Code Case was annulled.There more than two dates Replacements, or Modifications' appear, the last ' ate is the date that the Code Case was annulled. The Section XI, Division I middle date (or dates)was the date of reartirmation of the Code Case.

l 1.147-3

Code Case N-210 was acceptable subject to the follow-N 375s 2/14/83 Rules for Ultrasonic Examination ing condition in addition to those conditions specified 4/14/83 of Bolts and Studs,Section XI, in the Co& Case. Paragraph (3)of the " Reply"should be Division !

replaced with the followiag: Repairs to piping, pumps,

{

and valves where the depth of the repaired cavity N-375-1 4/14/83 Rules for Ultrasonic Examina-does not exceed 25 percent of the wall thickness.

4/5/84 tion of Bolts and Studs, Sec-tion XI, Division 1 N 211 3/20/78 Recahbration of Ultrasmic Il uip-l 3/20/81 ment Upon Change of Personnel,

4. Code Cases that are not on the approved list of thisSection XI, Division I guide (paragraph C.1) or other regulatory guides, or for which authorization by the Commission has not been N-252 11/19/79 Low Energy Capacitive Discharge granted, are not acceptable on a generie basis.

7/16/82 Welding Method for Temporary or Permanent Attachments to D. IMPLEMENTATION Components and Supports, Sec-tion III, Division I, and XI The purpose of this section is to provide information to f

applicants regarding the use of this regulatory guide.

Code Case N-252 was acceptable subject to the following condition in addition to those conditions specified in

1. Except for those Code Cases that have been annulled the Code Case: The applicant should indicate in the by action of the ASME Council,the NRCstaff willauthorize Safety Analysis Report the application, the material, appropriate use of the Code Cases listed in this guide under and the thickness of the material to which the strain regulatory position I upon specific request by the applicant gage or thermocouple willbe attached by CD welding.

in accordance with footnote 6 to 50.55a, the Codes and Standards rule. Code Cases that are actually used are to be N-288 8/25/80 Ifnirostatic Rst Requiremaits for identified in the Inservice inspection Program.

5/25/83 Class I and Class 2 Components,Section XI, Division 1

2. Code Cases to be applied during an inspection interval or Code Cases for a preservice inspection need not be
3. Code Cases that were endorsed by the NRCin a prior changed because a subsequent revision of the Code Case is version of this gi.ide and were superseded by revised Code listed as the approved version in this guide.

Cases on or after November 1,1978,should be considered as not endorsed as of the date of the Councilaction that approv-

3. Code Cases to be applied during an inspection interval ed the revised version of the Code Cases. These Code Cares or Code Cases for a preservice inspection that were previously that are no longer endorsed are listed in the following by approved for use need not be changed because the Code number, effective dates,7 and title.

Case has been subsequently annulled.

  • i31 11/3/75 Basic Calitration Block fa Ultra-
4. Code Cases on the approved list may be applied to

+113 11/20/78 sonic Examination of We.ds 10in.

procedures for an inspection interval and procedures for the 1/21/82 to 13 in. Thick,Section XI, Divi-inservice inspection that were established prior to the 12/13/82 sion 1 effective date of the Code Case within the limits specified in the Code Case and applicabic regulations or recommended 7Earlier date-date Code Case was approved by ASME Council; E

! ster date-date revision of Code Case was approved by ASM E Council.

Where more than two dates appear, the last date is the date on which the Code Case was revised. Ine middle date (or dates) was the date 8

of reaffirrnation of the Code Case.

Code Case N 475 was not listed in prior versions of this regulatory guide.

1.147-4

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APPENDIX l

Numerical Listing of Code Cases 1551 (N-34)

N-308 1705-1 (N-98)

N-311 N-113-1 N-335 1738 (N-118)

N-343 l

N-211 N-355 N-216 N-375-2 I N-234 N-389 N-235 N401 N-236 N402 I

N-278 N406 l

N-306 N-408 N-307 1.147-5

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