Regulatory Guide 1.147: Difference between revisions

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{{Adams
{{Adams
| number = ML13350A192
| number = ML12305A244
| issue date = 09/30/1985
| issue date = 02/28/1981
| title = Inservice Inspection Code Case Acceptability ASME Section XI Division 1
| title = Inservice Inspection Code Case Acceptability ASME Section XI Division 1
| author name =  
| author name =  
| author affiliation = NRC/RES
| author affiliation = NRC/RES, NRC/RGN-I
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
Line 10: Line 10:
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = RG-1.147, Rev. 4
| case reference number = Task SC 721-4
| document report number = RG 1.147
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 5
| page count = 4
}}
}}
{{#Wiki_filter:SRi.es1on498 U.S. NUCLEAR REGULATORY COMMISSION'                                                                    September 1985        .
{{#Wiki_filter:}}
                              REG ULATORY GUIDE
                              OFFICE OF NUCLEAR REGULATORY RESEARCH
                                                                REGULATORY GUIDE 1.147 INSERVICE INSPECTION CODE CASE ACCEPTABILITY
                                                          ASME SECTION Xl DIVISION 1
 
==A. INTRODUCTION==
implementation in the inservice inspection of light-water- cooled nuclear power plants.
 
Section50.55a, "Codes and Standards," of 10CFR
  Part 50, "Dom-stic licensing of Production and Utilization                        Any information collection activities mentioned in this regu- Facilities," requires, in part, that each operating license for              latory guide are contained as requirements in 10 CFR Part 50,
  a boiling or pressurized water-cooled nuclear power facility                  which provides the regulatory basis for this guide. The informa- and each construction permit for a utilization facility be                    tion collection requirements in 10 CFR 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==
meet the requirements of Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," 1 of the                          The ASME Boiler and Pressure Vessel Committee pub- American Society of Mechanical Engineers (ASME) Boiler                        lishes a document entitled "Code Cases."'                      Generally, and Pressure Vessel Code or equivalent quality standards.                    the individual Code Cases that make up this document Paragraph 50.SSa(b), in part, references the latest editions                  explain the intent of Code rules or provide for alternative and addenda 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 Cases may be authorized by the Commission upon request                        the Code and tben are annulled by action of the ASME Council.
 
pursuant to paragraph 50.S5a(aX2)(ii), which requires that                    In such instances, the intent of the annulled Code Case becomes proposed alternatives to the described requirements or portions              part of the revised Code, and therefore continued use of the thereof provide an acceptable level of quality 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 I, "Quality Standards and Re-                  longer acceptable or there is no further requirement for it. A
  cords," of Appendix A, "General Design Criteria for Nuclear                  Code Case that was approved for a particular situation and not Power Plants," to 10 CFR Part 50 requires, in part, that                      for a generic application shuld be used only for the approved structures, systems, and components important to safety be                    situation because 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 commensurate 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 1 requires that they be identi- fied and evaluated 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 product in 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 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 t
          Co plu nay be obtained hom the American Society of Mechanical          endorselnent status.
 
Enaimenr, United Englimeuing Center, 345 East 47th Street, New York, N.V. 10017.                                                                      *Lines indicate substanilve changes from Revision 3.
 
USNRC REGULATORV GUIDES                                    Comments should be sent-to the Secretary of the Commission, Regulatory Guides are Issued to describe and make available to the          U.S. Nuclear Regulatory Commissionn,                          DC 20555,- public methods acceptable to the NRC staff of Implementing                    Attontlons Docketing and Service 8rancnr--..I
  specfic -parts of the Commission's regulations, to delineate tech.
 
niques ue by the staff In evaluating $Pecific problems or postu-              The guides are Issued In the following ten broad dl¥visonsi..
    lated aUcidents, or to provide guidance to applicants. Regulatory            1. Power Reactors                 
 
===6. Products===
- Guides      are not substitutes for regulations, and compliance. with the'l Is not required. Methods and solutions different from those set        2. Research and Test Reactors     
 
===7. Transportation===
  *out,  n the guid~es will! be acceptable                                    3. Fuels and Materials Facilities 8. Occupational Health.
 
findings.'requisite  to the    issuance orIf continuance they. provide of a basis  for the a permit  or 4. Environmental end Siting          9. Antitrust and Flnanclal Review
                                                                                5.. Materials and Plant Protection 10. General -.............
  ..license by the Commission.
 
Copies of Issued guides may be purchaseda t thecurrent Goverpment This guide was Issued after consideration of comments received from          Prlntlna Office price. A subscription service for future uldes In wr.
 
the public. Comments and suggestions for Improvements In these              cific d vislons Is available through the Government PKnting Of C&
  guides are encouraged at all times, and guides will be revised, as          information on the subscription servIce and current 0POrices mae appropriate, to accommodate comments and to reflect now Informo-            be obtained by writing the Superintendent of ?ocument=                  Un, Government Printing Office, Post Off0 e Box '3702, shlngton, tio0n1or experience.                                    l    .e            DC 20013-7082.
 
F2                        '.'~
 
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-vessel insert welds.
 
precluded by regulatory or other requirements or by the recommendations in this or other regulatory guides. Con-                    N-211 4      7/13/81      Recalibration of Ukrasonic Equip- tingent endorsement if applicable is indicated in regulatory                                            ment Upon Change of Personnel, position I for specific cases. However, it is the responsibil-                                          Section XI, Division I
  ity of the user to make certain that no regulatory requirements are violated and that there are no conflicts with other recom-              N-216          3/10/78      Alternate Rules for Reactor Vessel mended limitations resulting from Code Case usage.                                        7/13/81      Closure Stud Examination, Sco- Lion 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 Calibra- 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 I
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 Xl, 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 I
 
==C. REGULATORY POSITION==
Code Case N-236 is 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 application 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 in service," refers to a cooled nuclear power plants. Their use is acceptable within                          refueling outage.
 
the limitations stated in the "Inquiry" and "Reply" sec- tions of each individual Code Case, within the limitations of                    b. In paragraph 1.0(a), third sentence - the phrase, such NRC or other requirements as may exist, and within                              "the next scheduled plant outage," refers to the the additional limitations recommended by the NRC staff                              next scheduled refueling outage.
 
and given with the individual Code Case in the list.
 
For clarification, Repair and Replacement of Class MC
    1551          11/6/72      Inservice Inspection of Welds on                  Vessels means Repair and Replacement of Class MC
    N-34          11/20/78    Nuclear Components, Section X;                    Vessels and Components (systems). Acceptance of this Code Case in no way infers NRC approval to
    1705-1      3/1/76        Ultrasonic Examination- Calibra-                  violate the technical specification or 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 plant is in operation.
 
N-I 13-1      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 effect Diviwsin I                                        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 Calibration
                  1/21/82      Cladding, Section XI                                        3/17/835      Block Configuration 1-3131 and
                                                                                            5/25/83'      T-434.3I Section XI, Division I
        Code Case 1738 (N-118) 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                  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.
 
2A numerical listing of the Code Cases appears In the appendix.
 
SCode Case N-278 was inadvertently allowed to expire because of
    3When more than one date Is given, the earlier date Is that on      an ASME administrative error on 3/17/83, Its mandatory amendment which the Code Case was approved by the ASME Council, and the            date. The Code Case without any technical changes was reinstated on later date (or dates) Is that on which the Code Case was reaffirmed      5/25183. Because of these circumstances, the Code Case Is considered by the ASME Council.                                                      to be in effect during that period of time.
 
1.147-2
 
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: Theapplicant should submit for approv- ASM. 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 for 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                N-401          2120/84      Eddy Current Examination, Sec- blocks should be noted (for reference) with the                                                  tion Xl, Division I
    significant indication data.
 
N-402          2/20/84      'Eddy Current Calibration Stan- N-306      1/15/81    Calibration Block Material Selec-                                          dard Material, Section XI, Divi-
 
* 4/5/84      tion, Appendix 1, 1-3121, Sec-                                            sion I
                            tion XlI Division 1 N-406          4/5/84        Alternate Rules for Replace- N-307      1/15/81      Revised Ultrasonic Examination                                            ment, Section XI, Division .1
              4/5/84      Volume for Class I Bolting, Examination Category B-G-I,                N-408          7/12184      Alternate Rules for Examination Division i, When the Examina-                                            of Class 2 Piping,. Section -XI,
                            tions Are Conducted from the                                              Division 1 Center-Drilled Hole Code Case N-408 is acceptable subject to the following N-308      9/30/81      Documentation of Repairs 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 Xl,                should define the Class 2 piping subject to volumetric Division I                                      and surface examination in the Preservice Inspection for determination of acceptability by the NRC staff.
 
N-311      5/11/81      Alternate Examination of Outlet
                                                                        2. Code Cases that were endorsed by the NRC in a prior
*I            4/5/84      Nozzle on Secondary Side of 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 of acceptable Code Cases as of the date of the AS4E 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-comer region meets the Code Case                      1646          8/12/74      Partial Postponement of Category stipulations for the state of stress in this region.                N-72          11/20/78      B-C Examination for Class I Com-
                                                                                        1/1181        ponents, Section XI
  N-335      4/2/82      Rules for Ultrasonic )-Iamina- tion of Similar and Dissimilar              1647          8/12/74      Partial Postponement of Category Metal Piping Welds, Section XI,              N-73            11/20178      B-D Examination for Class: I
                            Division I                                                    /l1/81      Components, Section XU
  N-343      4/2/82      Alternate Scope of Examination                1730          11/3/75      Acceptance Standards for Class 2 of Attachment Welds for Exami-              N-112          7/1/79        and 3 Components, Section XI,
                            nation Categories B-H, B-K-I, and                                          Division I
                            C-C, Section Xl, Division I
                                                                        1804            1/14/77      Minimum. Section        Thickness N-355      7/16/82      Calibration Block for Angi                  N-167          1/14/80      Requirements for 'Repair - of:
                            Beam Ultrasonic Examin,                                                  Nozzles, Section XI, Division 1 of Large Fittings in Accorda, with . Appendix iii-3410, Sec.              N-210          3/20/78        Exemption to Hydrostatic Tests tion XI, Division 1'                                        3/20/81,      After Repairs; Section Xl, Divi- sion I
  N-375-2    4/5/84      Rules for UltrasonicExamination of Bolts and Studs, Section Xl, Division I
  N-389      7/25/83      Alternative Rules .for 1Repairs,'        "Earle date-date Coda Came.was              roved by -ASME Cowute"l    .  .
                            Replacements, or Modiflccations,                date"d later sr.        Code Coswa aweuned.l      . mia than two dst__:a-.
                                                                              the lat te        date      thaante Code        = u. n.e. The Oection XI, Division I:                  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.              N-375s8      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 Code Case. 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-375-1      4/14/83
                                                                                          4/5/84 Division I
                                                                                                        Rules for Ultrasonic Examina- tion of Bolts and Studs, Sec-
                                                                                                                                                  0
                                                                                                        tion XI, Division 1 N-21 1        3/20/78      Recalibration of Ultrasonic Equip-
                  3/20/81      ment Upon Change of Personnel,              4. Code Cases that are not on the approved list of this Section XI, Division I                  guide (paragraph C.I) or other regulatory guides, or for which authorization by the Commission has not been N-2S2        11/19/79      Low Energy Capacitive Discharge        granted, are not acceptable on a generic basis.
 
7/16/82      Welding Method for Temporary or Permanent Attachments to                               
 
==D. IMPLEMENTATION==
Components and Supports, Sec- tion III, Division 1, and XI                The purpose of this section is to provide information to 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              I. 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 NRC staff will authorize 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 1 upon specific request by the applicant gage or thermocouple will be 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      Hyrostatic lbst Requirements for      identified in the Inservice Inspection Program.
 
5/25/83      Class I and Class 2 Components, Section XI, Division I                      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 NRC in a prior              changed because a subsequent revision of the Code Case is version of this guide 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 Council action that approv-              3. Code Cases to be applied during an inspection interval ed the revised version of the Code Cases. These Code Cases              or Code Cases fora 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.
 
1731          11/3/75      Basic Calibration Block for Ultra-          4. Code Cases on the approved list may be applied to N- 113        11/20/78    sonic Examination of Welds 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 I                                  effective date of the Code Case within the limits specified in the Code Case and applicable regulations or recommended
    7 Earfler date-date Code Case was approved by ASME Council:        in other regulatory guides.
 
later date-date revision of Code Case was appioved by ASMECouncil.
 
Where more than two dates atar, the tlat date Isthe date on which          8 the Code Case was revised.sTh middle date (or dates) was the date            Code Case N-375 was not liated in prior versions of this regulatory of reaffirmation of the Code Case.                                      guide.
 
1.147-4
 
APPENDIX
    Numerical Listing of Code Cases
1551    (N-34)                    N-308
1705-1 (N-98)                      N-3 11 N-1 13-1                          N-335
1738    (N-118)                  N-343 N-211                              N-355 N-216                              N-375-2 N-234                              N-389 N-235                              N-40 1 N-236                              N402 N-278                              N-406 N-306                              N-408 N-307
              1.147-5}}


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Revision as of 17:03, 10 March 2020

Inservice Inspection Code Case Acceptability ASME Section XI Division 1
ML12305A244
Person / Time
Issue date: 02/28/1981
From:
Office of Nuclear Regulatory Research, NRC Region 1
To:
References
Task SC 721-4 RG 1.147
Download: ML12305A244 (4)
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