ML20206Q567

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Rev 5 to Reg Guide 1.147, Inservice Insp Code Case Acceptability,Asme Section XI Div 1
ML20206Q567
Person / Time
Issue date: 08/31/1986
From:
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:
References
REGGD-01.147, REGGD-1.147, NUDOCS 8609050045
Download: ML20206Q567 (7)


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netision 5 August 1986

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WA REGULATORY GUIDE

% + .W. . . /OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 1.147 INSERVICE INSPECTION CODE CASE ACCEPTABILITY ASME SECTION XI DIVISION 1 A. INTRODUCTION This regulatory guide lists those Section XI ASME Code Cases that are generally acceptable to the NRC staff for Section 50.55a, " Codes and Standards," of 10 CFR implementation in the inservice inspection of light-water-Part 50, " Domestic Licensing of Production and Utilization cooled nuclear power plants.

Facilities," requires, in part, that each operating licensa for a boiling or pressurized water-cooled nuclear power facility Any information collection activities mentioned in this regu-and each construction permit for a utilization facility be latory guide are mntained as requirements in 10 CFR Part 50, subject to the conditions in paragraph (g),"InserviceInspec- which provides the regulatory txtsis for this guide. The informa-tion Requirements," of 50.55a. Paragraph (g) requires,in tion collection requirements in 10 GR Part 50 have been part, that Classes I,2, and 3 components and their supports cleared under OMB Clearance No. 3150-0011.

meet the requirements of Section XI, " Rules for Inservice inspection of Nuclear Power Plant Components,"3 of the B. DISCUSSION American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code or equivalent quality standards. The ASME Boiler and Pressure Vessel Committee pub-Paragraph 50.55alb), in part, references the latest editions lishes a document entitled " Code Cases."1 Generally, and addenda in effect of Section XI of the Code and any the individual Code Cases that make up this document supplementary requirements to that section of the Code, explain the intent of Code rules or provide for alternative l'ootnote 6 to 50.55a states that the use of specific Code requirements undar special circumstances.

Cases may be authorized by the Conunission upon request pursuant to paragraph 50.55a(a)(2)(ii), which requires that Most Code Cases are eventually superseded by revision of D proposed alternatives to the described requirements or portions thereof provide an acceptable level of quality and safety.

the Code and then are annulled by acFon of the ASME Council In such instances, the intent of the annulled Code Case bewmes part of the revised Code, and therefore continued use of the General Design Criterion 1, "Quably Standards and Re- Code Case intent is sanctioned under the rules of the Code. In cords," of Appendix A, " General Design Criteria for Nuclear other instances, the Code Case is annulled because it is no Power Plants," to 10 CFR Part 50 requires, in part, that longer acceptable or there is no further requirem-nt forit. A structures, sy stems, and components important to safety be Code Case that was approved for a particular situation and not designed, fabricated, erected, and tested to quality standards for a generic application should he tsed only for the appraved I commensurate with the importance of the safety function situation because annulment of such a Code Case could result to be performed. Where generally recognized codes and in situations that would not meet Code requirements. De E standards are used, Criterion I requires that they be identi- ASME wnsiders the use of Code Cases to be optional for the fied and evaluateil to determine their applicability, adequacy, user and not a mandatory requireynent.

and sufficiency and be supplemented or modified as neces-sary to ensure a quality product in keeping with the required The Code Cases li:ted in this guide are limited to those safety function. cases applicable to Section XI of the Code.

fo Q All published Code Cases that are applicable to Section XI of the Code and were in effect on September 5,1985, were l e KE  %:es may be ietnined from the American Society of Mechan.

ical I ngineers. (Jnited 1.nginecting Center, J4s 1.ast 47th Street, New York, N.Y.100 8 7, 'L in es in dicate sut stantive changes from I evision 4.

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O(L O USNHC Hr'GULATORY GUIDES The guides are issued in the following ten broad divisions:

Regulatory Guides are issued to describe and make available to the public me t hods acc ept able to the NHC staff of implement 6ng 1. Power Reactors 6. Products specif 6c parts of the commission's regulations. to dettneate tech- 2. Research and Test Heactors 7. Transportation niques used by the s%If in evaluating specific problems or postu- 3. Fuels and Materials F ac616 ties 8. Occupational Health lated accidents or tn provide guidance to appiscants. Hegulatory 4. t~nvironmental and siting 9. Antitrust and F6nancial Review Guides are nok substitutes for regulations, and compliance with S. Materials and Plant Protection 10. General them is not required. Methods and solutions dif ferent from those set Copies of issued guides may be purchased from the Government in' dings #Nuis$t'e' t e Nsu e c o con inuan of a er to license by the Commission. Print 6ng Of fice at the current Gpo price. Informat6on on current D This guide was issued af ter consideration of comments received from the public. comments and suggestions for improvements in these guides are encouraged at all t6mes, and guides will be revised, as appropriate, to accommodate comments and to reflect new informa-GPO prices may be obtained by contacting the super 6ntendent of Documems, U.S. G over n ment Pe mting Of fice, post Of fice Hon 3 708 2, Wash 6ngton, Oc 20013 7082, telephone (202)215-2060 or (202)215 2111.

tion or emperience.

Written comments may be submitted to the Hules and Peratedures information service on a standing order basis. Details on t his nranch, OHH A()M, U.S. Nuclear H egulat or y Commission, service may be obtained by writing N rl5, S285 Port Hoyal Road, Washington. Od 20SSS. Lormgfield, V A 22161.

reviewed for inclusion in this guide. Code Cases that are not Code Case 1738 (N-118) is acceptable subject to the listed herein are either not endorsed or will require supple- following condition in addition to those conditions mentary provisions on an individual plant basis to attain specified in the Code Case. The last sentence of the endorsement status. " Reply" should be replaced with the following: The provisions of this Code Case may not be applied for 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 regulatory or other requirements or by the recommendations in this or other regulatory guides. Con. N-211 4 7/13/81 Recalibration of Ultrasonic Equip-tingent endorsement if applicable is indicated in regu'atory 7/13/84 ment Upon Change of Personnel, l position I for specific cases. Ilowever, 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 reeme N-216 3/10/78 Alternate Rules for ReactorVessel mended limitations resulting from Code Casc usage. 7/13/81 Closure Stud Examination, Sec-7/13/84 tion XI, Division 1 l l 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 12/5/84 sion I l 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 4/2/82 Section V, Section XI, Division I continuing change in the status of Code Cases,it is planned 2/14/85 that this guide will require periodic updating to accom-modate new Code Cases and any revision of existing Code N-236-1 9/5/85 Repair and Replacement of Class Cases. MC Vessels,Section XI, Divisim 1 C. REGULATORY POSITION Code Case N-236-1 is acceptable subject to the follow- l ing conditions in addition to those conditions

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

number, date of Councd 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. I the limitations stated in the " Inquiry" and " Reply" sec. I 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 refuelag outage.

and given with the individual Code Case in the list.

For clarification, Repairand Replacement of Class MC 17051 3/1/76 Ultrasonic Examination Calibra. Vessels means Repair and leplacement of Class MC $

N-98 11/20/78 tion Block Tolerances,Section XI Vessels and Components (sys+ ems). Acceptance of 1/21/82 this Code Case in no way int 3rs NRC approval to l 12/5/84 violate the technicalspecification or any NRC require-ments with regard to breach of cantainment during N-1131 12/13/82 Basic Calibration Block for Ultra- repair and replacement procedures while the plant is l

I 2/14/85 sonic Examination of Welds 10 in operation.

in. to 14 in. Thick,Section XI, Division 1 Where a numbered Code paragraph is rot identified by a particular edition of the Code, the Co le in effect 1738 12/22/75 Examination Acceptance Stand- at the time of the ASME meeting (11/3/78) that N 118 11/20/78 ards for Surface Indications in approved the Code Case should be governing.

1/21/82 Cladding,Section XI l 1/21/85 N 278 3/17/80 Alternative Ultrasonic Calibration 5

3/17/83 Block Configuration 1-3131 and

  • The Code Case was annulled on 3/2 I (ASME mandatory annulment date). It was reinstated on 7/l 81. liccause there wa.:

no change in the Code Case, the N RC con ers that the Case was 2 n e fect during the period 3/20/88 through 7/13/81.

A suunrrieal tintint d the Onde Caes appects in tie appendLx.

3 3 When Omle Case N-278 was inadvertently allowed to expire because more than one date is given, the earlier date is that on of an ASME admiriistrative error on 3/17/83, its mandatory amend-which the Code Case was approved by the ASM E Council, and the ment da *. The Code Case without any technical changes was rein-later date (or dates) is that on which the Code Case was rearfirmed stated on 5/25/83. liecause or these circumstances, the Code Case is by the ASMl; Council, considered to be in crrect during that period or time.

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s 5/25/83 T-434.3,Section XI, Division 1 N-375-2 4/5/84 Rules for Ultrasonic Examination C3 Code Case N-278 is acceptable subject to the following of Bolts and Studs,Section XI, Division I

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k/ conditions in addition to those conditions specified in the Code Case: When a universal calibration block is N-389 7/25/83 Alternative Rules for Repairs, used and some or all of the reference holes are larger Replacements, or Modifications, than the reflector holes at comparable depths recom- Section XI, Division 1 mended by Article IV,Section V,1980 edition of the ASME. Code, a correction factor should be used to Code Case N-389 is acceptable subject to the following adjust the DAC level to compensate for the larger condition in addition to those conditions specified in reflector holes. Also,if the reactor pressure vessel was the Code Case: The applicant should submit for approv-previously examined by using a conventional block, a althe appropriate edition and addenda of the Code that ratio between the DAC curves obtained from the two is to be used for the repair, replacement, or modification blocks should be noted (for reference) with the before start of the work.

significant indication data.

N-306 1/15/81 Calibration Block Material Selec- N-401 2/20/84 Eddy Current Examination, Sec-4/5/84 tion, Appendix 1,1-3121, Sec- tion XI, Division I tion XI, Division 1 ,

N-402 2/20/84 Eddy Current Calibration Stan-N-307-1 12/5/84 Revised Ultrasonic Examination dard Material,Section XI, Divi-Volume for Class 1 Bolting, Table sion i IWB-2500-1, Examination Cate-gory B-G-1, When the Examina- N-406 4/5/84 Alternate Rules for Replace-tions Are Conducted from the ment,Section XI, Division 1 l Center-Drilled liole,Section XI,

! Division 1 N-408 7/12/84 Alternate Rules for Examination of Class 2 Piping,Section XI, N 308 9/30/81 Documentation of Repairs and Division 1 Replacements of Components in

([V ]) l 9/30/84 Nuclear Power Plants,Section XI, Division 1 Code Case N-408 is acceptable subject to the following condition in addition to those conditions specified in N-311 5/11/81 Alternate Examination of Outlet the Code Case: The applicant for an operating license 4/5/84 Nozzle on Secondary Side of should define the Class 2 piping subject to volumetric Steam Generators,Section XI, and surface examination in the Preservice Inspection Division i for determination of acceptability by the NRC staff.

Code Case N-31I is acceptable subject to the following N-409 12/5/84 Procedure and Personnel Qualifi-condition in addition to those conditions specified in cation for Ultrasonic Detection the Code Case: The applicant should indicate in the and Sizing of Intergranular Stress Safety Analysis Report that the stress analysis of the Corrosion Craocingin Austenitic notzte inside-corner region meets the Code Case Piping Welds,Section XI, Divi-stipulations for the state of stress in this region, sion 1 N-415 9/5/85 Alternative Rules for Testing N-335-1 6/20/85 Rules for Ultrasonic Examina- Picssure Relief Devices, Sec-l tion of Similar and Dissimilar tion XI, Division 1 Metal Piping Welds,Section XI, Division i N-416 12/5/85 Alternative Rules for flydrostatic Testing of Repair or Replace-N 343 4/2/82 Alternate Scope of Examination ment of Class 2 Piping, Section l 2/14/85 of Attachment Welds for Exami- XI, Division I nation Categories B-II, D K 1, and C C,Section XI, Division 1 N-419 7/18/85 Extent of VT 1 Examinations, Category B-G-1 of Table IWB-N 355 7/16/82 Calibration Block for Angle 2500-1,Section XI, Division I Beam Ultrasonic Examination (f(/]j l 2/14/85 of Large I:ittings in Accordance with Appendix 111-3410, Sec-N-424 7/18/85 Qualification of Visual Examina-tion Personnel,Section XI, Divi-tion XI, Division I sion i 1.147 3

N-426 7/18/85 Extent of VT-1 Examinations, and the thickness of the material to which the strain Category B-G-2 of Table IWB- gage or thermocouple willbeattached by CD welding.

2500-1,Section XI, Division 1 N-288 8/25/80 Ilydratatic Test Requiremmts for

2. Code Cases that were endorsed by the NRC in a prior 5/25/83 Class I and Class 2 Components, version of this guide and were later annulled by action of the Section XI, Division 1 ASME Council should be considered as deleted from the list cf acceptable Code Casesas of the date of the ASME Council 3. Code Cases that were endorsed by the NRCin a prior action that approved the annulment. Such Code Cases that version of this guide and were superseded by revised Code were annulled on or after November 1,1978, are listed Cases on or after November 1,1978, should be considered as below by number, effective dates,6 and title, not endorsed as of the date of the Council action that approv-ed the revised version of the Code Cases. These Code Cases 1551 11/6/72 Inservice inspection of Welds on that are no longer endorsed are listed in the following by \

N-34 11/20/78 Nuclear Components,Section XI number, effective dates,7 and title.

I1/20/81 1731 11/3/75 Basic Calitration Block fa Ultra-1646 8/12/74 Partial Postponernent of Category N-113 11/20/78 sonic Examination of Welds 10 in, N-72 11/20/78 B-C Examination for Class 1 Com-f.

1/21/82 to 13 in. Thick,Section XI, Divi. )

1/1/81 ponents,Section XI 12/13/82 sion 1 1647 8/12/74 Partial Postpmement of Category N-236 1/8/79 Repair and Replacement of Class N-73 11/20/78 B-D Examination for Class 1 1/21/82 MC Vessels,Section XI, Divi-1/1/81 Components,Section XI 12/5/84 sion 1 9/5/85 1730 11/3/75 Acceptance Standards for ous 2 N 112 7/1/79 and 3 Components,Section XI, Code Case N-236 was acceptable subject to the follow- j Division 1 ing conditions in addition to those conditions speci-fled in the Code Case:

1804 1/14/77 Minimum Section Thickness N 167 1/14/80 Requirements for Repair of a. In paragraph 1.0(a), second sentence - the phrase, Nozzles,Section XI, Division 1 "while the plant is not in service," refers to a f refueling outage.

N-210 3/20/78 Exemption to llydrostatic Tests 3/20/81 After Repairs,Section XI, Divi- b. In paragraph 1.0(a), third sentence - the phrase, sion 1 "the next scheduled plant outage," refers to the l

next scheduled refueling outage.

Code Case N-210 was acceptable subject to the follow-ing condition in addition to those conditions specified For clarification, Repair and Replacement of Class in the Code Case. Paragraph (3) of the " Reply

  • should be MC Vessels means Repair and Replacement of Class replaced with the following: Repairs to piping, pumps, MC Vessels and Components (systems). Acceptance and salves where the depth of the repaired cavity of this Code Case in no way infers NRC approval to does not exceed 25 percent of the wall thickness. violate the technical specification or any NRC requirements with regard to breach of containment N 211 3/20/78 Recalibration of Ultrasmic Equip- during repair and replacement procedures while the 3/20/81 ment Upon Change of Personnel, plant is in operation.

Section XI, Division 1 Where a numbered Code paragraph is not identified l N-252 11/19/79 Low Energy Capacitive Discharge by a particular edition of the Code, the Code in effect 7/16/82 Welding Method for Temporary at the time of the ASME meeting (11/3/78) that or Permanent Attachments to approved the Code Case should be governing.

Components and Suppotts, Sec-tion 111, Division 1, and XI N-307 1/15/81 Revised Ultrasonic Examination 4/5/84 Volume for Class 1 Bolting, Code Case N 252 was acceptable subject to the following 12/5/84 Examination Category 11-G- 1,

condition in addition to those conditions specified in When the Examinations Are Con-I the Code Case
The applicant should indicate in the ducted from the Center-Dnlled Safety Analysis Report the af . cation, the material, IIole,Section XI, Division I to!arlier date-date Omle Case was a proved by ASME Council; 7 larlier date-date Onde Case was approved by ASME Council; later date date Code Case was annutk I. Where more than two later date- date revision of Code Case was approved by ASM E Council dates appear, the last date is the date that the Code CasJ was Where more than two dates appear, the last date is the date on which annulled.1he mktdle date (or dates) was the date of tenffirmation the Code Case was revised. The middle date (or dates) was the date of the Code Case. of reaffirmation of the Code Case.

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f N-335 4/2/82 Rules for Ulmsor.ic Examination 1. Except for those Code Cases that have been annulled 2/14/85 of Similar and Dissimilar Metal by action of the ASME Council,the NRCstaff willauthorize 6/20/85 Piping Welds,Section XI, Divi- appropriate use of the Code Cases hsted in this guide under sion 1 regulatory position 1 upon specific request by the applicant in accordance with footnote 6 to 50.55a, the Codes and N-375s 2/14/83 Rules for Ultrasonic Examination Standards rule. Code Cases that are actually used are to be i 4/14/83 of Bolts and Studs,Section XI, identified in the Inservice Inspection Program.

j Division 1

> N-375-1 4/14/83 Rules for Ultrasonic Examina- 2. Code Cases to be applied during an inspection interval

, 4/5/84 tion of Bolts and Studs, Sec- or Code Cases for a preservice inspection need not be tion XI, Division I changed because a subsequent revision of the Code Case is

. listed as the approved version in this guide.

4. Code Cases that are not on the approved list of this l guide (paragraph C.1) or other regulatory guides, or for l which authorization by the Commission has not been 3. Code Cases to be applied during an inspection interval granted, are not acceptable on a generic basis. or Code Cases for a preservice inspection that were previously
  • approved for use need not be changed because the Code D. IMPLEMENTATION Case has been subsequently annulled.

, The purpose of this section is to provide information to 4. Code Cases on the approved list 'nay be applied to y

applicants regarding the use of this regulatory guide. 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 8 in the Code Case and applicable regulations orrecommended Code Case N475 was not tisted in prior versions of this regu-tatory guide. in other regulatory guides.

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APPENDIX Numerical Listing of Code Cases 1705-1 (N-98) N-343 N-113-1 N-355 1738 (N-II 8) N-375-2 N 211 N-389 N-216 N-401 N-234 N-402 N-235 N-406 l N-236-1 N-408 N-278 N409 N-306 N-415 l N-307-1 N-416 N-308 N419 N-311 N-424 l N-335-1 N 426 O

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UNITED STATES ,,xsr cu.ss um NUCLEAR REGULATORY COTAM!SSION 'oST^ot * 't'5 do WASHINGTON, D.C. 20555 wN.". 8c. i PEPMIT No G $7 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE. $300 120555064215 1 10P11S US NRC AGM-DIV 0F TIOC mutuntui vuninvJ DESK-RECSB DC 20555 hA HINGTON 9

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