ML20083Q552

Rev 1 to Nuclear Guide 1.147, Inservice Insp Code Case Acceptability,Asme Section Xi,Div 1

ML20083Q552
Person / Time
Site:	Oconee, Mcguire, Catawba, McGuire, 05000000
Issue date:	01/06/1983
From:	Dalton D DUKE POWER CO.
To:
Shared Package
ML20083Q427	List: LG-83-163, Forwards Amend 19 to Duke Power Nuclear Guides.Amend 20 Will Be Forwarded in Apr 1983 ML20083Q452 ML20083Q478 ML20083Q493 ML20083Q501 ML20083Q521 ML20083Q552 ML20083Q561
References
1.147, NUDOCS 8302250436
Download: ML20083Q552 (7)

Text

_, , . - . _ _ . . . .. -

. , ;. ,. , , a_ _ ,. .. _, ., , . _ . - . , . . . .

. FORM NG-1, REV 1

- m.

DUKE POWER COMPANY Page 1 of 3 Nuclear Guide , 1.147

(, NUCLEAR GUIDE Effective Date 1/6i33 Revi.Jon 1 1 Titl*,*

Inservice Inspection Code Case Acceptability ASME Section XI Division 1 Reference NRC Regulatory Guide Number 1.147 Revision 1 l

Disposition

• of Current Disposition of Previous RG Revisions Plants Affected This RG Revision Revision Number Disposition Partial Compilance O Partial Compilance 50conee Partial Compilance O Partial Compilance BMcGuire Partial Compilance O Partial Compliance GCatawba l Partial Compliance E Project 81 Partial Compilance O D

• Disposition is either " Adopted, " Adopted with coment", " Partial Compliance",

('

"Not Applicable", or "Under Review". If " Partial Compliance" is indicated, attach Fonn NG-1A.

I me Dept quality Assurance f,D. ( @

l Date 9/27/tA r r 998?-

/ /

1 d Approval Action:

Waived O waived i Approved .

Approved j G)k U l L /P /0* I' W Construction Date ~ Design 7 nginTering Date

/

$n O waived D waived I Approved ii 1A U W Urte E

/ ud Approved vuastty esu m nce uw lW vate h

asa.a.

Nuclear Production

^

~ 2- ,.r..... , . _ . . , . . . . _ , , ,

i . s.

l FORM NG-1A REY 0 j i

1 c , 1

• DUKE POWER COMPANY Page 2 of 3 lNuclearGuide 1.147 NUCLEAR SUIDE . Revision 1 l

..___,_m . . _ . . _ . . _ _ . . . , a; - _ . . _ _ . . _ , . .

2 .

Sunnary of Alternatives taken to Regulatory Guide .

Regulatory Guide: Duke Position:

Accepts specific Section XI Duke Power Company will evaluate ASME Code cases and apply specific Code cases as appropriate.

3 Alternatives (Rewrite the affected Regulatory Guide Section below. Continue on additional sheets as necessary. Position statements should directly correspond to the affected Reg Guide section or be a continuation of the Reg Guide format.)

(SEE ATTACHMENT) l 4 l

Justification (Must be sufficiently detailed to permit evaluation by Department heads and NRC)

ASME Code Cases are to clarify the intent of existing requirements or to provide, when the need is urgent, rules for materials or construction not covered by existing Code rules. The licensee has the responsibility to evaluate and determine applicability of specific Code cases as they are formalized to assure quality standards are maintained. Duke Power will continue with the past practice of evaluating Code cases and identifying Code cases actually used in the Inservice inspection Program.

I-9

,-,- ,, - - _ . ..- ~.,- - . ,- _ .,, ,.,--.--e . , - ,.----..,e

DUKE NUCLEAR GUIDE (j

1.147 Rev 1

3. C.1 Section XI ASME Code Cases are accepteble 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" sections of each Individual Code Case.

C.2 Not appilcable C.3 Not applicable D.I Code Cases that are actually used are to be Identified in the Inservice inspection Program pursuant to 10CFR50.55a(a)(2)(II).

D.2

(

Not applicable D.3 Adopted D.4 Not applicable 1

(.

i

. m . .

s. . -

.g U.S. NUCLEAR REGULATORY COMMISSION Rsvision 1 February 1ss2

[ ..

.I /

1 REGULATORY GUIDES OFFICE OF NUCLEAR REGULATORY RESEARCH SRM. DNISION REGULATORY GUIDE 1.147 g,d APR 3 0 GBT- I l

INSERVICE INSPECTION CODE CASE ACCEPTABILITY i

~

ASME SECTION XI DIVISION 1 ,,

A. INTRODUCTION implementation in the inservice inspection of light water-cooled nuclear power plants.

Section 50.55a, " Codes and Standards," of 10 CFR Part 50, " Domestic IJcensing of Production and Utilization R, DISCUSSION Facilities," requires,in part, that each operatinglictase for ,

a boiling or pressurized water. cooled nuclear pewer facility The ASME Boiler and Pressure Vessel Committee pub-and each construction permit for a utilization facility be lishes a document entitled " Code Cases."8 Generally, subject to the conditions in paragraph (g)," Inservice lnspec- the individual Code Cases that make up this document tion Requirements," of 550.55a. Paragraph (s) requires,in explain the intent of Code rules or provide for alternative part, that Casses 1,2, and 3 components and their supports requirements under special circumstances, meet the requinments of Section XI," Rules for laservice Inspection of Nuclear Power Flant Components,"3 of the Most Code Cases are eventually superseded by avision

, Amencan Society of Mechanical Engineers (ASME) Boiler of the Code and then are aanulled by action of the ASME

. and Pressure Vessel Code or equivalent quality standards. Council. In such instances, the intent of the annulled Code ,

Paragraph 50.55a(b), in part, references the latest editions Case becomes part of the revised Code, and therefore

• and addenda in effect of Section XI of the Code and any continued use of the Code Ose intent is sanctioned under supplementary requirements to that section of the Code. the rules of the Code. In other instances, the Code Case is Footnote 6 to $50.55a states thzt the use of spacific Code annulled because it is no longer acceptable or there is no Oses may be authorized by the Commission upon request further requirement for it. A Code Case that was approved

, eursuant to paragraph f' 25a(aX2Xii), which requires that for a particular situation and not for a generic application 1 jroposed alternatives b 4he described requirements or should be used only for the approved situation because portkos thereof provide an acceptable level of quality and annulment of such a Code Case could result in situations safety, that would not meet Code requirements. The ASME considers the use of Code Cases to be optional for the user General Design Criterion 1," Quality Standards and Re- and not a mandatory requirement.

cords " of Appendix A, " General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50 requires, in part, that De Code Cases listed in this guide are limited to those stru:tures, systems, and components important to safety be cases applicable to Section XI of the Code.

designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety function All published Code Cases that are applicable to Section XI to be performed. Where generally recognized codes and of the Code and werein effect on July 15,1981,were reviewed l*

standards are used, Criterion I requires that they be identi- for inclusion in this guide. Code Cases that are not listed fled and evaluated to determine their applicability, adequacy, herein are either not endorsed or wGI require supple-and sufficiency and be supplemented or n,odified as neces- mentary provisions on an individual plant basis to attain aary to ensure a quality productin keeping with the required ondorsement status, safety function.

The endorsement of a Code Case by this guide constitutes his regulatory guide lists those Section XI ASME Code acceptance of its technical position for applications not Cases that are generally acceptable to the NRC staff for precluded by regulatory or other requirements or By the ICopi.s our be obt.ined fs.m the Amerteen S ctety of Mech.mi !

• rs .

Emf'."isot,UaJted Easin.ertas Chaser,345 E 47th Str.et N.w Y k.

x. . u i.iuc. .h f,s. ,i i .

umae aenuuronyouioca gepa; ,,u,,me,ygijgg.,,A,s.-.g,.g. gg.

^"*""*"'""""""***"**

"T. '%#."# Ja.Tl' : 't?!".ll*.!"*J3","O','JI,::

't"a'.'*Jt."'.r."4"*,J,r"4"L*J".ic Mal:','an a #' ','m " " " ' * " * " " ' " " * ' * " * " ' " ' ' " * ' " * " " * * '

! 2'oi' "

.*mW tea;:r'*:,'r#2 fat.'ta"t"2.am'* 2 k P.O ". T M n.-, 1:Fairn',..u

. tif,'hrn"2 4.."'.#.,r,".J.a.'

J. *20. .f,::"1.".cn s., w'.:e rt

!:s. u:.t".* . u. n:o.2..t.r.J.a?."4 774'"w n.

a'.a.n.tf,=";"". ,

{ * '"Ji ggfM'.,M.g"ip;ig,;

,y; g .. .

w . .e.......u .e . e R: t.' *Mra *#aT"sarJ" ,, 'J:Oi";"ap=T, ::".'

n.'j,*.,'a#,,"' 0 n tt ."J.:ng,#, e igagg ;,a.gg,'"J.%'=

.*,**"O... .e.'.it"""."*3.?. ei'JJ'is.ti  ;. in

,a .?:.:. .

E,tJ.g."Wi gg , gig;,.,u,, . . . . nei e =. g ,g, g,, ,, =m,,i,wp

._.v.- ,. _

.g ,

' . a 8 Recalibration of Utrasanic Equip.

recommendations in this or other regulatory guides. Con. N 211 7/13/81 ment Upon Gange of Person tingent endorsement if applicable is indicated in regulatory j Section XI, Division 1 position I for specific cases. However,it is the responsibil.

kyof theusertomake"artainthatnoregulatory.m ' ts ,.

(

ses violated and that there are no conflicts with otherrocam- N-216 3/1008 mended limitations resulting from Code Oss usage. 7/13/81 Alternate Rulesfor Goeure Stud Examination, Sec-Reacer

.- -- - -- - - tion XI, Division I .-

Time Between Utrasonic Calibra-  !

Acceptance or endorsement by the NRC staff applies N-234 1/899 only to those Code Ones or Code Case revisions with the tion Decks,Section XI, Divi- ,

J date of " Council Approval" as shown in the regulatory sion I

- l position of this guide. Earlier or later revisions of a Code N 235 1/899 Utrasonic Calibration Checks per Oss are not adorsed by this guide. New code Ones wSI Lection V,Section XI, Division 1 require evaluation by the NRC staff to determine if they qualify forinclusionintheapprovedlist.Because of the con-tinuing change in the status of Code Cases,it is planned that N-236 1/8F9 Repair and Replacement of Cass MC Vessels,Section XI, Division 1 this guide will require periodic updating to accommodate new Code Cases and any revision of existing Cote Oses.

Code Case N-236is acceptable subject to the following conditions in addition to those conditions specified C. REGULATORY POSITION la the Code Case:

1. De Section XI ASME Code Casess listed below (by a. In paragraph 1.0(a), second sentence the phrase,

~. number, date of Council approval,8 and title) are accept- "while the plant is not in service," refers to a able to the NRC staff for application in the laservice refueling outage.

Inspection of components and their supports for water.

soolsd nuclear power plants. Deir use is acceptable within b. In paragraph 1.0(a), third sentence - the phrase, the limitations stated in the " Inquiry" and " Reply" sec- "the next scheduled plant outage," refers to the tions of each individual Code Case, within the limitations of next scheduled refueling outage. .

nach NRC or other requirements as may exist, and within j the additional limitations recommended by the NRC staff For clarification, Repair and Replacement of Cass MC and given with the individual Code Case in the list. Vessels means Repair and Replacement of Cass MC

( Vessels and Components (systems). Acceptance of Inservice Inspection of Welds on this Code One in no way infers NRC approval to 1551 11/692 violate the technical specification or any NRC require-N-34 11/20/78 Nuclear ComponentsSection XI ments with regard to breach of containment during Utrasonic Examination-Calibra- repair and replacement procedures while the plant is 17051 3/196 N-98 11/2008 tion BlockTolerances,SectionXI in operation.

• Where a numbered Code paragraph is not identified 1731 11/3p5 Basic Olibration Block for Utra.

• by a particular edition of the Code, the Code in effect N 113 11/20/78 sonic Examination of Welds 10 at the time of the ASME meeting (11/3/78) that j

in. to 13 in. Thick,Section XI, Dmsion 1 approved the Code Oss should be governing.

l 1

12/22p3 Examination - Acceptance Stand- N-252 11/19p9 14w Energy Capacitive Discharge I 1738 Welding Method for Temporary N-118 11/2008 ards for Surface Indications in or Permanent Attachments to Cadding,Section XI Components and Supports, Sec-tion 111, Division 1, and XI Code Case 1738 (N-118)is acceptable subject to the following condition in addition to those conditions Code One N-252is acceptable subject to the following condition in addition to thces conditions specified in specified in the Code Case. Replace the last sentence of the " Reply" with the following: he provisions of t's a Code Case: The applicant should indicate in the this Code Case may not be applied for the examina- Safety Analysis Report the application, the material, tion of clad surfaces of noaales, including the inner and the thickness of the material to which the strain sage or thermocouple will be attached by CD welding.

surface of the nozzle.to vesselinsert welds.

8A sum ical Ms. ins of th. Co Cas.s an.em in th. an.e.is.

e... .~

a.. r-2.?:'. AT'cl ** "?n2:N,'s'a'i' int

t. ..: -

r.t.:O.s*a.c#t.ST4;i " Ed m, a**' ** c 3.147-2 t

,. u. . . -e. n . .r . . . - , - __

- ,~

N-278 3/17/30 Alternative Utrasonic QHbratka 1647 8/12p4 Partial Postpmement of Otegory i Block Configuration I-3131 and N-73  !!/2008 B-D 'Fua=I== tion for Cass I p.

T 434J,section XI Division 1 1/1/81 Components,Section XI Code Qas N 2781s acceptable subject to the following 1730 11/305 Acceptance Standards for Oass 2 .

sometions in addition to thoes cometions specified in N-112 7/109 and 3 Components,Section XI, the Code Ose: When a universal caHbration block is Division l' ^ . - -

used and some or an of the reference holes arelarger than the soflecto? holes at comparable depths secour 1804 1/1407 Minimum Section Thickness mended by Article IV,Section V,1980 edition of the N 167 1/14/80 Requirements for Repair of ASME Code, a cosrection factor should be used to Nonales,Section XI,' Division 1 adjust the DAC level to compensate for the larger .

se0ector holes. Ala ,;T the rsactor pressues vessel was N-210 3/2003 Exemption to Hydrostatic Tests previously examined by mains a conventional block, a 3/20/81 After Repairs,Section XI, Divi-estio between the DACcurves obtained from the two sion1 blocks should be noted (for refersace) uth the signif. ,

Isant indication data. Code Qas N-210 was acceptable subject to the follow-  !

Ing condition in addition to those conditions specified N-244 f/25/80 Hydrostatic Test Requirements in the Code Case. Replace paragraph (3) of the " Reply" for Oass 1 and Ossa 2 Compo- with the following: Repairs to piping. pumps, and meats,Section XI, Division 1 valves where the depth of the repaired cavity does not exceed 25 percent of the waH thickness.

,, N 306 105/81 Olibration Block Material Selec-

. tion, Appendix I,13121 Soc. N-211 3/2008- Recalibration dUltrasenicliquip.

tion XI, Division 1 3/20/81 ment Upon Gange of Personnel,Section XI. Division 1

. N-307 1/15/81 Revised Ultrasonic Examination Volume for Cam 1 Bolting, 3. Code Ones that are not on the approved list of this Fuamination Category B G-1, guide (paragraph C.1) or other regulatory guides, or for

! Division I, When the *=amina- which authorization by the Commission has not been tions Are Conducted from the granted, are not acceptable on a generic basis, i -

Qater Drilled Hole .

D. IMPLEMENTATION N-311 5/11/81 Alternate Fuam, nation of Outlet Nozzle on Secondary Side of 7he purpose of this section is to provide information to l

- Steam Generatoss, Sectios XI, applicants regarding the use of this regulatory guide.

, Division 1 l 1. Except for thoes Code Osas that have been annuned Code Case N-311 is acceptable subject to the foBowing by action of the ASME Council,the NRCstaff willauthorize condition in addition to those conditions speciSed in appropslate use of the Code Ososlistedin this guide under the Code Case: The applicant should indicate in the regulatory position 1 upon speci6c request by the applicant safety Analysia Report that the stress analysis of the in accordance with footnote 6 to {50.55a, the Codes and nozzle inside corner region meets the Code Oss Standards rule. Code Oses that are actually used are to be stipulations for the state, of stress la this sesion. IdentiGed in the Inservice laspection Program.

2. Code Oses that were endorsed by the NRCin a psior 2. Code Osas to be applied during an inspection laterval version of this guide and were later annuDed by action of the or Code Osas for a preservice inspection need not be ASME Council should be considered as deleted from the Est changed because a subsequent revision of the Code One is of acceptable Code Cases as of the date of the AS4E CoancB listed as the approved version in this guide.

action that approved the annulinent. Such Code Ones that were annuned on or after November t,1978, are listed 3. Code Qses to be spflied during an 8 y+iaa interval a

below by number, effective dates,s and title. or Code Cases for a preservice inspection . hat were M.L, ;i approved for use need not be changed because the Code 1646 8/12p4 Partial Postpamernant of Otegory Case has been subsequently annuBed.

N 72 11/2008 B CExamination for Qass1 Coar 1/1/81 ponents,Section XI 4. Code Cases on the approved list may be applied to procedures for an inspection interval and procedures for the r{

g e s inservice inspection that were established prior to the effective date of the Code Case within the limits specified taruer dete-dese code case was egd " ter *"

Ashes es nes:

h the M h W apMW re#ms or secommended

\ IpYes#*Yh[ r ins $se*u'*e NdSeSe** ae code case was aseemedITn"e la other regulato y guides.

seassie eau (se seess)was tan dose or mmrmsuse et me code ones.

3.147 3

-- . , - . . .m --

j . ,

APPENDIX

(-

a s.

NuanericalIJsths of Code Cases .

~ ' ". ' -

1551 (N-34) N-235 1705-1 (N-98) N 236l 1731 (N113) N-252 '

• 1738 (N118) N-278 N 211 N-288 N 216 N 306 N-234 N 307 N-311 9

2 LMITED STATES NUCLEAR RSOULATOmv COMMISSM { ]

WASN tN OTON, D. C. 30SSS Posvaes ano Fass Pa:D OPPICIAL SUS 8NSSS u.s. seucksan assukaten v g-coesassessese PENALTY WOR PAIVATE USE.83SO - M k d be

( .

e O

e 1

l l .

y I k G ,

- e- S e e

--- --