ML20236G580

Safety Evaluation Supporting Util 850930,860827 & 1208 Submittals of Second 10-yr Inservice Insp Program Plan & Associated Relief Requests from ASME Code Insp Requirements

ML20236G580
Person / Time
Site:	FitzPatrick
Issue date:	10/27/1987
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20236G576	List: ML20236G572 ML20236G580
References
NUDOCS 8711030103
Download: ML20236G580 (7)

Text

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j NUCLEAR REGULATORY COMMISSION

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SAFETY-EVALUATION BY THE OFFICE OF. NUCLEAR R'EACTOR REGULAT'ON-I ON THE SECOND TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM POWER AUTHORITY OF THE STATE OF NEW YORK-JAMES A. FITZPATRICK NUCLEAR POWER PLANT' DOCKET NO. 50-333' 3

INTRODUCTION-The Technical Specifications.for the James A. FitzPatrick Nuclear Power. Plant-state that the structural integrity of. the components' (including supports).

shall be maintained at the level required by the original-acceptance standards:

throughout the life of the ' facility.

Inservice: examination shall be performed on the American. Society of Mechanical Engineers '(ASME) Boiler and Pressure -

3 Vessel Code Class 1, Class -2, and Class 3 components and supports in accordance with the requirements of the Commission-approved edition ~ of.Section XI of the ASME Code in effect one-year or.less prior; to the start of:the' inspection intervals.

Further, an augmented program'is required for the highly stressed circumferential welds in the main steam and feedwater lines greater than 4-inches in diameter. The program ~shall consist of total. inspection of:

these welds each inspection interval.

The regulations require that inservice examination of components and system pressure test conducted during the second' ten-year inspection! interval shall comply with the requirements of the latest edition and addenda of <the' ASME Code incorporated by reference in 10 CFR 50.55a(b) onithe date twelve month's.

prior to the start of the second ten-year inspection interval. The components (including supports) may meet'the requirements set forth-in" subsequent editions and addenda of the ASME. Code incorporated by reference in 10 CFR.

50.55a subject to the limitations and modifications -listed therein.

Pursuant to 10 CFR 50.55a(g)(5), if the licensee determines that conformance to an examination requirement of Section XI of the ASME Code is not practical' for his facility, information will be submitted to the Commission in support of that determination and a reouest made for relief from~ the ASME' Code requirement. After evaluation of the determination, pursuantLto 10 CFR 50.55(g)(6)(1) the Connission may grant relief and impose alternative requirements as it determines are authorized by. law and will'not endanoer life or property or the common defense and security and are otherwise in~the.public interest, giving due consideration to.the burden upon the licensee that could result if the' requirements were imposed-l s

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2 On September 30,1985, the Power Authority of the State of New York (the licensee) submitted the second ten-year Interval Inservice Inspection (ISI)

Program Plan (Revision 0) for the James A. FitzPatrick Nuclear Power Plant to meet the requirements of the 1980 Edition Winter 1981 Addenda of Section XI of.

the ASME Boiler and Pressure Vessel Code. The staff.and its contractor, Idaho National Engineering Laboratory (INEL), have evaluated the second ten-year ISI Program Plan and additienal information related to requests for relief from certain ASME Code requireunts determined to be impractical to perform during the inspection interval.

EVALUATION The ISI Program Plan was evaluated for (a) compliance with the appropriate l

I edition of the ASME Code, (b) acceptability of examination sample, (c) exclusion criteria, and (d) compliance with the Commission's augmented

(

i inspection programs. The requests for relief from the requirements of Section l

l XI of the ASME Code which were determined to be impractical to perform for the James A. FitzPatrick Nuclear Power Plant were reviewed and evaluated by the staff's contractor, INEL. The INEL Technical Evaluation Report (TER),

EGG-SD-7412, March 1987, including an evaluation of the ISI Program Plan and the relief requests, is attached. The staff has reviewed the TER'and concurs with the evaluations and recommendations except in the case of the reactor vessel, l

examination category B-A welds. The procedure for the examination of these I

welds is under review by the regulatory staff at this time.

1 A summary of the relief request evaluations and determinations made by the staff is provided in Table 1.

CONCLUSION We conclude that relief granted from the examination and testing requirements and alternate methods imposed through this document give reasonable assurance of the piping and component pressure boundary and support structural integrity, that granting relief because of ASME Code requirement impracticality is authorized by law and will not endanger life or property, or the common defense and security, and is otherwise in the public interest considering the burden that could result if the requirements were imposed on the James A.

FitzPatrick Nuclear Power Plant.

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. TECHNICAL EVALUATION REPORT ON'THE.

1 SECOND 10 YEAR' INTERVAL INSERVICEEINSPECTION1 PROGRAM PLAN:"

ll NEW YORK POWER AUTHORITY,t

-JAMES A. FITZPATRICK NUCLEAR. POWER PLANT..

DOCKET NUMBER.50-333

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- Published March 1987

-q Idaho National Engineering Laboratory.

EG&G Idaho, In'c.

Idaho Falls, Idaho 83415

.i Prepared fori U.S.- Nuclear Regulatory Comission -

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' Washington,'D.C. 20555 under-DOE Contract No. DE-AC07-761001570-FIN No. D6022 (Project;5).

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ThisLreport presents'the results;of) the. evaluationLof, th'e James A'. FitzPatrick Nuclear Power;PlantiSecond 10-Year Iriterval LInservices

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-Inspection'(ISI) Program Plan,throughLRevisionLO,.: submitted 1

!j September -30, fl985, including the requests for relief from' the; ASME Code.

Section_XI requirementsLwhich th'e Licensee has' determined to b'-

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2

. impractical; 1The James A. FitzPatribk Nuclear: Power Plant Second 10aYear1 t Interval ISI Program Plan is evaluated in'Section:2..of this' report.

The.ISI" Program P1an is evaluated for-(a), compliance.withithe appropriate editionfof

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4 Section XI, (b) acceptability of examination ; sample,i(c) exclusion ~ criteria,_

and (d) compliance'with ISI-related commitments'identifled:during the'NRC's-previous PSI.and'ISI reviews. -The requests for relief from the-ASME. Code requirements which the Licensee has_ determined to be1 impractical forf the-second 10-year inspection interval are evaluated in Section 3.of this report.

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This work was funded'under:

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U.S. Nuclear l Regulatory Commissions FIN:-No. D6022 7 Project'.5~

Operating Reactor Licensing. Issues Program,-.

' Review'of ISI for'ASMELCode Classi,t2,:and 3 Components:..

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SUMMARY

d The Licensee,' New York Power Authority, has preparedithe; d

James ~'A. FitzPatrick Nuclear Power Plant'Second~10-YearJInterval Inservice j

Inspection (ISI) Program Plan, Revision 0,.;to meet the? requirements'of,the:

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.1980 Edition, Winter 1981AddendaT(80W81)'of:theASMECodelSectionXI..(The:

second.inspectionintervalbeganJuly[28,l1985;and?endsLJuly'28,fl9956 j

. The information in:the James A'. FitzPatrick Nuclear Power PlantLSecond:

4 10-Year.' Interval.ISI. Program P1an', through' Revision:0,1 submitted September 30, 1985, was reviewed,:: including theLrequests for relief.from-thel ASME Code-Section XI requirements.which.the'Licenseelhas? etermined to be.

41 d

m impractical.

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Based on the review of the James A. FitzPatrick Nuclear Power PlantiSecond i

a 10-YearInterval-InserviceInspectionProgram' Plan, Revision 0,/thei Licensee's response to the NRC's Request for Additional.Information, andithe' recommendations for the' granting of relief from the ISI examination requirements that have been determined to'be impra'ctical,Jit has'beenc

/

concluded that the James 'A. FitzPatrick Nuclear Power'Pl' nt Second1IO-Year-a

~ Interval Inservice Inspection Program Plan, Revision'0,;with the e'xception a

of Requests for Relief Nos. ' R5A,. R7,' a'nd RIO;;is? acceptable and Lin-1 compliance with 10 CFR 50.55a(g)(4).

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1 '. ; INTRODUCTION..............................................f.<.........

71G M o.

p.

Ln 2.

EVALUATION OF INSERVICE INSPECTIONLPROGRAM PLAN...s..-...'....:.;<.......

3:-

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. 2 2Ll ~ Documents - Eval uated........-.... _..... ~....

4'

...31 f<d

2. 2. Compl i ance wi th Code Requi rements... c.............. J.i.d.1........ 3-V @6 c

+

s e

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' 2. 2.1 Compl i ance with ! Appl icabl e: Code L Editions ;..........'.... <...f... 3 /..

g 1

4' g' "!

3 2.2.2 ' Acceptability.of:the Examination Sample.................. 4 44 u.

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2. 2. 3 Excl u s i on Cri te ri a........ 1..........,......................... ) 4; y

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2.2.4 Augmented Examination Commitments.=............................:. '. 4 j i[

w a

(

f i

q 2.3 C o n c l u s i o n s.,.........................................'.............. '. 5 -

,j a;

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- - s 3.

EVALUATION OF RELI EF REQUESTS........................./... '..:.~. le.'.~...... 6 n-

>1

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+

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3.1 C l a s s 1 C omp o n e n t s.................................... i. -...........,. 6 L i

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3.1.1 Reactor:PressureVessel................h.a..........'...r.....6; s

'3.1.1.1 Request for Relief No. R13,< Examination Categorf1BJ,)

A d

Item 181.11-(circumferential^shell? weld), Pressure-Retaining Welds 11n.the Reactor; Pressure? Vessel',i........... 6; i

c

,o I

g jg

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3.1.1.2 Request for. Relief NoL R14, Examination;Catsgory B-A; 1

ItemsBl.21'(circumferential[ head-weldshndtB1;22 (meridional head welds), Pressure Retaining Welds inithe.

j Reactor Pressure Vessel.........;...... W.................8 i

gc e

3.1.1.3 Request for Relief No; R6, Examination Categ'ory B.0,1 Wy v

Item B14.10, Pressure Retainin 7k Housings.............-.........g Welds in Control 1 Rod i

5 gl'

........................... 4 9 F j

4 E

3.1.2 Pressurizer (Does not. apply to'BWRs) y 3.1.3 Heat Exchangers~and Steam Generators (No relief / requests) 3.1.4. Piping (Pres'sureBo'undari.........'...:............................

11i

' 'l

~

-3.1.4.1 ' Request for Relief'No'. R2, Examination 1 Category B4,;

1 L,

Pressure Retaining Weldsfin Class T Piping....'.............;11!

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3.1.4.2. ; Request for Relief' No. R4,. Examination Category-B-@

1

, Items B9.11 and 89.21, Pressure; Retaining: Welds. int

i C1 ass 1-Piping.......'.~....

............................... 12L

.j 1

3.1.4.3 Requestafor. Relief No. R9,: Examination Category B-K-1,.

7" r

- Item B10.10, Integral ' Attachments for; Piping......-.......v.

14 s

3.1.5 Pump Pressure Boundary........................................

17

(

3 3.1.5.1. Request for Relief No. R5B' Examination Category B-L-2' Pump Casings..................................'....'....,...

17-H 3.1.5.2 Request for Relief No.iR7L Examination Category B-Gal j Items:B6.180, B6.'190, and B6.200, Pressure: Retaining:

W

.j Bolting, Greater than 2 -inches l in Diameter........ i...... 419 -

i 3.1.6 Val ve Pressure Bounda ry........ }.............................. 21 q

3'.1. 6.1 Requ'est for Relief No. R5C,. Examination Cate Valve' Bodies................................ gory B-M-2;

=j

.............. 21-3.1.7 Genera1...................................................... 423-i 1

3.1.7.1 Request for Relief No. RSA, Examination Category.B_-G-2,

_~ j U

d Items B7.10, B7.50,1B7.60, B7.70,..and 87.80,; Pressure' Retaining Bolting, 2 inches and Lessiin Diameter........r. 23 1

3.2 C l a s s 2 Compo n e n t s................................................ 2 5 fi I

i-3.21. P re s s u r e Ve s s e l s........................................ -.....

t..

3.2.1.1 Request for Relief No.. R15;t Examination Category C-A,.

o

-Item C1.30 (tubesheet-to-shell weld), Pressure Retaining Wel ds i n Pres s u re Ves s el s........<......................... 2 5

3. 2. 7. Piping...............................................'...........

27 3.2.2.1 Request for Relief No. R1, Examination CategoryLC-F,

,j Pressure Retaining Welds'in C1 ass.2.Pi ECC, and CHR. Systems................... ping oftRHR,- -

....27i

~i y'

U n

3.2,2.2 Request for Relief No. R3, Examination Category C-F, 1

Pressure Retaining-Welds in Class _2 P Sy s t ems....................... '....... i p i n g ' o f= n o n ' EC C '

1 g

..................... 29.

3.2.3 Pumps (No r'elief. requests)

L 3.2.4 Valves-(No relief requests) 1 e

o 3.2.5 General (No relief requests)-

j 1

3.3 Class 3'~ Components -(No relief requests).

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3 '. 41 P. r e s s u re Te s t s. :............ >.. ;..,.. '......... '... a...'...

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d.

4 43.4.l.ClassD1:Systemf@essureTests4No/ relief < requests)l g.IJ 1a.9.d c

13.4!2/'Classi2iSystemPressure? Tests.L(NoreliefJrequests);n.

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3.4.3 Class 13 System PressurMTe,s's-t s.. -.......'...... 3.......;.....~.,..r..31

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l 3.4'.3.1 !Reque.st'for Relief No. R12 MSystem' Hydrostatic Test 4off' [.

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!:c iC1 ass:3 Cooling WaterfSystems....;.......'..'.......n....;. 31 y}

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3.4'.4 Generalf('Noirslieffrekuests):

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'3 k 5.1! ' Ul thasonic~ Exasinatien 1Techriique's. hs..... v........ I.....'....W34

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u No. R11',;;.NRC-Required!IGSCC.

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....,.. /,,...,

3.5.1.1l Request forLRe1ief..

ay Examinations ^in' Stainless 15t. eel. Piping 2Sy' stems'. ;.... c.. 4 34?

l d

4

3. 5. 2 ' Exemp ted ' Componen t s s....... e. :.........'.......... '...............' 3 7J

.j 3.5.2.1. Request for Relief lNoER30D ExemptionslfarfC1 ass 13l m,.

L P i p i n g.................... '........ '.......... ;. :. l. '.......... ! 3 7 :

x, l

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3. 5. 3 : 0 t h e r..........' '........................ ;.. -....... r............. 3 9

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3.5.3.1 Request for.-Relief No 'R8,f Examination Category AC,'

~

L Component Standardf Supports (All ClassL1,< 2, and 3L d

Snubbers)..................n

...............is.. 39-1 3.5.3.2 RequestT for Relief No. ' RIS, VTJ4. Examinat a

Componert Supports....c................._ ion ofu.'. '...........

l?

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4. ' CONCLUSION.................................................'.

......;. 43;

>g E

5.

REFERENCES............................................m a

.. -......... s.. 4 5 -

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1 t X,.

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1

.. TECHNICAL EVALUATION REPORT,ON THE'..

l SECOND 10-YEAR > INTERVAL INSERVICE-INSPECTION! PROGRAM PLAN:.

1 l

'NEW' YORK. POWER AUTHORITY,n -

1AMES A. FITZPATRICK NUCLEAR POWER. PLANT,-

DOCKET NUMBER'50-333 j

e j s

l'." INTRODUCTION O

?

Throughout-the service life of a.watericooled ' nuclear power facility -

~

10 CFR~ 50.55a(g)(4) '(Reference 1) requires that components -(including;

]

supports)whichareicla'ssifiedasfAmericanSociety'ofLMechanicalEngineers 4

-(ASME). Boiler and Pressure Ve'ssel Code Class 1, Class,2, Land ClassL3. meeti therequirements,except:the<designJand.. access'.provisionsandthepreservicel l,

examinationrequirements,'setiforthiniASMECode;SectionXI,L"Rulebfor-d Inservice Inspection of Nuclea' ri ower;PlaritLComponents," (Referencei2) Lto.

P the extent practical..within.the liniitationstof design,; geometry l,fand; j

~

l materials of construction'n of the components. Th'is section of thet d

~

regulations also requires that inservice examinationsLof components ~ and '

L syster. pressure tests conducted during the second:120-month inspection interval shall comply' with the requirements in:the.. latest edition and '

q addenda of the Code incorporated by referencein'10 CFR 50.55a(b) on the

.i date 12 months prior to the start of'the.second 120-month: inspection-interval,. subject to the limit'ations and modif.ications listed therein.: The -

.j i

components (including' supports) n'ay.~ meet requirements:setiforthlin subsequent editions and addenda of this Code which a~re; incorporated by:

reference in 10 CFR 50.55a(b) subject to.the limitations and modifications listed therein.

The Licensee, New York Power Authority,'has. prepared the-0 James A. FitzPatrick Second 10-Year. Interval Inservice Inspection-(ISI).

Program Plan, Revision 0, to meet l the requirementsiof the 1980 Edition,-

)

~

Winter 1981 Addenda ~(80W81)'of the ASME-Code Section XI. VThe second 1

inspection interval began July 28, 1985' and ends July-28, 1995.

l As required by 10 CFR 50.55a(g)(5), if the licensee determines that 'certaini

~

Code examination requirements are'. impractical and. requests < relief from them,"

the licensee shall' submit information and justifications:to the Nubleari j

~

L'

. Regulatory Commission (NRC) to support that ' determination. -

t l

\\

.' Pursuant t'o 10 CFR 50-55a(g)(6), the NRC will evaluate thel licensee's;

1' q

m

+

x

c J

/

,\\ i Q8 i

' +

determinations under 101CFR 50.55a(g)(5) that; Code, requirements are-1 Impractical.

The staff 'may grant'. relief fand may(impose ' alternative' 1

requirementsasit.determinesare.authorizedby;1awLandNil.1notjendanger 111fe.~or property.or the common ~ defense and security?and are'otherwise;i.n"theb j

,2 public interest giving due consideration to the' burden u'pon'the licensee' 4

that could' result if the requirements were[ imposed on"the fadility;;

Theinformation'intheJamesA.FitzPAkrickNucleapPoWerPlant)Second 10-YearIntervalLISI'ProgramPlan,throughLRevisionIO,.submittsd5 h

~ September 30,11985 (Reference'3) h~as.been reviewed; "This-revies was?

7

-performed using the' Standard. Review Plans-of NUREG-0800((Reference 14),1

-1j Section :5.2.4, " Reactor. Coolant' Boundary. Inservice Inspections"and; Testing,""

and Section 6.6, '" Inservice Inspection;of ClassL2 and:3 Components".

.In a' letter: dated June 9, 1986 (Reference 5),Hthe?NRC requestadIthe' additional information that was required in;or' der.to~ complete the revi.ew' of?

1 the ISI Program Plan.

The requested information was provided by the?

q Licensee 'in a letter dated August '27,1986:(Reference 6). ~ Included Jin this response were.. I'6 requests for relief. from ths' ASME Code. Section-XI-requirements which the Licensee has determined to be impractical._- As'.a l

result of telephone' conversations with the Li.censee on October 23,;29, andi y

1 31, 1986, most of the relief requests were revised and re-submitted by the Licensee on December 8, 1986 (Reference _7).

l The James A. FitzPatrick Nuclear Power Plant;Second 10-Year. Interval ISI:

<1 i

Program Plan, Revision 0, is evaluated in Section 2-of this report. >The ISI Program Plan is evaluated for (a) compliance with;.the appropriate: edition' oft Section XI, (b) acceptability of examination. sample',:(c) exclu'sion criteria,J

.i and (d) compliance with ISI-related commitme.nts. identified during the NRC's previous PSI and ISI. reviews.

The. requests for relief. are evaluated in Section 3 of. this report.

Unless-

'otherwisestated,referencesto.theCoderefertotheASMECodeFSectionXI,,

j 1980. Edition including Addenda through Winter-1981.- Specific ^ inservice' t'est

,1 (IST) programs for. pumps and valves are being evaluated in'.other' reports.

J A

2

~

'l

+ _ _ _ _ _ _ _ _ _ _ _. - - = -

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2.-EVALUATION 0FINSERVICE.INSPECTIONPROG'RAMPLAN) 4 m

, :q t This evaluation consisted. of'a review 'of therapplicable program' documents.fto t

determineLwhether or.not1they.arenin compliance With}the CodeLrequirements #

~

g and any, license conditionsLpertinentito ISI' activities.

This:sectionM N

.o i describes the submittals reviewed-and the;results:ofJthe reviewi L2.1 Documents Evaluated:

LReview has'been completed.on the.following'information:

+

y,

.(a) James A. F.itzPatrick!.Second110-Year 1 Interval (ISIS Program <P1an, '

1 Revision,0; submitted; September 30f'1985; x

sj w

q (b)

Licensee's' " Response':to NRC's1 Request fori dditionalllInformation"-

A 1

submitted August 27, 1986;.

(c)

Licensee's submittal of revised relief requests dated:-

~

December 8, 1986.-

1 1

(d)

Licensee's " James A. FitzPatrick Nuclear: Power.Pl. ant lIntergranula'r.

~

Stress Corrosion Cracking Inspection Pl'an for theLReload 7/ Cycle 8.

RefuelOutage,"'submittedOctober'28,;1986((Referen.ce::8)..

j (e)

Licensee's " James A. FitzPatrick(Nuclear Power Plant'Intergranular Stress Corrosion Cracking Weld Inspection Program F submitted; February 5, 1987.(Reference 9).

4 2.2 Comoliance with Code Requirements 6

3 2.2.1 Comoliance with Aeolicable Code Editions-

' The: Inservice Inspection' Program Plan shall1be based ~on the Code editions.

'h defined in 10 CFR'50.55a(b).

Based on the starting 'date.of July"28,1985) 1 for the second 10-year inspection interval,fthe, code; applicable totthe'

~

second 10-year. inspection interval ISI program is the 1980 Edition with?

3

+

I

.1 9

d m

, 1 m

~

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E o

m Addenda through Winter 1981.

As stated in Section=1cof this report,:the:

Licensee has written the James A FitzPatrick Second?lo! ear Interval [ISIL l]q Y

. Program. Plan,f Revision 0, to meet the requirements of:the 1980 Edition,,

.j Winter 1981 Addenda of the Code.

h

.4 The extent.of examination for Code Class ~ 1and Class;2 piping welds has' been determined by the':1974 Edition:through. Summer-1975 Addendaf(74S75).1 9

Although this is: required by 10 CFR 50.55a(b)(2)(iv)(A) and allowed by1 L

10.CFR 50.'55a(b)(2)(ii) rand 10 CFRL50.55a(b)(2)(iv)(B) ::th'e Licensee has a

included the use of 74S75 fin Req ~uests forl Relief' R1, R2; La'nd.R3.'

2.2.2 ' Acceptability of the'Examina' tion'Samole.

1

-Inservice'. volumetric, surface, and visiaallexaminatioris Lshall::be' performed 1

on ASME Code Class 1, 2, ;and;3 components and their s'uppoets' u' sing y

y samplingfschedules described in Section'XI!of the ASME Code"and>

.H 10CFR50.55a(b)'.

Sample; size and: weld selection h' ave'been implementediinL accordance with.the Code and appear to be correct.

q q

2.2.3 Exclusion Criteria i

.,d The criteria used to exclude components from examination shall.be 1

consistent with Paragraphs IWB-1220, IWC-1220, IWC-1230,.IWD-1220,-and 10CFR50.55a(b).~Theexclusioncriteria;h' ave ~beenapplied-byLthe-3 Licensee in accordance with the Code as discussedEin Section l.'3.1'and j

Table B-1 of the.ISI Program Plan 'and appe~ar.to be correc.t.

2.2.4 Auamented Examination Commitments a

e 3

The.followingaugmentedexaminationswillLbe' implemented)duringfthe!second' 10-year. inspection interval:'

-(a)

Intergranular Stress Corrosion Cracking!(IGSCC)

An; augmented

~

ultrasonic examination of stainless-steel _ piping weldscwhichiare; i

considered susceptible to IGSCC will be'_ performed as required _ in:

NUREG-0313, " Technical-Report'on: Material Selecti_onL and Processing j

y Il 4

.=

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MW T%-

b.q ;.,

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a-g GuidslinesiforjBWR Coolant?PressureL oundarkPiping'P...

.s..

B

~

7 L(Reference :10).z The systemsisubj.ect : to. these ! examinati.on's i ncl ude 1 oj

. e the iReactor Recircul ation lSystemf(#'02),j Cobh Spray )(#14)h Readtoe

, E

Water,Cleanupi(#12)', portions'of.thelRHRE(#10)LSystempandfotherl

1. y x y

. c.

s

~

.systemsasin'otedlinfsection3.5.1.liof?thisfreport.;

w 4

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-(b) liigh Energy Line's] Penetrating Containment-:; Augmen_te' d exa'minationsi.

3.

willibeperformedonfh_ighenergy: piping 1 systems?whichpenetrate contAinmentLfor which th'e~ effecis ?offpostilit6djipeibreaksL wouldh 1

, 3 3-be; unacceptable.-

~

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,.;.f s..

j 1

(c) ' Scram' Discharge' Volume Pipjng s The weldsiindtheLScram Dischargei,

d e

c,

. Volume piping will'be[examinedlin accordance withithe; requirement'sj

<Wi

of Sdctibn XI and:th'e:recommeridAtions ofiNUREG O803, c"Generici

%q i

m Safety. Evaluation Report Rigarding Integrity Off BWR:ScramlSjstem(

E Piping"i(Referenceill).

/

1 2.3 Conclusions

^

1 f

Based on the review of the documentsflisted.above, itLis concluded thAtlthe" '

James.A.'FitzPatrick Second 10-Year? Interval.TInservice In'pection: Program; s

y i

Plan,. Revision 0, is acceptable!and in;complianc'e withi10iCFR 50.55a'(d)(4)j'

[

Therequestsforlrelieffrom~theLASMECode"requirementswhichltheLicenseel.

55 hes determined to be impractical areIevaluated in'the[folloWingLsect' ions N

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EVALUATION DE RELIEF REQUESTS '

J U

0

.1

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Therequestsforrelief, submitted! December 8,1986dfromltheASMECode V

a

.~

i J

c requirementsiwhichjthe ' Licensee'has 'determi_ned tolbedimpracticallfor thej l

~

y

'se'cond 10-yearlin'spection' interval"are.. eval uated nin L thel following s sections n -

D y

7 a

3.1 Class'1 Comoonents' N

3.1.1 Reactor-PressureiVessel"(RPV Q g.

t 3.111.1 Reauest for' Relief No. R13. ' Examin'ation Ca'teao'rvDB-A~ Item l

B1.11. Pressure'Retaihina Welds"in ths1 RsactSr b essupelVessel5 h

%)

Code Requirement: 'Seckion?XI;? Tab 1EIWBi2500,-1,JExamidation d

Category 8-A',l Items.81.11L(circumferentialsshellweld)iand!

Bl.12. (longitudinal 1 'shell' welds) Jeach f requires l a 100%)

volumetric examin'ation;~asidefined by'FigureLIWB-2500'1, of the^

sR length of one beltline region:weldi; fl Licensee's Code Relief Reaue"sti. LRelief istrequest'ed ffromL examining 100% of,the Code-required volume oni.theelengthofionei beltline region circumferentialtweldt andfon theilength of oneS beltline-region longitudinal' weld.

y 1

Licensee's'ProposedAlternativeExamination:i;The(i.icenseet j

proposes, as an alternative to.'theLCodeirequireme't,ithat!a' l

n composite.of.the longitudinal welds in;the beltline. region?be

. examined so that' the total length examined:wi,ll be'equinient0 0

to the length.of one. beltline region tiongitudin'aliweldr(150.

j inches).-

c',

The Licensee states that the circumferential weld!(Weld:

No. VC-3-4) in the beltline region willibeJexam'ned to theT i

a maximum. extent possible? (weld length off180(inches!orL25%)'.

1 Additionally, whenever possible, 1ong'itu'dinalLwel'dLlengthsTint the beltline region will'be substituted to meetithe requiredi -

.t 6'

. 4,7 ;

3; N

7

._____E-..-_-J

. - - - - - ~ -

N,x x %,;;W Y

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~

1Angth'.:LTheLice'nseeDestimates?thationly400linches,of;

~

longitudinal weld'lengthiin.the beltline regionLisLavai.lablei, d

.for.1nspectioni.

\\

'\\

Licensee's Basis for Reauestino Reljlf: dThe. de'signLofftheE

~

}

1 N

m ReactorPressureVesselpresents:ob'tructionsL(sacrifihialf

^

d s

shield wall and thelpermanentrinsulationisystem)Ttstlwillf noti 0

allowf100% of thb required volumeif one beltline regionfweld){

Lfor:ItemNumtiersBlillLand'Bl.12ito{beexaminhLLCompliance; d

q with the' code ~ requirements'of one"circumfsrentialibeltline1 b

' region-weld and onellongitudinal beltlin' iregion weldlisin'oti L

~

e feasible.-

Evaluation:

The Licensee's submittal:ha'stbeenirev'iewed,H including the drawing referenced in the request $farLrelief.~

' ' g'l q

Based.on the RPV-design, van ' acceptable percentagelof thel

.: y s.

"E Code-requiredexaminationwillbefperformediontheione j

circumferential beltline ~' region ~ weld when longitudinalLweldL d

lengths in the beltline region 1arelsubstituted for the-e 1

remainder.

Performance of volumetric.exaniinations of 'a.

composite weld length of longitudinal beltline region welds l that.will equal-~one longitu'dinal biltline regionfweld length is acceptable.

The RPV would:h'aveltobe redesigned and prefabricated in order to complete..the.volumetbic examinations.

as required by the Code.

==

Conclusions:==

Based on the above: evaluation, itJis concluded.

d

(

that the proposed,alternativeLexaminationsLprovide an1 acceptable level of: inservice:stru'ctural. integrity and that compliance with the. specific requirementsiof Section XI wouldt result in. hardsh' ip or u' usual difficulties withoutJa-<

n j

compensating" increase.in the-1evel'of qualityTandfsafety.

j Therefore, it:is recommended that'. relief be' granted as; q

requested.-

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.. a y$

'3.1.1 2: Reauest' for: Relief No. R14; Examination'Cateaorv B-A. Items' -

a Bli21 and Bl.22. Pressure ~Retainina-Welds in the Reactor-O Pressure $ssel 3

o

. c +w

Code Requirement: JSection 'XI,iTable:IWB-2500-1,nExamikat' ion l l

M li..

Category Bi Items'Bl.21['(circumferential?headwelds);an'dt B1.22- (meridional' head welds)feach requirestac100%)vblumstrick g

examination,.'as!definedbyFigure"IWB22500-3,nofLthi?lengthtof)

R one' weld.

m Licensee's' Code'Relisf Reauesti 'RelieflisLrequestedifrom:

j

-2 examining'100% of:the Code-requiredivolume"onsthellength.off ohe.

~

circumferentialjhead' weld?and!onthE11engthif orie)meNdibnali head weld.

1 1

Licensee's Prooosed Alternative' Examination

{Theilicensee' proposes to, exam'ine a; composit' : weld length;of circumferentiali e

head welds and.a composite weld Llength.of meridiona1L head weldsi where'accessallows'tomeetitheCode'requi$mentsof/the::

inspection of one circumferential head'.weldf(317 inchis)Lan'd one meridional head' weld'(69Linches)..

w' Licensee's~ Basis for Recuestino' Relief: "The: design.of th.e

.a Re' actor Pressure Vessel presents obstructions (ves'sel. skirt ands numerous interferences'from the contro1Erod drive!andi instrument penetrations) that will;notia110w: 100%:of the:

required volume t'o be' examined.

Evaluation:. The Licensee's submittal.has:been. reviewed,

. including the referenced interference drawings.. Based on the

~

RPV design, the performance of volumetric examinations ofia.

composit'e weld!1ength:of circumferential? head we ds;that will equal one circumferential head weldJ1engtf(31711nches)landjthe-performance of volumetric examinationslofla composite weld' length of meridional head welds that: wil12 equal. one meridi' nal-o head weld length (69 1.nchss) are~' acceptable alternativesLto:the; 8

s q

___'______'_1 6

t

'ei N

t-

tr a:

]u l/

gy x

w. ;,

+

.+

/

f.

I g

g r

j S -

~ CodeLrequirements', - The 'RPV 'would;havef to be ;Eedesigned :and.1 refabricatsd in; order to complete 7the vblumetricJexaminations L ' >

asirequired=by~th'e'-Codet p

==

Conclusions:==

~ Based on theiabove evaluat n,fitisconcluded

' Lthat1the'proposedJalterna'tiveexaminations; provide.anL' j

j

acceptableilevelJof Linservice structural (ihtegrity anhth'at-

]

Leompli.ance 'with the specific r$quirementsLof1SeftibnMotil'd!

^

Lresult in hardship?or? unusual difficulties' wit'houtlai M

compensatingiincrease in.ithezlevel-ofiqualityLandl safety.

l Therefore, fit 1.srecommendedthaireliefbe'.grantedas:

requesi.ed. -

y x-3.1.1.3 'Recuest for' Relief No. R6. Examination CateoorviB-O'. Item 1:-

0 B14.10: Pressure Retainina: Welds in Control Rod'N)usines Li 2

a Code' Requirement:

SectIon;XI, Examination (CitegorylB-0,1Itemi

~

B14.10- requires a:.100% volumetric or surface'.e'x' amination ~ ofl10%)

i T

of 'eripheral' control. rod drive'(CRD) housings'.:

/

p

- Licensee's Code Relief Reouest: iRelief 'is f reqtiest'ed from.:

M examining l100% of the welds. in)10%;of(the-pe'riphera1 CRD) 1 q

housings.

f Licensee's Prooosed Alternative Examination: 'A'pa'rtiAU examination will; be performed on an'. estimate (24[to 32 of?the-.

p j

upper housing--welds which.are accessible threughL.the vessel lq skirt. personnel.ac' cess openings..The Licensee will attempt.tol inspect the. accessible l upp.etc.RDMusingLweldsiso that(tke?

s a

total weld length inspected willLequal the: Weld lengthL of[10%

1 of the peripheral. CRD' housings.

In addition, a visual. examination;(VT-2)?on1100% of;the.weldst in.the CRD housings will befperformedLduring'the hydrostatic?

a examination at"theLend of the inspect' ion-intervaliinDaccordance' with IWA-5000 and-IWB-5000 and.the requirements of Examination l-

-. Category B-P of S'ection XI. of 'the Code.

i.

1 t

.9 e,

E_______iii

_m_.______i_-----J--

w

?ib.

1y'

?

a 3"

4

- 4 g

.b f

,y q.

x

.g 3,

m,

z,

V,.

=

L m

Licensee's Basisifor-Reauestina' Relief:,JThe Licensee; states.,

9' "1

Lthata'm'ajority;ofithefCRDLho_usingper.ipherarwelds;and'th'ei

. stub tubelto-flange welds.are inaccessible duelto structural; interferencesTand cannot be: surface'or volumetrically!examinedd >

1, ai

.n)

" Evaluation:L The Licensee's submittil hasieenireviewedh

$j

.i includingthereferenced?plhotograph'sLand[ interference:

J 1

drawings.1 LThese:ph$tograph's.anddrawingsOhowIthat%heloN1y]

accessibleareasare;thEoughithelvesse1<skirtmanwaysatt:

~

H 4

locations 0,L90,1180,and270; degrees.JItfisshownth'atial partiallexamination;can[bilpeEformed o$lonly 6Lto18' welds"at + l i

-each opening.

Thisiwouldibe!a Ltotahnuder ofl243oL32l 1

~

lpartialcexaminationst-Bas'edson?the'RPVdesigndsurface"orf volumetric examinationlofLt'he7 accessible upper [CRD30using?,

v1

.c.

welds so that t'he total weldLlength inspected equals.thet weld?

7

~

length of 10% of the peripherals CRD:hou'singsdalong}with the:

4 visua11examinationperformed(during'thehydrostatic--

examination, is' an -a'cceptable alt'ernativelto'the/Codel requirement. ~The RPV would have to bejrsdesigned and prefabricated in' order to complete.theisurfai:e or. volumetric l examinations as required by the Code, t

==

Conclusions:==

Based on the' above" evaluation, lit is l concluded 1 i

that the proposed alternative examination provides an:

N acceptable level of inservice structural. integritygand that; compliance with the ~ specific requirements 'of Section XI would result in hardship 'or; unusual! difficulties without a compensating increase in the11evel;of qualityf add?safetyt 0

1 Therefore, it is recommended thattrelief'be granted *as requesi.ed.

3.1.2 Pressurizer.(Does not. apply to BWRs) 3.1.3 Heat Exchanaers and Steam Generators.(No relief. requests) 10 oy d

m L

n:

e, y

EeN lM 4 ' jy' s.

y c

.n r

1 t.

,w.

du -

tM

?

j.,

g;

M y

i o

a p1 3.1;4 LPioina Pressure Boundarv.-

t

,a

?!

3.1.4.1 Reaue'st for Relief;No. R2. Examination.Cateaory B-J. Pressure m

Retainina Welds'in Classt1 Pidino

,l j;

,, m

'\\N fs, Code-Requirement: SectionLXInTable11WB-2500.-1MExaminatibnf

/' _

Category B-JLNotef(1) states l that = examinations'shall' inc10def N

's the'lfollowing: l(a)J11fterminaliends)ikeabhlpipe'orl branch}'

1 A

unconnected)tojessels;L(b)TA11,0terminalendsLandjjointsTini a

~

~

each pipe or branchLrun connectedito.otherl components where::the?

tressilevels exceed the(follonng lisits?under loads?

u' s

ass'ociated:with$specificiseismicevent'Landoperationk1>

Y

~o s

conditions:- '(1)' primary.piussecondarystressLintensitylrangej M

. of:2.4 S for'ferriticisteeliand-au'tentticsteel,- '

,)

m s

.(2) cumulative; usage fastor, U,iofLO;4;/(c); A11fdissimilar; '

- metal;weldsbetweencombinations)of::-(l')'cadonforlowalloy t l h

~

s ee s to' igh ' alloy steels, -(2); carbon 1or low allsyLsteels?to; highnickelalloys',-(3))high' alloy;steelstohigh.nickell alloys; and-(d)ddditional piping' welds so Ihat the total i

i1

. number of circumferentia1L butt weldi(or branch connectionior s

socket welds) selected for examinat' ion equalsJ25% of thef '

d circumferential' butt welds:(brl branch connectionLorisocket)

~

welds) in the reactor coolant piping system.

Thi'/toulidoe's?

"i s

not include welds excluded by IWB-1220[These additional welds-may be located in?onelloop.-(one'looptisTcurrently defined forg BWR plants in the 1980 Edition).

Lh Licensee's Code--Relief Reauest: 'Reliefis/requestedfromthel R

requirements of Tab 1'e IWB-2500-l', Examination Category B-J,:

E Note (1);ofSecti_on_XILfor' Class:11pipingwelds.

j a

[l License,e's Pronosed Alternative Examination:s:The Licensee::

proposes to use the ' requirements of Table 1IWB-2500 Land (Table,

~

IWB-2600,l Category.B-J,LofiSectionXIof;thelASME-Code;in'the; 1974 Edition through the: Summer 1975" Addend'a to determine the:

[

extentofexaminationofp'ressure-retainingwelds111ASME; Code-d 11"

~,

-(

m I

)

i e

y g

j a

( _.

~

w y

o li"

+

• :; Y t

)U i

N,;

w s

-b N

(

b 4

' Class:1 piping.

e w

r Licensee's Basis' for Reauestin'a ReliAf;l?The' Licensee 1 states y

1 that the' determination of the extent of'examinationLofj l

n N

1 o

-pr' essure-retainingiwelds;finASMECode[Classf1 piping (bylth(

requirements. of Tab 1'e IWB-2500 'and TableiIWB-2600. Category B-(

/ q of'Section XI'of the ASME Code in' thel 1974TEdition,; Summer'1975i ; '

~

~

Addenda (is'allowedbyfl0CFR50!55a('b)(2)(ii).

b

~

o q

. v g

' Evaluation;. 10'CFR 50.55a(b)(2)(ii)istates:' "Iffthei

'm

\\[

facility's application'for"a? construction / permit'was docke'ted

~

prior to. July'1,g19781 thelextentLof exaniinationlforJC6de:

C1 ass.1 pipe weldsL mayL be -determined /by Lt'h'e? requirements: of;

.4 Table: IWB-2500 andLTOle: 'WB d600FCateforyjB Jlof Sebtio'niXI N.'

I k

theASME'Codelin,the1974:Editioniandiaddendathroug(the d

Summer 1975 Addendator otherfrequirements tk Commission'may' j

adopt."'Sincethe! application!forasbnstruction{permitfor theJamesA.FitzPatrickNuclear;PowerPlantIwasLdocketedpriorL

'[

to July 1, 1978, the Licensee mayLuse these^requirementsfin'::

1 lieu of the requirements.of Table IWB-25'00-1, Examination Category B-J, Note (1)- of' Section 'XI of 80W8h:

==

Conclusions:==

Basedonthe-aboveevilluation,Jitisconcluded-

~

a that,becausetheuseof74S75(todeterminethefextentof-A examination of: pressure-retaining-welds' inLASME CodejclassLI h

piping for a. nuclear' power plant whose'applicationLfor a.

-construction permit was docketed prior to July 1J1978?is;.

allowedby10CFR50.55a('b)(2)(ii),relieffis'..notLrequired.

3.1.4.2 Reauest for Relief'No. R42 Examination-Cateaorv B-J; Items B9.11 and'B9.21. Pressure Retainino Welds in C1 ass 10Pio'ina l

Code Requirement:

Section XI, Table'IWB-2500-1, Examinatio'n?

il Category B-J, Item B9.11.(circumferentialjwelds : nominal pipe J

size.14 inches): requires 100% surface.andvolumet'ri.c-N examinations ~as defined by Figure IWB-2500-8_andlltem B9.21 1.

t 12-S

'a 4 i

3., ;

j.

! ) ':

a i

?j 3 ].;

q f.,1

/

j; 1

'f j i

-'E i

r

.g 1

1

,..f Jj L(circumferential welds,mominal. pipe. size <411nches)_ requiresL a -

}

.c

.100% surface: examination as defined _ by_ Figure IWB-2500-8T-1 1

Licensee's Code 'elief Recuest:

Relief isJrequested froml b

R performing the'.CodeJrequired volumetric and/or. surface d

examinationsLon the 15 circumferential welds listed below:'

4 a

LClass 1, 3-9 Weld No.

m LItem No.

N 4-10-1838

-89.111 20- M-128B:

89.11 R

' 10-1398.-

-B9.11?

4 24-10-152BL B9.Ilc I

6112-9118:

B9.lli:

l 1

'10-14-491C' B9.11L 1 14-512CE JB9.11?

10-23-670B.

~B9;11:

24-29-5428 B9.11:

24-29-606B.-

.89.11" M

24-29-573B 89.11 24-29-637B-.

89.'11 '

18-34-391B B9.11 18-34-425C -

89.11L

• 3-13;1040CL B9.21 Licensee's Procosed Alternative' Examination:1.None.

Licensee's Basis for Reouestina Relief:'iThe LicenseeJstates' l

sthat these welds are l inaccessible to Lthe' Code-requiredL D

L volumetric and/or surface examinations. LThey are-located within containment-penetrations-andithe' clearance!doesfnot

~

allow accessibility to the weld for/the-surface and volumetric examinations. - These welds.will. be visually examined (VT.-2);

~

i

,c.-

-duringthehydrostatictestingon'ce[every10'-yearinspection" interval.

Evaluation: 1 The Licensee'sLsubmittalihas been reviewed, including'the drawings referencedlin the requestjforrelief.-

These drawings._show that the welds' listed'above'are located" insidecontainmentpenetrations=anditherEfope,-are' completely,

~

inaccessible for the. surface and.. volumetric

• examinations.

.t

- 13 i

3 l

r g

t.

___.m

---

m--

w e

g-(

[

[-o' _. Q -A:

' j.[.

a x

w The 1.icensee hasistatedcthat the welds listed above will!be-visually lexa' ined (VT'-2) for leakage during itheLhydrostAtiet m

. testing once,every 10-yearJinspection interval'. iThe' visual ~

examinations for ledkage :should ~be performed.on' the open Tend (of theLcontainment: penetration'..

. V+

?

As shown 'in'the-piping weld a'nd-support l_isting;for the second?

10-year interval,Ithe'first: pressure boundary ~ welds (process; l

pipe-to-flued head). outside th'eicontainment :onleach)okthese; process pipes willjbeLvolisme'trically examined over 100%idflit's1 1

length'aspartTof.theJaugmentedexaminat'i$n' described /1.nL y

section2.2d(b)oflthisjreport.

4 The combination of(theLvolumetFic examinationiof.thMfirst pressure - boundaryc weld l outsiile ' containment l andith'el performance

- ofavisualexamination~(performedon..theopenendfofthe' l

containment penetration)'for, leak' age during the' hydrostatic >

j testing' provide:an acceptable 11evelLof inserviceistructural-

- integrity.

q l

==

Conclusions:==

.Basedonthe'aboveevalustion,itlisconcluded:

that' compliance with theispecific requirements of SectiohJXI o-H would result in hardship or:enusualfdifficulties without:a compensating increase. in the. leveliof' quality;and safetyL l

l Therefore, itis.recommendedthat[reliefbegranted;as; j

requestedprovidedthatthevisuhlexamin'ation:(VT-2)lforL leakage during1the required hydrostatic testingsis; performed oni j

the open end of the containment penetration..

1 3.1.4.3' Reauest for Relief No R9. Examination Cateaury B-K-1.' Item B10.10. Intearal-Attachments-for-Pidino; d

.m J' l Code Requirement:

Section'XI,-.ExaminationCategoryB-X-lh

!]

Item B10.10 requires.a 100%_ volumetric or; surface' examination,..

~

as. applicable, _ of. the integrally ~ welded / attachments: of- [ip'ing) required to be: examined by Examination: Category 8-J.L JThe; L

14' 4

mm

4 c

m o,

s

)

b..

I q

g w

c o

..-4 q,

A*

p QW g

.m.

f

'I, y,

examinationrequiremeniisiareasdefiddibyIFiguresIWB-2500-13,;

-14, and_;15..

o'

.g Licensee's Code Relief Reauestf The Licensee req'uest'sLreli'ef[

1 f'

fromperformingLthe'volumet'ricorfsurfaceeximinstioni;

required by.ItemB10.10'ofExaminatibnCategory:B-K[1honthefoljowingl7, L

'16 welds:-

R 4

1:6 Class 1 Welds'

/

[

?7f03-963P 20-lh5'128-10-10-183A'-

23-23-671A1

' mM y

33-10-128A' 137-29-542C:

37-10f139A'

'37-29-573C

,g.

m

' ~

?37-10-152At

,37-29-'606C 4

'18-12-9110:

537-292637C3 14 13-1040Bi 31-34-391Ai

.20-14-491B; 31-3444258b Licensee's Procosed Alternative Examination

'.The Licensee 1

proposes to perform.~a visual' (VT21) examinationdn., -the1 subject; q

b welds to the requirements.of SubsectionilWEr " Requirements fori q) 7 ClassMCcomponents,'" Table'IWE-250051,rExaminat' ion

• Category E-B, ' Item No~. E3.10; of theiASME. Boiler;and! Pressure i

Vessel Code, Section'X1', 1980lEditionithroug'h' Winter.;1981l Addenda.

L l

Licensee's Basis for'Reaue'stino-' Relief: ' TheprehousL10-year-submittal. had cla':sified these'integrallyiforgdd flued head welds as Examination Category 'B-K_12 ThisLinformationTis-o

,d providedintheform'oflareliefrequestTtoclarify(andprovide consistencywiththe' previous $10-year'151ProgramsubittA1.;'

9

- As'outlinedby-the-ASME-SectionXICommittee'inCodeCsseN-322i for the integrally-forged flued head.' attachments 6f Figure 1(c;)6 oftheCodeCase,examinationfisnotirequiredprovidedind' welds:

.m are located within1the-boundary.of Exami' nation: Category B-K-1~.

The design of containmentipenetrations4are similarsto?

,z y v-Figure 1(c)1of Code Case N-322. ;The penetration's;are:shown.

on-E, y

15 L

, ['-

I g

[f-lp M

,t hfJ J"

m y

y 07 c.e s

m

.n q

]

i

\\

O the FitzPatrick~ ISILisometrics. ' A VT41 examin'ation;will be-performed 'because of the importance;of the integrity)of the.

primary containment: boundary, d

e.c,

l.

The' welds! listed above h' ave been classified underL 9

y Subsection l IWE;. " Requirement's1for Clas's' MC; components,"n

.)

Table !IWE-2500-1,= Examination : Category E-BD Item No. E3.10,;of !

R theASME!Boilerand/PressureVessS1LCode,fSectionXI?195d Editionthrough' Winter-1981(Addendak y

.i Evalustion:

The Licensee's s'ubmittalihas tien reviewed:

L]

including the referenced (drawinss.

Section'XI,L. Table 1IWE-2500-12,!ExaminationCategoryE-B;

~

'" Pressure Retaining Welds;in ContainmentiPenetrations," '

j ItemE3.~13 requires'.a'vis'ualexaminationo(VTal)fof'25%ofeach.

]

/

flued head circumferential weld joinedi oShe penetration;

[

t Examination shall' include welds madetin accorda'nce with Section'III, in Figures NE-1120-1 Land:NE1113'2'1. ' Examination; shall include the weld metal and.the baseim'etals for one plate; 4

or wall thickness bey'ond the-edge of thetweld. ' Portions of L

welds selected shall:be random'and representative.

l Code Case N-322 is not;an NRC-approved. Code case and,x therefore, may not be:used as.' justification for relief.L However, the welds listed:above are of.the!sameldesign asishoWn in Figure NE-1120-1(c) of SectionlIII of the ASME Code.

Based

~

on the design of the subject welds, they were incorrectly 4 classified :as Examination Category B-K-1. in thetISI; Progrlam-Plan for the'first 10-year. inspection interval;and shouldlbe examined in accordance with Examin'ation Category E-B'of-

-Section:XI.

F

==

Conclusions:==

' Based on the above. eval'uation,'it is concludedi that the subject welds 'should be classified as' Examination Category E-B welds instead of Examination Category B-K-1:and' y

y 16, L

t

s:

~%

co' g

11 cn a:

.O

+

.Q,

)

,m

,).

.Lp

.that 'the:Eiaminatio'nl Category E-B requirenientsL willibe met'.

N Therefore, relief 1s:~not< required.

7 q 9

3.1.5 -Pumo Pressure ~Boundarv' u

1 1

r 3.1.5'1-Reauest'for Relief No. R5B; Examination Cateaorv'B-L-2.'

1

Item'B12.20.'iPumo'Casinas?

y

' Code Requirement:

SectionLXIkExaminationl, Category?B-D2hltemi s9 i

h

~

d

'B12.20l(pumpcasings) requires'avisualLexaminsti6nf(VT-3)?ofc

?

a

' theiinternalisurfaces?offatlleast one' pump 11nj eachfgroup of; p

y t-j pumps performingisimilar functionstintthe" system.:;This;

~

~

o

~

examinat' ion-may bE performed.on theJsame pumpLselectSdLfoN r

volumetric: examination. of welds. -iTheL examinAtionimay be W

performed at the'end~of the 10-year interval.-

1

}

Licensee's Code' Relief Reauest:: Relief isl requested. from ,

j performingthe' Code-requiredvisua11 examination (VT;3))onithe'.

j 4

i internal pressureLboundary surfaces offrecirculationipump, S

j casings.

o Licensee's Pronosed Alternative' Examination:

The? internal?

surfaces!of recirculationspump casings:.will Lbe visually examined,(VT-3)'whenever the surfaces are made accessitile due'.

( 1 to routine maintenance.

Licensee's Basis' for'Reauestina Relief:~ The Licensee" states' L

L.

that it has b'een and continues to be:the' Licensee's: policy tot l

3 examine' thel internal surfaces 4 of.. pumps ' whenever theyj are :ma'de.

1 e

H

~

accessible due to routine' maintenance The !Licenseentates>' >

that it.does not ' intend toLdisas'semble.' components Tsol'ely(for, u

the purpose'of' inspection becauselthis' lcou?d cause additioriali R

wearandthepossibility,'however? slight,'existsforfdamageit'o; 1

the interior surfaces of pumps..

.1 o

L The.pumpsnotexaminedduring'the10-yearperiod,Lbecausethey) n b

_j l

.17,

i o

~,\\

{

l

\\

4; e

,w j

n

,e

.e r

1 were not' disassembled,' will..be examined (Niring the h'ydrostatic-

- t,r

~

y examinationLfor1 leakage intaccordance with IWA~-5000 and IWB-5000 and the requirements of: Examination (Category B-P!of" j

L iSection XI of theLCode.-

+

Relief ~from examination of specific components will tie' d

requested near the endlof-the" interval.

1 Evaluation:' TheVisualTexaminationListodetermIn'ewh'etheri unanticipatedisevere'degradatio'nofthecasing!is'occurr$ngdue; i

to phenomena'such as erosion, corrosion, or cracking. ;However,-

H previousexperience.duringexamination.fof(pumps'atotherfplants:

~

g has not shown any' significant ~ degradation: of casings.:. The '

l concept'of visualfexamination if!the pump.is: disassembled for1 q

maintenance is acceptable. :The' disassembly offthe pumps:solel'y' for the' purpose' of L inspection:isLa majo'r: effort : arid, ;in.

q addition to the possibility of additional l wear oridamage to thet internaltsurfaces of the pumps, could resultLinilarge amounts?

~

of radiation-exposure to'pe'rsonnel.

Therefore,. compliance with the specific requirementsfof Section XI wouldLresult'inJ

. hardship or unusual difficulties lwithout a compensating:

increase in the level-of quality.and' safety.

However, if the.

pumps are disassembled for maintenance, the' internalisupfaces would be examined,.in which^ case relief lwo'uldfnotlbe requ' ired for those particular pumps.

The Code:permitsithe visual'l examination of the internal surfaces:ofithe1 recirculation pumps; q

to be performed at_ or'near the endtof the;secondfinterval,

~

y therefore, relief from the exaidination requirementsLis not-d

.necessary until that time'.;.Th'e Licensee will be in compliance,

. with the_ Code requirements up.to the?lastiexaminatio'n period.of the interval.

Since it is'not-known at this time whichL 1

components will require relief,lit..is; reasonable' for the m>

decision to grant _ relief to be postponed until:after the

~

s Licensee determines that relief,is required.

The Licensee

{

should submit-a new relief request, near the end of the second?

j 10-year interval, which identifies-the specific componentsjfor-which relief is requested.-

18-1l

J

<Mi

3 m

- 7',

, ~, y' -

'U Q,

^

R

,'y

9 L7

~

W zo

.i..

.,)

?h-

.\\u

. Conclusions

Based on the above evaluation,11t"isTconcludedi N

[

that' compliance with the specific requirements of Sestion' XI; would.resulttin hardship.or' unusual'difficulti's with6ut a'-

e compensating increase.in the.. level'ofLquality.and safety. iThe-LLicensee'should subhiit a new relief treguest' nearithef ehd' offtheL i

second interval which'ideritifiesithefspecific componentsi or

~

f which; relief is requesthd. jThereforeMit/is'recommende[thst4 L(1)TheLicensee'sproposa1Lt'o'performthe, visual: examination; (VT-3) on:the; internal; surfaces.oflthe recirculation pumps.

w' eneverf they..arelmade 'aciessible dueTto pumpjdiiassembly for-h 1

7.

y mai ntenance! purposes h shoul d. be accepted; an'd/(2)1 Relilef { shou'1'dL notbegranteduntilthespecificLeomponentsforlwhichreljeff.-

is requested 'are identified.

t 3.1.5.2' Reauest for Relief No.LR7! Examination Caleaory B-G-1; Items i

B6.190 and B6.200. Press'ure'Retainino Boltino. Greater than'2

' inches in Diameter:

Code Requirement: Section XI, Table'IWB-2500-1, Examination 1

~

Category B-G-1, Item B6.190 requiresia v.isualf examination:

(VT-1) of all flange ' surfaces,'which include' theol;indannular.

s surface of flange surrounding each stud;Lwhen 'the connectionLis

' disassembled.

Item B6.200 requires?a visual ~ examination (VT.1) of the surfaces' of all-nuMushingss.and washers..

Bushings and threads in thel base materiallof flanges.are:

required to be-examined only when theLeonnections'are disassembled.

Bushings.may.be: inspected in place..

t Licensee's' Code Relief Reauesti. Relief isLrequested from' performing the.. visual examin'ation (VT-1); of the: nuts,: bushings,

. washers,. and flange surface while-theLpump;is' assembled..

Licensee's Prooosed Alternative Examination:i If.the.pumpjis disassembledforroutinemaintenancewithin.the" inspection.-

intervali the nuts, washers, bushings,cand' flange surface.will'

. be visually examined (VT-1).:

-19

. [h. } r,

g<j yv t

1 -

-l

}

R n-/

7 gj ~ ' a :

h i, m-2

'g g.

,1 7~

q o

't

~

j.'

[;

'~

,;[;

.7, Licensee'sB$sif for Recuestino Reliefh The.'Licenseejtatesi b

i

,n a,

)

that :it[d'oes not intend; to' disa'semble componentsisolely for s

1 the:purposetof:: inspection because th'is[c6uld cause' additional:

.?

~wearandLthepossibility,thoweverslight',Texist'(for/ damage [tof, L

y s

the ;. bol ting.1 However. fin-place visuaVexamination ofcthe, nuts,V Y

. ashers,; bushings, and'f1ange surface does'not revealtthe? areas:

q c

w most susceptible to failure a'ndfsubsequentidegradationLoff pressure-retaining integrity.s lIn'-pl ace {i nspec t i on ;r'es ul t s Ti n e

~

y

?large ' amounts; of ra'diation exposure.

y 7

m<

S t._

'1

.willbeperformedduringthehydrostiticexamination1atItheend;.

'[' jf

'Ifthepumpisnotd' disassembled,avisualieaminationdVT-2)f, ofthe.inspectioninterval1;in:laccordance:with;;IW15000JahO

(

IWB-5000landitheLrequiremehtsiof?Examinatio'nCAtegory[B-Ploff

[d SectionLXIfof;the Codef -TheLboltihg.will be volumetfibally1 '

N i

texaminedinaccordancewiththe!Codereqbirements..

S

,.m.3.-

-i Evaluation: ~ Althoughithe Licensee' mayinot have 'confiden'ce)in :

4 l

j thismethodofexaminationiforfdeterminingthe;condif. ion.;ofDthe?

']'

subject: components; -it'has notJsupplied enough justificati'on to:

1 establish that the Code-required visual examinationiis-impractical'.. Lack of confidence in' examination' results' is notr 4

a justification' for reliefLfromithe Codetrequirementst Code' s

n l

~

requirement changes should.be1 submitted to thi ASMElCddel '

' Committee for consideration. The Ocensee states that the recirculation pump' casing bolting ((Item,B6.180)' willf be?

volumetrically examined in accordance with -the Codel requirements.

Since these:componentsLwillibe readily:

accessible 1atthe;timeinspectionLpersonnel?are; performing lthe-;

i volumetric-examinationson.thel pump;casingb'olt'ing,(itfisLnot.

unreasonable to require'the Licensee;to perform the visuali examination (VT-1) of the nuts, washers,. bushings, 'andIflange; surface at'the same' time..

Conclusions:

Based ~on'the above. evaluation,-it'is concluded.

~

that the Licensee has..not justified;the determination of.

20-

+

-l

s

.,m

+

x' m

gjg

' }7, '

W A

t k'

^*,

^l I

j 4

\\

impracticality lfor the"v.ikuallexaminatio'niVT-lhof/thelndts, 4

washers,' bushingskand. flange surface's 'and that requiring:.. thel LicenseetoperformtheLCode-re_quiredLexamihation!wouldnot resultin. hardship.

Therefore pit is? recommended that reliefs 4

be~ denied.

i I

3.1.6 Valve' Pressure Boundarv.

io a

[.

'3.1.6.1

Reauest for Re1ief No. RSC. Examination Cateoorv B-M-2; 2 Item B12.50. Valve 1 Bodies:

1 1

Code'Riouirement:

Section XIJ Examihatihnicategory1B-$ 2,[ Item:

,l

_t 1

g y

4 B12'.50 (Valve Body,. ExceedingL4 Sin.; Nominal.- Pipe Size) requires <

. a visual:'exa'mination l(VT-3)!ofitheIinternal esupfaces of A10e1 1

bodies.. The examinationsLare limitad,toLone' valve withinLeachL group of: valves that)are-of the s'amefconstructionalfdesignL

]

such as globe, gate, o'r check valve;;and manufact ning method,b h

and that perform similar functions:in the! system,fsuch as.

containment isolation-and system overpressure prote'ction. ?The-examination may be ' performed on~the:same valve 1 selected;for?

3 volumetric examination. The-examination'may be performed'at U

y the end of the 10-year interval.

a Licensee's Code' Relief Raouest:

Relief is. requested from performingtheCode-requiredvisual; examination?(VTs3)ionthe i

internal' surfaces of valve.b'odies-exceeding;4;inndiameter nominal pipe size in the. mainisteam, feedwater,. coresprayj high-pressure coolant injection, residual' heat removal, and '

y recirculation piping systems.-

o Licensee's Prooosed Alternative Exam'ination: "The internal:

1 surfaces of.valveibodies.Will be visually. examined.'wheneverI he.

a t

surfaces are made accessible due to' routine' maintenance.

The!

q Licensee states that the valve maintenance: procedures'will be-updated to include'a VT-1/VT-3 examination when components are-d m

disassembled for maintenance and that'this will._be accomplished!

l prior.to the next' refueling. outage.

21

.u

.]'

' f

• J r

x

.3, s

~

g,}

sf w,

o

.w i'73' r

iLice'nsesB' asis'forReauestinakelief:)NTheitiedsse1sthtes!

b J

e Lthatit"has;beenandcontinuestMbethejlicensee'spolicyLto examine 'the internalJsurfaces offvalve; bodies whenever they:are made a'ecessible due'to' routine! maintenance? TheK lcensee?

L Lstates1th'at'itdoesnot. intend'to.disas'semble~componentsfsolslyg for the purpo'se of inspection.because'this could causs~

/ additional wear'and the possibil'ity, however slight, ex_ists?for-damage lto' the interior-surfaces lof.: valves. -

i The valves.not.examin'ed during the~10-yearjperiod becauseLtheyL were Lnot disassembled ^will: biexamined d0 ring theLhydrostatih i

i i

examinationforleakage,inaccordancewithIWAL50009 ands'

'l

~

. IWB-5000 and the} requirements of Examination / Category lBkP off Section XI of1the~ Code.

Relief from examination of specific components?willib' :

e requested near'the end of the intervalL Evaluation:

The visual examination is' to detErmineiwhethe-:

j unanticipated. severe degradation;of. the' casing ;is occurring;due' H

to. phenomena luch as erosion,. corrosion, Lor cracking.

H6 wever,.-

previous' experience during examinationiofjpumpsi.at.other plants has not shown any 'significant.degradationLof casings), DTh.e; concept' of visual-examination-if ths valve is disassedled for-J i

maintenance is acceptable. ;The disassembly!of the?valvesi J

solely for the purpose offinspection;isfa. major l effort:and,' in!

addition to the possibility of additional.1 wear:or..damageito the:

internal surfaces of the valves,1could result in large?amou'nts"

~

3 ofradiationexposuretopersonnel.LTherefore,fcomplisncewith g

thespecific: requirement'sofSectionIXI)wouldirds'ultLis hardship.or unusual difficulties (without a compensating S

increase in the level.o_f quality and safety.z LHo' wever,Lif the.

valves are disassembled ~for maintenance, the interna 1Csurfaces?

'I will'be examined,:in which casejrelief would:not!belrequired H

for those'particular valvesi The Code permits the visual examination of the internal: surfaces 1of the valve bodiesitolbe' 22

___________-a--_s---------

n.

w O

1 performed at' or near the end of the second interval, therefore, relief from the examination requirements is not necessary'until that time. The Licensee will be in. compliance with the Code requirementsJup to the-'last, examination. period.of the interval.

Since it is not-known at this time which; components will require relief, it. is reasonableofor the decision to grant relief to be postponed untiliafter the~ Licensee' determines.that relief is. required.

The Licensee should submit:a'new relief.

request, near the' end of the-second '10-year interval, 'whichi 1

identifies the specific components for which relief is.

requested.

==

Conclusions:==

Based on the'above evaluation,.it.is concluded:

that compliance with the-specific requirements of.Section:XI would result.in. hardship ~or unusual difficulties's without a ~

compensating increase.in'.the level of-quality.and safety. The Licensee should submit a new relief. request near the end of Lthe second 10-year -interval which identifies the._ specific.

components for which relief is requested.

Therefore,~it is' recommended that:~ (1) The. Licensee's proposal to perform the visual examinations (VT-1/VT-3) on the _ internal: surfaces ofcthe valve bodies whenever they are made accessible due to valve; disassembly for maintenance purposes.should-be accepted; and (2) Relief should not be granted until' the specific colhponents for which relief is requested are identified.

3.1.7 General t

3.1.7.1 Reouest for Relief No. R5A. Examination Categg.rv bag'-2. Items B7.10. B7,50. B7.60. 87.70; and B7.80. Pressure Retainina-Boltina. 2 inches and less in Diameter Code Requirement:

Section XI, Examination _ Category B-G-2,

?tems 87.10 (bolts, studs,- and nuts on Reactor Pressure.

Vessel), B7.50 (bolts, studs, and nuts.on piping), B7.60 (bolts, studs, and nuts on_ pumps), B7.70 (bolts, studs, and--

23

-s p

,;p q s c

^

m <>

s y

i:

^

1 i ~ '

l U*

p

nuts onTvalves), end B7.80_.'(bolts,Lstudshandfnutsiin1CRD)

' U:b

]

h'ousihgs) requireJaivisuallexaminationL(VTf1); offthe surfaces:

l w

e

,o L

of all; bolts, studs,- and nuts.-.

u

'Thebolting:may;be:examinedh!(a)Jinplacefunder.iension;[(b)j

~

t

-whenthel connection..is-disassembled;orj(c);whenthiboltinglis 3

c i

removed?l Bolts, studs,'and" nutsin!CRDLhousing;should be; l.)

examined when disassembled.

Deferrallof: inspections: toL the~end' f

b of the intervslL isL not permissible.

w

+ -

'l 9

s L

Licensee's' Code-Relief Reauest:.Relieffislrequestedfrom.

performing thef Code-required (visual examinationMT-1) hon.the' f t

p'ressure-retaining; bolting. :

a p

3 - v Licensee's Pronosed Alternative Examination:.1TheJsurfaces df.,

1 the pressure-rstaining; bolting will be. visuallyf examinsd;(VT-1)i

'whenever. the-surfaces' are mide accessibleidueit'o routihe q

maintenance.-

l Licensee's Basis for RecuesiinaiRelief: TheLLicensee! states:

1 3

that it has been and continues to;be the Licensee's' policy to examine:the: pressure-retaining;boltingwhenever;the; components-

.,9 are made accessible due to routine maintenan~eL It[fsithe, c

Licensee's position that in-place. visual examination.'of' bolting; d

i does not reveal the areas lmost.susceptibleTt'o failure 'arxi(

L subsequentdegradationof. pressure-retaining; integrity,{andt d

that in-place inspection resultsfin large:amountsiof radiation.

g l:

exposure.

The. Licensee states:that11t does notfintend to1 disassemble components solely for[ tid purpose?of3ns'pectioni l

because this:could cause additional; wear and'-the possibility, L

however slight,.' exists for~da'mageltoithe bolting.:

i 1

The bolting'not examined during' tjie110l-ye'arfperiodhbecaus'eltheL J

A

. component'was no't disassembled," willf be examined lduring;thei.

i hydrostaticiexaminationfor.;leakagein?accordancewith'IWAf5000' and-IWB-5000 and the' requirements'of Examination Category B-PL j

i l'.

1. c!

24

?

' J' e

.~

4:.

.- >+i

e

~T.,,...

y,-

< w:p Aa,

. 11 '

M %, %

cp s,

1,

i T

.-q i

'of Section:XI'of th'e. Code.:

)

Relief from examination' of, specific componentsMillL be :

requested near the:end of the 10-yeariinterval'.-

i l

1

+

-A thought..the' License'e may not.have confidencelin' 1

-Evaluation:.

. this; method:of examination < for determining. the:conditionsof {the!,,

subject' components,iit h'as; notisuppliediedoughijustificationitoe 1

~

establish 1thatitheLCodesequired visualnexamination[i's',

Impractical' iLack!off confidence in examihationfresultslih; not).

l l

Ja: justification forf rslief from thE Coddurequirementss(Code" a

'requirementchangesTshSuldbesubmittedLttheASMECodei 7R

~'

o

. Committee forL consideration, f Therefore, Iitlis 'notfunfeasonable '

I torequireithel.icenseeLo;perfSrmlhe! Code-requiredL t

q j

s

-examination; 1

x

,1

Conclusions:

iBased on'the above' eval'u'ation,3 it'isiconcludedL d

.thattheLicenseebasinot'justifiedthediterminationOf i

..c impracticality-for the visual examination (VT-1)iof the.-

1 pressure-rethining bolting surfacesLand thst requiring the; u

Licensee to perform the Code-required examination'would noti n

result in hardship.

Therefore, Lit is recommended that. relief f a

be denied.

I 3.2 Class 2 Comoonents 3.2.1 Pressure Vessels J

i H

3.2.1.1 Reauest for Relfef No.'R15i Examination Cateoo # C-A. Item '

~

a C1.30 (tubesheet-to-shell' weld). ' Pressure ~ Retainino'Weldslin-O...

\\,.

Pressure Vessels-7 1

. Code Requirement:

Section:XI,.Tabl'e IWC-2500-l',: Examination j

. Category C-A,. Item'C1.30L. requires (:a;100f volumetpic l examination,-j as defined bi; Figure IWC-2500' 2,! ofithe -

tubesheet-to-shell. weld. : InLthe. case of! multiple vesselsiof 3

1 25; o

j f.:

t t

y

'N t

-~

Lil

+

JM

,3

L g

4

'O'.

/Qp

~

, w:

-[f' c~ ' (if uf, y

.f t

similar design, size, and' service, the: required leI'aminationb y [,,,

[,,td

.may' be limited to one-vessel or distributedlamonhthe vesshlsb id [

The vessel areas selected'for the..initialJexamina' tion shahbe[ $

O p o$NT

_ reexamined over the: service lifetime ;of theLeomrion'enth Licensee's Code' Relief Recuest:.

4;4; e

. Relief,is~ requested frbm'-

{

performing the: Code-required 'volumetHe Examination 5f the '

d q

.tubesheet-to-shel.1 weld of;the ' heat exchanger (RHR).,

~

l

. J.

e Licensee's Proposed Alternative Examination:. Volumetric.

i 1

i examination will be.made if.tha' heat exchangercisfdisas_semb1sdi l

for maintenance.

t

.a Licensee's Basis for Recuestina Relief: :The channel head, cover n

_- d f '

1 r

'c '

will req'uire removal toLinspect the tubesheet-to-channel'headi

,Jpr' weld.

The channel head cover h'as' a' clearance ofifeet: from [O

. 2 the RHR Heat Exchanger floor.' Upon~remo'valfof;tha' channel head e,-.

cover, inspector access to_the channel head-td-tubesheet weld!

y4

~

is available.

General Area 'radiationLlevels ' ham been',y

~

-approximately 250mr/hr to Irem/hr during' previous ISI inspections of the RHR heat. exchanger; welds. - Itiistestimated

.{

q that disassembly, inspection, and : reassembly would' require w

approximately4.5 person'remexposureto'completethisworkf l

Actual exposure within the channe1< hepd (inspector access) is' not available, and radiation levels may be significantly-O.

i higher.

Evaluation: The Licensee's submittal has been! reviewed!

L-'

g L

including the referenced ' drawing. : L Because. thb' disassembif of.,

the heat exchanger is a major ~ effort and' of the. ALARA concerns',

the concept of performing' the volumetric examinationion the

-tubesheet-to-shell weld if the heat exchangehis disassembled

.for maintenance is1 acceptable.

However;.if!theheaNexchangerL-isdisassembledformaintenance,.reliefwb0>ldn'ot'berequiredc since the Code-required volumetric examiriabon would be:

s performed.

Since the volumetric; examination:of the..

y a:

~

26 y

.g I h'

' =,

q r

.,/

I

=

,a p7 F_

'q ift

]j M. wr a

-l 4

.tubesheet-to-shell~~ weld may be/ performed at or near the:end ofg b

the second yearfinterval', relief from.the.examin'ation f

m requirementsLis'not necessary until then because the Licensee; j

u will-be in compliance with the Code requirements up to:thatt 9

'1 time'

'Since it is not known at this' time'if the weld will be; j

examined or-not, it is reasonable'to postponeithe decision. to

' Li grant relief, if required,L until afterLthe Licensee submits; a ll

~ new relief request;near the endLof the second interval.

j z

,9

Conclusions:

. Based on the above evaluation,.it is' concluded r

that, if needed,-the Licensee should submit:a new relief ~

L request near the end:of the second 10-year interval..-

a Therefore, Lit is recommended that:

(1) The Licensee's proposal to perform the Code-required Evolumetric examination if. thel heat i

exchanger is disassembled for maintenance should be accepted; (j

and (2)' Relief should not'be granted at~this time.

j

}l l

3.2.2 Pioino i

l 3.2.2.1 Reauest'for Relief No. R1. Examination Cateoory C-F. Pressure Retainino Welds in Class 2 Pinino of RHR. ECC; and CHR Systems

. Code Requirement:

Section'XI, Table IWC-2500-1,. Examination 1:

j Category C-F, Note (1) states that the' welds' selected for' l

examination shall' include:. (a) all welds :at. locations. where the stresses under the loadings resulting from' Normal. and Upset"

]

~

plantconditions,ascalculatedbythesumoffEqs.'(9)and'(10) d in NC-3652,-exceed 0.8(1.2Sh + S ); (b) all weldsiat'.

A terminal ends of piping or branch runs;T(c)~ all dissimilar; metal l welds; (d); additional welds, at structural-discontinuities, such that the total number of welds selected for examination. includes the followi.ng percentages of -

i i

H circumferential piping welds' for boiling water reactors:

qN

. (1) none of the' welds exempted by IWC-1220, -(2)inone of: the:

welds in residual heat removal and emergency core cooling-l systems,-(3) 50% of the main' steam system welds,'(4) 25% of'the.

p 27' i.-'

l 1

_-_--.n-

}@;?

~

my;;,

[

fg jjhv.

W,, -

m.

'J.

1 W

e

h, lp' > : -

!j r

i

, g ' mT T'

n, H

y

~;<

g pfl.g y

!pm i

f.t

O m-7 x

i it ' '

i h

',f-'

,.f.i p

5 1

Weld.s.:in.allothersystem's;f(efiermina1LendsParefths).'

Y' y extremities?of pipingirunsfth'at con'nectjtorstfuctures, i

% g

' [i

components t (suchl asYvessel s[ pumps,f valves)',forl pipe l ancho~rs...n i

' each ofLwhich[actEasL rigid 'resiraint's!oriprovidelat[least tqof. g L

2 1.

s

. nr m

. degrees off... restraint to piping 7th,ermal ? expansion;;

T j-a<

(f) 7structuralidiscontinuities (include' pipe]weldLjoints. tot lm

~j Lvesse1[ nozzles, v$1 eLoodies,' pump icasing' Rdipe fittingsj([0ch A ' l [

s

<d las elbows.E tees',yreducers,J flanges,;etc. conformingsto;

...s

g ANSILB16.9[,fandpipe; branch!connectionsiandtfittings;F X

d a m c (g) exami na ti o'n F requi rements L ar.e unde rjdevel opment'.y - m u

q*;.q a

y m.

s.

k 3

h/

-[,

,1

-;+,

Licensee's Code Relief Recuesth ? Relief is;requ.estedifrom>the f' 1

m m.....

a 3'

requirementsof' Table lIWCW2500'-1! Exam'inationLCategoryLCeFI

~

Note (1) 'of Section-XI?for Class 2; pipin, g we elds in RHR, ECC,-

7 y

o and CHR systems.,

M,

. ji

"~

i Licensee's Proposed Alternative Exa dnation: ITh'eTicensee O

proposes to; use the; requirements LofTparagraph71WCd220, Tabl{

j IWC-2520CategoryC-Fand'C-Gj1andparagraph;IWC-2411Einithei l

. ~.

1974 Edition through the Summer'1975fAddendaito determine, thel

~.

- extent of examination' of? pressure-reta'iningJwelds(inlASMEf C6d{

s a

- Class 2 pipingLfor'RHR, ECC,7and HR;systemsb

~

m o

m, Licensee's Basis for Reauestina Relief:fThe Lii:ensee! states.

n that the determination of the extens: of'examinatjoniof).

os-pressure-retaining:weldsLinASMECode1 Class.'21pipinglfor?RHR,;

q ECC, and CHR-systems;by the requirements of par..,..agraphlIWC-1220,v,

.. c n;

Table IWC-2520 Category C Fiand:C-G,2 and, paragraphlIWC-2411?of ~

SectionXIofthe'ASMECode;in(thell'74 Edition',LSummerI197C

~

9 1

...... ~,..

Addenda is allowed by 10iCFR 50.55a(b)(2)(iv)(A)D

• g 3 1

f

- Evaluation:. :10 CFRf 50.55a(b)'(2)(iv)'(A)fstates:t 'Apppoppiate CodeLClass 2 pipe welds in Residu.al:HeatL, Removal:Systemsb ~

+ ~

.. +.

,n Emergency Core Cooling.' Systems,tand, Containment-Heat;. Removal!

.~

s

,2

.. a.

Systems,; shall Jbe examined. ',The f extenty,ff, examination: forn theseLsystems,sha11Lbe determined'by thefrequirements of3 m

-I L

-28 4

' y,' t y 4 y t,

4

[l y.

_' Q

^

?

S

x.--

j

>M

'x

1 r _,

3 S-d

.J u>

. _,. U

jlf, n

c,

.e

~

4 N+4 y

m u-y j..

4 s

t, y

r n

Lparagraph;!IWC-1220,iTablehIWCi252'OCategory[Cyfand%G,9and?

L paragraphilWC'-241'1'in'ths1974l Edition (andAddenda:t6Foughith@'

M Summer 11975 Addenda lofSection?XILof;the;ASMEiCode." Sinceithe{

n

~

-useLoffparagraphIWC21220,TablejIWC225'20icategoryC-FandCN

~

3 j

h-E land ' paragraph IWC-241'1?of Section1XI[in.'74.S75)tolNe'terminec thei

[

extent sf. ekaminationfof Class 2 pip'e weldsjin?RHR,.l ECCU and :

, d a

[_'

CHR'sys'temsiis? required lbyjl0;CFR-50.55a(b)(2)(iv)(A)Qthef jj

w......

,..t I!

-1.icensee?should:be using theseLrequipements in lieu of:the:!',

s

.... ~

requirements of Table (IWC-2500-1[ Examination Category C-F,(m

?,

3

',mm.

p Note :(1)f of Section XI.

f L

y c,

4 f

'(o

..R,

Conclusions:

. ' Based'on the above evaluation', it?is concluded!,

'f s

s that,L.because the use of)4S75 i;o determine the extenhol i

examination of pressure-retaininglweldsLiin[ASME[ Code Classf 2; $

ll t

,4'i piping in RHR,7ECC, Land.CHR sys'tems is required.by 10 CFR-50'.55a(b)(2)(iv)(A),' relief!is not1 required.y y

. ' r.

M

'3.2.~2.2 ' Reauest for Relief No'. ' R3; Examination ~ 'Cateaory C-F? Pressurei

)

~

Retainina Welds 'in Class 2 Pinina of, non'-ECC' Systems 1

j Code Requirement: (SectionXIhTabIe41WC-25'00-l', examination -

CategoryfC-F', Nota (1)st'ates/thattheweldstsedctedifor?

~

~

+

examiriation shall.. include:- ( a) ; alliwel d's J at l ocati ons4he re :

a the stresses under the loadings resulting.from NormalsandLUpset plant conditions,, as. calculated lby' the sum of;Eqs. (9) and.l(10).-

+

in NC-3652, exceed 0.8(1.2S6 + S ); (b)' all ' welds at-A terminal ends of piping or-bran'ch runs;/(c))allJdiss'imilar.

metal welds; (d) additionalowelds,eatcstructural4 discontinuities,.such that the. total; number.-offweldstselected-

.for examination includes' th'e4following percentagesTo'f circumfere'ntial piping weldhfdriboiling water reactors:

j (1) 'none~ of thel welds exempted by. IWC-1220',f(2)'~ nonelof. the; welds:in residual; heat" removal 'and? emergency corelcooling >

...a-systems,1(3)L50%of.theLmainisteams90emwelds,'('4)V25%'of;the Lwelds'in all Lother systems; (e)1terminaljends are the '

'N c

extremitiesofpipingruns;thkconnect'to-lstructdes,.

b o

af Y

3

,y 29 N

4

.a

. bi5 ',

?,

3 n

v.

g..

+

r

,m

-c

..=

~

w s, T

+r-

- c.,

^

N 4

/;a'; m n.

t,

ll,1 t

=

. i 9

(

l

(

l l l

g,[

W tig>

gr' e

x

.i i s

,J

,1

(,(.

y l

E I.

M g

T components /(suchas(vessh1sl,fpumpdv'aNesQ.or(pipeiancho'rsl,4

c, '

-eachof?whichactiasLrigidlrestraihtsforprovideathleastitwo24 c

. degrees' Lofirestraintjto-piping / therma]Lexpansion;(

'(f) structural ~ discontinuitiesiihclude pipe" weld joints [to:

J':

E vesselnozzles,ivalveLbodies,fpumpfcasings,jipekittingsMuch!

aselbows,iteespreduc'ers'f1Nngesletc.fconforming[toANSI(

W LB16.9), andfpipe branch connectionsiandLfittings;i f<

(g) examin'ation requirements are: under; development.

m Licensee's Code' Relief Reauest:5

' f Relief isL requested froin thel' requirementsiof Ta'bl61WC 2500-IF Exainination[C'atEgory[C-F[

f 4

g Note '(1) of Section1XI for Class'2 { pip'ing weldsfininon-ECCi systems.-

w

,s x

Licensee's! Proposed Altern'ative Examination: lThe' Licensee; '

. \\'

proposestousethe/requirementsof, paragraph >IWC-1220dTable?

IWC-2520'Categ'oryC-FLandfC-G,JandparagraphiIWC-2411inlihe?

1974. Edition.throughthe1 Summer 1975:Addendatode'termineithe?'

extent -of' examinationof pressure-retaining > weld 5[in" SME Codef,

Class:2 piping (non-ECCS)..

i

+

c

g d'

(,<

Licensee's Basis-for-Reauestina Reliif:.iTheLicenseelst' ate $

2 a

that' the' determination of the. extent;of!eEaminationif.:

pressure-retainingweldsLinfASME!CodeLClasss2. piping'(non-ECCS) by the requirements of paragraph?IWCf1220XTable'IWCi2520]

Category C-F and C-G,' and paragraph' IWC-2411L of..Sectjon!XI of -

the ASME Code in the 1974 Edition, Summer 1975fAddendalis allowed by 10 CFR 50.55a(b)(2)(iv)(B)..

,x Evaluation:

10 CFR 50.55a(b)(2)(iv)(B)l states:~ '"For?ainuclearJ

. power plant'whose application ~ for a construction peraitiis; '

M docketed. pri orJ to July :1,y 1978, L. the; exf ent offexami nat i on ( fori R'b

~....u Code Class 2 pipe weldsTmay be determined 0bycthe' requirements:

e

+

of paragraph IWC-1220i TableflWC-2520gCategory;C-Fland:C-_G andl

. ~..

V paragraphIWC-2411inthe11974_ Editions.andLddendatthroughthe' Summer 1975 Addenda of Section XI of the[ASME Code;or otherk,

,y

~

m y-8

?30 R

i s

31 i

[i 4

.g g

1 i<

e - '

mx an

j; y-f L

?i 6

e i

( 7'.

}

p:

2 I

z y' y

N requirementsithe/CommissionmayLadopt."JSincel;thehapplicakion;,

1 for'acons'truction?permitifo'r'thhJamesiA?FitzPat'rickLNuclear?

Power P1 ant"was 'docke_ted priorf tojulyf1,[1978,:ths Licens'ee:

~

may use these requirements tinilie'u ofithe: requirements ofe Table; >

IWC-2500-1,.Ex' amination)CategoryC$ Note l(l1).;

' 'I "4

Conclusio'ns :

Basedonthe.aboy' devaluation /itlisconcluded

'that, because the use of!74S75 todetermin'e Lthe extent eff.c

]

i

examination of pre'sure-retainingfwelds;in-ASME Code' Classi 2J W

s

' piping forf aLnuclear. power plant whoseltapplicationMor 'a?

,d construction.permitLis'docketedp'riorJto. July-IL1978!is; ~

. '.S

,d allowed by.10 CFR 50.55a(b)(2)(iv)(B) ' relief is.not' required.:

j o

y

'1 3.2.3 E mps (No. relief requests) 3.2.4 Va'lves'(No relief requests)

I 4

3.2.5 General (No relief. requests) s 3.3 Class 3 Comoonents (No reliefLrequests)-

?

1 3.4' Pressure Tests'-

'y

,l

)

3.4.1 C1 ass 1 System Pressure Tests. (No relief requests)!

f 3.4.2 Class 2 System Pressure Tests-(No relief _ requests)'

O 3.4.3 Class 3 System Pressure Tests d

'- E

'M 3.4.3.1-Reauest for Relief No. R12. System Hydrostatic' Test-of C1' ass"?'

Coolina Water Systems 4

Code Requirement: Section-XI,(IWD-5000, " System Pressube( m 1

Tests,"-paragraph IWD 5210 statesi "_(a))Ths pressure retaining q *d components iithin the boundary of;eadhl system specified @ the-il Examination Categories of. Table :IWD' 250091Shall 2be' pressurel o

l!

9 4

I 31 a

q

.y

' D;,1 s

.y

[

('5 L t

i

.o s..

m,

• p"m n) nw:

, m, ;. m n

,a 2

0

',.'.f:. p n' f ~

2

~

+' 4' c.

' *j 8

' ?:

1 L. l:l

.lY,

• I' 1.M > p

)\\

3 3'

i

-H

,a e

testedfandtexaminedtin accordance jithlTable IWD-2500-1%during;

"'d h

the following~ t'ests:: j(l)1systemfinseNice fest,f1WA-5211(c);; i N

-(2) system functionalLtest, IWA-5211(b);[(3)Tsystemhydrostatic.;

stest~,yIWA-5211(d)';:(b) The sys' tem hydrostatic' test-shall be?

~

conducted in accordanceiwiiihlIWAf 5000,(as applicable. iThe h

contained fluid in the : system shall; serve:asithe pressurizing medium,! The system test' pressure?shallibe determined byi

'y

'l

,u a

P:

L IWD-5220 and,the system. test. temperature shall be" determined by y

(

IWDiS230..

f e

Licensee's'~ Code Relief Recuest: LThe:LidenheeLrequestsfrelief[

fromtheLrequirements?off1WDtS000lfor..thefsystemhydro'staticj;

]

-testing of the following Class;3. cooling water systems:-

E)

,I, Reactor Building Service. Water Cooling System" N

ReactoriBuilding Cooling Water, Turbine' Building. Service Water Cooling System Fuel-Pool Cooling and Clean-upl System:

Residual Heat Removal

~

M Reactor Core Isolation Cooling System 4

ControlLRoom Area Service-Chilled. Water 5 System Service: Water System-System 463 3

Emergency. Diesel Generatorj (EDG)? Fuel' Oil ?LinesL(AT C)j EDG Air Start Up; Lines "A", :"B",. "C.",f and L"Dt' 1

EDG. Jacket Water System' 4

1 EDG Lube Oil System q

1 Licensee's Pronosed' Alternative ~ Examin dign:',Th' e, alternative -

1 inspection program for Class'3 cooling water-systemsLisiasi t

follows.

Cooling Water System Components

'3 Subiect to Examination Method

Reference Piping.and Components (Not Buried).

.VT..

'IWA-2212-

. Piping and Components (Buried)

. Flow Verification."IWA-52441 j

a a

]s Licensee's' Basis for Reouestino Relief:

ClassL3' systems'Lat the y

James A. FitzPatrick Plant' falifintoltwo categories:: ((1)? the'

.. Reactor Core / Isolation Cooling (RCIC)isystem, land;(2) Cooling!

D water systems. TheRCICLsystemwasdesignedtoIbelpressurej j

tested and, therefore, will' be' tested tinifull accordance'with; the Code requirements.

m

.32 A'

,<f ;

a f

4]

i___2__.__

i i

I s

b'

_6h3

,a?

/

14 EK 4*

d g

j-c4

+

2 w

c~

~

(

y c '

~.4 The: cooling ~ water systems' wereLdesibned ahd cons'tructed(prilor i'

- to<the issuance of!the first Code:Editio'nithatFaddressedi 4

' Class:3systsmsLandcompone'nts'(1974LEdition)4LSine'e(thei O

systemswere'designedandconstructed'withoutithe:'currenti

~

. inspectionrequirementsinfm'ind,Lisolationvalvestha[would?

'S H

permit hydrostatic testing to currentLrequirement's!were notG installed.

3 s

71, #

J The.alternativeLinspection program detailed atio've will',-

therefore, befimplemented to ensure theLinteg Nty oE the:

1 m

ze pressureboundary6ffthe'secoolingwater? systems.;Thisjprogrami incorporatesfeatures;ofhhe'1980EditioSofMhe'Codethrough.

s,

- the Winter.1981 Addendalforivisualiinspec'tionL of[pipinga '

I systems., To proside' additional' assuranceJof[ integrity, th'esef W

~

inspections willobe conducted duringLsystem inservicettests::

four times per interval, which exceeds' theLCode-req'uirementsi

' (once per period, three t'imes' per interval).s Th'eladditionale inservicetestisfinlieuofthe'hydrostaticLestfre.quiredby-(

t IWD-5000..The Licens'ee' states thatithis' inspection program jas;

~

originally. approved:during the firstEintervak Pihing) support.

inspections required.byLCategory D-A, D-B, and, D-C wil1[be ~ 1;s performedinaccordance'witkCoderequipements,tasisummarizedf in Appendix A-3 of theLISI pEogram.-

1 l

Evaluation:

Because' isolation valves.'we're. not' included 'in '.the :

design of the Class 3 cooling l water systemsfand',itherefore, were not installed, the hydrostatic, testing 1of*these piping'.

systems cannot be performed as required by IWD-5000Lof,Section XI.. Based on the' design of the Class 3 cooling.wateri systems,' the. proposed alternative; examination 0.is; acceptablek The Class 3 cooling 7 water systems listed above-would have to be-redesigned'and. prefabricated'in-ordertto perform the 1

Code-required hydrostatic tests.-

5f q

==

Conclusions:==

Based on the above evaluation, fit'is concluded

~

that;the propo' sed ~ alternative examination provide's ^an -

r, L-

.33 4

' f, y I j

t

\\

,Ay

's

7 33

;q f

yc /

.'a.]

3 ((.

[

s.

if I

E

,' }

e, J

' i,

't y(

I

~

1 acceptable (level ofJinservice)strudtural integrityfand[thatl,

j j

l compliancewiththelpecificieq'uirementsiofSectionXIwo'uld, H

4 o

result?in hardship'or unusual'difficultiesLwithout'.ai L h wq t

compensating increase in th'e levellof. qu.ality!andLsafetyi V

'y 7

o Therefore, itJis'recommendedithat relief be/grarited as:

y

~

q requested.

g

]1 3.4.4 General ^ (No. relief requests)I 4

s 6,

,j

'3.5 General

.&+

3

(

.m m 3.5.1 Ultrasonic' Examination'Techniaues

[

J 3.51.1. Reauest for Relief No.' Rll. NRC-Reauired1IGSCC Examinations 1n'

'{

7 Stainless Steel Pioina Systen.s!

3 j

g

' (l;.

Code Requirement: Section XI,' TablegIWB-2500-1, Examination-Category B-F, Item No.'B5;10 requiresjboth.:a 100%-surfac'e:anh,

1 l

volumetric examination,,as defined by Figure 21WB-2500-8, of the. 4 l

nozzle-to-safeendbuttweldsi(nomina 17pipesize14 fin.');intheh RpV;ItemNo.B5.20.requiresa;100%' surface' examination,asl-D defined lby..FigureIWB-2500-8,LofLall" nozzle-to-safeendbutt=

E welds 7(nominalpipe' size <4Iin.)iinftheRPV;land[I'emLB5h30) t

, 1+

requires both a 100% surface and volumetriciexamin'ation,;as:

g defined by FigureL IWB-2500-8,' of all[dihsimilar'metalibutt--

]

welds (nominal pipe size 14.in.) in. piping;

.z SectionXI,TableIWB-2500-1,ExaminationCategory:B-JhItem?5a

/j 1

No. B9,11 requires _both'a.100%' surface'and, volumetric ~

j examination'of circumferential welds (nominal: pipe size 14 ini)?

as defined by Figure IWB-2500-8;;andcItem No.:B9.31Lrequires/,

,i

both a 100%' surface and volumetricLexamination of branch pipe!

'l connectionwelds-(n'ominalpipe' size 14in.)iasidefinedsby;.

T Figures IWB-2500-9,..-10,-.and -11.

,,j

, ~,,

t

.R

. Licensee's' Code Relief Reauest: 'The Licensee. requests reliefd 3

]4j

j 3

34.-

.0 4

,n' M

~

?

,'3

_ _ _m

,)

9.1 q

J

[g

(

~ ' )

XM

@]

)'

Wp

%gV( ','

y m.

o j

'~

i

< 1,<

n.

(

x 7

4 from'the st'andard LCode volumenic?exaniinatihn 'Ir thiwelds" e<

f N,

that;will; bel ultrasonically examined forShei etect'ioniof t d

4 IGSCC.:iThefollowing(isaUiskof?thelsystemsland;thelnumbdr N

,I of welds subject)toithe ultrasonic examination for that j.;

detection of;IGSCC:

u Eggjnation Cateaory B-F ~

j

' Code.1..

LNumber_f?...

y'

~...,.

o s

System l Item No; '

M Welds?

a:

Reactor-Recire.'-

l B5.-10,

~ 12 --

?103

B5.10<

128 ;,

W2l s

'CRD

- B5.20..

3*

li RWC B5.130s

', f 6 ;

ill '

I Core.Spr'ay.

1B5.10:

'10" 2;

<B5.130 110i

-20 r

RHR-1B5.130-

~20

1 '

B5.130t Jet Pump 724

36 1 t

12 Examination Cateaorv B-JJ o-Codei L

LNumbersof-3 System JItem No.

'M'

Welds j

-Reactor Recire.

..B9.11 14 -

'161

' B9.11'

12,

.30?

d B9.11'-

.22:

11)

{

4B9.111 281 i 35 Q

~

EB9,31 a47 410.

89.31.

.12 16:

RWC B9.112 l6 1.

L Core Spray 89.11,

. -10. '

-16

~!

RHR.

B9;11:

20 i4.

H Jet Pump Nozzle 8-1 Licensee's Prcoosed Alternative Examination:2: The Licensee will perform. ultrasonic examinations'onitheSstainles: steel piping.

s welds for the detection of IGSCCliin accordance.withithe

]

requirements of the-latest revision;of NUREG-03'13, Inspection.

and Enforcement Bulletin ~ (IEB) 83-02iand Generic':. Letter 84211,-

as.well as any later developed requirements t

1 Licensee's Basis fer Reauestina Relief:, Th'e Licensee ^ states?

lj 6

u that,inaccordancewith_therequiremedsofNUREG-0313fReiL1,;

L

,j

' Inspection'andEnforcement1Bu11etin(IEB)f83202L(Referencejl2)l,3

~

j"

~ 35-

',1 f.

j

~

q

,;p

't a

k n

,i q Nt A nroam

__u

.&r

,,o,,.

mmm" wg u @

g,f. ;

^ae Q

'7g,

' A, j

s r

o

,g y

W v

. c y+

/

,e i

g q

3 m

e) an

.s

=

d' Generic Letter 84-11/(Reference 13)das <wellj as anyflateri,,

jy I

developedire'quirements-(NUREGO313'RevJ2,'.uonPissuekiiwilt p

s 7 ~

... e "n

continuelto perform fultrasonict examination fon. stainless' steel! ' ' '

m pipingiwelds forf the detectionLof?IGSCCL Wheisystems1sut@cti i

to.these.examinationsincludethe1 Reactor / Recirculation'.Syst'em; l

d

]

(#02),.CoreSpray;(#14),fReactor?Waten!CleanupT(#12),portiNs of the;.RHR;(#10)L System,)and;otherl systems)asi.noted:abovLesjThef; Licensee considersLthat,:because.c ~.ofsthe more! stringent; e

.M

~

n requirements?for personnel; qualification'n' stas simposed.byf

. *d

^

IEB 83-02,i.th'e. quslityfof Linspection$has bee'n; enhanced 9er(o M"k

~

m. :

these' stainless steel welds..

~

n 4

y 1 -

,4 gy n

Therecentlyissueddraft1reportof;NUREG-0313LRev%2[

c p

discussesftheIGSCCLinspecti$nissue;iNSectio'n;5.0,page[Silb J

T

' Additionally,.manyl cat'egoriesL of weldsLare inspecteditiaj l higher frequency-th'anithe' ASME Code requirementsMeference? '

}

. Table 2, page 5.7 offthe draft NUREG) '

e

) -

Therefore,theLLicensee, Vin'accordancewith Sectio'n1IWA2240Lofj j

l L

.the'1980 Edition,iWinterl'98'1 Addenda,requestsithathiihel ultrasonic examinations = performed lon these' welds to$e'tectl Jd IGSCC be used inllieu Loff the, Lstandard CodeLv'olumetridi

'9 i,

examination ~forCategoryLB-Ff(ItemNos.B5/10,iB5720, land) l B5.130) and Category B-W (Item Nos.LB9.'10 Land-B9.30)Jto meet 4 l

the'ASME. Code examination requirements. LThis"avsids!.

.(

duplication'of. examinations and' decreases)overal.1 radiation y

i exposure to inspection personner. '

D j

'3 3

h Evaluation:

The Licensee'sEsubmittal)has:been" reviewed, q

including:the Enclosure toLthe;relieffrequest which(11sts theh 4

1

.specificweldsforwhich.' relief.'isrequested.I[Thiultrasonic

'd examination'for the detection of IGSCC i,sLa:more stringent a

. m,

examination thanLthe standard: Code volumetric examinationffore j,

~

o the Examination Categoriesiand:ItemiNumtiersilistedJabove.

L1 l:

>y j

3 IWA-2240, "Al ternative L Examin'ations, "i states itha't :al tern'ati ve) t d

'e i

36:

m,

.g a

)C '

,i

....y i

. g.

o.

.l

~ i examination methods,; a combination' of methods, or newlyc developedLtechniques'may'be' substituted for'the methods-specifiedt in' Division 1 of Section XI, provided the Inspector j

.is' satisfied that the.results are demonstrated to b'e; equivalent'.

i or superior. to those of the1specified. method.

Because a.more; stringent examination,will'be perfohmed, the Licensee;will'be" in accordance with IWA-2240.of/Section'XILof'the Code by performing the ultrasonic examination on these welds to detect' IGSCC in lieu of the' standard Code volumetric' examination,for.

Examination Category B-F (Item Nos; 85.10, 85.20,land B5.130)1

]

and Category: B-1 (Item.Nos. B9.10.. and 89.30).

==

Conclusions:==

Based on th'e above eval'uation, it"isJconcluded that a more stringent examination will be performed'and.the I

Code requirements will be met.

Therefore,- relief is 'not required.

3.5.2 Exemoted comoonents j

3.5.2'.1 Reauest for Relief No.-R10. Exemotions for Class 3 pioino Code Requirement:

Section XI,; paragraph IWD-2610l states that the pressure retaining components within the boundary of each system specified in the Examination Categories of Table IWD-2500-1 shallibe ' subject to visual examination (VT-2) of IWA-2212.in conjunction with the sy' tem pressure tests'of

.)

s t

IWD-5000.

The visual examination shallJ be performed at the a

{

frequency specified in Table IWD-2500-1.

Licensee's Code Relief Reauest:

Relief is! requested from'-

performing examinations'on Class 3. component connections,'

d piping, and associated valves and. vessels-(and their. supports).

1 a

that are 4 in.' nominal pipe size and' smaller.-

-l Licensee's Prooosed Alternative'Examinatio~n:- The criteria cif '

1 IWC-1220(d) of the,1974 Edition through Summer 1975 Addenda of Y

.x

.a

.am D,.~- )

s i;.

i 34 a i,

i' 7

g.-

7. -

g 4

m Section :XI willibe _usedffor exemptionsifor[Classs3 pipingT j

U Licensee's Basis for Reouestina' Relief: ?Since-thej980l Edition"

'h

.through' Winter 1981' Addenda'ofSectionXIJdoesInot::addressL AV exemptions'forTClass'3Lpiping,the1 criteria.off!WC-1220(d)}ofy A

the1974; Edition.throughSummer1975.AddendaofSsetionXI!will l

' t be: used. : Specifically,- component-con'nections',: piping;?and j

~

associated; valves andLves'sels((and theirl supports) th'at[arej 4:in'. nominal pipe: size and: smaller are' exempt from

+

examination.. Items exempt from examinationiwill beLexaminedL during the, additional inservice lt'est, :as 'specified)inJ 1

'4 Section1.3.6:ofthe;ISIhprogramplanfor?Coolingwatensyhtemsl

'and"during the hydrostatic testifor.the' Reactor? Core:Isolatibni Cooling (RCIC).

a tg i n Evaluatio2:

IWC-1220.exemptscomponent" connections [ piping,-

.And.associatedvalvesandvessels.(andtheirJsupports);that'a'rer 1

4 in. n'ominal pipe' size and. smaller from;the1volumetriFandJ m

surfaceexaminationsbutdoesnotexempt?theClassl2 pipings from the visual examinations.

Since. the exami. nations: required; for Class. 3. pip _i.ng within the, system boundariesiof/ Examination

. Categories D-A, D-B, and D.C of TableTIWD 25001? are: visual 1

1 l'

examinations'(VT-2'and.VT-3)t, the ' Licensee should inotiexempt.

these components from examination per IWC-1220,, Requiring the Licensee to perform.the' Code-required exanJinationsion the' N-Class 3 piping would not result' in' hardship.'

==

Conclusions:==

Based on the above evaluation,.it-is concluded

~

that the Class 3 piping should.not belexempt fro'm;the' visual examinations per IWC-1220.and:that' imposing the Code requirements would not result. in -undue hardship.. Therefore,Jit l

is recommended that-relief be: denied.

~;

o i

'i l

5 l

a M

38 l

W

7

~

q yd

-w

' T

", 's, gm y n y

. :g; 4

f-A

'I t

.i i

1 r'

i 3.5.3: athgp hy

,,j' p

3.5.3.1: t Reauest for Relief ~No. R8; Examination (Cateoorv F-C; Comooneritt '

l l

TAl'l' Class 1~.2. and 34 Snubber's)

M Standard Sucoorts 2

4 c

,' q 1

j m

y' M

CSde Requirement:1 Section XI,7 Table)IWF-2500-li Examination

~Categt.*y F-Cf(Snubbers lonly Item Noss F3.10F F3;20F F3.30,: '

on

.;a 1

F3.40,.andF3.50),lItemsF3.10,F3:20/F330,fandLF3305 require 1

~

avis'uaN(VT-3)examinationJasl:definedibyIFigure:IWF-1300-1,4' j

~

~

L

'of mechanical.connectionsito' pressure-retaining: components and;

.a t

w

~

?

buildingistructure(F3.10), weld; connections to ? b'uildingi structurel(F3.20),1 weld and mechanical connections ati intermediate jointsfin multiconnectedlintegra1 Land [no'nintegral; j

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supports l(F3.30), and componentidisplacement settings.of; guides?

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.y and st op's, ' mi s al i gnmen t o fi s upports, ; a s s emblyL ofL supportt i t ems ?

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(F3.40); Item F3.50. requiresEa' visualj(VT-;4) examina' tion,i as s;

definedbyFigureIWF-1300-1LofspringLtypelsupports', constant:

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load type supports,ishock' absorbers,<hydraulicLand mechanical-1 L

type snubbers; IWF-5000 contains the*inserv. ice test l

L requirements forEsnubbers.

l Licensee'.s Code Relief Reauestis LThilicenseeireques'tsirelief? <

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-a

1. q from the : inspection requirementsioffTable IWF-2500kl,;

ExaminationCategoryF-C(Snubbers lonly5-RItemNos.;F3]IO,.

L l-F3.20, F3.30, F3.40, and F3.50).and:IWF-5000,fInservice-Testing for Snubbers.

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Licensee's Proposed Alternative'Examinationii The; inspections-b required by the Code, as stated.above, will.be performed ini

-accordance'withtheJamesA.FitzPatrickT'echkicil?

- Specificat. ions.

1 Licensee's Basis for Reauestina Relief: 1The Technical' Spec ~ifications, ; Amendment' No. 592 ! toffacility _0perst'ing. Licensei.

No. DPR-59 forl the James A. FitzPatrick' Nuclear. Powerf Plant,t hasbeenapprovedbythe.NuclearRegulatoryTCommission,ina-s

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letter dated Mayf29,11985?(Reference'14); lThe;Technica1L Specification's'regardingisnubberftestingLan(the[Sifety:

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Evaluation;by: t'h' ' Office 'of NuclearlReactor! Regulation; ar'e i

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~ ttached for. reference inL Appendix D.:of thelISI6 program plann a

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. This: amendment'; revised the Techni.ca16Specificationsipertaininga to.the operability:andfsurveillahce. req 01'rements for hydrau'lic)

~

and-mechanicalisnubbers.

The Licensee:stateslthat the' 2

Technical: Specifications are;moreFcons'ervativefin.bsthi

. inspections required ~and;samp_ ling criteria"th'an ASME:

'I

. Section;XIf IWF-5000 and. Table IWF-2500-IL:(Examination Category F-C)..

m Evaluation: LThe Licensee'sLs~ubmittal thastbeen reviewed:

including the;11stingL of Lsnubbers,.thef referenced. lett'er, L andh the. snubber section 'of the subjeht Technical.5 Specification.

. Per IWA-2240,' " Alternative Examinations,"filternative examination methods,;a combination of methodsk or. newly developed techniques may be: substituted for the' methods?

specified iniDivisi'on l'of-Section.XI,Lprovided the' Inspector-

'is satisfied that the resultsLare demonstrated to be equivalent

. or superior; to.those of the specified methodi i

The use of the Technical Specification lfor:the examination of

^

snubbers is equivalent to the Code requirements and, therefore,.

in accordance with IWA-2240, is an acceptablesalternative.

NOTE: -Functional tests are not1within the' scone of this-document and will -be evaluated' elsewhere. Therefore.'the

?

J section of this relief reauestsiAvbivina functiona1 testina of' snubbers is not' included 'in this' evaluation.

~

~

Conclusions-Based 'on the above evaluation, fit is concluded!

that the' proposed alternative examination. is~ e.quivalent to(the -

. Code' requirement and, thus',f providesian:acceptableLlevel ofd inservice: structural integrity ihersfore, fit 1"s recommended j that: relief be granted forJthe visualjexamination only...

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M.5.3!21 Reauest for Relief No'.LR16; VT-4 Eiasination' of' Co'moonent' ?

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j Code Requirement)

Section XI,(TableTIWF-2500-1, examination:

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- CategoryF-C,!ItemF3.50requirestavisualL(VT-4)fexaminationn

. asdefinedbyFigure.IWF-1300-1,LoffspringRtype"s'upportsy constant-loa'd types'upports, sho.ck absorbers,Lhydrauliciand:

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mechanical type snubbers.-

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IWA-2214, " Visual Examination VTf4,"; requires? that: f(a')f The.

VT-4 visual ex' amination; shallebe conducted to. determine?

conditionsrelatingtohtheoperabilityof' components <or?

devices, such 'as. mechanical e and. hydraulicL snubbers,l components w

supports, pumps, Lyalves,iand. spriingfloAdediand constant weight; 4

7

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hangers; and (b) The.VT-4iisual!examin$ tion'shallic'onfirm~

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functional ' adequacy, verificationtofsthe set' tings,for? freedom of motion.

This _ examination may require!(1) disassemblyTof3

.componentsordevicesand-(2).operabil_1tytest.-

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Licensee's Code Relief Reauest:1 The Licenseejrequest's) reliefs I

'O fromtherequirementsofilWA-2214(a);andf(b)fof)thelASMEl Code -

and concurrently Examination: Category: F,-C,JItem No2F3;50;of -

Table;IWF-2500-1.

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Licensee's Pronosed Alternative Examination, A VT' 'd

- examination on. component supports-(Item'F3150)4 111'only be' performedwhenthecomponentLisidisassemblekformaintenance-U Snubbers will be functionally. tested in accordance with Section -

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1.3.5.2 (Technical, Specifications)Lof the ISIirogram p1an. -

y Licensee'sBasisforReauestinaRelief:4!During}theperformance of visual inspectionston. component" supports -(i.e.Lspring-loadedi and' constant-weight hangers), verification off the 1oad?

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settings,- functional. adequacy, and < freedom"of motion;

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inspections will'be performed withoutfdisassembly o'flthel,

componentsupportor.withoutLanoperabilityftest(wliidhlmaybet 2]

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x' required. as ! stated ?.inilWAf 2214(b)(1)' and !(2)$:.

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- The-Licensee states >that-(the TechnicaliShecif'ications are more;

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o conservativeLin both inspections'requiredLandisampling criteriai H

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thanASMEISectionXI,IWF-5000!andTablef!WF-25004

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Evaluation:

The Licensee's submittal hasibeen reviewed,:

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includingthesn~ubberlsectionofLthe-subjectTechnicalf Speci fication. -

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s Per.IWA-2240,'" Alternative Examinations," alternative examination methodsg:a combination,of.. methods, lor'newlyL

- developedtechniquesmay;belsubstN0tedfor)themethodst o

specified in' Divisio'n 11of Section;XI,[provided: the Inspector, c

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' is satisfied that'the res'ults:are demonstrated to be:equivalen,t:3-l

- or superior to those of thespecified method.

j The use of the James!A..FitzPatrick TechnicalLSpecifications

~

i for the examination of snubbers is equivalent ~to the-Code; requirements and, therefore, iniaccordance withflWA-2240,.-is an-acceptable alternative...

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Conclusions:==

-Basedonthe:aboveevaluation,Titis?concleded[

1 4

that the proposed. alternative.examinatio.n.is equivalentito the' o

Code requirement and,' thus,-provides aniacceptable levelisf n

inservice. structural integrity.

Therefore,LitiisLrecommended:

that relief be granted as! requested..:

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4 14; CONCLUSION" n

Pursuant.to 10 CFR.50.55a(g)(6),(it has?been determined that,certain;Section XI. required inservice examinations are impractical.::Infthese.. cases,-

the Licensee!has demonstrated that;eitherLthe;proposedialternativesLwouldl 1

provide an' acceptable levelJ offqualityf and safety. or that compliancefwith:

~

a

.the requirements would: result inLhardships'~ or unusual' difficulties without a'

^

compensating increase;in the'1evel of' quality and~ safety.-

4 This technical evaluation has not identified any practical, method b kich.

the existing James A.~FitzPatrick N'uclear Power Plant canTmeet al'11the-d

?

specific inservice inspection requirements ~of Section X'I'of the ASME! Code.-

Requiri.n'g compliance;with;all the exact Section XI required inspections:

would require the redesign-of a.'significant numberLof plant systems, obta'ini

- sufficient' replacement' components,l install the new components, cand' obtain a; baseline examination of these components.' ' Examples of components that woulds e,

require redesign'to meet the= specific-inservice examinatio'nLprovisions arei reactorpressurevessel,.CR0 housings,-containment" penetrations,andClass13 cooling water system piping.. Even'after the: redesign. efforts, complete

~

compliance with the'Section.XI examination, requirements <proba'bly could not:

be achieved. = Therefore, it is concluded'that?theTpublicLinterestfisk not ?

g, served:by imposing certain provisions of 'Section XI of th'e ASMEiCode that-have been determined to be impractical.

Pursuantto10CFR.50.5'Sa(d)(6),

relief is allowed from these requirements.which'are impractical' to; J

implement.

H The development of new or improved examination techniques will' continue tof eonitored.

As improvements in'these.areasLare achieved, the..NRC may require.

that these techniques be incorporated in the next-inspection'-interval ISI program plan examination. requirements.-

l BasedonthereviewoftheJamesA.'Fitz'PatrickNuclearTPowerLPlantSecod1 10-Year Interval Inservice Inspection Program Flan,: Revision'0,' the.

1 Licensee's response to the NRC'.s request'for additional..information, Land the' recommendations for the granting of' relief from theLISI:ex' amination requirements. that have.been determined to be : impractical,: itLhas been j

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concludedth'at'thESecond'10-Year.Inte'rvallInservicejinspection; Program?

f P1an, Revision 0, 'for;[ James?A.'- FitzPatEick' Nuclear Power Pl. ant,iwith the

- exception of Requests for Relief Nos.7R5A,; R7, -and 'R10, tis' acc'eptable and 1n 1

compliance with 10 CFR~50' 55a(g)(4)'..

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5. PREFERENCES 1.

Code of Federal. Regulations, Volume 10, Part ~50.-

'2-

American Society.of Mechanical Engineers' (ASME) LBoiler!.and LPressure Vessel Code, 'Section XI, Division '1p1980 Edition through' Winter:1981 Addenda ~and the 1974: Edition through Summer 1975 Addenda, including 1 '

H

~

Code Cases for Nuclear Components.

o 1

3.

Letter, J.C. Brons [New York Power"AuthorityL(NYPA)] to D.B. Vassallo-(NRC), " James A. FitzPatrick Nuclear. Power Plant Second'10 ' Year

. Interval Inservice Inspection Program Plan,' Revision 0," submitted September 30, 1985.

4.

NUREG-0800, Standard Review Plans, Section 5.2.4,'" Reactor Coolant Boundary Inservice Inspection'and Testing," and Section 6.6, " Inservice 1 Inspection'of C1 ass.2 and 3 Components," July:1981.

5.

Letter, H.I. Abelson (NRC) to J.C. Brons (NYPA), " James' A.' FitzPatrick' Nuclear Power Plant Request for Additional Information' on Second) 10-Year Interval Inservice Inspection P.rogram Plan,".~ dated _

'l July 11, 1986.

6.

Letter, J.C. Brons (NYPA) to D.R. Muller (NRC), " Response to the'NRC's Request for' Additional Information on James A. Fit: Patrick Second.

q 10-Year Interval Inservice Inspection Program Plan," dated-August 27, 1986.

7.

Letter, J.C. Brons-(NYPA) to D.R. Mullar (NRC), " Revised Relief ~

1 Requests for the James A. FitzPatrick Nuclear Power Plant =Second 10-Year Interval ISI. Program for Welds and. Supports," dated-December 8, 1986.

8.

Letter, J.'C. Brons- (NYPA) to D.R. Muller '(NRC), " James A. FitzPatrick '

Nuclear Power Plant Intergranular. Stress Corrosion Cracking Inspection Plan for the Reload 7/ Cycle 8 Refuel Outage," dated October 28,;1986.

45 P

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. y Letter,:J;C.(Brons](NYPA)ftoD)R.cMuller(;(N'RC),"lJamesA(FitzPatfick1 L 9.'.

Nuclear Power Plant Intergranular! Stress CorrosioniCracking Weld'-

,,H 4

Ins'pectionLProgram,"LdatedFebruary'5,jl987..

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10. - NUREG-0313, " Technical; Report 'on Mitiefia'lf Selection and Proce'ssing -

'l Guidelinks(forlBWR Coolant \\ Pres'sure Boundary Piping,"lRevisioh[1,--.

July ~ 1980.'-

0

> d N

ll.

NUREG-0803, " Generic Safety Evaluation'ReportLRegarding. Integrity of i d

q

'BWR Scram System Piping,"JAugust:1981.

- o e

l 1

12.

Inspection and Enforcement Bulletin,83'-02,_ " Stress Corrosion Cr:acking w,

~

in.ilarge Diameter Stainless Steel Recirculation System _ Piping-;at BWR:

1 Plants," March 4, 1983.

~

1 13.

Generic Letter 84-11,." Inspect'ionsLof.BWR Stainlessi Steeli Pipiag,"

April'19, 1984.

f 4

J l

14.

Letter, H.I. Abelson-(NRC) to J.P. Bayne..(NYPA), " Changes-to the Technical. Specifications,"' dated. May: 29,: 1985..

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LeisuoGRAPHIC DATA SHEET.

' EGG-SD-7412:

H6 testinuCvio 4 o= fut htvenst '

E varti.=osweriv[all Evaluation Report on the Second 10-Year

Techni 2 68.vt OL. a.

' Interval. Inservice. Inspection Program Plan: 'New Yo'rk; Power. Authority, James ~ A. FitzPatrick Nuclear. Power:

. o.n.., co,a,,o

-Plant, Docket' Number 50-333:

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. March l '.

L1987

.. o.n...o.,imoio B.W. Brown,. J.D. : Mudlin.

. March' Ej

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H EG&G Idaho,.Inc.

1 P. O. BoxL1625.

' n = = = = =vas a 1

LIdaho Fallsi ID: 83415 J

FIN-D6022_(Project 5))

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io s,onsoa.=o ono.=a.tio= =..e =o...v o.oomsss <

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n.tvesosne,omt Division of: BWR Licensing-Tecnical:

H Office of. Nuclear. Reactor Regulation U.S. Nuclear Regulatory Commission Washington,'D.C.' 20555 is eu,,u u.av oru j

,u..,..at a This report presents the results of the evaluation of the. James.A'. Fit:DatrickL Nuclear Power Plant'Second 10-Year Interval Inservice Inspection (ISI). Program Plan-through Revision 0,' submitted September 30,:1985,- including the freguest'; for relief-from the ASME Code Section XI requirements which the Licensee has detJrmined:to be.

impractical... The James A.. FitzPatrick Nuclear Power? Plant Second:10-Year. Interval:

ISI' Program Plan is evaluated in Section12 of-this report. The ISI Program Plan is evaluated for (a) compliance with the: appropriate edition.of.Section XI, (b) acceptability.of' examination sample, (c)Lexclusion: criteria; Tand (d) complian'ce with ISI-related commitments 2 identified during the NRC's. previous. PSI'and ISI; 1

reviews.- The requestsL.for relief.fromLthe ASME Code-requirementsLwhich the Licensee H

has determined to be' impractical for the second.10-year -inspection; interval' are evaluated in Section.3 of this report.

i i s...,6.e.,.ut,

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i. occu.e=t.=.6nis.. ma rwoaosioascai, tons sv.n. a

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[<x M

y" i iMr.? John Cb Brons'..

James A. FitzPatrick Nuclear? '

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Powerz Authority of'the State of New Yore Power Plant F Wl 4;

cc -

.Mr. Jay DunklebeFgerl..f.

Mr. Gerald C. Goldstein:

- Assistant.GeneralfCounsel Divistori:of Policy Analysis-t

. Power Authority of the' State _

..;and Plannino

• d of'New York:

1 1New York State: Energy Office

10. Columbus-Circle.

LAgency, Building 12" ~ '

' 5:.

<j NewiYork.New. York.~10019..

. Empire - StateL Plazal h

+

' Albany, New: York; l12223J o

~ Resident Inspector's Office-L...

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. U. S. Nuclear' Regulatory Commission Region'al Administrator, RegionEI i

' Post Office Box 136 U.S. Nuclear Regulatoryz Connission,L Lycoming, New York. '13093..

'631LPark Avenue

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King of. Prussia,a Pennsylvania '19406f F

a 1'

Mr. Radford J. Converse-t Mr.. A.: Klausman?

4 1

Resident-Manager Senior Vice' Presiderit -1 Appraisal 9

James A.- FitzPatrick Nuclear-

.andiCompliance'Servicesi'

'4 Power Plant Post Office :Boxi 41.

-Power' Authority of the' State'

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C

'of NewlYorkJ'

?

Lycoming, New York 13093 10 Columb'us Circle f

New York, NewLYorkT1100194 y

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Mr. J.' A. Gray, Jr.

'Mr~ George WilverdingL Ma~ nager' u

Director Nuclear Licensing - BWR..

. Nuclear' Safety Evaluation'"

Power Authority of the State Power Authority.'of the~ Statei of New York of New Yorke.

123 Main Street 123 Main Street White. Plains -New York 10601

. White Plains,.New York?!!0601 Mr. Robert P. Jones, Supervisor

.Mr. R. E.KBeedlet.

Town of Scriba.

Vice President l Nuclear SupportL

^

R. D. #4 Power? Authority.of:the State Oswego, New York 13126

.-of New. York: ~

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123 Main. Street:..

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Mr. J. P. Bayne, President White Plains, New York :10601 Power Authority of the State of New York

.Mr. S.;S) ZullaL'

- 10' Columbus' Circle Vice' President Nuclear Engineering-New. York, New York 10019 Power Authority of the State' of;New York e

Mr. Richard Patch 123 Main'Streeti Quality-Assurance Superintendent White. Plains,: New York'.10601.

' James A..FitzPatrick Nuclear

-a Power Plant-.

Mr. R.-Burns-

t..

d Post.0ffice Box.41

Vice. President Nuclear,0perations!,

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.Lycoming,-New York 13093 PowerAuthority~ofthelState?

u of New York' 123 Main l Street-

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, White Plains, New. York L106011 -

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