ML17244A811

Summary of 790724 Meeting W/Util,Westinghouse & Gilbert Associates in Bethesda,Md Re Seismic Upgrade,Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts, Seismic Stress Analysis & Cracks in Feedwater Piping

ML17244A811
Person / Time
Site:	Ginna
Issue date:	08/16/1979
From:	James Shea Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
TASK-03-06, TASK-RR NUDOCS 7909170563
Download: ML17244A811 (21)

Text

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SUMMARY

DISTRIDUTIDM:

iIlIMINgm glllII/(Pnfl'. I-IIIIt Docket 50-244 Local PDR ORBPZ RDG NRR RDG H.

R. Denton E.

G.

Case D, Eisenhut R.

Yollmer'B.

Grimes L. Shao M. Gammill J. Miller M." Russell

.T. Carter D. Crutchfield D. Ziemann Y. Noonan Seismic Reviic Group A. Schwencer T. Ippolito R. Reid G. Lainas P.

Check R. Clark F.

Pagano G. Knighton J.

Shea OELD 01&E(3)

H. Smith R. Fraley, ACRS(16)

T.- Mambach J.

Mong P. T. Kuo U. Levin T. Cheng C. Hofmayer K. Jabbour J.

Glynn S. 'Hosfor d J. Fair R.

M. Klecker M. J. Collins R. A. Hermann J. Strosnider T.

H. Liu J.

B. Henderson J.

R.

Buchanan TERA II1gz/~'rriccW OVANAMCW DATCP

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LICENSEE:

Rochester Gas 81 Electric Corporation (RGBE)

.'ACILITY:,

R. E. Ginna Nuclear Power Plant d'UBJECT:

SUtNARY OF MEETING HITH RGSE NRC and RGSE representatives met in Bethesda,

Mary1and, on July 24, 1979'for presentations by RG8iE repardinr!:

o RGSE decision to upgrade. the Ginna Station Seismic Analysis

of Category I Piping Systems; o

RGSE responses to IE Bulletin 79-02, "Pipe Support Base Plate Design Using Concrete Expansion Anchor Bolts";

o RGImE responses to IE Bulletin 79-07, "Seismic Stress Analysis of 'Safety Relat)ng Piping - Algebraic Summation Error"; and o

RGRE responses to IE Bulletin 79-13, "Inspection for Cracks In the Steam Generator Feedwater Piping."

The meeting attendees are listed in Attach[gents 2 and 3.

The meeting progressed as summarized below.

~dr i i

d dd The RGSE decision to upgrade the Ginna Nuclear Power Plant seismic analysis of Category I piping systems and the seismic upgrading program were discussed by various RG&E representatives within, the context of the meeting,. outline provided by RG8E and included with

.this. meeting summary as Attachment l.. The RGSE representatives stated that the analyticalprogram and the potential resultant modifications will require three years for completion at an estimated cost of five million dollars.

The RG5E schedule for completion of the program follows:

r data gathering 5/1/79.started on initial systems outside containment.

'cope expanded and schedul.e. accelerated..upon receipt-.of IE Bulletin 79-14 and the Ju orrscc&

OUIINAMCW DATCW Crack.'ihspections.

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1 Rochester Gas 5 Electric Corporation AUG 16 1979

'/31/79 data from inside containment to be completed.

9/lb(79 following completion of inside containment data collection

," people wil'1 then be assigned to complete remaining systems

'utside containment.

All field inspections and sketches compl ete.

-. floor response spectra containment, interior structure, and RCS being modeled now.

10/1/79 floor response spectra for contyinment complete.

1/1/80 spectra for other'structures in program completeI..

piping analysis

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piping models and support stiffness work already 'in progress on some systems; e.g.

B-Main Steam, A-RHR.

1/1/80 analysis of'ystems inside containment complete.

1/1/81 analysis of systems outside containment complete.

modi fications Spring 1981 inside containment complete.

Spr ing 1982 outside containment complete.

2.

Pipe "Support Base Plate Oesigns Using Concrete Expansion Anchor Bolts - IE Bulletin 79-02.

RGSE presented additional information (documented by later RG&E submittal 7/26/79) to the July 6, 1979 response to IE Bulletin 79-02 which the staff concluded satisfied the intent of the bulletin.

3.

Seismic Stress Algebraic Summation Error Information (later documented by RGSE letter dated July 26, 1979) provided by RGEE in addition to that provided earlier by RG8E letter to NRC. dated April 25, 1979 was sufficient to satisfy the staff with respect to the requirements of Bulletin 79-07 for the three piping systems affected by the algebraic sumaation error, i.e. residual heat removal line - loop A, main steam line - loop B, and the char ging line.

4.

Cracks in Feedwater Piping - IE Bulletin 79-13.

RGGE discussed the feedwater system nondestructuve examination that has been performed, OI I ICa~

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Y4 AUG 16 1979 Rochester Gas 8 Electric Corporation metallurgical examination results to date, crack repair program, and the cause of cracking.

The crack indicators at the

-A and B

steam generator feedwater nozzle to pipe welds in the. base material of the 90 degree elbows that attach to the feedwater nozzle,. based on ultrasonic and radiographic examination,I, were.'described in detai3.

Crack indications were estimated to be 1/32 - 1/16 inch in dept) originating from the inside surface of the elbow.

The extent of crack indications on the "A" steam generator elbow are approximately 300 degrees around the inside circumference while the "B" steam enerator elbow is exhibiting crack indications around the entire 360 degrees) inside circumference.

Additional confirmatory information relative to the depth of cracks and results from the inspection of all other (18) feedwater pipe welds inside containment was presented.

No other cracks were detected.

The feedwater pipe elbows that contained the cracks (both loops) were replaced.

The information presented by RGSE which included preliminary results from more recent metallurgical analysis of the cracks was later documented by RG8E letter dated July 27, 1979.

The staff concluded that the RGSE responses to IE Bulletin 79-07 and the corrective action,'eplacement of 'feedwater pipe elbows,.-satisfy".the requirements. of the bil1letjg.

I Attachments:

As stated James J.

Shea, Project tlanager Operating Reactors Branch 02 Division of Operating Reactors CC:

See next page OrRICC~

DVRHAMCW DATC~

DOR:ORBP JJShea:s 8/g /79 DOR:EB VNoona IE HJ ong 8/ p/79 8//3'/79 DOR:ORB82 DLZiemann 8// /79 DOR:

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Rochester Gas 8 Electric Corporation 4

AUG 16 1979 CC

.Lex K. Larson, Esquire

LeBoeuf, Lamb, Leiby 5 MacRae

.1757 N Street, N.

W.

Washington, D.

C.

20036 Mr. Michael Slade 1250 Crown Point Drive

Webster, New York 14580 Rochester Committee for Scientific Information Robert E. Lee, Ph;D.

' P. 0.

Box 5236 River Campus Station

'Rochester, New York 14627 Jeffrey Cohen New'ork State Energy Office Swan Street Building Core 1, Second Floor Empire Stat'e Plaza

Albany, New York 12223 Director, Technical Development Programs State of New York Energy Office Agency Building 2 Empire State Plaza

Albany, New York 12223 Rochester Public Library 115 South Avenue Rochester, New York 14604 Mr. Leon D. White, Jr.

Vice President Electric and Steam Production Rochester Gas 8 Electric Corporation 89 East Avenue Rochester, New York 14649

Attachment 1

RGE Decision to U

rade Ginna Station Seismic Anal sis of Cate or I Pi in S stems 3 Year Pro ram Commitment Na 1979 Dynamic analysis of essential safety systems to current standards for dynamic analysis.

Modifications to piping as required to upgrade to new standard to extent practical.

II Basis for ori inal Seismic uglification Housner ground response spectrums

.08 @BE, 0.2 SSE with 0.5% critical damping.

r Equivalent Static Analysis of 2~~" and larger Cat I piping systems.

)plasmic DW press

A

+

S

+

S

< 1.8 S

Field run piping 2" and less to conservative B31.1 code spacing criteria for vertical and horizontal forces.

Design verification by dynamic analysis of 2 piping systems inside containment A RHR, B Hain Steam.

System walkdown by seismic Westinghouse,

GAI, RGE engineers, June 1969.

Documentation (minimal record keeping requirements of late 1960s).

0 Attachment 1

III Challen es to existin Seismic Anal sis Major Modification Programs (high energy backfits out-side containment.

1974, Standby Auxiliary System

1975, Spent Fuel Pit Cooling 1977)

Corporate Decision 1974 to design and construct major modification to current codes and standards

- Section 3 with dynamic analysis including structural response.

NRC seismic SEP review program (structures, equipment, piping) Independent review of original seismic quali-fication using current analysis techniques.

Current Regulatory Seismic Concerns.

IE Bulletins 79-02 Anchor Bolts 79-04',Velan Valves 79-07 Algebraic Summation 79-14 As-Built Configuration

Attachment 1

IV Benefits to RGE of Seismic U

rade Anal sis U

rade Pro ram Provides a consistent design basis seismic analysis baseline for essential Cat I piping systems for future evaluation during next 10 years.

Provides a level of design documentation for analysis and support design consistent with current practice and record keeping requirements.

Permit a systematic approach to development of design and analytical data versus chaotic efforts associated with current, and future bulletin concerns.

Provide seismic input data based on current system configuration to SEP evaluators (scheduled to maximize manpower productivity).

Provides consistent means of evaluation for future modi-fication requirements (i.e.

SEP, 3 Nile Island, High Energy Inside Containment, etc.).

Upgrades plant seismic design to current, industry standards.

Includes effects of soil-structure inter-action, structural amplification, higher damping values, multi-mode behavior.

Attachment 1

SEXSKXC UPGBSDXBV PEQGP~

M~SRC PKKTXSQ BKXHESOR, NB JUL'Y 24, X979' s~~am coutaixunmn<. an@ fn4mx'fox'~~x'e turbine, aexi1iaxy, imtexmediat e, cont.vol, cia.e'eel genaratox.'ui.lckixvgs sjetsaaiaaria ca<~gery" X. 2 1:J2~ aa6 Xaxger, main zmm cubi'.Meal. 2" ~tZan above stxucturea

. tiara pMgxhe - maim stean.

vein &edwater, aux feechrat~x'mv$.ce water',

ccmtainment. spray, aux spray.

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BOCA. ancX. yxge hxeak Sa f'atxgaa anaXyees Being perfoxm~cT 1

px'essmizm.

re%i;ef, vaLve cKscharge piping 8'tzuatax'aX AnaE xs met2xeCoriginal pI'anC. cbesign uti3.ized gxa~ad response spectra uggra8ing prolix'm vill use f3.oor response 53p&~S CX~Nt5.C L~ecX lk&ss Nod&I X

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Attachment 1

5 7'zkC&rco&xtecta6 btii3.6izlgs - ~bxlt6, auxiliary, iateraaediate

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gx'aud response spectra baaed, om..06g

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as: izxpat for general.in@ floor response spectra:

cKifferenMa1 cH:spXa~m~nte to be. cakcaX.at:ecX fox GBK cmly CX'L~CXB Rag. Cai8a X.66 reapcmee spectra R&g~~

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%lpga'88INg pxcgx'Blk wxll QsD'espoxlsP spectra

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x'RspQxts& Bpe~s vil1 cALv%'lope pQxILCs of p3 pittcf Glqpports 3D: 8+~A.c= macK~X X...

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effect. of reactor coolant, cysts. inc:lccda6 fQx 3;Rxcfo 8 Scowl I:1ocs 5, effect af. bxanr2a Jibes irxcluded with main.

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. Guide X.60 Ba~ping vaXues Ray Guide X 92 or REGLE 4'3; combinatioe o$ moda3.

responses crit;aria cXeveXopecf for aEX'ovabL'e Xoas3s on equ.ip-meaC, eedeZs valves'.: and bxaneh piping method:.original plant opponent supports ut.iI'i ed mann-factuzers; standards fabriwated. support;s designed and fabricated t,o AXSC'o8m uggxa8'in@ prcrgram WXX'I'nalytic support.s S.n 3 st ages X

caleukation oZ stiffne sea for p%;ping:

analyses 2

comparison. of new load's against. orig inaX 3.

redesign. ot existing sappozts a@8 Benign of new supports as zxecesaaxy eaBedments wj!X X be incXudei in c~X cuX;~ ting rupport sti;XSnesees aacX, evaluating integrity of'xist ing suer pox ts base plat:e fXexibiX'x.ty wx X X be incXudcd Xoading combinatioxxs evaluated wiXI 4e same as PxpiAg'

Attachment 1

F4~~ j.a AS'IX., Subsection NF st.ress criteria

(.1974 P-R~

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D.'eve'oacXs'zIcX',

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D~ KlRpparts acXcX: new" supports wZxere necessa~

to stresaea and equipment zzozz1e laacXe

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N~tkt'B3.n pipxng baal,ow at1o~ah3.e stru~cxres Xoc al macXi.fieaMo~reinEazcement.

o5 stmcturat st;eel ancX concrete where xnc xaasecX l,aade exisCio.g nece so~ fox',

j;so@cc&cs aa-built, Isometrics eon<atm.'ng aU. ~seismic inpixt'~

imformaMan dimensions, wale tMrkness, materials

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ancX cXetKLXe8 sCcees reports fax pi~os c orx'cspoxlcX VAR: iscBIkctx'xcs stresses:

at. each.. critic=al:. Zocati,on in piping system aupyo~

amcX: narz1e loacXe summary" repo~

aE support, analyzes coxyarisoxL oX'alcu3;ated values with code a13.owe5Ies aa-builds.t

. cXiamjags piping ort&ogx'aphic cixawi,ngs gxplR sDpjpo~ loc:Htx.on axkcX t9%t a.'L1 cXx'pwi'ocpx raCed: support 1.oaves f2;oor response spectra far each Ca<egory I atnxetne iael.uded in y-nizam a< X.oca~oxU-aacX eZ.emations of Cat go~ I pipj,ng ayatems; ancX mech-mi.ea3.

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Attachment 2

LIST Of ATTENDEES SEISMIC MEETING r

JULY 24 1979 NRC

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Mambach J.

Shea H. J; llong P. T.

Kuo L. C. Shao K. A. Levin T. M. Cheng C.

K. Hofmayer K. N. Jabbour J.

C. Glynn D. Crutchfield D. Ziemann V. Noonah S. Hosford J. Fair RG&E R. Neer edy J. Hutton R. Smith L. D. i<hite, Jr.

J.

C.

Noon Gilbert Associates K; T.

Momose P.

C.

Shah

~ti tt t R. J.

Sero bt.

S.

Lapay orrica3r.

OQAHANCW DATE~

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Attachment 3

LIST OF ATTENDEES PIPE SUPPORT PLATES 5 ANCHOR BOLTS A

EBRAIC SUtC4ATI N PIPE S

RESS ER OR FEEDMATER PIPE CRACK MEETING JULY 24

'1979 NRC J.

Shea

- R. H. Klecker bl. J. Collins R. A. Hermann J. Strosnider T.

H. Liu J.

B. Henderson RG&E R.

E. Smith J. Hutton, A. Curtis Mestin house D. Campbell C.

W. Hirst R. J. Sero,.

H. S.

Lapay T.

E. Capgbhll, T.

R. Mager

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