ML20128C371

Summary of 760602 Meeting W/Mark I Owners Group in San Jose, CA Re General Guidelines for Defining Failure for Each Structural Failure Mode Being Considered in plant-unique Structural Analyses

ML20128C371
Person / Time
Site:	Monticello
Issue date:	06/16/1976
From:	Guibert J Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9212040374
Download: ML20128C371 (11)

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UNITED STATES g[ paato \]

NUCLEAR REGULATORY COMMISSION WASHINGTON, o. C. 2o665

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JUN 1 6 576 DOCKETS N05.: 50-237, 50-245, 50-249, 50-254, 50-259, 50-219, 50g/ 50-265, 50-271, 50-277, 50-278, 50-298, 50-260, 60_263

- 50-296, 50-298, 50-321, 50-324, 50-325, 50-331, 50-333, 50-341, 50-354, 50-355, and 50-366.

LICENSEES: Boston Edison Company, Carolina Power 6 Light Company, Commonwealth Edison Company, Detroit Edison Company, Georgia Power Company, Iowa Electric Light 6 Power Company, Jersey Central Power 5 Light Company, Nebraska Public Power District, Niagara Mohawk Power Company, Northeast Nuclear Energy Company, Northern States Power Company, Philadelphia Electric Company, Power Authority of the State of New York, Public Service Electric and Gas, Tennessee Valley Authority, Vermont Yankee Nuclear Power Corporation.

FACILITIES: Oyster Creek Nuclear Generating Sta-ion, Nine Mile Point Unit 1, Pilgrim 1, Dresden Units 2 and 3, Millstone Unit 1, Quad Cities Units 1 and 2, Monticello, Peach Bottom Units 2 and 3, Browns Ferry Unit 1, 2 and 3, Vemont Yankee. Hatch Units 1 and 2, Brunswick Units 1 and 2, Duane Arnold Energy Center, Cooper, Fitzpatrick, Enrico Fermi Unit 2, and Hope Creek Units 1 and 2.

SUMMARY

OF MEETING HELD ON JUNE 2, 1976 WITH REPRESENTATIVES OF THE MARK I OWNER'S GROUP On June 2, 1976, a meeting was held in San Jose, California with l representatives of the Mark I Owner's Group, General Electric Company l

(GE), and their technical consultants. The purpose of the meeting was l to discuss general guidelines for defining " failure" for each structural failure mode being considered in the plant unique structural analyses.

Enclosure 1 is a list of meeting attendees. Enclosure 2 contains the meeting agenda.

1 i SUMMAPY l W. E. Cooper, TELEDYNE, described the methods which he had developed on behalf of the Mark I owners Group for computation of the plant unique structural element capacities of structural components in the torus l

support system. A detailed description of these methods is contained

! in Enclosure 3. General discussions between the NRC staff and the representatives of the Mark I Owners Group resulted in substantial 9212040374 760616 PDR ADOCK 05000263 P PDR

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- - - o JUN 1 6 676 agreement on the acceptability of the above mentioned analysis methods.

Several items requiring further clarification were identified:

a. Utilization of a strain ratio in place of a load or stress ratio should be limited to specific structural components (i.e. , anchor bolts, pipe hangers, and sway braces),

b. Strain-rate effects which could potentially result in a non-conservative transference of load from one structural component to another must be considered,

c. When utilizing the procedures of Appendix F to Section III of the ASME Boiler and Pressure Vessel Code, a 0,75 factor should be applied to the strain limit curve to determine the useable ultimate strain for an inelastic analysis,

d. The short term pI; gram plant unique analysis must be based on the plant structural configuration as of the date that the plant unique analysis is submitted to the NRC.

c. The plant unique analysis must also be based on the plant operational conditions which will be in effect after the completion of the short term program, e.g. , with or without continued AP operation.

The Owners Group agreed to document the information presented at this meeting, including the clarifications identified above, in a revision to hVTECH Report MKI-02-012, " Description of Short Term Program Plant Unique Torus Support Systems and Attached Piping Analysis".

The NRC staff stated that all structural failures predicted by the plant. unique analyses must be reported, even if such failures do not lead to loss of containment function, In addition, the NRC staff stated that, if a facility does net meet the plant unique analysis acceptance criteria and a significant structural modification is required to restore adequate safety margin, such structural modifications should be designed to the applicable Code requirements.

N John C. Guibert, Project Manager Operating Reactors Branch #3 Division of Operating Reactorr e

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- 3- JUN 1 6 676

Enclosures:

1. Attendance List

2. Agenda

3. Letter from W. E. Cooper to R. H. Buchhol:, dated May 21, 1976 1

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s ENCLOSURE NO. 1 ATTENDANCE LIST l

MEETING WITH MARK ~I OWNERS GROUP 4

JUNE 2; 1976 GENERAL ELECTRIC COMPANY NPPD R. W. Buchhol: R. P. Lovci

! L. V. Sobon

, W. Z. Masters NRC STAFF i BECHTEL POWER CORPORATION G. Bagchi B. D. Liaw B. S. Shicker D. G. Eisenhut C. Y. Wang R. J. Stuart J. C. Guibert KAISER ENGINEERS D. W. Ogden I

DECO /TRC F. E. Gregor i

NUTECH f N. W. Edwards l R. E. Keever TOSHIBA K. Saba

! Y. Sunami HITACHI H. Ukaji A. Nishimura CHICAGO BRIDGE 5 IRON COMPANY-R. F. Reedy i

TELEDYNE t

W. E. Cooper

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ENCLOSURE NO. 2 MARK I CONTAINMENT PROGRAM TRC/NRC MEETING JUNE 2,1976 MEETING AGENDA

1) IDENTIFICATION OF STRENGTH RATIO / FAILURE CRITERIA FOR FAILURE MODES a) TENSILE COMPRESSION AND SHE R FAILURES b) FLEXURAL FAILURE c) STABILITY IN COLUMN, SHELLS

,. d) ANCHOR FAILURE e) BEARING FAILURE f) OTHER, AND COMBINATIONS OF AB0VE

2) DEFINITION OF OPERABILITY FOR a) ACTIVE PUMPS AND VALVES ATTACHED TO ECCS PIPING b) ISOLATION VALVES ATTACHED TO OTHER LINES c) OTHER(BELLOWS,ETC.)

3) ADDITIONAL ANALYTICAL AND EXPERIMENTAL TECHNIQUES WHICH MAY BE USED IF FAILURE CRITERIA (ITEM 1 AB0VE) IS NOT SATISFIED 4

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, - -._ -.-  %~s*1 j .,'* ENCLOSURE NO. 3 l i

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4 May 21, 1975 i 2006-9 J

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Mr. R. H. hchhol::

. Manaser. S;tcial Utility Pre;rrs j General Electric Cc:~aany - HC 2,33 "

4 175 Curtr,er isvenue l San ucsa, CA 95125 .

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) SJbject: Dr:ft Criteria for Cc 7Jiatica cf Str-Jctural Ele ent C3pscity (IRC-032) i

References:

l. Nutech F.eport El-02-012. 02scripti:n of Shcrt Term Progra-, Plart !5iaue torus Sup: ort Systc .s and Attached Piping Analysis, l'.ay,1976.

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2. TH?, letter 20.M -5. W. E. Ceaper to Pio Ianni,

, GE-B'.GFD, Recom01ded D:si;n Criteria for B'dP.

Mark I Suppre:sien Ch=12r and Supports-Revised, ,

March 1, 1976.

1 1

Dear Mr. Buchholz:

, Introduction

Reference i describes the analyt! cal' program associated with the Mark I Contain unt - Short Ranga Pr:gr:a - PISnt Unicue Analysis. It ccatains specific acceptance criteri: fer associated piping, excressed in ter s of an Se value as tabulated in 50: tion III and general li.-iting-criteria fer other porticas .of the torus and supports. The general lir.itino criteria are i expressed in ter ,s of satisfcctica of the appropriate Se tien III limits l (for dasica, nor al or usset cenJiticas) er are ex.orassed in terrs of a quantity defined as a stran:th r:tio (5.0. The cuantity SR is the ratio of the calculated stress'or str:in to that rescective value of stress or strain i

which would rasult in strue:urai failure of that nortien of the structure.

Note that structural failura ray cr rsy not result in loss of contair. ant.

. Analyses are cerf:r .2d for a set cf ic:ds t: be defined' by GE and. either 3 SR s 0.5 or tne Ccda rules cess te saticfied. In addition, sensativity analyses are to be parfor ad for certain higher lead values and either SR 51.0 cr the Coda rules ,must be satisfied.

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Mr. R. H. Su:hholz General Electric Cc ;any thy 21,1975 Page 2 The specific :;rp:se of this letter is to su;; cst netbeds for ec rutation of the di e-ine:or in ene SR ratio f:r censi:erati:n a: e n ' ?.0-T.'.0-9 E .'.E rieting to be held in Sen Jose en Wednescty, June 2,1975. Precaratice of th:se su; es:i:..s was rsatested at a TEC rcetir.; ci Pay 14,1370 Ea under-stand that ycu will arrange fer a meeting roca and inforn the attendees as to tir.e and placa.

General A 7 reach In additi:n to pipino f:r which seccific criteria are centained in Reference 1, tne ertihns'of tr.e contain cnt of interest to tha plant unic.ve analysis are the torus (shall plates and stiffening rings) and the torus supports (teru: attt:h. rant re the colcan hold-coi.n na-bers)gion, coitnns, coltrn base and, when oresent,The lead seistic, pressura differentiels within tha torus, and those tr:nsmitted to the torus via the ring header support colurns.

If the Section III rules for design, normal or unset conditions, as applicable, are satisfied in any portion of the structure, a specific SR valti need not be calculated. Vhen an SR value rust be calculated, the precise valuc need not be calculated as icng as the appropriate 0.5 cr 1.0 linit can be c:nservatively calculated. That is, ap;roxirate but cc7serva-tive.neth:ds ray be used to evaluate the denominators required for SR evalu-4 tion. Either analytical cr experimental rathods .rry be used to evaluate

.he denoninator. The valua r.ay be based uren oublished inforration which is sufficiently well cocumented to provide a basis for independent judgswnt j as to adequacy for the intended purpose.

I The following section of this letter describes some specific rethods which ray be'used to ceroute the denominator. It is not intended that accept:ble r.ath:ds are lirited to those included herein, caly that these included are acceptable. As general guidelir.es: ,

1. Yield and tensile strength values shall be taken from Section. III i unless higher values can ba .iustified on the basis of r.ateriass data for the spacific caterial, as frca picnt records.

2. No credit ray be taken for higher strengths as a result of strain rate ef fsets unless a

pecific strain rate is calcuisted und data for the a;plicable class of r. tcrials is applied.

i 3. lieither of the above effects'rty be censidered in cc ruting the S c

, valus applic:ble to piping. The Section III tabulated value must y be used.

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Mr. R. H. h:hholz ~ M General Electric Ccecany M3y 21, 1976 Page 3 4 P.:en ti terature r.aterial preperties r.3y be used for all 4 evalu3tions.

5. a. It is the intent of the plant unicue ar.31ysis that the plant con.'icuration and ~cenditions (e.g. , !?)

considered re::r:sent thesa aeplicatie at the tira the analysis is co 71etc. Credit .sy be taken for rodi-ficistions trolersnted prior to that tira, if acccot-able sa values are not attained, an ection plan rust be submitteJ to M.0 as d2 scribed by Ecierence 1.

b. Ta accepttble SR values and the rethods described in this letter a e applicable to rodificaticns inie ented prior to conlatica of the evaluation er cro;osed by the action plan. hwever, the fracture tcughness of any cdded materials rust be censidered in addition to the strength -

considerations described by Refarence 1. For pressure

. retaining r.aterials and racerials for ntnoressure parts or pads which are par anently attached by welding to pressure parts, the recuirer.ents of the Code applicelle to the initial construction or of a later revisien should be considered. As guidance in this consideratica fer support ratcrials:

3-(1) Faterials satisfying t.ke exemtion rules of Paragraphs AM-218.1 and Mi-213.3 of 52ction VIII, Division 2 are accentable without specific testing.

(2) F.aterials not exetsted for reasons of size or

- cceposition by NF-2311 (a) through (g) and which have a s;:cified ulti. ate tensile stren;th in excess of 125 ksi shall satisfy the re:;uire :ents of HE-2303,

c. In censiderina rodification , the utility ray choose to acoly more censervativa structural design criteria in anticio?.tien of Lcng Tern Procr:1 considara ticas. The draft Boundica Lenq-Term Criteria of Rafarence 2 provide guid:nce in this ccr.-idara-tion. (Mte, hexever, that the draft Short Tern criteria contained in Reference 2 are not censistent with Short Tem Program cbjectives as they have devaloped since F. arch.1,1976).

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Central Ele. :ric Co- any May 21, 1575 Page 4 9

Soecific "et%ds for C- utstic, e.' Str.':tur:1 - Eli e.t Cm:ity (SIC) ,

1. Podified *echtel crittria The r.sthods described herein asstre the ese of elastic stm :

' analysis ar.c are tce criteria crevic',: sly used by !? catel 4 the Short Tern Pre ra i mdif tad to ccccu .t for censarvat ---

inherent in the elastic cnalysis. The SEC cauatien cent..ns two ten s. T.. fir:t of these is a odifyin7 fact'r o for aralysis conservatisr.s,Aich is based eren infor- sl !;AC-GE-iutech-Ecchtr.1- "

TER discussiens of !!:rch 2. ii60. The second tem is the e.cantity used by Iichtel tiith- the 110*. factor for strain rate and prcperty I effects elininated,

a. Colu.n buckling SEC = (1/0.6) (Cole: n Research Ccuncil Static Capability withBendingCorrectien) e

=

(1.5)(CRCwithbendingcorrection) ,

The nu erator of Eauttien (4) of Section III XVII-2213.2 may be used to cc pute the CRC static capability.

3 XVII-2215.1 nay be used to considar the effects of bending.

b. - Colu n-Torus Vald Region Shear -

SEC = (0.'6/0.5) (0.57 S u ) = 1.2(0.57) Su = 0.68 Su where Su =.ultirate tensile strength

c. Ring Girder and Local Torus Shell SEC = (1/0.5) (Sj) = 2Sy

d. Pins and Lugs (1) For shear stresses, use SEC = 0.53 Su as in b, above.

(2) For bearino stresses " '

SEC = (1/0.6) (Su ) = 1.6 S u e

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Mr. R. H. Cu:hhol2

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. May 21, 1975 Page S

2. Accendix F "'tk. d The pro:edu 2s Of A::endix F cf S=ction III are intended to cssure that violation of a crossure retaining Octr.:ary will n:t c: cur.

Therefere, tne c: hods of F-1220 can de used to establish con-servative Structural Ele ant Cr.:acity (SEC) vali.es. The folle.fing provide guidance in applying the cethods of F-1320:

a. Ra F-1322, systen analysis considerations are not applic:ble to the plant u.ia:e analysis because the lo:dir.y are cen-servatively defir.ad. The "systens" analysis nich esteblished the loads was essenticily elatic, kt it is kn:wn that an elastic-plastic "systens" analysis wou!d have result-d in smaller icads. Therefore, tna rules cf F-1323 are not applic-able and the rules of F-1324 r.ay be used.

b. The equatica of the fom 5,, + (Su - S. )/3 cich at: ears five ~

places in the lcwar half of Tcble F-13,22.2-1 are devele;ed to assure that the r.3xim.n strain does not exceed ene-thirc of the unifom eicagstien of tre c:aterial. This lir.ic shall also be used as a strain limit in cenjunction with F-132".S. The' unifom elongation ray be taken as the strain hs.rdaning ex-

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ponent given as a functicn of tensile strenpn Oy the attached figure which is taken frc= Welding Research Council Eulletin 101.

c. In applying the collaose loed rethod of F-132$.2 to the ring girder, the guidance of Case 1733 shall be c:dsidered.

d. In the last colu n of Table F-1322.2-l', the reference to footnote (3) should be to footnote (3) and (6),

e. In Table F-1322.2-1, for the strain limit load, the sphol should be P 5 rather than PI .

3. Exoerirental .vathed l

Experimental r-ethcds ray be used in the ranner described by F-1321.3 to establish Pc, et, or et er to provide data with resrect to the inelastic res:5nse 'of a cE :enent. Lhen tnese values ar2 deterntned experir.2ntally, tre nultiplying ccef ficier,t less than Unity (0.3 for PC , 0.7 for PI and PS) in Table F-1322.1 ray be taken as ;nity. '

Very truly y urs.

TELEDYNE I'ATERIALS RESEARCH

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William E. Ccocer Consulting Engineer l WEC:raf l

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