ML20211D597

Forwards Summary of Independent Development of Finite Element Models & Determination of Natural Frequencies for Piping Problems in Containment Spray Discharge Line & Accumulator Loop 4

ML20211D597
Person / Time
Site:	Diablo Canyon, 05000000
Issue date:	04/11/1983
From:	Bezler P BROOKHAVEN NATIONAL LABORATORY
To:	Hartzman M NRC
Shared Package
ML20209C072	List: ML20209C071 ML20209C150 ML20211D519 ML20211D576 ML20211D597 ML20211D640 ML20211D663 ML20211D703 ML20211D744 ML20211D774 ML20211D783 ML20211D811 ML20211D833 ML20211D868 ML20211D885 ML20211D946 ML20211E007 ML20211E125 ML20211E373 ML20211E436 ML20211E515 ML20211E542 ML20211E561 ML20211E607 ML20211E650 ML20211F179
References
CON-FIN-A-3357, FOIA-86-151 NUDOCS 8702240055
Download: ML20211D597 (9)

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l 3.n J ,j . j 1,, BROOKHAVEN NATIONAL LABORATORY I~l 9ma1!'}

( .i ASSOCIATED UNIVERSITIES, INC.

Structural Analysis Division -

Upton. Long tsland. New York 11973 Department of Nuclear Energy Building 129 (516) 282x 2447 FTS 666' April 11, 1983 Dr. Mark Hartzman Room No. P-520-A Phillips Bldg.

US Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20014

Dear Mark:

The independent development of finite element models and the detemina-tion of natural frequencies for two piping problems from the Diablo Canyon Nuclear Power Plant Unit 1 (DCNNP-1) has :been completed. The problems evalua-tion were:

Containment Spray Discharge Line 265-8, PG&E Problem No. 8-118 Accumulator Loop 4 PG&E Problem Nos. 6-4, 6-7 The finite element model development was based on the infomation and drawings included in the Document Package for eac.h problem provided by PG&E. The ana-lyses were performed using the BNL developed PSAFE2 computer code and the BNL updated version of the SAP V computer code.

A brief summary of results is attached. This inc ludes a computer genera-ted drawing, a natural frequency; comparison table and a summary of comments for each model. The natural frequency comparison tables list both the BNL and applicant estimates of the natural frequencies for each problem. The comments summarize the bases for the BNL model development, dif ferences between the BNL and applicant models and those instances where information was extracted by CNL from the computer listings supplird by the applicant for each problem.

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Dr. Mark Hartzman April 11,1983 Computer listing information was primarily used to define those portions of problem 6-4, 6-7 beyond the scope of this study (Reactor System Primary Piping). However, it was also used if the desired information was not defined in the information package or that definition was inconsistent witn other data or dimensions.

As per the discussions with Jim Knight on February 15, 1983, pertaining to the analysis to be performed for these piping systems, BNL has now satis-fied the requirements for cor'innatory analysis of these piping problems (i.e. , Task 2, problems 3 and 4, FIN No. A-3357). If you want us to expand

• the verification efforts for these problems, please advise us thereof.

erely yours, ,

U i Paul Bezler, Group Leader Dynamic Response Evaluation Group PB:Jm

' Attachments (3)

ATTACHMENT-1 Problem 6-4, 6-7 Comments

1. Node labels taken consistent with Westinghouse labels. Relabeled for SAPV run.

2. Westinghouse model of reactor system, through node 4200, accepted.

Westinghouse computer listing used.

3. Dimensions from PG&E DWG's 437985, Rev. 2 and 446484, Rev.17.

4. ' Distributed mass model used (Westinghouse used concentrated masses throughout). .

5. -The definition of the bend defined by nodes 425 and 426 (SD bend, 6' angle) on DWG 437985 are inconsistent with pressurizer (1-4) centerline and accumulator (1-4) centerline locations shown on the same drawing. Westinghouse computer listing data (LR elbow,16 angle) are consistent and were used.

6. The vertical dimensions of the pipe run from node 4200 to 4006 on DWG 437985 are inconsistent. Westinghouse computer listing used.

'. Modeling differences noted:

a) Connectivity in vicinity of valve 8948-D adjusted to correspond to drawing.

b) Location of node 4462 adjusted to reflect 3-1/2" lateral offset of valve 8808-D CG.

c) Line of action of supports 12-99SL,12-98SL,13-27SL 13-30SL,13-31SL and 56N-49R adjusted to correspond to support drawings. Angular. changes of up to 10 r eq ui red, d) Stiffness of supprt 58N-60R increased from 4.17 x 105 to 4.17 x 10' to conform with PG&E submittal.

e) Wall thickness of valve 1-8818-D modeled as 2.154"(3t).

8. Insulation specification for line 1/S6/3847/6SPL from valve 1-8818-0 to 8 x 6 reducer (node 33) undefined. Westinghouse computer listing used.

9. Insulation specification for lines 1/S1/1297/10 and 1/S$/256/10 unde-fi n ed. Westinghouse computer listing used.

10. Elbow designations not shown. Westinghouse computer listing used.

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ATTACHMENT-2 Problems 8-118-Comments

1. Node labels taken identical to PG&E's lablels.

2. Five nodes (98,117, 245,. 270 and 442) added to reduce span lengths.

3.- All dimensions. frap PG8E DWG's 446540, Rev.11 and' 447117, Rev. 6.

4. Span length differ,ence of 3' noted between nodes 85 and 95 (BNL span la rger).

5. Span length dif ferences of the order of 0.3' noted in vicinity of. nodes 85,125, 205 and 270 (BNL spans larger).

6. The X coordinates of nodes 90 and 93, supports 98/4R and 55S/162R, . unde-fi n ed. PG&E computer listing used.

7. Support 55S/162R not shown.

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ATTACHMENT-3 Tables and Drawings 9

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PRC3LEM 8-118 FREQUENCY COMPARISON A

MODE FREQUENCY FREQUENCY (HZ)

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2 13 . 8 0 14. 88 3 20.09 21 . 17 4

4 21 .17 21. 4 0 5 21 . 3 5 22.98 6 22. 97 23.15-7 24. 24 24. 79 8 26 .68 28.01 9 29 .48 29.35 10 32 .04

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- " . ENGINEERING SERVICES fi2 ~83 MEETING ANNOUNCEMENT SU~I7f DEPARTMENT OCNPP-IDVP 8Y W.E. Cooper /J.Q. Cragin SUSJECT: DCP Piping Program

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45/8/C32 DATE: Monday, April 11, 1983 TIME: 10:00 - 4:00 ORGANIZATION TES, RLCA, OCP AGEfGA: 1. Welded attachments for large bore piping -

2. Welded attachments for small bore piping

3. Use of CCM-M9 and DCM-40 for small bore supports 4 Miscellaneous RFIs

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2. Welded attachments for s:.lall bare piping

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Recipients: G. A. Ibneatis H.R. Danton R.H. Engelten H.E. Schierling R.R. Fray

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APR 121983

s. Parela Vones City Clerk Office of the 7 City Clerk Post Office 'iox J21 San Luis Otismo,.relifornic 93406-0321

Dear :

.s. Vooes:

I an pleasen to respond to your letter of March 7,19.'13 to Chairnan Pallariino which t'as t'een referreo to m for reply. Your. letter transmitted Resolution No. Mr , which was aconted by the San Luis Obispo City Council, urc.Jnc the nuclaar r:eeulatory Comission to riefer the licensing of Diablo Canyen, Unit 1 until cormletion ef t"e reverification cror3ran <tna, associated safety studics and co nletirn cf all r. lent r.auf fications to safety related structnres, svsteis ani' ccoronents. Your letter also raised t..c areas of concern which et:. have a0'iressed separately in the [nclosure.

Fitn respect to tho ;!asolution, the I.RC Oroer of hovenber 19, 1931, clearly sets forth the rewirenents that nust bc Let and nrocedures that are to de follouec for the authorization of fuel loaoing. In Section 5 of Attacnoent 1, the Order states:

" Prine to authnrization to proccen witn fuel Iceding the 6.C shall be satisfieti W i t!' the resuits of the seiscic cesien verification proorar referred tn in paraore.pn 1, ano with eny plant ncaification rasultinc fren thct prograr trat nav he necessery rrier to feel louinr. T.% :.PC nay ir cose aoditional recuirer ents prior to fuel loading necessary to protact health and safety t.aser' ucon its review of tc pro.jraa cr any of tr.o it.fornation crovicee ey rol.E nursuant t o r a re' ra H. a. . This ce incitoc sar.e or all of the raouirerents caaci fiui in ti.e let te r to Pv.d. riotec he <e'eer 1",1W.-l . "

%r annrovel et a toc-sts n process for a <<ecision rer.+roiric reinstaterent et tho license cone not ecrnit any deviation frce these recuirer +nts.

Tt r arproval is lit.ited to the concept of two steps for cecisions renarcin ; .

reinstaterent of tre licensa, but it. ir no way restricted to the tar';ct scW.ili nropess ..v "w. . . At this t1re, NT and tK inceter W r.* c+sien vari ficet to rr-r .e (i.'.b) are pecvirin.. u.,.itr ..c- 4 tar tie- tr.

% for: of (.y i- am tal;. rr vr ts, interi. Wer*.ical r. .ets, W s+.cti a s nt tNir fin.31 rg. orts en tr.e verions f aats at S c ne ico verificati:".

46 rt. t.1theu ? s.r- inton- tc ivo t su.:s t tat ial i.ri j t ta nur eccisian te t~r rindin.;s, cer.clusions, anr, recr.v ence ur.us at im 1 n , er..i r & co'.c i t i r:n

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't. P cle 'ver:es review. De will .not be restricted in our o,<n review efforts by the snecific schecule prepcsed but will tal:e the tine necessary to a:ture curscrives anc the public that there are no deficiencies that would prevent safety-related strt'ctures, fUpCtions.

systens and conpenents fron perforaing their inteNec safety Let ne assure you that under no concition will we authorize the Diablo Caryon

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facility to begin oneration until we have reasonable assurance that the reblic -

i.ealth, and safety is adequetely protected. l' ore specifically t.c will rcquire a high. level of confidence that no sigr.ificar.t design or construction ocficier.cies I

effecting safety at any authorized level of operation exist at the facility cefore reaching, a decision to authorize that level of operation.

Sincerely, 4

(,,- .6 b Rarold P.. Centan, i irector Of fice cf biclear ?.eactor Seculation Enclesure:

• As stated

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Enclosure Response to Two Concerns The first c0ncern is that "the NRC recently adopted a licensing schedule which permits, restoration of the plant's license and fuel loading before the reverification progran is completed, before the results are analyzed, and before 'any corrective action called for in that program, if any, can be implemented." We have not adopted a licensing schedule, we have approved a process for reinstatement of the license consistent with the Commission Order.

The Comnission Order of November 19, 1981, which suspended the low power license, sets forth the requirements that must be completed prior to reinstatement of the license. These requirements relate to seismic analyses and design activities performed prior to June 1978 by PG&E and its contractors (i.e.,

service-related activities) and to the implementation of the cuality assurance program for those efforts. The activities associated with the Commission Order have become known as Phase I of the independent design verification program (IDVP) and will be completed in two steps. In addition, the NRC Office of Nuclear Reactor Regulation required PG&E in a letter, also dated November 19, 1981, to initiate an independent design verification effort of safety-related structures, systens and components with respect to seismic analyses and design activities performed af ter 1978 and with respect to non-seismic analyses and design efforts performed by PG&E and its contractors.

These efforts have become known as Phase II of the design verification --

program. By the Comm1ssion's approval of the program plan on December 8, 1982, the utility is required to submit a status report on all Phase II activities prior to any decision regarding restoration of the license.

Such work must be sufficiently complete to ensure that all major deficiencies were detected.

The design verification efforts for Phase I and Phase II are well underway.

The activities that we require now to be completed prior to a fuel load decision exceed tnose originally specified in our Order. We have expanded the program to include the following additional IDVP activities: (1) audit of the implenentation of the Diablo Canyon Project quality assurance progran (2) audit of a sample of quality assurance program implementation of construction activities, (3) review of the PG&E/ Westinghouse design interface, and (4) verification of the appropriate Hosgri and non-Hosgri spectra.

At the time of authorization for fuel loading all efforts required for reinstatement of the license will be completed except for nodifications to those structures, systers and componer.ts that are not required for Sten 1, in order to protect the public health and safety. In addition, the Phase II activities (i.e., non-seismic, safety-related analysis and design) of PG6E and the IDVP will have proceeded to an extent that will allow us to reach a conclusion with respect to any additional design verification that might be reouired. At this time the IDVP has completed its review of those structures, systems and conponents that comprise the initial sanple to be verified under Phase II. Prior to fuel loading, PG&E and the IDVP will both submit to the NRC a report on the status of their respective Phase II activities. Again, wE will require a high degree of assurance, at the time of a decision regarding fuel loading, that any further design verification efforts in the seisnic and ncn-seismic area will not reveal any najor deficiency in Diablo Canyon Uni t 1.

1 1

. . 1 The second concern is "the licensing schedule for the plant also has no provision foC,the completion of studies of three plant safety systems ordered by ,the NRC, nor for the analysis of those studies, nor for the implementation of their recommendations." The results of the seisnic design analyses that have been ongoing at Brookhaven National Laboratory (BNL) since late 1981 will be fully taken into consideration in the NRC evaluation and determination regarding the seismic design adequacy of Diablo Canyon Unit 1. The firht BNL-effort involved the containment annulus structure and selected associated piping systems and was documented in a report.

We have requested the IDVP to review this report, consider the results in its own design verification efforts, and provide us with its conclusions.

The NRC staff is evaluating the BNL report in parallel and will have the additional benefit of the independent view provided by the IDVP.

In mid 1982 the NRC requested continued participation by BNL to undertake a horizontal seismic analysis of the containment annulus structure, seismic and stress analyses of a buried tank, and additional analyses' of piping systems. The purpose of the BHL analyses is to provide the NRC with additional insight 'as to the character of results obtainable by use of current state-of-the-art analytical techniques without regard to methods or procedures -

previously approved ih the licensing process for Diablo Canyon. These analyses are therefore not intended as a substitute for the design and evaluation efforts now underway nor are they a substitute for the analytical effort being performed by the IDVP. Our experience has been, however,

. that such analyses often provide insights to assist in our review. The BNL analyses will be sufficiently completed and taken into consideration prior to any decision regarding restoration of the license.

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GREEN TICKET NO. 12914 DISTRIBUTION w/ incoming *

. Document Control (50-275/323)*

NRC PDR* ,

L: PDR* --

PRC System *.

LB#3 Reading G. W. Knighton B. Buckley .

M J. Lee

• D.'Eisenhut/R. Purple J.'L.' Jordan, DEQA:IE J. H. Taylor IE Attorney, OELD T. M. Novak/M. Stine M. Bridgers, EDO'(ED0#12914)

Correspondence Clerk, NRR (ED0#12914)

SECY (3)

W. Dircks J. Roe _

T. Rehm .

Engelken-G. Cunningham H. Denton/Ei Case PPAS T. Speis R. Mattson R. Vollmer H. Thompson P. Check Snyder.

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APR 13 333 The Honorable Douglas H. Bosco United States House of Representatives h'ashington, D. C. 20515

Dear Congressman Bosco:

1 I an pleased to respond to your letter of March 2'), 1983 to Chaiman Pallacino which has been refcrred to ce for reply. In your letter, you urged the kuclear llegulatory Com.ission to fully resolve the seisnic and other safety issues prior to the reinstatenent of the low power license.

As you know, the HP.C Order of Hovenber 19,1981, (copy attached) clearly sets fcrth the requirer.ents that cust be r.et and procedures that are to ::e fellc.ed for the authorization of feel loadinc. In Section 5 of Attachtent 1, the Orcer states:

" Prior to authorization to proceed with fuel loading, the hP.C shall be satisfied with the results cf the seisuic cesign verification progrep referred to in paragraph 1, and with any riant Ncification l

resulting frc, the precraa that nay be r.ecessary ;;rior to fuel leading.

l The id.C nay inpose additional recuire. ents prior to fael loccing necessary to pedtect health and safety based upon its review cf the orogran or any of the infornation providert by PG&E pursuant to para;raph

4. This nay include sor.e 'or all of the recuirerents specified in the letter to P6&E, dated Novenber 19, 1961."

Our approval of a t.;o-step process for a cecisicn regarding reinstate-cnt of the licensc tices not permit any deviation from these recuirerents.

j The a ereval is lirited to th concent nf t'en sites 4r ecfSirn: n treir-rs i r's t e t. e t c f t.': 11ce se, '.ut is in rc ..cy n3:ri.m  ; . - - -

-: +1r rrc.pn .e :'y NJ . I. tn i s t.i t .e , 1 3.' E a r. ' tt.e i n<.'. ..gno :nt . s t i p w r t :i c a t1;n progran (IDt?) are previding us .with nuch infer.7tien in t0h f e rn c f s e.-i :.n t .ly re; orts, irterin technic?l r:.Terts, er.d s.ectir,5 pf c' ir fi al rr ..r ts - -

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s e .c-stiens of the I'n F , er.Nr no ccnr.i tivr. ..ill . c c . . c. i t . r .: .. I . .a to - .

the ;: lice cf tF.c rac:ss ary anc Me<1uete "';C et /ic. . 'e t i l nr.: te rs r. : ri t y ir, cur c.:n revica ef forts cy tre specific scgcole pre: .u c M t s.ill ic. e tM ti:+ necessary to assure curselves ."d the ,melic '.'i t t' - re t re r.o (cficirt.cies that ect:Id prcvent St.ft ty-relati c. structores , 5,m .c93 v.r! cv ,. ots fron perforning their intenced safety fuoctions.

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%s The honorable Dougla's H. Bosco Let ne assure you that under no condition will we authorize the Diablo Canyon facility to begin operatien until we have reasonable assurance that'the public health and safety is adequately protected. Fore specifically we will require a hioh 16 vel of confidence that no significant design or construction ceficiencies affecting safety at any atsthorized level of operatien exist at the facility beforc reaching a c'ecision to authorize that level of eperation.

I bore this letter.provides inforration responsive to your concerns.

Sincerely, (Signed William J.Dircks William J. Dircks Executive Director for Operations

Enclosure:

As stated a

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GREEN TICKET #12946 DISTRIBUTION w/ incoming

• Document Control (50-275/323)*

NRC PDR* -

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PRC System

• LB#3 Reading .

G. W. Knighton J. Lee

• D. Eisenhut/R. Purple J. L. Jordan, DEQA:IE J. M. Taylor, IE L. Chandler ,

T. M. Novak/M. Stine M.'Bridgers, EDO (ED0#12946)

Correspondence Clerk, NRR (ED0#12946)

SECY (3)

• J. Roe T. Tehm Stello Engelken G. Cunningham L. Underwood PPAS T. Speis R. Mattson R. Vollmer H. Thompson Grace Snyder

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