ML20080T013

Summary & Evaluation Rept of Rl Cloud & Assoc Rept, Idvp Valves

ML20080T013
Person / Time
Site:	Diablo Canyon
Issue date:	09/01/1983
From:	BROOKHAVEN NATIONAL LABORATORY
To:
Shared Package
ML20080S984	List: ML20080S989 ML20080S991 ML20080S994 ML20080S998 ML20080T003 ML20080T005 ML20080T009 ML20080T013 ML20080T016
References
FOIA-83-483 NUDOCS 8310180626
Download: ML20080T013 (4)

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w IkTRCDUCTION 0 -

The Interin T*.r.bnical ficport 37 (11R-37) was prepared t;y Robert L. Clour! .

and Associates (RLCA) for the Diablo Canycn Huclear Pcwer Plant Indepadent '

Design Verification Progren (OCfiPP-iDVP). The report serkrizes the independent analysis and verification of an initial sample of valves at the Diablo Canyon Pcwer Plant Unii.1. The verifir.at, ion results showed that the stresses for each of the valve samples':aet, the allnuobics defilled by the I fcensing criteria and no concerns were noted. ~

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SUMMARY

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", Tnolysis p:w and'~virlfication' of eidended structures in the 0C99-3. ~The valve semple consisted of the auxiliary fecdt<. iter valye FCV-95 and the atin steci isoletion valve FCV-41.. ._ ,;s . . _. - -

' ~ The auxiliary feeduater va'Ive' FCV-95 is a :autor acutated, four inch, gate va1ve teudted en the four lach auxiliary' recdeater line 760 in the Unit 1 Auxilluy Building. The valve ~is acunted in-line with the pipe anni has no-other support. The acutatnr consists of a electric notor anti t. tea r box ,

weighing 210 lbs. and having a cent.er of gravity located 26 in, above the pipe  !

ce nte rlir.e.

The main steam isolation valve FCV.41 cons hts of an assembly of two -

in-line, swing check valves udider! tosether. The aw.bly is raconted in and supported fran the 28 in, raain stean lead line number 228, whir.h is lccated en the pipe:cy structure outside of the Unit 1 Contatr.trent Psuil(ling. One of the sninS check valves prevents back flow of stem ir.to the. contairment structure.

The othe; check valve is controlled by a pair of pnetut.fc actuators i.tich bold the valve open during non::al eperation. The direction of ste'am ficw would : lose this check valve and prevent steam flmt into the plant then the actu6ters are depressert2eri. The two pressurizers are piston-cylinder asse7t-blies locatec' and supporteri en opposite sides of the valve assembly, E.:ch dctuator neights 454 lbs,

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Considering FCV-95, its physical dimensiet: and overall configuration -

were field' verified. Next a finite elecent ecdel, ruthetically represer4 ting  ;

the c.ess and stif fness charar.terist.tcs of the ahe yolk and actuator (extended structure) was develcpil. Using this redel the natural frequencies of the exterded structure were deter.airu:d to be in the rigid rar.ge (> 33 la),

since the extended structtire was rigid it was ceter.Tdnect that there were no amplificot tons in the strcture and thus accelerdtfons et the actuator are identical to those transnitts.d by the pipe to the vahe body. This value of qualification acceleration, 7.48 9 resultant, nas tden fren Table 7-7 of the  !

HosEri report, The qualification acceleration was then app!!ed as a

' equivalent static load at the actuator. center of gravity and valve loads, f do[rces end stre'sses were' deter'dilne'd'.{hil ' calculated stresses %ere fednd to be helw allmtable stresses as defined by tihe'llcensing criteria, ..

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- -strasses were below the alloGbles defined by the licdnsing criteria. - * ,

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A review and caparf son to the Pacific Gas t. Elec_tric design anilysis ror- ~ ~ ~ ' -

each valve was made. For each valve the deshr. anal.yssis ytes found to be ./;f .

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sufficiently different fron the verf fication analysis as to preclude i direcE '  :~

--ccmparison of results. In each ca.4e; however, the design anal.ysis involved -

%k ow u1 conservat'ive estbretes of qualification accelerations arid'e ch was considered conservative,

., As a rsstilt of this revipt three E0l's (950,1082 and 116) wre isst:ed.

E01950 was issued because scw dittensions of valve FCV-95 were incorrectly s pe cif f s.d, this EDI was closed when the valve was subsequently modified and-it was deterrined that all other specified valves confora to the design -

condition. E01's 1002 and 1116 were isst:ed because the design analysis results for each valve differed frc 1 the ve.rificatica analysis results by cure than 13. These E0!'s were cicsed beca'ise the des fun analyses were ceaserva-S ive and show.d all stresses to be belcw allcwables.

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EVALUATION /

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The procedures followed by htCA in perforif ng~ this tvependent analysis .

and verification are accepteble r.nd would be expected to reveal any deficicne,les in the 'PCME design analyses itvie: cd. The inronnation provided -

-in the report, however, is insuf ficient to allmt any judgeant of the correctness of the RLCA r.todels or analysis results.

Differences between the indeper. dent ar.d design anal.ysis procedures were said to preclude any direct compcicison of these results an<l so none were

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presented. However, RI.CA did issi'e E01's tidset! on these result differentes.

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Pertinent design analysis results s!;ould'have in:cn presento.d in the report to -

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, .uppri the. E01's dD and to allow-independent assessment.

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.. . RLCA noted that in the 4esfr;n analy~ sis of FCV-95, yoke dimensions and an. '

, acttiator welsht different than actual were used. In t!)is case,' the chosen values yielded conservai,Ive results, is this an isolated instance of . , .

incorrect data use or should it have been the basis fo7 a generic concern?

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