ML20245A498

Forwards Safety Evaluation & Franklin Research Ctr Rept TER-C5506-329, Structural Evaluation of Vacuum Breakers (Mark I Containment Program), Per Util 830609 & 860313 Responses to Generic Ltr 83-08

ML20245A498
Person / Time
Site:	Hatch
Issue date:	04/01/1987
From:	Rivenbark G Office of Nuclear Reactor Regulation
To:	James O'Reilly GEORGIA POWER CO.
Shared Package
ML20204G396	List: ML20204G392 ML20205R213 ML20236F615 ML20245A498
References
GL-83-08, TAC-57156, TAC-57157, NUDOCS 8704060264
Download: ML20245A498 (2)

Text

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Dear Mr. -Of Reilly:

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SUBJECT:

, 11 MARK'I CONTAINMENTiDRYWELLiVACUUM' BREAKERS 'l x D L. < LREi EdwinLILHatchNuclearl, c -

Plant, Units'1and2: , 1. m 5d

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u . , . , - Y' b$i l Our', Generic Letter 83-081 related6to modification ofEvacuum' breakers ;on Markllo n containments identified a. potential failure >modeLofLthe wetwell/drywell vacuum 1

( breakers.in chuggingjand condensationioscillation'phaseslof;bloyidown/to jhe.( ' ' ~

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a torus'during .a. loss of coolantiaccidenti LInTthat Generic Letter we? requested '

1 that the impacted licensees-provide!a.commitsentyto' submitithe results: oft. j plant unique, calculations which either formed)the: bases 1for. modifications'to; s *)

. vacuum breakers or provide justification..for their?as-built acceptability d s d

By a' letter dated June' 9,;1983Jyou~ provided a response to Generic Letter? _

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83-08,' submitting the'results of anlevaluation!that pou; stated demonstrated ' ',

d T, . the as-built'acceptabi_lity of the ' Hatch Units :1;and,2 ' vacuum' breakers. 2, l.

L On Jan.uary 17, 1986 wesentyouaRequest'forJAdditionaliInformation1(RAI).

The purpose of this RAI was to obtain: verification that;thespalletiimpacti ,

3 velocity'used in" your vacuum breaker stressianalysis was determined using thes a approved methodologyLconsistent with the conditionstand restrictions 'sLE , -d n prescribed by .the staff. Your; reply dated March 13 L1986?confirmedithat*youl <

used'the approved. methodology.

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The staff's technical assistance contractor,1FrankliniRessarch Centsrj(FRC)/

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has reviewed the results of your stress analysis toiverify that theivacuum; <

breaker stresses calculated by using the-pallet impact velocity asTinput'to; #. .

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analytical. model of the' valve' are within Lthe' ASMETcode all(owable values %7 ;

for the materials used. Copies our' Safety Evaluation and thelFRC Tech'nical?

Evaluation are enclosed'.. -

A Basedonourreview,we; conclude!thattheanalSicalmethoduse'd!to:evaluatei l

critical" stresses is adequate, the' maximum' stress:in'the Hatchtvacuunitbreake?s' , d is less'than'30%1of the; Code' allowable,'and the existing designLisy '

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H structurally adequ' ate' and: requires. no. modification. <

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iThis ; completes;ourdeview of Multipian.t:- ActionL Item 1D-20Tfor the' Hatch Nuclear :=

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'. Plant,. Units 1 and 2. '

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. A Sincerely, , , U q

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' George W. Rivenbarli, .. . . Project Manager- , 1)

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Divisio.n of-BWR L.icensing! y

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