ML19329F214

Endorses Science Applications Inc Topical Rept SAI-050-77-PA Analysis of Probability of Pipe Rupture at Various Locations in Primary Cooling Loop of B&W 177 Fuel Assembly Pwr. Rept Meets Request for Reactor Vessel Supports Info

ML19329F214
Person / Time
Site:	Midland
Issue date:	10/06/1977
From:	Howell S CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Vassallo D Office of Nuclear Reactor Regulation
References
4320, NUDOCS 8006230739
Download: ML19329F214 (2)

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Stephen H. Howell YTJIi. G Vice President General Offlees: 1945 West Parnail Road, Jackson, Michigan 49201

• Area Code 517 7884453 October 5. l77

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v I'r. D. 2. Ve.sse.llo. A sistant Director Ti;ht 'Tatcr Recctors Divisien of Project & nagenent U. S. Huelser Ec:"alator.r Co rissica

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EEACIO3 VE3SEL SUF?0H2 SY3 C

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0505 2, 21.13.3 STRIAL: 4320 Our letter of Sept:nber 10, 1976 sivised thct Conster's Fct.er Cc ;cn; vas

articipatin ; in a 3E Users Crou; to evaluate the probability of a failure of the reactor coolant syster in the an

ralar recien between the res.ctor vessel and the cavity shield util relative to the reactor vessel sur; ort concerns addressed by your July 14, 1976 letter.

he results of the proba-bilit,* study were suhitted to Sr. Charles Tramel, Project "an2cer, Divisien of 0;er=. ting Rezeters on Septenber 27, 1977 by Science A;;11 cations; Inc. es Co;ical Ee; ort IIc. Sil-05C-77-?A "An.bc. lysis of the Frchability of Fire 3

Etr.n;ure at Various Loccticns in the Prinary Ccolin; Ico; cf a Salsecck and

'Tilcon 177 Tuel Assenbly Pressurised Unter 2eactor - Including the 2ffects of a Periodic Insrection." "he SAI '"orical Perert uses sinilar r.ethodolo-y cs the re; ort subnitted by the Conbustica Engineering Use-s Grcu; but has tahen cdventace of en;erience seined in the preparatien en1 :iEC revic.7 of that report a'd a;;ro;riately c:gands the de;th of cnalysis.

37 this letter, Consin.iers ?crer Cen;any endorses the SAI To;ical 2egorr, and its conclusions. ITe believe that it fully se.tisfies your request for inferation concernin; the adequacy of the ::idlani ?lant reactor vessel su;; orts.

'ie cre available to discuss the salient features of this report with you es required.

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