ML20126E336

Requests Licensee Results of Analysis Re ECCS to Determine Degree to Which Emergency Core Cooling Must Be Relied Upon to Maintain Containment Integrity.Rept Should Include Assumptions & Justification & Mathematical Models

ML20126E336
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	12/30/1966
From:	Morris P US ATOMIC ENERGY COMMISSION (AEC)
To:	Wall H CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
NUDOCS 8101190501
Download: ML20126E336 (2)

Text

. - - . . - . -- .- .-- - - - - - . - - - . - -.

I ar I

l l

Dgg 8 0 h46 ,

1 I

1 30ekst D.30-155 1 l

l 1

Consumers 7ever Company 1%5 Parnell Boed Jackson, stichigan bje03 )

l Attention: IIr. 5. R. Wall

Vice President Gentlemen Oura nt designs for high power nuclear reactors 1-w. p ate extensive l

provisions for emergency more ecoling in the event of a major rupture l in the primary coolant system. Se purposes of these systems are two- '

fold: to limit the release of fission products from the sore and to protect and maintain sontainment integrity in the event of such a postulated accident. Significant advances here recently been ande in the technigaes for analysing more behavior ib11 swing such a rup- l ture, la order to establish performance sogairements for emergency '

oore ookling systems and to evaluate the adegascy and reliability of such systems. >

We have recently discussed this matter as it relates to the Big Rock

• Foint reactor with representatives of your sospeny and hope that you will be able to assign top priority to the review of Big Rock 7 Dint emergersey oore cooling provisions in the light of seasiderations being given to projects now in the licensing stage af moview.

In addition to the consideration that anods to be given to the pro-sent emergency core W W provisions for the Big b ek 701st feeility to determine the need for additional geweisions to limit the release of fission products from the oors in the event of a enjor supture in the primary cooling syntes, we believe that you abould perform suitable analyses to determine the degree to ultich emergency more cooling sust be relied upon to maintain sonw ammat integrity. Dese analyses should ineinaa, but mot necessarily be limited to, the following considerations:

1. Analysis of the ions of coolant fm m the sore, for a sufficient tandre of piping break vises (assuming that the breair. occur very rapidly) to define the limiting condition, and to show the ultimate dis-pf//f6fdf sipation of all k'st loads and the effect of the rescur vessel sategrity.

OFTICE P

._ _FMai=- -was sa.se or

.4ati[ysis M -4 Bela49%-Wel k M - M -

p**

SURNAME >

DATE > **-erres-e s, a.esseum ev.m .mt Purm ABOW818 (Rev.H3)

--..-_v. ._....,-.-4, ,,_--_.___..m.. . . , . . _ . , _ , , - . . _ . _ - ~ . . ~ . . . . - . _ . ~ . , . . . . _ , . . . . . -_ ,

DEC 8 01966 Consumers power Oseqpeny 3 som from acurses enternal to the pressure vessel.

It shaul A in=1uAm the therWal God Beahan4*al history of the core, imeluding Seeay heet, effective host lead of the sore and load on the remotor vossal he to the redistribution of fission promaets, ,

and potential metal-water reactions. De effect of significant variations in applioshle parameters should also be taaluded to show the margias armil-able in the results. hould you eenclude fmm the above that the integrity of the reactor vessel may be jeopardised, you abould continue your analysis to ahow the espability that may be armi1mkl= in your plant fm m other cooling systems and components that might be suitable and available for preserving the integrity of your reactor vessel. ,

E. Analyses to determine the performanaa ngairements for systems to prevent oore moltdown following the loss of coolant accident for all potential primary coolant piping kroaks and break loostions. It is also resmated that you inform us of any action you plan to take as a result of these analyses.

It is regnested that you inform us when a report of the results of the above analysis will be srailable to us. Se report abould include suf-ficient information, such as mathematical models, assumptions and their justification, coaguter oodes, etc., to parait us to make an independent assessment of your analysis samt its results.

If you believe it would be halpful to discuss this pueblem furthe, we I would be happy to meet with you at your convenience.

ainam W yours, eristnet signed nr 1 I

Peter A. Norris yeter A. Morris, Dimetor Division of Beactor Licensing Distribution Bec: P. A. Morris Pub. Doc. Hm. E. G. Case Formal. R. S. Boyd Suppl.M ((((( R. Impara, SS DRL Reading CO. (2)

R&PRSB Reading ACRS(18)

C. Henderson J. Shea H. Stelle

,,,c, , n:aspSB n:DepA. ni c ag.

PMorris

$URNAME , RBok/k' EGC q

ler*/66 12ztu66 1

,,m , 12/9/66

_ac. .... m ..._........-...-.~

- - - . .__ .___ - -. . _ . . - - - - - - . - - - .