ML20037A945
| ML20037A945 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 12/08/1966 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Bower D COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8008250807 | |
| Download: ML20037A945 (2) | |
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DEC 8 1966 t
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Docket No..'iO,.10...
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Commonwealth Fdiscm Company g
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",,htenticas Mr'. D. Robert Bod r -
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current destgas for hi@ pcwr nuelaae reactors incorpersN"~ extensive provisicas for emergency com cooling in the event d a Y ruptm in the primary coolmat system. The purposes of there systems m %
folds ta_ limit the release of fission proeuets from the ease samt u"I protect aa8 malatata ecm ni""*94 integr1%y in tk event'of such a e
postulated seeident.
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. Signifiasmt advanoes have %,been mah in$ i the techniques for smalyzing eene behavier feliceing seek a ruptum# $ l' is seder to establish p L m requiremaats for emergemey esee" systems one, to evninate the adegumey_est glability d ad.
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discussed this_ watter_as it *wlates to IkoMan thit I with I.. Z -
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_ representatives d your ecapsmy aat, as acted by Mr.' Jos11a in his 5 iI m -- _ -
July 29,1966 letter, Commonwealth Etisce is reviewing Dresden thit 1 la the li@t of ecosideraticas being gives to prow aos in b licensing stsge of review.
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In additica to the ecmsiderstica that you are pasently giving h l
emergammy core ecoling provisicas for the Dresden that 1 facility te
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determine the need for additionsi provisions to limit the rel m g i
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i, fission padmets from the con is'the event of a major rupture la thi' IJ' Prisery cooling system, we believe that you should perform suitabla -
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- emnlyses to deteruime the degree to which energeney oore ecoling must be relied upca -to maintain ecstainment lategrity. Muse @ h 1a n
include, but not W a -ily be limited to, the following ecosidersticas
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Analysis of the less et coolant from the~eces, for oc E8cPRSB Readin sufficient number et piping bzoek sizes (assuming that C*
the breaks oesar very rapidly) to esfine the limiting F g. Henderson'6iV E.G. case eenditica, met to shmr the altimate.diastystiam et althin t heat Iceas ent the offset af the.11mittag breek'sise em R ~P.CMorris n, g 3g remeter vessel latogrity. this smalysis should emelste(,;
y, gjsen C any m1N et the ease from soeuwee external to the p O B.^I6 ara'SS
' pressure vessel. It should im=1=Ae the theruni and f meebasical history of tho' esse, imeloding deser/ heat, f N.ittson CO (2) effective heet iced et the ecze sad load en the remeter E'BS (3) vcssel due to the medistributics of fissica products, and potential metal-water reacticas. She effect of, signifiesat varisticas la sypliemble paraustere should, also be inelm to shes the margine av=11=hla in.the-ev-z.,
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results. Ebould you'cceelude frca the above that the:
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1, if ' integrity of the reactor vessel ~may be jogardizedj you ' ?,3 I
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=hnis ecatinue your smalysis to shoe the espability that_
may.be ~svntlable in your plaat from other =~14== systems" j
il and simpements that might be suitable and svailable for;'
- 1 preserving the integrity of your reactor vessel.'
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Analyses to determine the performanes zuguirements for systems to prevent ease unitdous feliceing the less of *
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~t breaks sad break leenticas. It is mise zegnested thatLyonA(
coolmat accident far' all pctestisl primary coolant piping g.
Ue inform us of aarestion you plamito take es a zeault d p@g9h
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,c 4. x.v;g It is requested that you inform us when a separt of tu results' et ee' above aanlysis will be available to us. This_ report shcald laslate ]
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- a suttleiest infermetica, such as~ mathematical models, assumptiens'est.;7 '~~ " ~
their Justificatica, ecaputer codes, etc., to pensit as to unhe'an i.'h. C independent assessment of your smalysis sad its results.
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If you believe it would be helpful to dissans this prohlam furtherAM based cm your efforts to date, we would be happy to meet,witk~you et@M'-
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your conventemoe.
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Sincerely yours,.
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Crfgfaal Signed by
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Peter A. ft..rh 6~,%
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P" Peter A. Morris, Maseter? r 7
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