ML19256D144

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Requests Assistance in Evaluation of Environ & Technical Issues Re Util Application.Response Requested by 670724
ML19256D144
Person / Time
Site: Crane Constellation icon.png
Issue date: 07/10/1967
From: Long C
US ATOMIC ENERGY COMMISSION (AEC)
To: Moore V, Newell J
US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 7910170636
Download: ML19256D144 (1)


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.I. :. 2. sell, Chief Please provide assistance in evclucting the folicwing

Enviten=catal 6 areas of the ;;atropolitan Sc,i oa cpplication Radution Safety carc

! (Docket 50-2S9).

i! ech. Eranch 1.

  • shat at=ospheric cilucion i ctors uces the Site T

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3 ranch recc==end for use in accident ca'culcticns at u

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this site?

'a*ha t low population center distances are reco== ended?

care 2.

Please provide your cc:= cats cn sig,nificant site

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and environ =cntal fcctors, particulcrly witn respect I

to the hydrolcgical consideraticas at tha s'.tc.

Is l TG....mo a u.m.y I,s.fiA6 s

' acnau the scope of the proposed conitcring prcpf.-cm cdaquate?'

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hast effect will enc use of a ecoling ponc or cool _ing I

towers have on liquid waste disposci?

.tha t ac tivity carc i

u=its can be accu =ulatec in t..c cco an; pon,e.,

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3.

To what c:s tent can credit be given for iodina

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acuus rc=ovat oy en:osuitate spray (anc wnac crecit nas

' C. G. l.ong, Chie f been given on other plants)?

RP3 93 Please provice your calculation or cose rates tor nc casign

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basis accidents.

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Are there-a'ny spErial site considRations occadse or tne

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l close proxicity of two airports (2-1/2 =i and 6 =i) and the fact; i'that TunWa'fs are-Jppr'oKi=aculy in line wich7de site e,c,,c so.

t cars 7436 l7-10-67 j (Your co==ents and questions are desired by 7/24/67.)

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V. U.ocre, Chief Picase provide assistance in evaluating the following !

!Instru=entationand areas of the Metropolitan Edison applicatica (Docket l Power Technelogy 50-289).

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! Branch 1.

How does the design of the nuclear,.ccatrol, con-I tain=ent isolation and enaineered safety factures

T o,.smo.n.t.

! in.ra s acnno instru=entation satis fy the Cc:=tission's gen 5ral design t

criteria and the proposed IEZE stcndard.

l lsaic 2.

Is the energency power systc= ceceptabic?

j 3.

Is it practical to consicer cdditional cutc=atic l

sa fe ty action to (a) =aintain cdecuate shutdcun cartin' acmo i ro s..w an c.u j.mraa (e.g., reduce feedwater flow cnd scrc= cn =ini=u=

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=oderator te=perature) or (b) stcrt injection of high arc concentration boric acid coincident with reactor control rod cerc= for sc=e accident conditicns?

(Your ce==ents and cuestions are desired by 7 / 24 / 67.')

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acma C. C. l.ong, Chief

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