ML20126E141

Forwards Request for Addl Info to Util 770321 Submittal & NRC Info Request Re Potential Radiological Consequences of Postulated Fuel Handling Accident Inside Containment.Info Requested by 780618

ML20126E141
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	05/22/1978
From:	Ziemann D Office of Nuclear Reactor Regulation
To:	Bixel D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
NUDOCS 8101120387
Download: ML20126E141 (3)

Text

_ _ _ _ - ._.

DISIfLIBUTION Q Doc NRC PDR

-- - - 3

j Local POR j Docket No. 50-15 ORB #2 Reading IEE VStello

-- DGEisenhut OELD i

~

OI&E (3)

Constmers Power Company DLZiemann

$4Y 221973 SNowicki l ATTN: Mr. David Bixel Nuclear Licensing Admin'ist'rator HSmith 212 West Michigan Avenue BGrimes -

Jackson, Michigan 49201

~

A thy

,[ ', ; ", , , ~l ,

B an Gentlemen: ACRS (16)

EEB We have reviewed your Mah:h 21,,1977,subnittal and your responses )

to our request for additional information . relating to potential radio- \

i

~

logical consequences of a pos1iulated fuel, handling accident ,inside

~

containment at the Big Rock Po1,n.t,Pla.nt. We find that a more , detailed ..

. review is necessary. Please provide .the a,dd,1ttonal information requested in Enclosure 1 by June 16, 1978,_ to permit us to continue our evaluatio.n.

',, Sincerely. ,

! 2r.21 :d t'2Td DI p ,., _ ;1,, S c u.C

^~ Dennis L. Ziemann Chief Operating Reactors Branch f2 '

,, ' [ ,' Civision of Operating Reactors',

~~

Enclosure:

Second Request for Additional Information cc w/ enclosure: Sea next page. , ,, , ,, ,

I a

GI.3 m c ; : a 3F7 y

Ph /

I~

f arrec= > A0h0RB. M OR:0RB #2 '

_ , , , , SJNowie < yh DLZiemann

,,,,, 5//f /78 5$478 r.., ___

NRC PORM Me (9-76) NRCM 0240 W u. e. movanaissut raswvme orries, t,.to - ame.eae POOR QUAUTY PAGES guu ii

Lnciosure i-  ;

i, t SEC0l!D

_R1QQEST I'OR ADDITIONAL It!F013% TION In your letters dated July 1 and lioverber 8,1977 you stated that the con-tainment purge isolation system is required to function to mitigate'th; con-sequences of a fuel handling accident inside the containment (FIMIC). Any systems required to maintain the conservatively calculated consequences of an accident below Part 100 exposure guidelines should be considered engineered safety fectare systeir.s. Provide system descriptions (including P&lD's cnd control system logic and schematic diagrams) and analysis to demonstrate the extent to which existing systems required to function during the FHAIC comply with the criteria established in the Hezards Summary Report for engineered-safety features. Provide also a description of the extent to which thcsc sys-tems will comply with the current IIRC criteria for engineered safety feature systems which is listed in the flRC Standard Review Plan, tiUREG-75/OS7. Ex-plain why it is not necessary to have these systems meet the current llP.C cri-teria for ESF systems. lhe information that you should provide for any changes to the existing plant is described in Regulatory Guide 1.70, I

(

Consurcrs Poecr C'./r.pany VAy , 9 1g73 l

cc U/enclo sure:

Mr. Paul A. Perry, Stcretary j Consur.ers Power Company '

212 West Eichigan Avenue )

Jactscn, Michigan /9201 4

i Judd L. Pacon, Ese;)re Consumtrs Po',>cr Compsriy 212 !!ast Michiaan Avenue Jackson, Michigan I,92 01  ;

l Hunton & Williams George C. Freeman, Jr. , Esquire P. O. liox 1535 i P.ic t."ond , Virgir.ic 23212 )

Peter l!. StcLetee, Esquire  !

505 P::.;1e: Building l Grand Ei.pids, Michigan 49503  !

Charlevoix Public Library 107 Clinton Street Chcrievoix, Micbigan 49720 l

l 1

l l

<0

____-____.m_m

-__.,________m-.---m.- -

-.____.m, -,,4.~.-.e.,. -__ ._--)