ML20151V290

Requests Listed Addl Info to Continue Review of Util Request for Enrichment Increase to 5.0 Weight Percent U-235

ML20151V290
Person / Time
Site:	Calvert Cliffs, 05000000
Issue date:	08/15/1988
From:	Hodges M Office of Nuclear Reactor Regulation
To:	Capra R Office of Nuclear Reactor Regulation
Shared Package
ML20151V292	List: IA-88-497, Forwards Safety Evaluation Accepting Proposed Reracking of Spent Fuel Storage Pools from Criticality Standpoint.Fuel Enrichment May Be in Conflict W/Table 54 of 10CFR51 & Data Used by Util to Assess Environ Effects.Salp Input Also Encl ML20151V290 ML20154F927 ML20195G296 ML20195G389 ML20195G536 ML20195G546 ML20195G550 ML20195G553 ML20195G616 ML20196B968
References
FOIA-88-497 NUDOCS 8808220213
Download: ML20151V290 (2)

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AUG 151986 MEliORANDUM FOR: R. A. Capra, Project Director Project Directorate 1-1 Division of Reactor Pro.iccts - 1/!!

FR0fi: M. W. Hodges, Chief Reactor Systens Branch Division of Engineering A Systens Technology Sl'PJE CT : REQUEST FOR ADDITIONAL INFOR?tATION ON CALVERT CLIFFS 1 & 2 ENRICHMEP'T filCREASE The reactor Systens Granch recuests the enclosed additional information in

! order to continue our review of the Calvert Cliffs request for an enrichnent I

increase to 5.0 weight percent 11 235.

origint tJgns M. .OoIfdE. Chief Reactor Systems Branch Division of Engineering A Systens Technology

Enclosure:

As stated cc w/ enclosure:

5. A. McNeil O!STR]BilTION LTntral Files SRXB P/F M. W. Hodges L. Phillips L. Kopp L. Kopp P/F 3

C000022on:3/n000: 3 & gM PPR ' mex osooog 7

Contact:

L. Kopp, SRXB Ph x20879 Ip b  :

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MWH0DGES  :  :

NAME :LK0PP:en' :LPIO{ LIPS

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DATE :8/t /88 :81) /08 :8/h/88  :  :

OFFICIAL RECORD COPY

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• PE0 VEST FOR ADDITIONAL INF0F.MATION CALVERT CLIFF 5 1 AND 2 ENRICFMENT INCREASE

1. The staff's position on the criticality of unieradiated fuel stored in the new fuel stcrage racks is that k ff will not exceed 0.98 if accidentally moderated by extreme low-density water or other hydrogencus raterial sus.> as may occur for fog, mist, and firefighting foan. The new fuel storage f acility must also be designed so that k,f f will not l

' exceed 0.95 if accidentally fully flooded with pure water. Both of these i conditions have been analyzed and shcwn to be met. Powever. TS 5.6.2 only refers to the 0.98 criterion. Sirce this Specification is being I

modified to increase the enrichrent limit, we recommend that it also be nodified to irclude the 0.95 criterion as well.

2. The reactivity effect of a possible 4-inch gap at the centerline of every  !

Ecraflex sheet was analyzed and found to meet the staff's limiting

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criterior. ilustify that gap formation larger than this, in site and extent, wculd not occur and describe any monitoring procran at Calvert Clif f s which would detect degraded Eeraflex sheets includino possible gap {

ferr3 tion. l I

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3. How ware the uncertainties in the ranuf acturing tolerances of U-236 l i enrichtent and fuel pellet density acccunted for in the determination of the n5/95 confide,re level uncertainty?  :

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