ML20151V290
| 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:
|
| References | |
| FOIA-88-497 NUDOCS 8808220213 | |
| Download: ML20151V290 (2) | |
Text
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r AUG 151986 4
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
.OoIfdE. Chief M.
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
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Contact:
L. Kopp, SRXB x20879 Ip b
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DATE :8/t /88
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s 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 will not exceed 0.98 if the new fuel stcrage racks is that k ff 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 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 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
{
l ferr3 tion.
I i
3.
How ware the uncertainties in the ranuf acturing tolerances of U-236 l
enrichtent and fuel pellet density acccunted for in the determination of i
the n5/95 confide,re level uncertainty?
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