ML20198H752

Errata to Amend 94 & 94 to Licenses NPF-37 & NPF-66, Correcting Typo That Was Inadvertently Introduced on TS Page 5-5

ML20198H752
Person / Time
Site:	Byron
Issue date:	12/29/1997
From:	NRC (Affiliation Not Assigned)
To:
Shared Package
ML20198H736	List: ML20198H733 ML20198H752
References
NUDOCS 9801130389
Download: ML20198H752 (1)

Text

DESIGN FEATURES

. 5.6 FUEL S'iORAGE CRITICAllTY 5.6.1.1 The spent fuel storage racks are designed and snall be maintained with:

a. Fuel assemblies having a maximum initial U-235 enrichment of 5.0 weight percent;

b. A k,,, < 1.0 if fully flooded with unborated water, which includes an allowance for uncertainties as described in WCAP-14416-NP-A,

" Westinghouse Spent Fuel Rack Criticality Analysis with Credit for Soluble Boron," Revision 1, November 1996;

c. Ak 5 0.95 if fully flooded with water borated to 550 ppm, which inclUdesanallowanceforuncertaintiesasdescribedinWCAP-14416-NP-A, " Westinghouse Spent Fuel Ra k Criticality Analysis with Credit for Soluble Boron," Revision 1, November 1996;

d. A nominal 10.32 inch north-south and 10.42 inch east-west center-to-center distance between fuel assemblies plac.d in the Region 1 racks;

6. New or spent assemblies with sufficient Integral Fuel Burnable Absorbers present in each fuel assembly, as described in the " Byron and Braidwood Spent Fuel Rtek Criticality Analysis Using Soluble Boron Credit," May 1997, CAC-97-162, which may be allowed unrestricted storage in the Region I racks;

f. A nominal 9.03 inch center-to-center distance between fuel assemblies placed in the Region 2 racks;

g. New or spent fuel assemblies with a combination of discharge burnup, initial enrichment, and decay time in the acceptable region of Figures 5.6-1, 5.6-2 or 5.6-3, as applicable, may be stored in the Region 2 racks in the applicable checkerboard configuration, as described in the " Byron and Braidwood Spent Fuel Rack Criticality Analysis Using Soluble Boron Credit," May 1997, CAC-97-162; and

h. Interface requirements within and between ad.jacent racks as described in the " Byron and Braidwood Spent Fuel Rack Criticality Analysis Using Solublo i credit," May 1997, CAC-97-167.

5.6.1.2 The k,,, for new fuel for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed.

ORAINAGE 5.S.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 423 feet 2 inches.

BYRON - UNITS 1 & 2 5-5 Amendment No. 94 glig{ y@34 Corrected December 29, 1997 P PDR