ML19211D300

Revised Page 5.5 to Tech Specs Re Design Features of Spent Fuel Pool

ML19211D300
Person / Time
Site:	Calvert Cliffs
Issue date:	01/15/1980
From:	BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML19211D294	List: ML19211D293 ML19211D298 ML19211D299 ML19211D300
References
NUDOCS 8001170472
Download: ML19211D300 (4)

Text

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DESIGN FEATURES VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 10,614 + 460 cubic feet at a nominal T avg f 532*F. _ t I 5.5 METEOROLOGICAL TOWER LOCATION i 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1. l * .

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  !                          5.6 FUEL STORAGE                                                                           ,

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CRITICALITY - SPENT FUEL 10 X l0m 5.6.1 The spent fuel storage' racks are designed and shall be maintainedU with a minimum-1215-x-13-inch-center-to-center distance between fuel lj l

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assemblies placed in the storage racks to ensure a k,,< The0.95 k with the sto

                              < 0.95 includes the conservative allowances for uncertainties described in Section 9.7.2 of the FSAR. In addition, fuel in the storage pool shall have a U-235 loading of <-44:Ongrams of U-235 per axial centimeter of
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Q. fuel assembif. . CRITICALITY - NEW FUEL 5.6.2 The new fuel storage racks are designed and shall be maintained with a nominal 18 inch center-to-center distance between new fuel assemblies such that K will not exceed 0.98 when fuel having a maximum . enrichment of 4.0 weig8bpercent U-235 is in place and aqueous foam moderation is assumed. The K of < 0.98 includes the conservative allowanceforuncertaintiesd8[[ribedinSection9.7.2oftheFSAR. DRAINAGE

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5.6.3 The spent fuel storage pool is designed and shall be maintained l to prevent inadvertent draining of the pool below elevation 63 feet. CAPACITY 5.6.4 The fuel storage pool is designed and shall be maintained with a combined storage capacity, for both Units 1 and 2, limited to r.o more , than G55-fuel assemblies. - ( l750 g 5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS 8001170 47d

              .                5.7.1    The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.

5-5 Amencment No- p, l CALVERT CLIFFS UNIT.2  ;

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     ,             DESIGtt FEATURES

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     ;             VOLUME I

5.4.2 The total water and steam volume of the reactor coolant systcm is

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10,614 + 460 cubic feet at a nominal Tavg f 532 F. _

    ,'             5.5 METEOROLOGICAL TOWER LOCATI0fl                                    -
    !              5.5.1     The meteorological tower shall be located as showa on Figure 5.1-1.

I 5.6 FUEL STORAGE CRITICALITY - SPENT FUEL s.; / " 5.6.1 The spent fuel storageLracks are designed and shall be maintained 'I with a minimum 4-h5-x43-inch. center-to-center distance between fuel 1{

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assemblies

                   < 0.95.with placed       in thepool the storage      storage filledracks with to         ensure a w3 unborated      k,t6r., equivalent The k ,toof 7 0.95 includes the conservative allowances for uncertainties de&[iibed
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In Section 9.7.2 of the FSAR. In addition, fuel in the storage pool ,

         .         shall have a U-235 loading of < 079 rams of U-235 per axial centimeter

_ O- ' of fuel assembly.

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Ab5 CRITICALITY - f1EW FUEL 5.6.2 The new fuel storage ra:ks are designed and shall be maintained with a ncminal 18 inch center-to-center distance between new fuel assemalies such that k will not exceed 0.98 when fuel having a maximum enrichment ' of 4.0 weig8(Ipercent U-235 is in place and aqueous foam moderation is assumed. The k of < 0.98 includes the conservative allowance for uncertainties dN[ribed in Section 9.7.2 of the FSAR. DRAINAGE 5.6.3 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 63 feet. CAPACITY 5.6.4 The fuel storage pool is designed and shall be maintained with a combined storage capacity, for both Units 1 and 2, limited to no more than E& fuel assemblies.

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t 5.7 COMP 0tlENT CYCLIC OR TRANSIEllT LIliITS 1763 024 5.7.1 Th'e components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.

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CALV$RT CLIFFS - UNIT 1 5- 5 Ameadment No./7}}