ML20095K276

Proposed Tech Specs,Requesting Temporary Exemption & TS Change to Allow Placement of Four Lead Test Fuel Assemblies in Unit 1 Reactor Core During Cycles 13,14 & 15

ML20095K276
Person / Time
Site:	Calvert Cliffs
Issue date:	12/21/1995
From:	BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20095K274	List: ML20095K270 ML20095K276
References
NUDOCS 9512280209
Download: ML20095K276 (2)

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5.0 DESIGN FEATUltES 5.1 SITE LOCATION The site for the Calvert Cliffs Nuclear Power Plant is, located on the western shore of the Chesapeake Bay in Calvert County, Maryland, about 10-1/2 miles southeast of Prince Frederick, Maryland. The site is approximately 45 miles southwest of Washington, DC, and 60 miles south of Baltimore, Maryland. The exclusion area boundary has a minimum radius of 1,150 meters from the center of the plant. -

l 5.2 REACTOR CORE 5.2.1 FUEL ASSEMBLIES The reactor shall contain 217 fuel assemblies. Each assembly shall consist of a matrix of cylindrical zircaloy or ZIRLO cladding fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO,)

as fuel material. Limited substitutions of zircoalum alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have no I representative testing may be placed in nonlimiting regions. 1 ns d R 5.2.2 CONTR0i.T ASSEMBLIES The reactor core shall contain 77 full length and no part length control element assemblies.

5.3 FUEL STORAGE 5.3.1 CRITICALITY l

l 5.3.1.1 The spent fuel storage racks are designed and shall be maintained i with:

l l a. Fuel assemblies having a maximum U-235 enrichment of 4.52 weight percent; l b. k,,, < 0.95 if fully flooded with unborated water, which includes l an a'flowance for uncertainties as described in Section 9.7.2 of l the UFSAR;

c. A nominal 10-3/32-inch center-to-center distance between fuel assemblies.

9512280209 951221 PDR ADOCK 05000317 P PDR CALVERT CLIFFS - UNIT 1 5-1 AmendmentNo.'D{

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INSERT A For Cycles 13,14, and 15 only, advanced cladding material may be used in four lead test assemblics as described in an approved temporary exemption dated November 28,1995.

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