ML20137B937

Proposed Tech Specs,Revising TS Section 5.3.1,fuel Assemblies to Allow Use of Alternate Zr-based Fuel Cladding Matl ZIRLO

ML20137B937
Person / Time
Site:	Wolf Creek
Issue date:	03/18/1997
From:	WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20137B934	List: ML20137B931 ML20137B937
References
NUDOCS 9703240107
Download: ML20137B937 (2)

Text

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Attechment IV to ET 97-0020 ,

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. l DESIGN FEATURES l

5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The =re the!! cent:!r 193 fue! crremb!!:: t"h :::" fue' creemb!y  ;

norme!!y cente!r:ng 2Si fue! red: c'ed t"h Zi rr'ey 4 except *het '"!!cd j rdedut!O . Of fee! rede by f!!: red: cen:!: ting of Z!rrr'ey i er et2!n! :: -

fer' er by "?cr9e m y M mrde !!just! Sed by e cyc! rper!'c re! cad i en-!y ! . Each fue! red 05:!! heur a ~2 min ! dee fue!!ength of444 l I

'nch=. The 5 t!r! core !ced5; the!! h ve m29 mum nefnc! enr!:hment of j 2.10 rer!;h! p ent U 235. ?!ced fue! ch !! be :!m!!:r % phyper! ded;n 10 the.!r i tic! Ocre !cedhg.The reactor shall contain 193 fuel assemblies. Each assembly shall consist of a matrix of l Zircaloy or ZlRLO clad fuel rods with an initial composition of natural or sl!ghtly enriched uranium dioxide (UO2) )

as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods,in l accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be l

. limited to those fuel designs that have been analyzed with applicable NRC approved codes and methods and '

shown by test or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed represeritative testing may be placed in non-limiting core regions. l l

CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 53 full-length ard no part-length control rod assemblies. The full-length control rod assemblies shall contain a nominal 142 inches of absorber material. All control rod assemblies shall be hafnium,  ;

silver-indium-cadmium, or a mixture of both types. All control rods shall be l clad with stainless steel tubing.

5.4 REACTOR COOLANT SYSTEM DESIGNPRESSURE ANDTEMPERATURE 5 4.1 The Reactor Coolant System is designed and shall be maintained:

a. In accordance with the Code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements,

b. For a pressure of 2485 psig, and

c. For a temperature of 650 F, except for the pressurizer which is 680 F.

1 VOLUME 5.4.2 The totalvolume of the Reactor Coolant System, including pressurizer 4

and surge line, is 12,1351100 cubic feet at a nominalyT of 557 F.

5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.

WOLF CREEK - UNIT 1 5-6 Amendment No. 3AGA9r48; 61 1

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