ML20086F493

Proposed Tech Specs,Modifying Requirements for Fuel Assemblies

ML20086F493
Person / Time
Site:	Catawba
Issue date:	07/05/1995
From:	DUKE POWER CO.
To:
Shared Package
ML20086F276	List: ML20086F267 ML20086F493
References
NUDOCS 9507130141
Download: ML20086F493 (3)

Text

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ATTACHMENT I DUKE POWER COMPANY  ;

CATAWBA NUCLEAR STATION I i

i PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS  :

1 SUPPLEMENT 1  ;

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9507130141 950705 ADOCK 05000413

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DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment vessel is designed and shall be maintained for a maximum internal pressure of 15 psig and a temperature of 328'F.

5.3 REACTOR CORE gQ jg lyrofi- l FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assemblies with each fuel assembly 7 nominally containing 264 fuel rods clad with Zircaloy-4, except that substitu- ;

tions of fuel rods by filler rods consisting of Zircaloy-4 or stainless steel, i  ;

or by vacancies, may be made in fuel assemblies if justified by cycle-specific E

reload analyses using NRC-approved methodology. Should more than 30 rods in the core, or 10 rods in any assembly, be replaced per refueling, a special report describing the number of rods replaced will be submitted to.the Commis-sion pursuant to Specification 6.9.2 within 30 days after cycle startup. Each fuel rod shall have a nominal' active fuel length of 144 inches. Reload fuel shall be similar in physical design to the initial core loading and shall have j a maximum enrichment of 4.0 weight percent U-235 with a maximum enrichment /

tolerance of i 0.05 weight percent U-235. '

CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 53 full-length control rod assemblies. The full-length control rod assemblies.shall contain.a nominal 142 inches of absorber material of.which 102 inches shall be 100% boron carbide and remaining 40-inch tip shall be 80% silver, 15% indium, and 5% cadmium.

For Units 1 and 2, all control rods shall be clad with stainless steel tubing,

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i except for Unit 2, a maximum of one Rod Cluster Control Assembly may have Iriconel clad control rods.

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5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE j 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 I of the FSAR, with allowance for normal degradation pursuant to l 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.

VOLUME 5.4.2 'The total water and steam volume of the Reactor Coolant System is 12,040 1 100 cubic feet at a nominal T,yg of 525 F.

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

CATAWBA - UNITS 1 & 2 5-6 Amendment No. (Unit 1)

Amendment No. (Unit 2) 1

INSERT 1 The reactor shall contain 193 fuel assemblies. Each assembly shall consist of a matrix of cylindrical zircaloy clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with NRC-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  ;

not completed representative testing may be placed in non-limiting core regions. Reload fuel shall be similar in physical design to the initi'al core loading and shall have -a maximum nominal ,

enrichment of 5.0 weight percent U-235 with a maximum tolerance of

+ .05 weight percent U-235.

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