ML20087P774

Proposed Tech Specs Increasing Fuel Enrichment

ML20087P774
Person / Time
Site:	Farley
Issue date:	03/30/1984
From:	ALABAMA POWER CO.
To:
Shared Package
ML20087P769	List: ML20087P768 ML20087P774 ML20087P782
References
NUDOCS 8404090358
Download: ML20087P774 (5)

Text

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Proposed Changes to Technical ' .>. d '

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Specifications 5.3.1 an,d 5.6.1 ,

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DESIGN FEATURES

.e 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1- The reactor core shall contain 157 fuel assemblies with each fuel assembly

- containing 264 fuel rods clad with Zircaloy -4. Each fuel rod shall have a

' nominal active-fuel. length of 144 inches and contain a maximum total weight of 1766 grams uranium. The initial core loading shall have a maximum enrichment of 3.2 weight percent U-235. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.3 weight percent U-235.

CONTROL ROD ASSEMBLIES 5.3.2 ~The reactor core shall contain 48 full length and no part length control rod assemblies. . The full length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80 percent silver,15 percent indium and 5 percent cadmium. All control rods shall be clad with stainless stecl tubing.  !

5.4- REACTOR COOLANT ~ SYSTEM

. DESIGN PRESSURE AND TEMPERATURE 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, i

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 9723 t 100 cubic feet at a nominal Tavg of,525"F.

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= 5. 5 METEOROLOGICAL TOWER LOCATION

' 5.5.1:The meteorological tower shall be . located as shown on Figure 5.1-1.

LFARLEY-UNIT 1 5-6 AMENDMENT NO.

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. DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY 3.6.1.1 The spent fuel storage racks are designed and shall be maiatained with:

a. AKeff equivalent to less than or equal to 0.95 when flooded with unborated water, which includes conservative. allowances for uncertainties and biases based on a maximum enrichment of 4.3 weight percent U-235.

b. A nominal 10.75 inch center-to-center distance between fuel assemblies placed in the storage racks.

5.6.1.2 The new fuel pit storage racks are designed and shall be maintained with a nominal 21 inch center-to-center distance between new fuel assemblies such that Kef t will not exceed 0.98, based on maximum enrichnent of 4.3 weight percent U-235, assuming aqueous foam moderation.

DRAINAGE-5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 149.

CAPACITY 5.6.3 The Sr. ant fuel storage pool is designed and shall be maintained with a

- storage capacity limited to no more than 1407 fuel assemblies.

5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 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.

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FARLEY-UNIT 1 5-7 AMENDMENT NO.

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DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES i

5.3.1 The reactor core shall contain 157 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy -4. Each fuel rod shall have a nominal active fuel length of 144 inches and contain a maximum total weight of 1766 grams uranium. The initial core loading shall have a maximum enrichment of 3.2 weight percent U-235.. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.3 weight percent U-235. t CONTROL ROD ASSEMBLIES l 5 3.2 The reactor core shall contain 48 full length and no part length control rod assemblies.- The full length control rod assemblies shall contain a nominal 142 ~ inches of absorber material. The nominal values of absorber material shall be 80 percent silver,15 percent indium and 5 percent cadmium. All control rods shall be clad with stainless steel tubing.

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~5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 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.

t' ' VOLUME 5.4.2.The' total water and steam volume of the reactor coolant system is 9723 t 100 cubic feet at a nominal T avg of 525'F. ,

5.5 METEOROLOGICAL TOWER LOCATION

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5.5.1-The. meteorological tower shall be located as shown on Figure 5.1-1.

4 FARLEY-UNIT 2 5-6 AMENDMENT NO.

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I DESIGN FEATURES M

5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage ra'cks are designed and shall be maintained with:

a. AKeff equivalent to less than or equal to 0.9b when flooded with unborated water, which includes conservative allowances for uncertainties and biases based on a maximum enrichnent of 4.3 weight percent U-235.

b. A nominal 10.75 inch center-to-center distance between fuel assemblies placed in the storage racks.

5.6.1.2 The new fuel pit storage racks are designed and shall be maintained with a nominal 21 inch center-to-center distance between new fuel assemblies such that Keff will not exceed 0.98, based on maximum enrichment of 4.3 weight percent U-235, assuming aqueous foam moderation.

DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 149.

CAPACITY 5.6.3 The spent fuel storage pool is derigned and shall be maintained with a storage capacity limited to no more than 1407 fuel assemblies.

5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 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 FARLEY-UNIT 2 5-7 AMENDMENT N0.

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