ML20217C388

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Proposed Tech Specs Allowing Use of VANTAGE-5 Fuel in Reactor Operation Planned to Be Submitted at Future Date
ML20217C388
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 07/01/1991
From:
ALABAMA POWER CO.
To:
Shared Package
ML20217C378 List:
References
NUDOCS 9107150252
Download: ML20217C388 (6)
v • d • e


Text

. _ _ _ .

ATTACHMENT 1 Proposed Changed Technical Specification Pages a

Unit 1

_ Pace Revision Page 5-6 Replace Page 5-7 Replace Unit 2 Paae Revision Page 5-6 Replace Page 5-7 Replace 9107150252 910701 PDR- ADOCK 05000348 P PDR

DESIGN FEATURES 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. Euch fuel rod shall have a nominal active fuel length of 144 inches. The initial core loading shall have a maximum enrichment of 3.2 veight 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 veight percent U-235 for Vestinghouse LOFAR fuel and 5.05 veight percent U-235 for Vestinghouse OFA and VANTAGE-5 fuel. Vestinghouse OFA and VANTAGE-5 fuel with maximum enrichments greater than 3.95 veight percent U-235 shall contain sufficient integral burnable absorbers such that the requirement of specification 5.6.1.1.c is met.

4 Vestinghouse LOPAR fuel does not require integral burnable absorbers.

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 absorbet 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.

5.4 REACTOR COOLANT SYSTEM DESIGN FRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:

a. In accordance vith 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.

VOLUME

- 5.4.2 The total vater and steam volume of the reactor coolant system is 9723 2 100 cubic feet at a nominal Tavg f 525'F.

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

FARLEY-UNIT 1 5-6 AM2NDMENT NO.

DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with a K less than or equal to 0.95 when flooded with unborated vater, whichinikbdesconservativeallovancesforuncertaintiesandbiases. This is assured by maintaining:

a. A nominal 10.75 inch center ~'-center distance between fuel assemblies placed in the storage racks.
b. .A maximum enrichment of 4.30 veight percent for Vestinghouse LOPAR fuel assemblies.
c. A maximum reference fuel assembly K= less than or equal to 1.455 at 68'r for Westinghouse OFA and VNUAGE-5 fuel assemblies.

5.6.1.2 The new fuel pit storage racks are designed and shall be maintained with aK f moderation. This18k.lessthanorequalto0.98,assumingaqueousfoam ssured by maintaining:

a. A nominal 21 inch center-to-center distance between new fuel assemblies placed in the storage racks, l
b. A maximum enrichment of 4.30 weight percent for Westinghouse I

LOPAR fuel assemblies.

c. A maximum reference fuel assembly Ka less than or equal to 1.455 at 68'r for Westinghouse OFA and VANTAGE-5 fuel assemblies.

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 designed and shall be maintained with a storage capacity limited to no more than 1407 fuel assemblies.

5.7 COMPONENT CYCLIC OR TRANSIDTI 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 1 5-7 AMENDMENT NO.

DESIGN FEATURES 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. The initial core loading shall have a maximum enrichment of 3.2 veight 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 veight percent U-235 for Vestinghouse LOPAR fuel and 5.05 veight percent U-235 for Vestinghouse OFA and VANTAGE-5 fuel. Vestinghouse OFA and VANTAGE-5 fuel with maximum enrichments greater than 3.95 weight percent U-235 shall contain sufficient integral burnable absorbers such that the requirement of specification 5.6.1.1.c is met.

Vestinghouse LOFAR fuel does not require integral burnable absorbers.

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 j

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.

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.

l VOLUME l

5.4.2 The total vater and steam volume of the reactor coolant system is l 9723 2 100 cubic feet at a nominal T avg f $25'F.

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

l FARLEY-UNIT 2 5-6 AMENDMENT NO.

1

DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with a K less than or equal to 0.95 when flooded with unborated vater, whichinIIbdesconservativeallowancesforuncertaintiesandbiases. This is assured by maintaining

a. A nominal 10.75 inch center-to-center distance between fuel assemblies placed in the storage racks,
b. A maximum enrichment of 4.30 veight percent for Vestinghouse LOPAR fuel assemblies.
c. A maximum reference fuel assembly K= less than or equal to 1.455 at 68'F for Westinghouse OEA and VANTAGE-5 fuel assemblies.

5.6.1.2 The new fuel pit storage racks are designed and shall be maintained with a K less than or equal to 0.98, assuming aqueous foam moderation. ThisIIgkssuredbymaintaining:

r 1

l a. A nominal 21 inch center-to-center distance between new fuel l assemblies placed in the storage racks.

l l

b. A maximum enrichment of 4.30 weight percent for Westinghouse J LOPAR feel assemblies,
c. A maximum reference tuel assembly K= less than or equal to 1.455 at 68'F for Westinghouse OFA and VANIAGE-5 fuel assemblies.

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 designed and shall be maintained with a storage capacity limited to no more than 1407 fuel assemblies.

5.7 COMPONENT CYCL' , OR TRANSIE!E 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 AMENDMErff NO.

a

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