ML20117N647

Proposed Tech Specs Section 5.3.1,allowing Use of Fuel Assemblies Containing Fuel Rods Clad W/Zirlo

ML20117N647
Person / Time
Site:	Vogtle
Issue date:	06/17/1996
From:	GEORGIA POWER CO.
To:
Shared Package
ML20117N644	List: ML20117N640 ML20117N647
References
NUDOCS 9606240008
Download: ML20117N647 (3)

Text

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ENCLOSURE 3 VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE TECHNICAL SPECIFICATION ZIRLO* FUEL CLADDING INSTRUCTIONS FOR INCORPORATION The proposed amendment to the Technical Specifications would be incorporated as follows:

Remove Page Insert Page 5-3* and 5-4 5-3* and 5-4

• Overleaf page containing no changes i

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9606240008 960617 PDR ADOCK 05000424 P PDR

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.e DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES [~ #

5.3.1 The core shall contain 193 fuel assemb1 es with each fuel assembly containing 264 fuel rods clad with Zircaloy-4 :=:pt f:- te feel er:- f er l w 9 ; nch ent 9 ep te tr! = (12) f :1 nd: chd dth !!"La . Each I fuel rod shall have a nominal active fuel length of 144 inches. The initial ,

core loading shall have a maximum enrichment not to exceed 3.2 weight percent 1 U-235. Reload fuel shall be similar in physical design to the initial core  ;

loading and shall have a maximum enrichment not to exceed 4.55 weight percent'  !

U-235. Limited substitutions of zirconium alloy or stainless steel filler rods i I

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 l methods, and shown by tests or analyses to comply with all fuel safety design 1 bases. A limited number of lead test assemblies that have not completed ,

representative testing may be placed in non-limiting core regions.

I CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 53 full-length control rod assemblies. The control rod assemblies shall contain a nominal 142 inches of absorber material.

The nominal absorber composition shall be 95.5% natural halfnium and 4.5%

natural zirconium and/or 80% silver,15% indium, and 5% cadmium. All control rods shall be clad with stainless steel.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE l

5.4.1 The Reactor Coolant System is designed and shall be maintained: I

a. In accordance with the Code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pursuan: 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 water and steam volume of the Reactor Coolant System is 12,240 100 cubic feet at a nominal T m of 588.5'F.

5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1 and 5.1-2.

V0GTLE UNITS - I & 2 5-4 Amendment No.62 (Unit 1)

Amendment No. 41 (Unit 2)

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ENCLOSURE 4 VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE TECHNICAL SPECIFICATION ZIRLO* FUEL CLADDING ENVIRONMENTAL ASSESSMENT Information Supporting an Environmental Assessment An environmental assessment is not required for the proposed change because the requested change to the license conforms to the criteria for " actions eligible for categorical exclusion," as specified in 10 CFR 51.22(c)(9). The change will have no impact on the environment. The proposed change does not involve a significant hazards consideration as discussed in the preceding section. The proposed change does not involve a significant change in the types, or a significant increase in the amounts of ,

any effluents that may be released offsite. In addition, the proposed change does not involve a significant increase in individual or cumulative occupational radiation exposure.

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