ML20215G174

Amend 66 to License NPF-2,deleting Fuel Rod Weight Limit in Tech Spec 5.3.1 Re Descriptive Design Features of Fuel Assemblies

ML20215G174
Person / Time
Site:	Farley
Issue date:	09/23/1986
From:	Rubenstein L Office of Nuclear Reactor Regulation
To:
Shared Package
ML20215G175	List: ML20215G174 ML20215G178
References
TAC-61949, NUDOCS 8610200183
Download: ML20215G174 (5)

Text

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UNITED STATES g

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WASHINGTON, D. C. 20555 Y

%,..... J ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 66 License No. NPF-2 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Alabama Power Company (the licensee) dated July 8, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission; C.

There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 I

of the Commission's regulations and all applicable recuirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-2 is hereby amended to read as follows:

8610200183 860923 PDR ADOCK 05000348 P

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. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 66, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shell be implemented within 30 days of receipt.

FOR THE NUCLEAR REGULATORY COMMISSION Ltuwd Lester' Rubenstein, Director PWR Project Directorate #2 Division of PWR Licensing-A

Attachment:

Chances to the Technical Specifications Date of Issuance: September 23, 1986.

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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 66 FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is -identified by amendment number and contains vertical lines indicating the areas of change. A corresponding overleaf page is also provided to maintain document completeness.

Remove Pages Insert Pages 5-6 5-6

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Figure 5.1-4 Plant Farley site Map Exclusien Area and Liquid Efflues.s FARLEY-UNIT 1 5-5 AMENDMENT NO. 26

i DESIGN FEATURES

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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 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 R0D 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 abscrber material. The nominal values of absorber material shall be 80 percent silver,15 percent indium and 5 percent cadmi um.

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 tne applicable Surveillance Requirements, b.

For a pressure of 2485 psig, and For a temperature of 650*F, except for the pressurizer which is c.

680*F.

VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 9723 + 100 cubic feet at a nominal Tavg of 525"F.

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

FARLEY-UNIT 1 5-6 AMENDMENT NO. 2E, E2. 66

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