ML20073S480

Amend 31 to License NPF-2,revising Tech Specs to Increase Storage Capacity of Spent Fuel Pool from 675 to 1,407 Storage Locations

ML20073S480
Person / Time
Site:	Farley
Issue date:	04/15/1983
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20073S481	List: ML20073S480 ML20073S490 ML20073S491
References
TAC-48219, NUDOCS 8305090019
Download: ML20073S480 (4)

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UNITED STATES

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y ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 31 License No. NPF-2 1.

ine Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Alabama Power Company (the licensee) dated March 19, 1982, supplemented by letters dated April 21 and September 14, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assura'nce (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 Comission's regulations; D.

The issuance of this 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 of the Commission's regulations and all applicable requirements have been satisfied.

0305090019 830415 PDR ADOCK 05000348 P

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, 2.

Accordingly, the license is amended by changes to the Tectnical 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:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 31, 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 the date of its issuance.

However, Technical Specification 5.6, both the existing page 5-7 and revised page 5-7, will be effective until completion of the spent fuel pool modifications.

When modifications are complete the old Technical Specification 5.6 is cancelled.

FOR THE NUCLEAR REGULATORY COMMISSION Steven A. Varga, Chief

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Operating Reactors Branch No. 1 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: April 15, 1983 l

ATTACHMENT TO LICENSE AMENDMEtiT AMENDMENT N0. 31 TO FACILITY OPERATING LICENSE NO. flPF-2 DOCKET NO. 50-348 Revise Appendix A as follows:

Remove Page*

Insert Page*

5-7 5-7 NOTE: Old page 5-7 and new page 5-7 are both effective until completion of the spent fuel pool modifications.

At that time remove old page 5-7 which is cancelled.

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DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:

a.

AKeff equivalent to less than or equal to 0.95 when flooded with unborated water, which includes conservative allowances for uncer-tainties 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 Keff will not exceed 0.98, based on maximum enrichment of 3.5 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 designed and shall be maintained with a storage capacity limited to no more than 1407 fuel assemblies.

5.7 COMP 0NENT 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 1 5-7 Amendment No. 31

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