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Amends 139 & 131 to FOLs NPF-2 & NPF-8,respectively,changing TSs to Revise SRs for Auxiliary Building & SW Building Batteries to Remove Existing 1.75 Volt Min Individual Cell Voltage Associated with Svc Test Acceptance Criterion
	ML20155H477
Person / Time
Site:	Farley
Issue date:	11/03/1998
From:	Berkow H; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20155H479	List: ML20155H477; ML20155H480;
References
	NUDOCS 9811100142
	Download: ML20155H477 (10)
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UNITED STATES g

j NUCLEAR REGULATORY COMMISSION g

wA8HINGToN, D.C. 20066-0001 o

SOUTHERN NUCLEAR OPERATING COMPANY. INC.

ALABAMA POWER COMPAt{Y DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.139 License No. NPF-2

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

A. The application for amendment by Southern Nuclear Operating Company, Inc.

(Southern Nuclear), dated December 30,1997, as supplemented by letter dated April 9, 1998, 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, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) 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 of the Commission's regulations and all applicable requirements 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 Oparating License No. NPF-2 is hereby amended to read as follows:

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9811100142 981103 PDR ADOCK 05000348 P

PDR

2-(2) Technical Soecificatiohs The Technical Specifications contained in Appendices A and B, as revised through Amendment No.139, are hereby incorporated in the license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days ofissuance.

i FOR THE NUCLEAR REGULATORY COMMISSION l

L bert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance:

November 3, 1998 t

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l ATTACHMENT TO LICENSE AMENDMENT NO. 139 1

TO FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 l

I Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginallines.

Remove Insert 3/489(a) 3/489(a) 3/4 8-13 3/4 8-13 I

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ELECTRICAL POWER SYSTEMS AUXILIARY BUILDING D.C.

DISTRIBUTION - OPERATING 4

1 SURVEILLANCE REQUIREMENTS (Continued) 5.

The battery capacity is adequate to supply and maintain in OPERABLE status all of the actual emergency loads for the design load profile described in the Finsl Safety Analysis Report, Section 8.3.2, by subjecting the battery to a service test.

d.

At least once per 60 months by verifying that the battery capacity is at least 80% of the manufacturer's rating when subjected to a performance discharge test. Once per 60 month interval, this performance discharge test may be performed in lieu of the battery service test per 4.8.2.3.2.c.5.

e.

At least once per 18 months, performance discharge test of battery capacity shall be given to any battery that shows signs of degradation or has reached 17 years or 85% of the service life expected for the application, whichever comes first. Degradation is indicated when the battery capacity drops more than 10% of rated capacity from its average on previous performance tests, or is below 90% of the manufacturer's rating.

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FARLEY-UNIT 1 3/4 8-9(a)

AMENDMENT NO.139 l

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= _ _ _ _ _ _ ___ _ _ _ _ _ ___ _ _ _ _ _ _

I ELECTRICAL POWER SYSTEMS SERVICE WATER BUILDING D.C. DISTRIBUTION - OPERATING SURVEILLANCE REQUIREMENTS (Continued) 4 2.

There is no visible excessive corrosion at either j

terminals or connectors, or the connection resistance of these items in less than or equal to 1500 microhms from post to post *, and 3.

The average electrolyte temperatures of ten of the connected cells deviate less than or equal to 5'?

from each other**.

c.

At least once per la months by verifying that:

1.

The cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration, 2.

The call-to-cell and terminal connections are clean, tight, and coated with anti-corrosion material, 3.

The resistance of each cell-to-cell and terminal connection is less than or equal to 1500 microhms from post to post *, and 4.

The battery charger will supply at least 3 amperes at greater than or equal to 125 volts for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

5.

The battery capacity is adequate to supply and maintain in OPERABLE status all of the actual emergency loads for the design load profile described in the Final Safety Analysis Report, Section 8.3.2, by subjecting the battery to a service test.

For any connection resistance determined to b? greater than 1500 l

microhms from post to post, the battery may be considered operable provided that within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the connection resistance is restored to less than or equal to 1500 microhms from post to post.

- If a deviation greater than 5'F is determined, the battery may be j

considered operable provided that within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the temperature deviation is corrected.

FARLEY-UNIT 1 3/4 8-13 AMENDMEhT No.139

A red UNITED STATES r

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NUCLEAR REGULATORY COMMISSION i

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WASHINGTON, D.C. 20666 4001 s...../

SOUTHERN NUCLEAR OPERATING COMPANY. INC.

l ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.131 License No. NPF-8

1. The Nuclear Regulatory Commissicn (the Commission) has found that:

A. The application for amendment by Southern Nuclear Operating Company, Inc.

(Southern Nuclear), dated December 30,1997, as supplemented by letter dated April 9, 1998, 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, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) 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 of the Commission's regulations and all applicable requirements 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-8 is hereby amended to read as follows:

- (2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 131, are hereby incorporated in the license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days ofissuance.

FOR THE NUCLEAR REGULATORY COMMISSION f

r rt N. Berkowf Director r

Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation l

Attachment:

Changes to the Technical Specifications l

l Date of Issuance: November 3, 1998 l

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ATTACHMENT TO LICENSE AMENDMENT NO.131 i

TO FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginallines.

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Remove Insert 3/4 8-12(a) 3/4 8-12(a) 3/4 8-16 3/4 8-16 1

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ELECTRICAL POWER SYSTEMS AUXILIARY BUILDING D.

C., DISTRIBUTION - OPERATING SURVEILLANCE REQUIREMENTS (Continued) 5.

The battery capacity is adequate to supply and maintain in OPERABLE status all of the actual emergency loads for the design load profile described in the Final Safety Analysis Report, Section 8.3.2, by subjecting the battery to a service test.

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d.

At least once per 60 months by verifying that the battery capacity is at least 80% of the manufacturer's rating when subjected to a performance discharge test. Once per 60 month interval, this performance discharge test may be performed in lieu of battery service test per 4.8.2.3.2.c.5.

At least once per 18 months, performance discharge test of e.

battery capacity shall be given to any battery that shows signs of degradation or has reached 17 years or 85% of the service life expected for the application, whichever comes first. Degradation is indicated when the battery capacity drops more than 10% of rated capacity from its average on previous performance tests, or is below 90% of the l

manufacturer's rating.

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l FARLEY-UNIT 2 3/4 8-12(a)

AMENDMENT No.131

ELECTRICAL POWER SYSTEMS j

SERVICE WATER BUILDING D.C. DISTRIBUTION - OPERATING

]

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l SURVEILLANCE REQUIREMENTS (Continued) l 2.

There is no visible excessive corrosion at either l

terminals or connectors, or the connection resistance of these items is less than or equal to 1500 microhms from post to post *, and 3.

The average electrolyte temperatures of ten of the connected celle deviate less than or equal to 5'F from each other**.

c.

At least once per 18 months by verifying that:

1.

The cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration, 2.

The call-to-cell and terminal connections are clean, tight, and coated with anti-corrosion material, 3.

The resistance of each cell-to-cell and terminal connection is less than or equal to 1500 microhms from post to post *, and 4.

The battery charger will supply at least 3 amperes at greater than or equal to 125 volts for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

5.

The battery capacity is adequate to supply and maintain in OPERABLE status all of the actual emergency loads for the design load profile described in the Final Safety Analysis Report, Section 8.3.2, by subjecting the battery to a service test.

For any connection resistance determined to be greater than 1500 l

microhms from post to post, the battery may be considered operable provided that within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the connection resistance is restored to less than or equal to 1500 microhms from post to post.

If a deviation greater than 5'F is determined, the battery may be l

considered operable provided that within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the temperature deviation is corrected.

FARLEY-UNIT 2 3/4 8-16 AMENUMENT NO. 131 l

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ML20155H477

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