ML20245H330

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Amends 22 & 3 to Licenses NPF-68 & NPF-81,respectively, Modifying Tech Spec 4.5.2.h.1(b) to Increase Max Total Charging Pump Flow Rate W/Single Loop Running,For Unit 1
ML20245H330
Person / Time
Site: Vogtle  
Issue date: 08/08/1989
From: Matthews D
Office of Nuclear Reactor Regulation
To:
Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA
Shared Package
ML20245H333 List:
References
NPF-68-A-022, NPF-81-A-003 NUDOCS 8908170008
Download: ML20245H330 (7)


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UNITED STATES

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- WASHINGTON, D. C. 20555

.-q y NUCLEAR REGULATORY COMMISSION

( %,....f GEORGIA POWER COMPANY OGLETHORPE F0WER CORPORATION

. MUNICIPAL ELECTIC AUTHORITY OF GEORGIA CITY.0F DALTON, GEORGIA

. g TLE ELECTRIC GENERATING PLANT, UNIT 1 AMENCMENT TO FACILITY OPERATING LICENSE Amendment No. 22-License No. hPF-68

.1.

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

A.

.The application for amendment to the Vogtle Electric Generating Plant, Unit 1 (the f acility) Facility Operating License No. NPF-68 filed by the Georgia Power Company acting for itself, Oglethorpe Power Corpo-ration, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, (the licensees) dated April 6,1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as crended (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 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 set forth in 10.CFR Chapter I; 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, w

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Accordingly, the license is hereby amended by page changes' to the Technical Specifications as indicated in the. attachments.to this license amendment E

and paragraph 2.C.(2) of facility. Operating License No. NPF-68 is hereby amended to read'as follows:

(2). Technical Specifications and Environmental Protection Plan-The Technical Specifications contained in Appendix A, as revised.

through Amendment No. 22, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto', are-hereby incorporated into this license. GPC shall operate the facility. in accordance with the Technical Specifications and the p

Environmental Protection Plan.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION-Original signed by:

David B. liatthews, Director Project Directorate 11-3 Division of Reactor Projects Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuance: August 8, 1989 4

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- UNITED STATES j

NUCLEAR REGULATORY COMMISSION

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.E W ASHWGTON, D. C. 20555 GEORGIA FCWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA V0GTLE ELECTRIC GENERATING PLANT, UNIT 2 AfiENDMENT TO FACILITY OPERATING LICENSE Amendment No. 3 License No. NPF-81 1.

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

A.

The application for amendment to the Vogtle Electric Generating Plant, Unit 2 (the f acility) Fat.ility Operating License No. NPF-81 filed by the Georgia Power Company acting for itself, Oglethorpe Power Corpo-ration, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, (the licensees) dated April 6,1989, 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, as amended, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this license amendment will not be inimical to the l

common defense and security or to the health and safety of the public; and i

E.

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

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

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2.

Accordingly, the license is hereby amended by page changes to the Technical

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Specifications as indicated in' the attachments to this license amendment l

and paragraph 2.C.(2) of facility Operating License No. NPF-81 is hereby anended to read as follows:

(2) Technical Specifications;and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendraent^ No. 3, and the Environmental Protection Plan i

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contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. GPC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and shall j.

be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION L

Original signed by:

David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuance:

August 8, 1989 0

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1 ATTACHMENT TO LICENSE AMENDMENT NO. 22

. FACILITY OPERATING LICENSE NO. MPF-68 AND LICENSE AMENDMENT NO. 3 FACIllTY OPERATING LICENSE I40. NPF-81 DOCKET NO. 50-424 AND 50-425 Replace the following pages of the Appendix "A" Technical Specifications with.

the enclosed pages; The revised page is identified by Amendment number and contains a vertical line indicating the areas of change. The corresponding overleaf page is also provided to inaintain document completeness.

Amended Page Overleaf Page 3/4 5-6 3/4 5-5 L

6

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9 EMERGENCY CORE-COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

.e.

At least once per 18 months, during shutdown, by:

1)

Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection test signal, 2)

Verifying that for the RHR Semi-Automatic Switchover to Contain -

ment Emergency Sump, each automatic valve in the flow path actuates to its correct position on RWST 1evel low-low coincident with Safety Injection test signal, and 3)

Verifying that each of the following pumps start automatically upon receipt of a Safety Injection actuation test signal:

a)

Centrifugal charging pump, b)

Safety Injection pump, and c)

RHR pump.

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f.

By verifying that each of the f'ollowing pumps develops the indiccted differential pressure on recirculation flow when tested pursuant to Specification 4.0.5:

1)

Centrifugal charging pump

> 2364 psid, l

2) - Safety Injection pump

> 1405 psid, and l

3)

RHR pump

> 165 psid.

l g.

By verifying the correct position of each electrical and/or mechanical position stop for the following ECCS throttle valves:

l 1)

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE, and 2)

At least once per 18 months.

Safety Injection System l

Valve Nunber l

L 1204-04-022 1204-04-139 1

1204-U4-023 1204-04-140 1204-U4-024 1204-U4-141 1204-U4-025 1204-04-142 J

1204-04-116 1204-04-118 i

1204-U4-117 1204-04-119 j

4 V0GTLE UNITS - 1 & 2 3/4 5-5

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) __

h.

By performing a flow balance test, during shutdown, following com-pletion cf modifications to the ECCS subsystems that alter-the subsystem flow characteristics and verifying that:

1)

For centrifugal charging pump lines, with a single pump running:

a)

The sum of the i:ijection line flow rates, excluding the highest flow rate, is greater than or equal to 284 gpm, and b)

The total pump flow rate is less than or equal to 555 gpm.

2)

For Safety Injection pump lines, with a single pump running:

a)

The sum of the injection line flow rates, excluding the highest flow rate, is greater than or equal to 406 gpm, and b)

The total pump flow rate is less than or equal to 660 gpm.

3)

For RHR pump lines, with a single pump running, the sum of the injection line flow rates is greater than or equal to 3788 gpm.

l-V0GTLE UNITS - 1 & 2 3/4 5-6 Amendment No-22 (Unit 1)

Amendment No.

3 (Unit 2)

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