ML20044A981

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Amends 31 & 11 to Licenses NPF-68 & NPF-81,respectively, Revising Surveillance Requirement 4.8.1.1.2h(6)(c)
ML20044A981
Person / Time
Site: Vogtle  
Issue date: 07/10/1990
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
ML20044A982 List:
References
NPF-68-A-031, NPF-81-A-011 NUDOCS 9007170119
Download: ML20044A981 (7)


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UNITED STATES

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NUCLEAR REGULATORY COMMISSION e

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nI wassiNoTow, o. c. rosss GEORGIA POWER COMPANY i

OGLETHORPE POWER CORPORATION i

MUNICIPAL ELECTRIC AUTHORITY OF GEORGI A CITY OF DALTON, GEORGIA i

V0GTLE ELECTRIC GENERATING PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE i

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-1 Amendment No. 31 l

License No. NPF-68 1.

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

A.

The app (lication for amendment to the Vogtle Electric Generating Plant, Unit 1 the facility) 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 May 25, 1990, 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.

Thereisreasonableassurance(i)thattheactivitiesauthorizedby this amendment can be conducted without endangering the health and i

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 comon 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 Comission's regulations and all applicable requirements have l.

been satisfied.

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

Sp*ecifications as indicated in the attachment to this license amendment J

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

Technical Specifications and Environmental Protection Plan I

i The Technical Specifications contained in Appendix A, as revised through i

Amendment No. 31, and the Environmental Protection Plan contained in Appendix B both of which are attached hereto, are hereby incorporated intothislicense.

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 be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 1

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

Attachment:

Technical Specification Changes Date of Issuance: July 10, 1990 1

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7 NUCLEAR REGULATORY COMMISSION

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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF Gr0RGIA

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-V0GTLE ELECTRIC GENERAT1NG PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE I

Amendment No.11 i

License No. NPF-81 1.

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

Theapp(licationforamendmenttotheVogtleElectricGeneratingPlant, A.

Unit 1 the facility) Facility 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,(thelicensees)datedMay 25, 1990, 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 pro-visions of the Act, and the rules and regulations of the Comission; C.

Thereisreasonableassurance(i)thattheactivitiesauthorizedby I

this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted I

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 comon 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 Comission's regulations and all applicable requirements have been satisfied.

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0-2.

Accordingly, the license is hereby amended by page changes to the Technical Sp*ecifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-81 is hereby amended to read as follows:

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised-through Amendment No.11, and the Environmental Protection Plan contained in 1

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 Ne implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 4

LGV David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuance: July 10, 1990 j

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ATTACHMENT TO LICENSE AMENDMENT NO. 31 FACILITY OPERATING LICENSE NO. NPF-68 AND LICENSE AMENDMENT NO.11 i

FACILITY OPERATING LICENSE NO. NPF-81 DOCKET NOS. 50-424 AND 50-425 t

i Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised page is identified by Amendment number and contains vertical lines indicating the areas of change. The corresponding overleaf page is also provided to maintain document completeness.

Amended Page Overleaf Page 3/4 8-7 3/4 8-8 l'

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o' SURVEILLANCE REQUIREMENTS auto-start signal; the steady-state gnerator voltage and frequency shall be maintained within these limits d' ring this test; 6)

Simulatingaloss-of-offsitepowerinconjunctionwithanESF Actuation test signal, and:

a)

Verify h deenergization of the emergency busses and load shedding from the emergency busses; b)

Verifying the diesel starts on the auto-start signal, energizes the emergency busses with permanently connected loads within 11.5 seconds,* energizes the auto-connected emergency (accident) loads through the load sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the emergency loads.

After energization, the steady-state voltage and frequency of the emergency busses.shall be maintained at 4160 +170,

-410 volts and 60 + 1.2 Hz during this test; and c)

Verifying that all automatic diesel generator trips, except engineoverspeed,lowlubeoilpressure,highjacketwater temperatures # # and generator differential, are automatically l

bypassed upon loss of voltage on the emergency bus concurrent with a Safety Injection Actuation signal.

7)

Verifying the diesel generator operates for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

During the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of this test, the diesel generator shall be loaded to an indicated 7600 to 7700 kW,** and during the remaining 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> of this test, the diesel generator shall be loaded to an indicated 6800-7000 kW.**

The generator voltage and frequency shall be 4160 + 170, - 135 volts and 60 t 1.2 Hz within 11.4 seconds after the start signal; the steady-state generator voltage and frequency sgall be 4160 + 170, -410 volts and 60 i 1.2 Hz during this test.

Within 5 minutes after com-pleting this 24-hour test, perform Specification 4.8.1.1.2h.6)b);,,

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8)

Verifying that the auto-connected loads to each diesel l

generator.do not exceed the continuous rating of 7000 kW; 9)

Verifying the diesel generator's capability to:

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  • All engines starts for the purpose of surveillance testing as required by Specification 4.8.1.1.2 may be preceded by an engine prelube period as recommended by the manufacturer to minimi7e mechanical stress and wear on the diesel engine.
    • This band is meant as guidance to avoid to it$e overloading of the engine.

Loads in excess of this band or momentary \\ariations due to changing bus loads shall not invalidate the test.

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  1. Failure to maintain voltage and frequency reqeirements due to grid disturbances does not render a 24-hour test as a failure.
    1. If Specification 4.8.1.1.2h.6)b) is not satisfactorily completed, it is not necessary to repeat the preceding 24-hour test.

Instead, the diesel generator may be operated at the load required by Surveillance Requirement 4.8.1.1.2.a5 kW for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or until operating temperature has stabilized.

M#The high jacket water temperature trip may be bypassed.

l V0GTLE UNITS - 1 & 2 3/4 8-7 Amendment No. 31 (Unit 1)

Amendment No.11 (Unit 2) i

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ELECTRICAL POWER SYSTEMS L

l SURVEILLANCE REQUIREMENTS (Continued) a)

Synchronize with the offsite power source while the generator is loaded with its emergency loads upon a simu-lated restoration of offsite power, b)

Transfer its loads to the offsite power source, and c)

Be restored to its standby status.

10) Verifying that with the diesel generator operating in a test mode, connected to its bus, a simulated Safety Injection signal overrides the test mode by: (1) returning the diesel generator to standby operation, and (2) automatically energizing the emergency loads with offsite power;
11) Verifying that the fuel transfer pump transfers fuel from each fuel storage tank to the day tank of each diesel via the installed cross-connection lines;
12) Verifying that the automatic load sequence timer is OPERABLE with the interval between each load block within + 10% of its design interval;

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At least once per 10 years or after any modifications which could affeet diesel generator interdependence by starting both diesel generators simultaneously, during shutdown, and verifying that both diesel generators accelerate to at least 440 rpm in less than or equal to 11.4 seconds; and j.

At least once per 10 years by:

1)

Draining each fuel oil storage tank, removing the accumulated sediment and cleaning the tank using a sodium hypochlorite solution, or equivalent, and 2)

Performing a pressure test of those portions of the diesel fuel oil system designed to Section III, subsection ND of the ASME Code at a test pressure equal to 110% of the system design pressure.

4.8.1.1.3 Reports - All diesel generator failures, valid or nonvalid, shall be reported to the Commission in a Special Report pursuant to Specification 6.8.2 within 30 dap.

Reports of diesel generator failures shall include the informa-tion recommended in Regulatory Position C.3.b of Regulatory Guide 1.108. Revi-sion 1 August 1977.

If the. number of failures in the last 100 valid tests on a per nuclear unit basis is greater than or equal to 7, the report shall be supplemented to include the additional information recommended in Regulatory Position C.3,b of Regulatory Guide 1.108, Revision 1, August 1977.

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V0GTLE UNITS - 1 & 2 3/4 8-8

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