ML20035B055
| ML20035B055 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/22/1993 |
| 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 | |
| ML20035B056 | List: |
| References | |
| NPF-68-A-058, NPF-81-A-037 NUDOCS 9303310053 | |
| Download: ML20035B055 (6) | |
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UNITED STATES h
i NUCLEAR REGULATORY COMMISSION-I 6
WASHINGTON. D.C. 20555 GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA DOCKET NO. 50-424 V0GTLE ELECTRIC GENERATING DLANT, UNIT I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 58 License No. NPF-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 facility), Facility Operating License No. NPF-68 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated February 2, 1993, 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 1; 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 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; L d 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.
9303310053 930322 PDR ADOCK 050t,0424 p
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Accordingly, the license is hereby amended by page 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-68 t
is hereby amended to read as follows:
Technical Specifications and Environmental Protection Plan
't The Technical Specifications contained in Appendix A, as revised through Amendment No. 58, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto,'are i
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.
L FOR THE NUCLEAR REGULATORY COMMISSION f,
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David B. Matthews. Dircctor Project Directorate 11-3 Division of Reactor Projects - I/11 Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
March 22, 1993 i
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UNITED STATES i
NUCLEAR REGULATORY COMMISSION
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Y' WASHINGTON D.C. 20555 D.
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i GEORGIA POWER COMPANY r
OGLETHORPE POWER CORPORATION t
MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA _
DOCKET NO. 50-425 V0GTLE ELECTRIC GENERATING PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.37 License No. NPF-81 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Vogtle Electric Generating Plant, Unit 2 (the facility), Facility Operating License No.
NPF-81 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated February 2, 1993, 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 regulaticns 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.
1
, 2.
Accordingly, the license is hereby amended by page 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-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. 37, 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 Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION j/
J
%4 David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
March 22, 1993 1
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r ATTACHMENT TO LICENSE-AMENDMENT NO.58
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FACILITY OPERATING LICENSE N0. NPF-68 AND LICENSE AMENDMENT NO. 37 FACILITY OPERATING LICENSE NO. NPF-81 f
i DOCKETS NOS. 50-424 AND 50-425-l Replace the following page of the Appendix "A" Technical Specifications witfi-the enclosed page.
The revised page is identified by Amendment number and 1
contains vertical lines indicating the areas of change.
Remove Page Insert Page I
i 3/4 8-7 3/4 8-7
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SURVEILLANCE REOUIREMENTS auto-start signal; the steady-state generator voltage and frequency shall be maintained within these limits during this test; 6)
Simulating a loss-of-offsite power in conjunction with an ESF Actuation test signal, and:
a)
Verifying deenergization of the emergency busses and load shedding from the emergency busses; b)
Verifying the diesel starts on the auto-start signal, ener-gizes 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 engine oversged, low lube oil pressure, high jacket water temperatures and generator differential, are automatically 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 6011.2 Hz within 11.4 seconds after the start signal; the steady-state generator voltage and frequency shall be 4160 + 170, -410 volts and 60 i 1.2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> test, perform Specification 4.8.1.1.2a.4;" pleting this 24-l Hz during this test.
Within 5 minutes after com 8)
Verifying that the auto-connected loads to each diesel generator do not exceed the continuous rating of 7000 kW; 9)
Verifying the diesel generator's capability to:
- 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 minimize mechanical stress and wear on the diesel engine.
- This band is meant as guidance to avoid routine overloading of the engine.
Loads in excess of this band or momentary variations due to changing bus loads shall not invalidate the test.
- Failure to maintain voltage and frequency requirements due to grid disturbances does not render a 24-hour test as a failure.
- If Specification 4.8.1.1.2a.4 is not satisfactorily completed, it is not
.l 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 for a minimum of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
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- The high jacket water temperature trip may be bypassed.
V0GTLE UNITS - 1 & 2 3/4 8-7 Amendment No. 58 (Unit 1)
Amendment No. 37 (Unit 2)
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