ML20117E882
| ML20117E882 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/28/1996 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | Southern Nuclear Operating Co, Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA |
| Shared Package | |
| ML20117E886 | List: |
| References | |
| NPF-68-A-095, NPF-81-A-073 NUDOCS 9609030151 | |
| Download: ML20117E882 (7) | |
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4 UNITED STATES g
j NUCLEAR REGULATORY COMMISSION -
t WASHINGTON. D.C. 20066-0001 49.....,o GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA V0GTLE ELECTRIC GENERATING PLANT. UNIT 1 dMENDMENTTOFACILITYOPERATINGLICENSE Amendment No.
95 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 June 17, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 set forth in 10 CFR Chapter I; 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.'
9609030151 960828 PDR ADOCK 05000424 P
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, 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amedment, and paragraph 2.C.(2) of Facility Operating License No.
NPF-68 is hereby amended to read as follows:
Technical Soecifications and Environmental Protection Plan The -Technical Specifications contained in Appendix A, as revised through Amendment No. 95
, 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 and shall be implemented within 30 days from the date of issuance.
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FOR THE NUCLEAR REGULATORY COMMISSION I
Herbert N. Berkow, Director i
Project Directorate 11-2 i-Division of Reactor Projects - I/II i
Office of Nuclear Reactor Regulation
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Attachment:
Technical Specification l
Changes Date of Issuance: August 28, 1996 l'
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UNITED STATES g
j NUCLEAR REGULATORY COMMISSION -
2 WASHINGTON, D.C. 20066 4001
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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA V0GTLE ELECTRIC GENERATING PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 73 License No. NPF-81 1.
The Nuclear Regulatory Commission (the Commission) has found that:
l 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 June 17, 1996, complies with the standards and requirements of the Atomic Energy j
Act of 1954, as amended (the Act), and the Commission's rules and i
regulations as set forth in 10 CFR Chapter I; j
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; i
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 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.
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2.
Accordingly, the license is hereby amended by page changes to the l
Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
i 4
NPF-81 is hereby amended to read as follows:
i Technical Soecifications and Environmental Protection Plan i
The Technical Specifications contained in Appendix A, as revised through Amendment No. 73
, 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 3
l Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Y
Herbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
August 28, 1996 m
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ATTACHMENT TO LICENSE AMENDMENT NO. 95 FACILITY OPERATING LICENSE NO. NPF-68 DOCKET NO. 50-424 A!iQ TO LICENSE AMENDMENT N0. 73 FACILITY OPERATING LICENSE NO. NPF-81 DOCKET NO. 50-425 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Paaes Insert Paaes 3/4 8-8 3/4 8-8 8 3/4 8-3 B 3/4 8-3 a
1.
-ELECTRICAL POWER SYSTEMS i
SURVEILLANCE REQUIREMENTS 1
5 minutes of stopping the diesel generator after having operated 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 /> loaded to an indicated 6800 - 7000 kw.
5 Momentary transie'nts outside of the load range do not invalidate l
this test.
- 9) Verifying that the auto-connected loads to each diesel _ generator i
do not exceed the continuous rating of 7000 kW; l
- 10) Verifying the diesel generator's capability to:
i:
a)
Synchronize with the offsite power source while the generator is loaded with its emergency loads upon a simu-lated restoration of offsite power, lL b)
Transfer its loads to the offsite power source, and l
j c)
Be restored to its standby status.
- 11) Verifying that with the diesel generator operating in a test i
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 i
j emergency loads with offsite power; i
- 12) 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; Verifying that the automatic load sequence timer is OPERABLE.
- 13) ~ with the interval between each load block within 10% of its design interval; i.
At least once per 10 years or after any modifications which could affect 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 isolable portions of the diesel' fuel oil piping system designed to Section III, subsection ND of the ASME Code at a test pressure equal to 110%
of.the system design pressure.
i h
V0GTLE UNITS - 1 & 2 3/4 8-8 Amendment No. 95 (Unit 1)
Amendment No. 73 (Unit 2)
j' ELECTRICAL POWER SYSTEMS i
BASES A.C. SOURCES. D.C. SOURCES. and ONSITE POWER DISTRIBUTION (Continued)
The Surveillance Requirements for demonstrating the OPERABILITY of the diesel generators are based on the recommendations of Regulatory Guides 1.9, Revision 3 " Selection, Design, Qualification, and Testing of Emergency Diesel Generator Units Used as Class IE Onsite Electric Power Systems of Nuclear Power Plants," July 1993; and 1.137, " Fuel-011 Systems for Standby Diesel Generators," Revision 1, October 1979, Appendix A to Generic Letter 84-15; Generic Letter 83-26, " Clarification of Surveillance Requirements for Diesel Fuel Impurity Level Tests;" and Generic Letter 93-05, "Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation." A pressure test of the diesel generator fuel oil piping will be required on the isolable portions of (1) the transfer pump discharge piping to the day tank, (2) the fuel oil supply line from the day tank to the vendor-supplied piping, and (3) the fuel oil return piping from the vendor-supplied piping to the regulator valve. The diesel generator fuel oil day tank will be tested by recirculating the fuel oil and verifying no tank leakage.
The diesel generator fuel oil storage tank will be tested by filling the tank to a level greater than the normal fill level and monitoring the level for a period of time and verifying no drop in fuel oil level.
The Surveillance Requirement for demonstrating the OPERABILITY of the station batteries are based on the recommendations of Regulatory Guide 1.129,
" Maintenance Testing and Replacement of Large Lead Storage Batteries for i
Nuclear Power Plants," February 1978, and IEEE Std 450-1975, "IEEE Recommended j
Practice for Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations," and 484-1975 " Recommended Practice for Installation Design and Installation of Lead Storage Batteries for Generating Stations and Substations."
Verifying average electrolyte temperature above the minimum for which the battery was sized, total battery terminal voltage on float charge, connection resistance values, and the performance of battery service and discharge tests ensures the effectiveness of the charging system, the ability to handle high discharge rates, and compares the battery capacity at that time with the rated capacity.
Table 4.8-2 specifies the normal limits for each designated pilot cell and each connected cell for electrolyte level, float voltage, md specific gravity. The limits for the designated pilot cells float voltage and specific gravity, greater than 2.13 volts and 0.015 below the manufacturer's full charge specific gravity or a battery charger current that had stabilized at a low value, is characteristic of a charged cell with adequate capacity. The normal limits for each connected cell for float voltage and specific gravity, greater than 2.13 volts and not more than 0.020 below the manufacturer's full charge specific gravity with an average specific gravity of all the connected cells not more than 0.010 below the manufacturer's full charge specific gravity, ensures the OPERABILITY and capability of the battery.
V0GTLE UNITS - 1 & 2 B 3/4 8-3 Amendment No. 95 (Unit 1)
Amendment No. 73 (Unit 2)