ML20085E977
| ML20085E977 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 10/04/1991 |
| 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 | |
| ML20085E980 | List: |
| References | |
| NPF-68-A-047, NPF-81-A-026 NUDOCS 9110210304 | |
| Download: ML20085E977 (6) | |
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j GEORGIA POWED COMPANY OGLETHORPE POWER CORPORATION MllNICIPAL ELECTRIC AUTHORITY OF GEORGI A CITY OF DALTON, GEORGIA DOCKET NO. 50-424 V0GTLE ELECTRIC GE!1ERATillG PLANT, UNIT 1 AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No. 47 License No. NPF-68 1.
The Nuclear Regulatory Commission (the Commission) has found that:
The app (lication for amendment to the Vogtle Electric Generating Plant, A.
Unit 1 the facility). Facility Operating License No. NPF-68 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corpo-ration, f4unhipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees) dated Jane 3, 1991, complies with the standards and requirements of the Atomic Erergy 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 opplication, 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 4
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.
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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 ?.C.(?) of facility Operatinq license No NPF-08 is hereby arended to read at follows:
Technical Specifications and Environnental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 47 and the Environmental Protection Plan contained in Appendix P. both of which cre 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 REGt!LATORY COMMIS$10N Y&
David B. Matthews, Director Project Directorate !!-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Attachnent:
Technical Specification Changes Date of issuance: October 4.1991
p ** ** cy UNITED STATES 9 - 1, 9 f) ti NUCLEAR REGULATORY COMMISSION
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WASHINoToN, D C Me GEORGIA POWER COMPAtly OGLETHORPE POWER CORPORATION HilNICIPAL ELECTRIC AUTHORITY OF GEORGM CITY OF DALTON, GEORGIA DOCKET NO.__50-425 V,0GTLE ELECTRIC GENERATlkG PLANT _,,UtilT ?
AMENOMEPT TO FACILITV OPERATING LICENSE Amendment No. 26 License No. NPF-81 1.
The Nuclear Regulatory Commission (the Commission) has found that:
The app (lication for amendment to the Vogtle Electric Generating Plant, A.
Unit 2 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 (the licensees) dated June 3, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as am?nded (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 sur.h activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendnient 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 Conmission's regulations and all applicable requirements have been satisfied..
2 2.
Acenrdingly, the license is bereby amended by page changes to the Technical Specifications as indicated in the attachnent to this license amendment arri p6ragraph 2.C.(M of Facility pperating License No. Npf-81 ts hereby arended to read as follows:
Technical Specifications and Envirnnmental Protection plan The Technical Specifications contained in Append!x A as revised through Araendnent No. 26, and the Environment 61 Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporatec into this license.
GPC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
ThS license amendment is effective as of its date of issuance.
FOR THE fiUCLEAR REClll.ATORY COMfi'SS10N
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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:
October 4, 1991
-ATTACHMENT TO LICENSE AMENDf1ENT NO.47 FACILITY OPERATlHG LICENSE NO. NPF-68 AND LICENSE AMENDMENT NO. 26 FACILITY OPERATING LICENSE P0. NPF-81 DOCKET NOS. 50-424 AND 50-425 Replace the following page of the Appendix "A" Technical Specifications with the enclostd page. The revised page is identified oy Amendment number and contains vertical lines indicating the areas of change.
Remove Page Insert Page 5-4 5-4 l
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1 DESIGr4 FEATURES
- 5. 3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy-4 except for two fuel assemblies which may each contain up to twelve (12) fuel rods clad with ZlRL0*.
Each fuel rod shall have a nominal active fuel length of 144 inches.
The initial core loadi ng shall have a me-enrichment not to exceed 3.2 weight percent U-235.
Reload fuel shall b siv er in physical design to the initial core loading and shall have a m. i enrichmera not to exceed 4.55 weight percent U-235.
CONTROL R0D ASSEMBLIES 5.3.2 The core shall contain 53 full-length control red assemblics.
The control rod assemblies shall contain a nominal 142 inches of absorber material.
The nominal absorber composition shall be 95.5% natural halfnium and 4.5%
natural zirconium and/or 80% silver, 15% indium, and 5% cadmium.
All control rods shall be clad with stainless steel.
5.4 REACTOR COOLANT SYSTEM DESIGN ORESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed ard shall be maintained:
a.
In accordance with th Code requirements specified in Section 5.2 of the FSAR, with al ance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and c.
For a te.:perature of 650 F, except for the pressurizer which is 680 F.
VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 12,240 + 100 cubic feet at a nominal T of 588.5 F.
3yg 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tawer shall be located as shown on Figure 5.1-1 and 5.1-2.
V0GTLE UNITS - 1 & 2 5-4 Amendment No.47 (Unit 1)
Amendment No. 26 (Unit 2)
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