ML20116N507
| ML20116N507 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/19/1996 |
| 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 | |
| ML20116N510 | List: |
| References | |
| NPF-68-A-094, NPF-81-A-072 NUDOCS 9608220147 | |
| Download: ML20116N507 (6) | |
Text
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WASHINGTON, D.C. 20666-0001
+9.....,o GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA V0GTLE ELECTRIC GENERATING PLANT. UNIT 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 94 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, Uait 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.
9608220147 960819 E
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. 2.
Accordingly, the license is hareby amended by page changes to the Technical Specifications as indicated in the attachment to this license l
amendment, and paragraph 2.C.(2) of Facility Operating License No.
l 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. 94
, 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.
FOR THE NUCLEAR REGULATORY COMMISSION rbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: August 19, 1996
un uq g-1 UNITED STATES s
j NUCLEAR REGULATORY COMMISSION g
WASHlHGTON, D.C. 20666 4001 o
%,*****,5 GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA l
CITY OF DALTON. GEORGIA V0GTLE ELECTRIC GENERATING PLANT. UNIT 2 4
AMENDMENT TO FACILITY OPERATING LICENSF Amendment No. 72 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 Act of 1954, as amended (the Act), and the Commission's rules and l
regulations as set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; l
C.
There is reasonable assuranc.e (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.
i
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i
' 1 2.
Accordingly, the license is hereby amended by page changes to the i
Technical Specifications as indicated in the attachment to this license j
amendment, and paragraph 2.C.(2) of Facility Operating License No.
NPF-81 is hereby amended to, read as follows:
Technical Suecifications and Environmental Protection Plan j
The Technical Specifications contained in Appendix A, as revised through Amendment No.
72
, 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.
F R THE NUCLEAR REGULATORY COMMISSION a
r ert N. Berkow, D rector Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: August 19, 1996 4
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i ATTACHMENT TO LICENSE AMENDMENT NO. 94 FACILITY OPERATING LICENSE NO. NPF-68 1
DOCKET NO. 50-424 ANQ TO LICENSE AMENDMENT N0. 72 FACILITY OPERATING LICENSE NO. NPF-81 DOCKET NO. 50-425 Replace the following page cf the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
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Remove Paae Insert Paae 5-4 5-4 k
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DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assemblies with each fuel assembly l
containing 264 fuel rods clad with Zircaloy-4 or ZIRLO'.
Each fuel rod shall l
have a nominal active fuel length of 144 inches. The initial core loading shall have a maximum enrichment not to exceed 3.2 weight percent U-235. Reload l
fuel shall be similar in physical design to the initial core loading and shall l
have a maximum enrichment not to exceed 4.55 weight percent U-235.
Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod configurations, may be used.
Fuel assemblies shall be limited to those fuel designs that have been l
analyzed with applicable NRC staff-approved codes and methods, and shown by I
tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions.
CONTROL R00 ASSEMBLIES l
5.3.2 The core shall contain 53 full-length control rod assemblies. 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.
i 5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:
a.
In accordance with the Code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and c.
For a temperature 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.
m 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1 and 5.1-2.
V0GTLE UNITS - 1 & 2 5-4 Amendment No. 94(Unit 1)
Amendment No 72(Unit 2)