ML20077S678
| ML20077S678 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/11/1995 |
| 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 | |
| ML20077S680 | List: |
| References | |
| NPF-68-A-079, NPF-81-A-058 NUDOCS 9501240202 | |
| Download: ML20077S678 (7) | |
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4 UNITED STATES S
E NUCLEAR REGUUd'ORY COMMISSION
'f WASHINGTON, D.C. 206dM201 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. 79 License No. NPF-68 1.
The Nuclear Regulatory Comission (the Com' vion) 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 May 20, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations as set forth in 10 CFR Chapter I; ti.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's egulations 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 Comission's regulations and all applicable requirements have been satisfied.
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i 9501240002 950111 PDR ADOCK 05000424 P
PDR e
. 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-68 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. 79
, 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 H bert N. Berkow, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regalation
Attachment:
Technical Specification Changes Date of Issuance:
January 11, 1995 t
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UNITED STATES S
NUCLEAR REGULATORY COMMISSION E
f tVASHINMON, D.C. 20t4H001
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GEORGIA POWER COMPANY OGLETHORPE POWER CORE 0 RAIL 0N MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA V0GTLE ELECTRIC GENERATING PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 58 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 May 20, 1994, 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 Comt.ission; 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 l
defense and security or to the health and safety of the public, and i
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.
, 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 Snecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 58
, and the Environmental Protection Plan contained in i
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 COPMISSION L
He rt N. Berkow, Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes j
Date of Issuance: January li, 1995 l
ATTACHMENT TO LICENSE AMENDMENT NO. 79 FACILITY OPERATING LICENSE NO. NPF-68 DOCKET NO. 50-424 AND TO LICENSE AMENDMENT NO. 58 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 Amendnent number and contain vertical lines indicating the areas of change.
Remove Paaes Insert Paaes 3/4 2-5 3/4 2-5 6-21 6-21 i
1
)
l l
4 EQWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) f.
With measurements indicating maximum I F,c(Z)\\
l
( K(Z) )
over has increased since the previous determination of F, c(Z) either of the following actions shall be taken:
1)
Increase F C(Z) by the appropriate factor specified in the CORE OPERATING!.IMITSREPORT(COLR)andverifythatthisvalue satisfies the relationship ir. Specification 4.2.2.2d, or 2)
F, c(Z) shall be measured at least once per 7 Effective Full Power Days until two successive maps indicate that
{ F, c(Z)\\
is not increasing.
maximum kK(Z) over
~
g.
With the relationships specified in Specification 4.2.2.2d above not being satisfied:
1)
Calculate the percent F,(Z) exceeds its limits by the following expression
(
[ maximum F c(Z) x W(Z) 3 l
over Z F, '"
x K(Z)
-1 x 100 for P > 0.5 P
/
e
[ maximum F c(Z) x W(Z)
}
over Z F "'"
x K(Z)
-1 x 100 for P s 0.5, and i
,,, 0. 5 2)
The following action shall be taken.
Within 15 minutes, control the AFD to within new AFD limits which are determined by reducing the AFD limits specified in the-CORE OPERATING LIMITS REPORT by 1% AFD for each percent F,(Z) exceeds its limits as determined in Specification 4.2.2.2g.1.
Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, reset the AFD alarm setpoints to these modified limits.
V0GTLE UNITS - 1 & 2 3/4 2-5 Amendment No. 79 (Unit 1)
Amendment No. 58 (Unit 2)
ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS RFPORT (Continued) a.
WCAP-9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY",
July 1985 (W Proprietary).
(Methodology for Specifications 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5_- Shutdown Bank Insertion Limit, 3.1.3.6 -
l Control Bank Insertion Limits and 3.2.? - Nuclear Enthalpy Rise Hot i
Channel Factor.)
j b.
WCAP-10216-P-A, Revision IA, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION", February, 1994 (M Proprietary). (Methodology for Specifications 3.2.1 - Axial Flux Difference (Relaxed Axial Offset Control) and 3.2.2 - Heat Flux Hot Channel Factor (W(Z) surveillance requirements for F. Methodology).)
c.
WCAP-9220-P-A, Rev. 1, " WESTINGHOUSE ECCS EVALUATION N00EL-1981 VERSION", February 1982 (M Proprietary).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
i The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, Er,CS limits, r,uclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional. Administrator and j
Resident Inspector.
SPECIAL REPORTS 6.8.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report.
i l
V0GTLE UNITS - 1 & 2 6-21 Amendment No. 79 (Unit 1)
Amendment No. 58 (Unit 2)
..