ML20005G419
| ML20005G419 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/04/1990 |
| 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 | |
| ML20005G420 | List: |
| References | |
| NPF-68-A-025, NPF-81-A-006 NUDOCS 9001190133 | |
| Download: ML20005G419 (6) | |
Text
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'k UNITED STATES f
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~ NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D, C. 20665 m
GEORGIA POWER COMPANY
-OGLETHORPE POWER CORPORATION l
MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA
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J, CITY OF DALTON, GEORGIA V0GTLE ELECTRIC GENERATING PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE R
Amendment No. 25 License No. NPF-68 1
.1. - 'The Nuclear Regulatory Comission (the Comission) has found that:
The app (lication for amendment to the Vogtle Electric Generating Plant, y -
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1 Unit 1 the-f acility) Fac.ility Operating License No. NPF-CD filed by y
the Georgia Power Company acting for itself, Oglethorpe Power Corpo-s ration, Municipal Electric Authority of Georgia, and C,ity of Dalton,
. Georgia, (the licensees) dated September 26, 1989, complies with the 3
standards and requirements of the Atomic Energy Act of 1954, as i
amended (the Act), and-the Commission's rules and regulations set p
- forth in 10 CFR Chapter I; L
L B.
. The facility will operate in conformity with the application, as B
amended, the-provisions of the Act, and the rules and regulations j
oflthe Commission; H
C.
There is reasonable assurance (1) that the activities authori:ed by i
this amendnent can be concucted without endangering the health and s:
' safety of'the public, and (ii) that-such activities will be conducted l-
. in compliance-with the Comission's regulations set forth in 10 CFR Chapter I; j
D.
The issuance of this' license amendment will not be inimical to the comon 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'c regulations and all applicable requirements have been satisfied.
T 9001190133 900104 N
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Accordingly, the license is hereby amended by page changes to the Technical L
. Specifications as indicated in the' attachment to this license amendment t
and paragraph 2.C.(2) of Facility Operating Licente 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. 25, and the Environmental Protection Plan 2
contained in Appendix B, both of which are attached hereto, are j
hereby incorporated into this license.
GPC shall operate the cfacility in accordance with the Technical Specifications-and the Environmental Protection Plan.
3.
This license amendment is ef#ective following shutdown from Unit 2 Cycle 1 operation.
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FOR THE NUCLEAR REGlA.ATORY COMMISSION i
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David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects - I/II' Office of h elear Reactor Regulation l
Attachment:
L LTechnical Specification-Changes 3
Date of Issuance: slanuary 4,1990 L
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k UNITED STATES -
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y NUCLEAR REGut.ATORY COMMISSION wAsmwotow. o. c. rosss t
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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION i
MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA i
CITY OF DALTON, GEORGIA-V0GTLE ELECTRIC GENERATING PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE 5
Amendment No. 6 o
1 License No. NPF-81 1..
The Nuclear Regulatory Commission (the Comission) has found that:
The app (lication for amendment to the Vogtle Electric Generating Plant, A.
Unit 2 the facility) Fecility Operating License No. NPF-01 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 Septenber 26,.1969, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.-
The facility will operate in.confurmity with the application, as amended, the provisions of the Act, and the rules and regul6tions of the Commission; C.
'There'is reasonable assurance (i) that the activities authorized by this amendment can be conoucted without endangering ~ the health and g
Li safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I;-
D..
The issuance of this. license amendment will not be inimical to the l
comon defense and' security or to the health and safety of the public; and l
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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Accordingly, the license is hereby amended by page changes to the Technical i
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 m
- The Technical Specifications contained in Appendix A, as revised
- through Amendment No. 6
, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto.-are hereby incorporated into this licene. GPC shall operate the f acility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective following shutdown from Unit 2 Cycle 1
. operation.
FOR THE NUCLEAR REGULATORY COMISSION s
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David B. Matthews, Director Project Directorate II-3 l-Division of Reactor Projects - I/II
[y Office of Nuclear Reactor Regulation L
Attachment:
. Technical Specification Changes
.Date of Issuance:' January 4,1990 L
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ATTACHMENT'TO LICENSE AMENDMENT NO. 25
'n FACILITY OPERATING LICENSE NO. NPF-68 I
AND LICENSE AMENDMENT NO. 6 3
FACILITY OPERATING LICENSE NO. NPF-81 s
DOCKETS NOS. 50-424 AE 50-425-Replace the following page of the ' Appendix "A" Technical Specifications with
-the enclosed page. The revised page-is identified hy Amendment number and contains vertical lines indicating the areas of change.
Amended Page 3/4 1-4 l
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MODERATOR TEMPERATURE COEFFICIENT
' LIMITING CONDITION FOR OPERATION-Y[
f, 3.1.1.3 The moderator temperature coefficient (MTC) shall be:
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l' a.
Less positive than +0.7 x 10 4 Ak/k/'F for the all rods withdrawn, beginning of cycle life (BOL), condition for power levels up to 70% RATED THERMAL POWER with a linear ramp to 0 ok/k/*F at 100%
i RATED THERMAL POWER; and
- b. -.Less negative than -4.0 x 10 4 ok/k/'F for the all rods withdrawn, a
,f, end of cycle' life (EOL), RATED THERMAL POWER condition.
APPLICABILITY:
Specification 3.1.1.3a. - MODES I and 2* only.**
L Specification 3.1.1.3b. - MODES 1, 2, and 3 only.**
ACTION:-
'a.
With the MTC more positive than the limit of Specification 3.1.1.3a.
above, operation in MODES 1 and 2 may proceed provided:
1.
Control rod withdrawal limits are established and maintained sufficient to restore the MTC to within the above limit within p:
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
These withdrawal limits shall be in addition to the insertion limits of Specification 3.1.3.6; 2.
The control rods are maintained within the withdrawal limits established above until a subsequent calculation verifies that the MTC has been restored to-within its limit for the all rods p
withdrawn condition; and L
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- With K greater than or equal to 1.
- SeeSp$balTestExceptionsSpecification3.10.3.
V0GTLE UNITS - 1 & 2 3/4 1-4 AMENDMENT NO. 25 (UNIT 1)
AMENDMENT N0. 6 (UNIT 2)
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