ML20217M843
| ML20217M843 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/19/1997 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217M848 | List: |
| References | |
| NUDOCS 9708250327 | |
| Download: ML20217M843 (6) | |
Text
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t UNITED STATES j
NUCLEAR REGULATORY COMMISSION j
WASHINGTON, D.C. 3066H001
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100THERN NUCLEAR OPERATING COMPANY. INC.
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA DOCKET NO. 50-321 EDWIN 1. HATCH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LIC %SE Amendment No. 207 License No. DPR-57 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-57 filed by-Southern Nuclear Operating Company Inc. (Southern Nuclear), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated April 29, 1997, as supplemented May 28, 1997, 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 reculations 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 9708250327 970819 PDR ADOCK 05000321 P
.... A
. E.
The issuance of this amendment is in accordance with 10 CFR Part 51-of the Commission's regulaticas 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.
DPR-57 is hereby amended to read as follows:
(2)
Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 207
, are hereby incorporated in the license.
Southern Nuclear shall operate the facility
'n 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 TH NUCLEAR REGULATORY COMMISSION 4
f' erbert 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, 1997 l
l AlljtHMENT TO LICENSE AMENDMENT NO. 207 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following sages of the Appendix "A" Technical Specifications with the enclosed pages. lie revised pages are identified b contain vertical lines indicating the areas of change. y Amendment number and Bermve Insert 3.4-25 3.4-25 3.4-26 3.4-26 3.4-27 3.4-27
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RCS P/T UMITS te00 3
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un 1400 ll IIldi E
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-16 f,200 ll llllWl$
g i I llll0 n
l I lilu j,000
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ll ll llII g
O
/
800
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y 400 512 PSIG
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-- BELTullE LIMITS
- BOTTOMHEAD LIMITS BELTLINE AND BOTTOM HEAD 68'T IM TS FLANGE REGION 76'F 0
0 100.0 200.0 300.0 400.0 500.0 600.0 MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F)
Figure 3.4.9-1 (Page 1 of 1) t**-"'
Pressure / Temperature Limits for Inservice Hydrostotle and Inservice Lookogo Tests Hotch Unit 1 3.4-25 Amendment No. 207
RCS P/T uMITS i400 3.4.,
n00 1
FPS i
^
2 I
1000 b
K I
w o
g t00 i
r 400 I
5 o
n 6
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l ac a
r
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400 0
f
~ ~ EELTUNE UMITS
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umawou uwr.
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- 80TTOM HEAD UMITS 80TTOW MEAD 00T
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[RheGE,ttocN7evl I
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0 la.:,AD 1 NW I 6 1 0
100 R00 300 400 WINIMUM VESSEL METAL TEMPERATURE ('F)
Figure 3.4.9-2 (Page 1 of 1)
Pressure / Temperature umits for Non-Nuclear Hoot-up.
Low Power Physics Tests. and Cooldown Following a Shutdown i
Hotch Unit 1 3.4-26 Amendment No. 207
RCS P/T UMITS 3.4.9 l
1400 f
VAUD TO 32 EFPY 1200 l
1 i
w 1000 8
[
E 000 Y
R D=A 000
.J Y
f w
l 400 u
C%
~BELTUNE AND 200 Tenee.r,smae NM te UwTs
\\
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M 0
L WAD I AG M-2 71 0
100 200 300 400 MlHIMUM REACTOR VESSEL METAL TEMPERATURE (*F)
Figure 3.4.9-3 (Poge 1 of 1)
Pressure / Temperature Umits for Criticolity Hotch Unit 1 3.4-27 Amendment No. 207
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