ML20206H397
| ML20206H397 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/20/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | City of Dalton, GA, Georgia Power Co, Municipal Electric Authority of Georgia, Oglethorpe Power Corp |
| Shared Package | |
| ML20206H399 | List: |
| References | |
| DPR-57-A-127, TAC 56882 NUDOCS 8606260057 | |
| Download: ML20206H397 (4) | |
Text
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l'.
f ucoq UNITED STATES
[
h NUCLEAR REGULATORY COMMISSION L
j WASHINGTON, D. C. 20S55
\\...../
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION 4
MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 127 License No. DPR-57 f
1.
The Nuclear Regulatory Comission (the Comission) has found that:
.I A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) dated January 17, 1985, 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
.l in 10 CFR Chapter I.;
B.
The facility will operate in conformity with the application, the l
provisions of the Act, and the rules and regulations of the l
Comission; C.
There is reasonable assurance (1) 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 i
in compliance with the Comission's regulations; 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.
2.
Accordingly, the license is amended by 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:
8606260057 860620 PDR ADOCK 0D000321 P
PDR t
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.127, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k
Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 20, 1986 l
i i
ATTACHMENT TO LICENSE AMENDMENT NO.127 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 1
Replace the following page of 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.
Remove Insert 3.13-2 3.13-2 i
e 4
j i
a 1
i l
1 4
i
i i..
l TABLE 3.13-1 FIRE DETECTORS MINIMUM OPERABLE BUILDING NUMBER OF DETECTORS DETECTORS REQUIRED A.1 Control Building El.112'-0" 1.1 Station Battery Room lA 2
1 l.2 Station Battery Room IB 2
1 1.3 Corridor and Work Area 15 7
1.4 RPS Vertical Cableway 4
2 A.2 Control Building El.130'-0" 2.1 Switchgear Rooms lA, 18, (1 in each IE, 1F, and Transformer Room 8
room or 5) 2.2 Corridor 7
3 2.3 RPS Vertical Cableway 2
1 2.4 East Cableway 15 7
A.3 Control Building El.147'-0" 3.1 Switchgear & MCC Area N.W. Corner 7
3 3.2 Switchgear & MCC Area N.E. Corner 4
2 3.3 Cable Spreading Room 50 25 3.4 LPCI Inverter Room 9
5 l
[
A.4 Control Building El.164'-0" 1
4.1 Control Room Unit 1 35 18 l
4.2 Control Room Unit 2 15 8
l 4.3 Peripheral Rooms 4
(1 in each roomor4)
B.1 Diesel Generator Building 1.1 Switchgear Room lE 4
2 l.2 Switchgear Room IF 4 ;
2 1
1.3 Switchgear Room 1G 4
2 1.4 Battery Room 1A 1
1 1.5 Battery Room 18 1
1 1.6 Battery Room IC 1
1 C.1 River Intake Structure 1.1 Building Area 11 5
D.1 Reactor Building El.130'-0" i
1.1 North Cable Tray Area, 1
Remote Shutdown Area, and North CRD Area 33 16
)
1.2 South Cable Tray and South CR0 Area 35 17 D.2 Reactor Building El.158'-0" 2.1 HVAC Room 20 10 3.13-2
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