ML20045G314
| ML20045G314 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/01/1993 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20045G315 | List: |
| References | |
| NUDOCS 9307130175 | |
| Download: ML20045G314 (7) | |
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UNITED STATES 1"
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NUCLEAR REGULATORY COMMISSION e
WASHINGTON, D.C. 205SW1 j
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 187 License No. DPR-57 l.
The Nuclear Regulatory Commission (the Commisrion) has found that:
A.
The applicatbn for amendment to the Edwin 1. Hatch Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-57 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 September 2, 1992, 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 (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 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.
9307130175 930701 PDR ADOCK 05000321 P
. 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 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.187 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 no later than 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
\\
David B.' Matthews, Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes l
Date of Issuance:
July 1, 1993 i
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WASHINGTON. D.C. 20555 4 001 GEORGIA POWER COMPANY OGLETHOPPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA DOCKET N0. 50-366 EDWIN I. HATCH NVCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.126 License No. NPF-5 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit 2 (the facility) Facility Operating License No. NPF-5 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalten, Georgia (the licensees), dated September 2, 1992, complies i
with the standards and requirements of the Atomic Energy Act of l
1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I-1 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.
1 j
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4 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-5 is hereby amended to read as follows:
Technical Sp_egifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 126, 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 no later than 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 4kef' David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
July 1, 1993 l-
6 ATTACHMENT TO LICENSE AMENDMENT N0.187 FACILITY OPERATING LICENSE NO DPR-57 DOCKET NO. 50-321 AND TO LICENSE AMENDMENT NO.126 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET N0. 50-365 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Paaes ipsert Paaes Unit 1 Figure 2.1-1 Figure 2.1-1 Unit 2 B 3/4 3-6 B 3/4 3-6 9
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NOTE. SCALEININCHES ASOVE VESSEL ZERO e
WATER LEVEL NOMENCLATURE HEIGHT ASOVE 800 -
VERSEL ZERO
$ 18NCHES)
R E ADING INSTR UMENT (81 573.S
+SSA BARTOWROSEMOUNT 750 - -
17)
ISS
+42 GE/MAC VESSE L tal 549
+32 OE/MAC
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FLANCE (3) 517 0.0 BARTON/ROSEMOUNT
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12) 470
- 47 BARTON/ROS4 MOUNT
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'404
- 113 BARTOWROSSMOUNT lol 315 202 BARTON/ROSEMOUNT 650 - -
-- 440 -
g,gg f
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. S77
- $73.8 ($1
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- 55917)
+40
$4.8 +40 -
+44 - -
R (0) g 7,,42 Hi ALARM 560 -e 540(4)
HPCI a, 141 32 LO ALARM OOTTOM OP STE AM RCIC YMM
-ORyER SulR7 517t3lNST R UME NT 0 - D(3) 0--
0(3F-RE ACTOR SCRAM ZERO S00 -
CONTRieUTE TO ADS
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- 470 01 C
-. 47 OW WW rem 2P
- 446 --- g,O R E ggy p
INITIATE HPCI, RCIC, g-450 - -
III 4oo
- -113 LOW LOW LOW (LIVEL 11 f
- 367
-150
- INITIATE RHR,C.S.,
3so -.384.54 START OlESEL ANO CONTRIBUTE TO A O.S.
l 2/3 CORg CLOSE M61V)
- 202 M E SCHT 315(0)
PE R MISSiv g 200 - -
(LEVELO)
ACTIVE FUEL 3so 317 - -
200
- M 54 Rf CIRC RECIRC
-178 4 OISCH ARGE
--*= SUCTION - 1815 NOZZL E NOZ2LE 160 - -
m-50 _ _
0.-
FIGURE 2.1-1 REACTOR VESSEL WATER LEVEL l
HATCH - UNIT 1 Amendment No.187
v 4
+
4 a
"T NOTE-ECALEININCHES ABOVE VESSEL ZERO WATER LEVEL NOMENCLATURE HEIGHT ABOVE 800 -
VESSEL ZERO
$ f tNCHist R E ADING INSTR UME NT (8) 573.5
+54.8 SARTON/ROSEMOUNT 750 -
1 71 869
+4 2 GE/MAC VESSE L tal 549
+32 GE/MAC U2
- ~
FLANGE (31 017 0.0 BARTON/MOSEMOtWT 12) 470 47 BARTON/ROSEMOUNT
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til 404 113 BARTON/MOSEMOUNT tot 315 202 BARTON/ROSEMOUNT C
640 yg s00 -
l
- gS t.,
{
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- $$9 878 (S) 171 42 HI ALARM 550 -= 54t(4)
HPCI & 44 1 '32 LO ALARM BOTTOM OF $TE AM
- ORYEREx4RT 517(3l ST UMENT 0 - 0(3) 0--
0(3F-RE ACTOR SCRAM ZERO CONTRIBUTE TO ADS LOW (LEVEL 3) 500 - -
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= 470 (2)
WATER CORE
~ ~ #I
- 446 SPRAY g
~ # III 400 -
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- -113 LOW LOW LOW (LEVEL il J
- 367
- 150 - - INITIATE RHR, C.S.,
'l 3gg,$g START DIESEL ANO l
CONTRIBUTE TO A.O S.
2/3 CORg CLOSE MSIV)
- 702 H E IGH T 318 (0)
P E R MIS $1V E M"
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(LEVE L O)
ACTIVE FUEL 250
-317 --
200 204 H RECIRC M
-178 54 -DisCH ARGE
' h W Puny Tr5 Amee deel Lindt is.58 Inshes 5 T ON - 161.5 NO22LE r
NO22LE 160 - -
too --
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50 - -
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u.o BASES FIGURE B 3/4 3-1
______MEM -ELLPL_
_ _ __ d fla_1-A _
Amendment No. 126