ML20237K165
| ML20237K165 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/24/1987 |
| From: | Rood D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20237K169 | List: |
| References | |
| TAC-65248, TAC-65249, NUDOCS 8708270079 | |
| Download: ML20237K165 (8) | |
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..s 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 NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE l
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l 1.
The Nuclear Regulatory Comission (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 Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, (the licensee) dated March 27, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amende(i (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 1
1 B.
The facility v., 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 Comission's regulations set forth in 10 CFR l
Chapter I; D.
The issuance of this ameno.nent 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.
8708270079 870824 PDR ADDCK 05000321 P
__________.___.________.____m___________
. 2.
Accordingly, the license is amended by changes to the Technical Specifi-cations 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 Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.146, 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 Darl Hood, Acting. Director Project Directorate II-3 Division of Reactor Projects-I/II
Attachment:
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Changes to the Technical Specifications t
Date of Issuance:. August 24, 1987 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 146 s
FACILITY OPERATING LICENSE N0. OPR-57 1-DOCKET NO. 50-321 Replace the following-pages of the Aprendix A Technical Specifications with the enclosed ~pages. The revised page is. identified by amendment number and contains vertical lines indicating the areas of change.
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GEORGIA POWER COMPANY OGLETHORPE P0"ER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-366 i
EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 l
AMENDMENT TO FACILITY OPERATING LICENSE l
I Amendment No. 82 l
License No. NPF-5 J
l 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 Georgia Power Company, acting for itself, Oglethorpe Power i
Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, (the licensee) dated March 27, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations 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 Conrnission; 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,f 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 anendment 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 amended l'y changes to the Technical Specifi-cations 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:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 82, 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 i
be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION j
l Darl Hood, Acting Director Project Directorate 11 '3 Division of Peactor Projects-I/II Attachraeilt:
Changes to the Technical Specifications Date of Issuance: August 24, 1987 i
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08/ / /87 08// 7 /87 08/$/8708/Jo/87 08/ g /87
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N ATTACHMENT TO LICENSE AMENDMENT-NO. 82 FACILITY OPERATING LICENSE NO. NPF DOCKET NO. 50-366 Replace the following pages of-the Appendix A Technical Specifi. cations with the enclosed pages. The revised page is identified by amendment number and contains. vertical lines indicating the areas of change.
Renove Insert Page Page 3/4 5 3/4 5-6 4
k i
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2.
Performing a CHANNEL CALIBRATION of the core spray header AP instrumentation and verifying the set point to be s 3.1 psid greater (less negative) than the normal indicated AP at rated core power and flow, d.
At least once per 18 months by performing a system functional test which includes simulated automatic actuation of the system throughout its emergency operating sequence and veri-fying that each automatic valve in the flow path actuates to its correct position.
Actual injection of coolant into the reactor vessel may be excluded from this test.
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HATCH - UNIT 2 3/4 5-6 Amendment No. 82 i
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