ML20211P409
| ML20211P409 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 10/08/1997 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20211P411 | List: |
| References | |
| NUDOCS 9710200188 | |
| Download: ML20211P409 (4) | |
Text
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t UNITED STATES s
NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 30m0001 SOUTHERN NUCLEAR OPERATING COMPANY. INC.
4 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 1
i AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 209 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 the Southern 1
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 May 9,1997, or, supplemented September 19,1997, 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 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 requiremerns have been satisfied, s
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.ntc 9710200100 971000 PDR ADOCK 05000321 P
PDR 7
l 2-2.
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)
.T.achnical Snacifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.209, are hereby incorporated in the license.
Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective prior to the restart from the Hatch Unit 1 outage currently scheduled to begin in October 1997.
FOR THE NUCLEAR REGULATORY COMMISSION a
H rt N. Berkow, Director 4
P oject Dbactorate ll 2 i
Division of Reactor Projects 1/11 Office of Nuclear Reactor Regulation i
Attachment:
Technical Specification Changee
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Date of issuance: October 8, 1997
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i ATTACHMENT TO LICENSE AMENDMENT NO. 209 i
FACILITY OPERATING LICENSE NO. DPR 57 1
DOCKET NO. 50 321 i
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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 areas of change, l
Remove 104td 2.0 1 2.01 l
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i SLs 2.0 1
2.0 SAFETYLIMITS(SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:
THERMAL POWER shall be s 25% RTP.
j 2.1.1.2 With the reactor steam dome pressure k 785 psig and core 1
flow = 10% rated core flow:
s MCPR shall be = 1.10 for two recirculation loop operation
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or k 1.12 for single recirculation loop operation.*
2.1.1.3 Reactor vessel water level shall be greater than the top i
of active irradiated fuel.
2.1.2 Reactor Coolant System (RCS) Pressure SL Reactor steam dome pressure shall be si1325 psig.
The specified limits are for Cycle 18 only.
l 2.2 SL Violations l
With any SL violation, the following actions shall be completed:
2.2.1 Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, notify the NRC Operations Center, in accordance with 10 CFR 50.72.
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2.2.2 Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.2.1 Restore compliance with all SLs; and 4
j 2.2.2.2 Insert all insertable cor. trol rods.
2.2.3 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the plant manager, the corporate executive responsible for overall plant nuclear safety, and the offsite review committee.
(continued)
HATCH 'JNIT 1 2.0-1 Amenduent No. 209
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