ML20247M491
| ML20247M491 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 05/25/1989 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247M494 | List: |
| References | |
| NUDOCS 8906050053 | |
| Download: ML20247M491 (5) | |
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' NUCLEAR REGULATORY COMMISSION UNITED STATES
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- WASHINGTON, D. C. 20655
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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 NO. 1 AMENDMENT TO FACILITY 0PERATING LICENSE Amendment No.162 License No. DPR-57 1.
The Nuclear Regulatory Consission (the Consnission) has found that:
The app (lication for amendment to the Edwin I. Hatch Nuclear Plant, A.
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 May 4, 1984, as amended September 12, 1984, August 19, 1987, and May 16, 1989 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 Connissior:;
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 Consiission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common oefense and security or to the health and safety of the public; and
.E.
The issuance of this aniendment is in accordance with 10 CFR Part 51 of the Connission's regulations and all applicable requirements have been satisfied.
G906050053 890525 7
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,n 2. -.Accordingly, the license -is anended by changes to the Technica1 '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)1'TechnicalSpecifications The Technical Specifications contained in Appendices A'and B, as revised through Amendment No.162, are herehy 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
.Matthews,k1 rector David Project Directorate II-3 Division of Reactor Projects-I/II-Office of Nuclear Reactor Regulation
Attachment:
Changes-to the Technical Specifications Date of Issuance:
!1ay 25,1989 i
ATTACHMENT TO LICENSE _AMENpf,ENLNp,,162
' FACILITY OPERATING LICENSE NO. DPR-57
~ DOCKET NO. 50-321 Replace.the following page of the Appendix A Technical Spec;;ications with the enclosed page.
The revised page is identified by amendment number and j
l contains a vertical line indicating the area of change.
_ Remove Page Insert Page 1.0-3 1.0-3 I
i l
l I
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__----O
K.
Instrument checit - An instrument check is the qualitative determination o" accept 4ble operability by observation of instrument behavior dur)ng operation This determination
, shall include, wh'ere pr ssible, compar.ison of the instrument with other independent instruments measuring the same variable.
L.
Instrument Functional Test - An instrument functional test means the injection of a simulated signal into the instrument primary sensor to verify the proper instrument channel response, alarm and/or initiating action.
M.
Limitino Conditions for Oeeration PLCD) - The limiting conditions for operation specify the acceptable levels of system performance necessary to assure safe startup and operation of the Unit.
When these conditions are met, the Unit can be operated safely and abnormal situations can be safely controlled.
4 M.
Limitino Safety System Sottino (LSES) - The limiting safety system settings are sett< ngs on instrumentation which initiate' the automatic protective action at a level such that a Safety I
Limit will not be exceeded. The region between the Safety Limit and these settings represents margin with normal operation lying on the conservative side of these settings. The margin g
has been established so that with proper operation of the e
instrumentation the Safety Limits will never be exceeded.
O.
Looic System Fune':ional Test - A logic system functional test means a test of all relays and contacts of a logic circuit from sensor to activated device to insure that components are operable per design intent.
Where practicable, action will go to completion; e.g., pumps will be started and valves opened.
p.
(Deleted)
Q.
Doerable - A system, subsystem, train, component or device shall be operable or have operability when it is capable of perfoming its specified function (s). Implicit in this definition shall be the assumrtion that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seel water, lubrication or other auxiliary equipment that are rsquired for the systes, subsystem, train, coponent or device to perform its functio'(s) are aim capabit of performing their n
related support function (s).
R, Operating - Operating means that; a system or comnonent is nerforming its intended functions in its recuired manner.
HATCH - UNIT 1 1.0-3 Amendment No. 162 i
p 1
- 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.162, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective os of its date of issuance and shall be implemented within 60 days of issuance.
FOR TiiE NUCLEAR REGULATORY COMMISSION Original Signed By:
David B. Matthews David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/11 Office of Nuclear Reactor Regulation l
Attachment:
Changes to the Technical Specifications Date of Issuance: liay 25, 1989 i
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