ML20072K335
| ML20072K335 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 03/22/1983 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA |
| Shared Package | |
| ML20072K338 | List: |
| References | |
| TAC 49705, DPR-57-A-095 NUDOCS 8303300509 | |
| Download: ML20072K335 (5) | |
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UNITED STATES
[Dgr [, g NUCLEAR REGULATORY COMMISSION g, j WASHINGTON, D. C. 20555
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GEORGIA POWER COMPANY OGLETHORPE POWEd CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCri NUCLEAR PLANT UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendm'ent No. 9 5 License No. DPR-57 1.
The Nuclear Regulatory Commission.(the Commission) has found that:
A.
The application for amendment by Georgia Power Conpany, et ali, (the licensee) telecopied February 22, 1933, as confirmed March 2,1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the.
Cocinission's rules and regulations set forth in 10 CFR Chapt,er I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulation:. 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; D.
The issuance of this amendment will not. be inimical to the comon defense and security or to the health and safety of the publ.ic; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable req 1rements have been satisfied.
s-2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License Nc. DPR-57 is hereby amendec to read as follows:
Technical Scecifications 1
The Technical Specifications contained in Appendices A and 3, as revised through Amendment No.9 5, are hereby incorporated in the' license. The licensee shall operate the facility in Ncordance with the Technical Specifications.
8303300509 830322 PDR ADOCK 05000321 P
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This amendment was effective February 22, 1983, and expired February 25, 1983.
FOR THE NUCLEAR REddLATORY COP 9(ISSION Jo in F. Stolz, Chief 0 rating Reactors Br nch #4 vision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: MAR 2 21983 e
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ATTACHMENT TO LICENSE AMENDMENT NO.9 5 FACli.ITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
lhe revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
Remove
' Insert 3.7-9 3.7-9 3.7-10
- 3. 7-1-0 e i e
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LIMITING CONDITIONS FOR CPERATION SURVEILLAPCE REQUIREENT5 3.7.A.5 0xygen Concentration 4.7.A.5 0xyaen Concentration
- a. After completion of the startup The primary contairment test program and demonstration oxygen concentration shall of plant electrical output, the be measured and recorded primary containment atmosphere daily in the main control shall be reduced to less than room.
4% oxygen with nitrogen gas dur-ing reactor power operation with reactor S olant pressure above 100 psig, except as stated in Specification 3.7. A.5.b.
b.
Within the 24-houz* period sub-
- A 72-hour period is allowed sequent to placing the reactor for the startup in progress in the Run Mode following a shut-on February 22,1983.
down, the containment atmosphere
- oxygen concentration shall be re-duced to less than 4% by voltne and a.aintained in this condition. De-inerting may commence 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a shutdown.
- 6. Containment At:esobere Dilution (CAD) 6.
Containment Atmosphere Dilution (CAD)
- a. Operability Recuirements
- a. Functional Test After completion of the startup test The pdst-LOCA Containmer't program and demonstration of plant Atmosphere Dilution (CAD) electrical output and thereafter System shall be functionally whenever the reactor is in power tested once per operating operation, the post-LOCA containment cycle.
Atmosphere Dilution (CAD) System must be operable and capable of supplying rdtrogen to the primary containment for dilution if. required.
by post-LOCA conditions. If this specification cannot be met, the system must be restored to an operable condition within seven days or the reactor must be taken out of power operation.
- b. Seven-Day Nitrogen Supply Seven-Osy Nitrogen Sucoly After completion of the startte test The level in the liquid program and demonstration of plant nitrogen storage tanks electric output and thereafter shall be recorded twice whenever the reactor is in power
If this specification cannot be met, the minimum voltne will bei restored within seven days or the reactor must be taken out of power operation.
l Amendnent flo..S&, 9 5 3.7-9 w
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LIMITING CONDITIDNS FOR OPERATION SURVELLLAKE Kr.QU tKr.MrAn>
Arelyzu 4.7.A.6.c.
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3.7.A.6.c. E2 '"d U2 2
Whenever the reactor is in power Instrumentation surveillance is -
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operation, there shall be at least listed in Table 4.2-11.
one CAD System H2 and 02 analyzer serving the primary containmant.
If one H2 and 02 analyzer is in-operable, the reactor may remain in operation for a period not to exceed seven days.
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- d. Post-LOCA Repressurization Limit The maximun post-LOCA primary con-tainment repressurization limit allowable using the CAD System shall be 30 psig. Venting via the SGTS to the main stack must be initiated at 30 psig following the initial post-LOCA pressure peak.
7.
Drywell-Sucoression Chamber 7.
Drywell-Sucoression Chamber Differential Pressure Differential Pressure Differential pressure between the The pressure differential drywell and suppression chamber,shall between the dIywell and be maintained equal to or greater suppression chamber shall than 1.5 psid except as specified in be recorded once each shift.
(1) and (2) below: If this specifica-tion cannot be met, and the differential pressure cannot be restored within the subsequent six (6) hour period, an orderly shutdown shall be initiated and the reactor shall be in a Hot Shutdown condition in six (6) hours and a Cold Shutdown condition in the following eighteen (18) hours.
- 1) This differential pressure shall be established within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> *
- A 72-hour period is allowed after having placed the Mode for the start-up in progress
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Switch in the RUN mode. The dif-on February 22,1983.
ferential pressure may be removed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to achiev-ing a shutdown.
- 2) This differential pressure may be decreased to less than 1.5 psid for a maximun of four hours during required operability testing of the FPCI system pump, the RCIC system pump, and the dIywell-pressure suppression chamber vacuun breakers.
Amendment' No. R,,W,9 5 3,7 10
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