ML20069F564
| ML20069F564 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/27/1982 |
| 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 | |
| ML20069F566 | List: |
| References | |
| TAC 47885, DPR-57-A-090 NUDOCS 8209280134 | |
| Download: ML20069F564 (5) | |
Text
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NUCLEAR REGULATORY COMMISSION r,
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GEORGIA POWER COMPANY
- l OGLETHORPE POWER CORPORATION 4
MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA l
CITY OF DALTON, GEORGIA DOCKET NO. 50-321 N
EDWIN
. HATCH NUCLEAR PLANT.I NIT NO.1 U
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AMENDMENT TO FACILITY OPERATaING LICENSE
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Amendment No. 90 j
jLicenseNo.DPR-57 t
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1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) telecopied February 8,1982, as confimed April 5, 1982,. 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 confomity 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; l.
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.
8209280134 820827 PDR ADOCK 05000321
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2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license anendment and paragraph 2.C.(2) of Facility Operating License No. OPR-57 is hereby amended to read as follows:
(2) Technical Specifications i
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 90, are hereby incorporated l
in the, license.. The licensee shall operate the facility in
- t accordance wity the Technical Specif.ttations.
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3.
This amendment was effective February 8,1982 and expired February 10, 1982.
FOR Th NUCLEAR REGULATORY COMMISSION '
I Johh F. Stolz, Chief j)
Op, rating Reactors Branch #4 j
D ision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 27, 1982 f
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l ATTACHMENT TO LICENSE AMENDMENT NO.90 l
I FACILITY OPERATJNG LICENSE NO. DPR-57 DOCKET NO. 50-321 J
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. Tie revised pages are identified by Amendment nunber and contai.n a ertical line indicating the area of change, s
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' Insert Remove 3.7-9 3.7-9 j.
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LIMITING CotOITIONS FOR CPERATION SURVEILLAPCE REQUIREbENT5 3.7.A.5 O_xygen Concentration 4.7.A.5 0xygen Concentration 3
- 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 l
primary containment atmosphere daily in the main control shall be reduced to less than room.
i 45 oxygen with nitrogen gas dur-ing reactor power operation with reactor coolant pressute above 100 psig, except as stated in Specification 3.7.A.5.b.
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- A 72-hour period is' allowed 24-hour + period sub- :$
for the startup in progress b.
Within th sequent to placing the reactor in the Run Mode following a shutg on February 7,1982.
down, the containment atmosphereK oxygen concentration shall be re-duced to less than 4X by volume and,,
maintained 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 Atmosphere Dilution (CAD) 6.
Contairment Atmosphere I
Dilution (CAD)
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- a. Ocerability Requirements
- a. Functional Test L
l After completion of the startup test The post-LOCA Containment program and demonstration of plant Atmosphere Dilution (CAD) electrical output and thereafter Sy stem shall be functionally l
whenever the reactor is in power testeo once per operating i
operation, the post-LOCA containment cycle.
Atmosphere Dilution (CAD) System must be operable and capable of supplying nitrogen to the primary contairment for dilution if, required.
by post-LOCA conditions. If this specification cannot be met, the system must be restored to an 1
operable condition within seven days
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or the reactor must be taken out of I
power operation.
- b. Seven-Day Nitrogen Sucoly Seven-Day Nitrocen Supply After completion of the startup test The level in the liquid program and dernonstration of plant nitrogen storage tanks electric output and thereafter shall be recorded twice whenever the reactor is in power weekly.
operation, the CAD System shall con-tain a minimum of 2000 gallons of liquid nitrogen.
If this specification cannot be met, the minimum volume will be restored within seven days or the reactor must be taken out of power coeration.
Amendment No. 90 3,7_9
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SURVEILIMifE' REQUIREMENTS LIM 111NG CONDITIONS FOR OPERATION E 'T"d 02 ^^*17*S' Analyz'r 4.7.A.6.c.
3.7. A.6.c. E2 *"d U2 2
whenever the reactor is in power
'. Instrumentation su' ve111ance is
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r operation, there shall be at least' listed in Table 4.2-11.
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one CAD System H2 and 02 analyzer serving the primary contairinent.
If one H2 and 02 analyzer is in-operable, the reactor may remain in operation for a period not to exceed seven days.
- d. Post-LOCA Repressurization Limit The maximum post-LOCA primary con-tainment repressurization limit allowable using the CAD System i shall be 30 psig.jventing via the SGTS to the main stack must be
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initiated at 30 psig following the initial post-LOCA pressure peak.
7.
Drywell-Sucpression Chamber 7.
Drywell-Suppression Chamber Differential Pressure g.DifferentialPressure Differential pressure between the The pressure differential drywell and suppression chamber shall between the drywell and be maintained equal to or greater suppression chamber shall.
than 1.5 psid exce.pt 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 Switch in the RUN mode. The dif-on February 7,1982.
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 IPCI. system punp, the RCIC system punp, and the drywell-pressure suppression chamber vacuum breakers.
Amendment No. 55,90
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