ML19350D413

Amend 82 to License DPR-57,relieving Licensee of Necessity to Maintain Two Operable Diesel Generators When Fuel Has Been Removed from Reactor Vessel

ML19350D413
Person / Time
Site:	Hatch
Issue date:	04/08/1981
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
ML19350D415	List: ML19350D413 ML19350D417
References
TAC 43627, DPR-57-A-082 NUDOCS 8104150454
Download: ML19350D413 (5)

Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION

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r WASHiNCTON D. C 20555 s, * *v [f

'1 GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION g

MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-m EDWIN I. HATCH NUCLEAR PLANT, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 82 License No. DPR-57 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Georgia Power Company, et al.,

(the licensee) dated April 2,1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in confomity with the application, 3

the provisions of the Act, and the rules and regulations of the l

Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health I.

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 common defense and security or to the health and safety of the public; l

and l

E.

The issuance of this amendment is in accorcance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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 No. DPR-57 is l

hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 82, are hereby incorporated l'

l in the license. The licensee shall operate the facility in i

accordance with the Technical Specifications.

k 8184150

_2 3.

This amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY C0fMISSION LLC 1

J n F. Stolz, Chief j

erating Reactors Branch #4 Division of Licensing

]

Attachment:

l Changes to the Technical Specifications l

Date of Issuance: April 8,1981 l

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ATTACHMENT TO LICENSE AMENDMENT fl0. 82 FACILITY OPERATING LICENSE fl0. DPR-57 DOCKET N0. 50-321 Replace the following pages of the Appendix "A" Technical Specifications with the Enclosed pages.

he revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Insert Remove 3.9-6 3.9-6 3.9-6a 3.9-6a e

~1,IMITING CONDITIORS FOR OPERATION SURVEILLANCE REQUIRE.4ENTS 3.9.B.3. One 125/250 Volt DC Power Svstem (Plant Battery LA or 1B) Inoper-eble (Continued) and the increased Surveillance Requirements as stated in Speci-fication 4.9.B.3 are implemented.

4. Emergency 4160 Volt Buses (lE, 1F, or 1G) Inoperable One of the emergency 4160 volt buses (1E, 1F, or 1G) may be in-operable for a period not to execed seven (7) consecutive days provi-ding the other two emergency 4160 volt buses and associated ECCS equipment are operable.

5. Emergency 600 Volt Buses (lC or ID) Inoperable One of the emergency 600 volt buses (lC or 1D) =ay be inoperable for a period not to exceed seven (7) days providing the other 600 volt bus is operable.

6. Emergency 250 Volt DC to 600 Volt AC Inverters One of the c=ergency 250 volt DC to 600 volt AC inverters may be inoperable for a period not to exceed seven (7) consecutive days providing the other inverter is operable.

C. Diesel Generator Recuirements (Reactor in the Shutdown or Refuel Mode)"

l Ehenever the reacter is in either the Shutdcwn or Refuel Mode, a minicum of two diesel generators shall be operable whenever:

• This specification is not applicable when fuel is not in the reactor pressure vessel; however, one diesel generator shall be operable and aligned to supply power as follows:

a.

To provide fuel pool cooling capability; and b.

To provide power for or.e train of SGTS when secondary containment is required.

Am:ndment No. jer,82 3.9-6

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS C.

Diesel Generator Requirerents (Reactor 4.9.D Electric Power Monitorine for in the Shutdown or Refuel Mode)

Reactor Protection Sys em

' (Continued) 1.

Work is being done which has the Specifications:

potential for draining the reactor pressure vessel, or 1.

The Electric Power Monitoring for the Reactor Protection System 2.

Secondary containment is required, shall be demonstrated operable:

or 3.

A c' ore or containment cooling sys-(a) At least once per 6 months

).

tem is required.

by perfaming a FUNCTIONAL

TEST, D.

Electric Power Monitoring for the Reactor Protection System (b) At least once per operating cycle by demonstrating the OPERASILITY of under-voltage, Scecifications:

over-voltage and under-fre-quency protective instrumenta-l'.

When either of the RPS MG sets or the tion by perfomance of a CHANNEL Alternate Source is in service, its CALIBRATION including simu-power monitoring system shall be lated automatic actuation of OPEPABLE.

the protective relays, trip-ping logic and output cir-(a)

If the power monitoring system 1c cuit breakers and verifying not OPERABLE and Operability the following setpoints:

cannot be restored within 30 cinutes of discovery, remove the (1) Over-voltace <l52 VAC, power suoply from service immediately

~ -

thereafter.

(2) Under-voltage 1108 VAC, with time delay relay set l

(b) One channel of a power monitoring to zero*

l system may be inoperable, as necessary for test or maintenance, (3) Under-frequency 157 HI, not to exceed 8, hours per r:anth.

with time delay relay set to zero*

1 I

I i

• Pending NRC approval of different value.

I li Amendment No. X, 82 3.9-Ca 6

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