ML19322B390

Amend 14 to License DPR-55 Incorporating Tech Spec Change 14.Proposed Tech Specs Encl

ML19322B390
Person / Time
Site:	Oconee
Issue date:	12/22/1975
From:	Galler K Office of Nuclear Reactor Regulation
To:
Shared Package
ML19322B379	List: ML19322B378 ML19322B382 ML19322B386 ML19322B390 ML19322B392 ML19322B396 ML19322B399 ML19322B401
References
NUDOCS 7912020238
Download: ML19322B390 (5)

Text

0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20555 9

DUKE POWER COMPANY nocrFT NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO FACILITY OPEPATING LICENSE Amendment No.1 4 License No. DPR-5.5 l

The Nuc1 car Regulatory Commission (the Commissi,on) has found that:

1.

The application for amendment by Duke Power Company (the A.

licensee) dated September 12, 1975, complies with the standards and requirements-of the Atomic Enargy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, B.

the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized C.

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; and The issuance of this amendment will not be inimical to the common D.

defense and security or to the health and safety of the public.

Accordingly, the license is amended by a change to the Technical 2.

Specifications as indicated in the attachment to this license amendment and Paragraph 3.B of Facility License No. DPR-55 is hereby amended to read as follows:

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Technical Specifications

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The Technical Specifications contained in Appendices A and B, as revised, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications, as revised by issued changes i

thereto through Change *No.14."

3.

This license amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY C0hMISSION Oricid :

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.EarLGoller _,,

Karl R. Goller, Assistant Director for Operating Reactors Division of Reactor Licensing

Attachment:

Change No.I 4 to the Technical Specifications Date of Issuance:

DEC 2 21975 N

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A'ITACHMENT TO LICENSE AMENDhENTS 1

AMENDMENT NO.17 TO FACILITY LICENSE NO. DPR-38 CHANGE NO.o,TO TECHNICAL SPECIFICATIONS; AMENDMENT NO.17 TO FACILITY LICENSE NO. DPR-47 CHANGE NO. 2 2 TO TECHNICAL SPECIFICATIONS; AMENDMENT N0.1 4 TO FACILITY LICENSE NO. DPR-55 CHANGE NO.1 4 TO TECHNICAL SPECIFICATIONS DOCKET NOS. 50-260, 50-270 AND 50-287 Revise Appendix A as follows:

Remove pages 5.4-1 and 5.4-la and insert identically numbered pages.

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l 5.4 NEW AND SPENT FUEL STORAGE FACILITIES Specification 5.4.1

_New Fuel Storage 5.4.1.1 New fuel will normally be stored in the spent fuel p the respective unit.

ool serving In the spent fuel pool serving Units 1 and 2 semblies are stored in racks in ' parallel rows, the fuel as-This spacing is sufficient to maintain a K effect ns.

an enrichment of 3.5 weightthan 0.9 when flooded with of less

, based on fuel with percent U In the spent fuel pool serving Unit 3 maintain a minimum edge-to-edge spacing of 3 t

which adjacent fuel assemblies.

aches between 27 storage cavity material combined with the minimum 3 95 edge-to-edge spacing between adjacent fuel assembli nches 22 sufficient to maintain a K effective of less than 0 95 es is flooded with unborated water, based on fuel with when 1 *,

of 3.5 weight percent U 35 2

an enrichment or the equivalent.

5.4.1.2 1

fuel assemblies are stored in five racks in anew er canal. The 4

nominal center-to-center distance o'f 2' 1 3/4" row having a oversized to receive a failed fuel assembly co t i One rack is other four racks are normal size and are capable of n a ner.

The new fuel assemblies.

receiving 5.4.1.3 New fuel may also be stored in shipping contai 5.4.2 ners.

Spent Fuel Storage 5.4.2.1 Irradiated fuel assemblies will be stored

shipment, in a stainless steel lined spent fuel po l, prior to offsite o.

The spent fuel pool servinh; Units 1 and 2 is si a full core of irradiated fuel assemblies in additized to concurrent storage of the largest quantity of new i

on to the fuel assemblies predicted by the fuel manageme t and spent n program.

Provisions are made in the Unit 3 spent fuel p up to 474 fuel assemblies.

ool to accommodate 7

5. 4. 2. 7.

loading), the spent fuel pool is filled with wateW 14 j

n t al core

. the concentration that is used in the reactor cavity and fue r borated to transfer canal during refueling operations t

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Spent fuel may also be stored in storage racks in the fuel j

5.4.'2.3 transfer canal when the canal is at refueling level.

The spent fuel pool and fuel transfer canal racks are designed 5.4.2.4 for an earthquake force of 0.lg ground motion.

REFERENCES FSAR, Section 9.7 i

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