ML20097J909

Application for Amend to License DPR-57,changing Tech Specs to Allow Up to Four Bundles to Be Loaded in Previous Positions Around Source Range Monitor in Order to Establish Required Three Counts Per Second

ML20097J909
Person / Time
Site:	Hatch
Issue date:	09/17/1984
From:	Beckham J GEORGIA POWER CO.
To:	Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML20097J911	List: ML20097J909 ML20097J920
References
NED-84-462, TAC-55813, NUDOCS 8409240107
Download: ML20097J909 (3)

Text

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Georg.a Power Company 333 Piedmont Avenue Acanta Onorg a 30308

• Tctephone 404 526-7020 Maibrg Address Post offee Box 4545 A!!anta. Georg:a 30302 Georgia Power f!'e souhern electre syncm J. T. Beckham, Jr, '

Vice Presrdent aad General Manager Nuclear Generahon NED-84-462 Septaber 17, 1984 Director of Nuclear Reactor Regulation

-Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Ccumission Washirgton, D. C. 20555 NRC DOCITr 50-321 OPERATING LICENSE DPR-57 EDWIN I. HA'ICH MX1 EAR PIANT UNIT 1 REQUEST FOR TECHNICAL SPECIFICATIONS CHANGE Gentlemen:

In accordance with the provisions of 10 CFR 50.90, as required by 10 CFR 50.59 (c) (1) , Georgia Power Cmpany hereby proposes an mendment to the Technical Specifications (Appendix A to the Operating License) for Plant Hatch Unit 1. 'Ihese proposed changes will:

1) allow up to four bundles to be loaded in their previous positions around a Source Range Monitor in order to estaolish the required three counts per second;

. 2) delete the description of control rod material to provide for the use of improved hydrid control rod assablies; and

3) revise the definition of CORE ALTERATION to clatify that the definition applies only with fuel in the vessel.

'Ibe Plant Review Board and Safety Review Board have reviewed these proposed changes to the Unit 1 Technical Specifications (Attachment 1) and have concluded that the proposed changes do not involve an unreviewed safety question. Also, the proposed changes have been evaluated and determined not to involve a significant hazards considerations. Enclosed (Attachment 2) is a' technical discussion and significant hazards evaluation.

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Director S of Nuclear ' ReL: tor ' Regulat. ion -

TAttention:> Mr. John F. Stolz, Chief .

' Operating' Reactors Braach.No. 4 4 Septaber 17, 1984'

Page?'No; i . ..

. l%es proposed changes to the Technical Specifications requested by iten 1

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,above do1 not': increase: the probability of occurrence or. consequences of a previously. analyzed accident or malfunction of equignent important to safety a har*% spent fuel studies (reference: GESSAR, NEDO-10741, Chapters 4 and.9).

bundles is not possible.-

deonstratejinadvertent' criticality with' 4

.Further,:the sme 'subcritical assablies and arrangement that was discharged'

'is' returned to the'sme core location. We possibility of- occurrence of an 4 accident differentithan : any : evaluated in the FSAR .is not created because there;is1 no design change to 'any plant . systens. Finally, the safety margin 4 -

isifnot freduced .because the bundles renain considerably subcritical.

Consequently, this change does not represent an unreviewed safety question.

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%e proposed changes to the Technical Specifications requested by iten 2

~ aboveido .not11ncrease the probability of occurrence 'or consaluences of a 7

previously analyzed

accident'or malfunction of Lequipnent important to safety

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because:the control rod' worth of the Hybrid I Control 1 Blades (HICR) is the L sane as the 'existingldesign and because existing; methodology for transient

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and ~ accident ' analysis' renains valid with the HICR^ assemblies installed. %e possibility of' occurrence of an accidet different.than any evaluated in the

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PSAR :is: not created ' by the use. of the HICR assemblies, because there is - no ,

~ functional . change 'in the control rods.. Finally, ~ because HICR weight, rod

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' worth, scran t speed and scran reactivity are : the same as control rods a currently is: use, safety margins specified 'in Technical Specifications - are not reduced.- Consequently, this - change does lnot represent an unreviewed safety questiont u

Because thel proposed changes to Technical Specifications requested .by iten!3 above only. revise a-definition in order to clarify.what constitutes a-CORE ALTERATION, the changes do not' increase the probability or consequences

ofia previouslyf analyzed' accident, do not create a different type accident, e ., -'

nor>'are -safety margins specified . in . Technical Specifications changed.

1Conseguently, this 'adninistrative change. does not constitute an' unreviewed .

L safety question.-

Pursuantz to :10 f CFR 170.21, ' a check . for the- amendnent application of i -

'8150.00 is enclosed..

' Pursuant :tolthe. requirenents of 10 CFR 50.92, J. L. Ledbetter of the Georgia -

Department of Natural' Resources will be sent a copy of this letter and all '

' applicable attachments.

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Georgia Power d Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Septenber 17, 1984 Page Three J. T. Beckhs,' Jr. states that he is Vice President of Georgia Power Cmpany and is authorized to execute this oath on behalf of Georgia Power Cmpany, and that to the best of his knowledge and belief the facts set forth in this letter are true.

GEORGIA POhH C31PANY By: O -

17c4v pJ.T.Beckhm,Jr./

' Sworn to and subscribed before me this 14th day of Septenber,1984.

pt 8, 7 D /[IO / / d Notary Public i r DLT/inb Enclosure xc: H. C. Nix, Jr.

Senior Resident Inspector J. P. O'Reilly, (NRC-Region II)

J. L. Ledbetter

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