ML20005G383

Suppls 891117 Application for Amends to Licenses NPF-37 & NPF-66,incorporating Further Clarification of Curve Applicability in Tech Spec Figure 3.4-2a,per 891229 Telcon W/Nrc

ML20005G383
Person / Time
Site:	Byron
Issue date:	01/10/1990
From:	Schuster T COMMONWEALTH EDISON CO.
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML20005G384	List: ML20005G383 ML20005H332
References
RTR-REGGD-01.099, RTR-REGGD-1.099 0507T, 507T, NUDOCS 9001190079
Download: ML20005G383 (2)

Text

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%j /nOne Commonwealth Edison First National Plaza, Chicago, IInois '

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~h [ Address Reply to: Post Office Box 767 -

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January 10, 1990 i

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Dr. Thomas! E.: Miirley:

Office'of: Nuclear Reactor Regulation ,

[U.S. Nuclear Regulatory Commission 1 Washington, DC-- 20555

& -Attns:' Document Control Desk M, _ .

. Byron' Station Units'1 and 2 vt LSubject Supplement'to: Application for Amendment

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.to^ Facility Operating Licenses Nos. NPF-37 and NPF-66 l y NRC Docket Nos. 50-k54 and 50-455- i

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[ LReferences a) November 17, 1989 letter from R.A. Chrzanowski .

to Dr. T.E. Murley-g; 1

I DeariDr. Murley1- . d g ,

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) . .In referenceL(a), pursuant to 10 CFR 50.90, Commonwealth Edison I y . proposed to' amend Appendix A,1 Technical Specifications of Facility Operating-l License NPF-66._;The proposed changes to the Technical. Specifications included. l

' requested changes to Byron _ Unit 1 Reactor Coolant ~ System Heat-up' Limitation H

. Curve,' Figure;3.4-2a, to incorporate!a-reduced applicability limitation.  !

l Therefore,'we wish=to also' amend Facility Operating-License NPF-37 to include  !

f -the previously requested revision to Figure 3.4-2a. l p[

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Additionally, in response to NRC questions posed during a j December-20, 1989 phone conversation, we wish to change the proposed change to _j

Figurei3 4-2a to' incorporate'further clarification of curve applicability.

^The calculations; performed per Regulatory Guide 1.99 Revision 2, which .

..resulted inLthe: applicability < limitations to 29.5 EFPY (Reference 2), utilized

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• actualucoppericontent'of 0.05 Wt. % instead of the conservative 0.1 Wt. %'of -f the. existing curve. The new proposed change to Figure 3.4-2a provides further clarification of this applicability limitation. This change to Figure 3.4-2a,

[ :Tochnical Specification page 3/4 4-33, is attached.

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- The desired changes to the amendment for Figure 3.4-2a and ref erence a 'to'this am'ndment e in Facility License NPF-37 have been reviewed and approved Eby both.on-site and off-site review in accordance with 10 CFR 50.92(c). The

. remainder'of;the previous submittal [ reference (a)] remains as originally

requested. Since no new changes have occurred other than clarifying the

, . applicability and basis of the Unit 1 curve, the original safety analysis, significant hazards evaluation and environmental assessment remain valid.

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$P 3 9001190079 900110 PDR ADOCK 05000454

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0C gV: ' Dr. T.E Murir,y -

' 2- Jcnuary 10, 1990-o -;

h Additionally,'it is-permissible to distribute copies of the Letter

' Report MT/ SMART-078(89) prepared by Westinghouse Electric for Commonwealth l Edison. The Letter Report was contained in the original' amendment submittal'  ?

s of reference _(a).

Commonwealth Edison is' notifying the State of Illinois of this supplement -to the application. for the amendment by transmitting a copy of this

. letter and its attachments to~the designated State Official.

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Please direct any questions regarding this submittal to this office.

Very truly yours,

. 'T.K. Schuster  !

Nuclear Licensing Administrator l :' > 1

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/sc1:0507T:1-2 1

~ Attachment

.cc : Senior Resident Inspector-Byron

.L.N. 01shan-NRR Office of Nuclear Reactor Safety-IDNS

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