ML20082H501

Suppl to 910627 Application for Amends to Licenses DPR-29 & DPR-30,changing TS Sections 1.1/2.1, Fuel Cladding Integrity & 1.2/2.2, RCS Changing 800 Psig to 800 Psia in Specs 1.1.A & 1.1.B

ML20082H501
Person / Time
Site:	Quad Cities
Issue date:	08/15/1991
From:	Stols R COMMONWEALTH EDISON CO.
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML20082H507	List: ML20082H501 ML20082H508
References
NUDOCS 9108260144
Download: ML20082H501 (2)

Text

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i August 15,1991 t

Dr. Thomas E. Murley, Director  ;

Office of Nuclear Reactor Regulation U.S. Nuclear Regblatory Commission Washington, DC 20555 Attn: Document Control Desk

Subject:

Quad Cities Nuclear Power Station Units 1 and 2 ,

Supplement to A plication for Amendment to }

Facility Operatin Licenses DPR 29 and DPR 30 Appendix A, Tec nical Specifications Technical Specification Upgrade NBC_DocheLNosu50:251and_50 26 Pro 0 ram  ;

Reference:

R. Stols letter to NRC dated (u) June 27,1991

Dear Dr. Murley:

As art of the Quad Cities Technical Specifications Upgrade Program, Reference ( submitted Commonwealth Edison's request for an amendment to Facility  :

Operating L censes DPR 29 and DPR 30, Appendix A, Technical Specification i Sections 1.1/2,1, " Fuel Cladding Integrity" and 1.2/2.2, " Reactor Coolant System".

Subsequent to the above referenced letter, it was noted that an Intended ,

change to proposed Section 1.1/2.1 had been omitted from the submittal. To correct 1 this omission, this supplement changes "800 psig" to "800 psla" In proposed +

Specifications 1.1.A and 1.1.B and changes "... greater than 800 psig and core flow c greater than 10% .." to "... greater than or equal to 800 psia and core flow greater than l er equal to 10%..." In proposed Specification 1.1.A.

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4 Dr. Thomas E. Murley 2- August 15,1991 Replacement pa cubmitted in Reference _

are(a)ges enclosed1.1/2.1 herein. 1 and 1.1/2.13 to proposed Section 1.1/

Please direct any questions concerning this proposed amendment to R. Stols -

at (708) 515 7283. j i

l Very truly yours, l h ,

Rita Stols Nuclear Licensing Administrator 4 t

Enclosure (A): Heplacement pages 1.1/2.1 1 and 1.1/2.13 to proposed amend ment to Technical Specification Section 1.1/2.1, " Fuel Cladding Integrity" cc: A. Bert Davis, Regional Administrator Rill L.N. Olshan, Project Manager NRR T.E, Taylor, Senior Resident inspector Ouad Cities Illinois Department of Nuclear Safety

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