ML20206A814

Advises NRC of Review of Cycle 10 Reload Under Provisions of 10CFR50.59 & to Transmit COLR for Upcoming Cycle

ML20206A814
Person / Time
Site:	Byron
Issue date:	04/20/1999
From:	Levis W COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20206A817	List: M990004, Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function ML20206A814 ML20206A883
References
BYRON-99-0052, BYRON-99-52, NUDOCS 9904290037
Download: ML20206A814 (2)

Text

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. (bmm73nwealth lidimn Casmpany it) ton Generating $tation 4150 North German Church Road II) ron,11. 610109794 Tel H15-234 5441 April 20,1999 LTR: BYRON-99-0052 File:

1.02.1052.194 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-001 Byron Station Unit 1 Facility Operating License No. NPF-37 NRC Docket No. STN 50-454

Subject:

Core Operating Limits Report for Byron Station, Unit 1 Cycle 10 (BY1C10)

't Byron Unit i has recently completed its 9th cycle of operation and is currently preparing for Cycle 10 startup. The estimated startup date is Apri! 22,1999. The purpose of this letteris to advise you of our review of the Cycle 10 reload under the provisions of 10 CFR 50.59 and to transmit the Core Operating Limits Report (COLR) for the upcoming cycle.

The BY1C10 core, which consists of NRC-approved fuel designs, was designed to operate within approved fuel design criteria, Technical Spedfications and related bases such that:

1)

- core operating characteristics will be equivalent to or less limiting than those previously j

reviewed and accepted; or 2) re-analyses or re-evaluations have been performed to demonstrate that the limiting postulated UFSAR events which could be affected by the reload are within allowable limits.

k We have performed a detailed review of the revised reload licensing documents, the associated bases, and references. Based on that review, a safety evaluation was prepared, which concluded that the reload presents no unreviewed safety questions and requires no Technical Specification changes. The Byron Plant Review of the 10 CFR 50.59 Safety Evaluation has been completed in accordance with station procedures. Finally, further verification of the reload core design will be performed during startup testing.

9904290037 990420

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- April 20,1999 -

BYRON-99-0052 Page 2 U. S. Nuclear Regulatory Commission if there are any questions regarding this letter, please contact Mr. Brad Adams at (815) 234-5441, ext. 2280.

- Sincerely,

( }'Yp Ak William Levis

)

Site Vice President Byron Station WUJUcb Attachment cc:'

Regional Administrator-NRC Region lll NRC Senior Resident inspector - Byron Station l

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