ML20196B363

Forwards Braidwood Unit 1 Cycle 8 Operating Limits Rept (Olr), Per Provisions of 10CFR50.59 & GL 88-16.Reload Licensing Analysis Performed for Cycle 8 Utilized NRC Approved Methodologies

ML20196B363
Person / Time
Site:	Braidwood
Issue date:	11/16/1998
From:	Tulon T COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20196B369	List: ML20196B363 ML20196B371
References
GL-88-16, NUDOCS 9812010088
Download: ML20196B363 (2)

Text

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l +2 Commonweahh Edison Company Braid wood Generatin:: Station Houte *l, Ilox 84 ilraceville. IL 601073Xil9 Tel HI5-45M 2801

,a November 16,1998 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington,DC 20555

Subject:

Braidwood Nuclear Power Station Unit 1 Cycle 8 Operating Limits Report I Braidwood Station, Unit 1 Facility Operating License No. NPF-72 NRC Docket No. STN 50-456 )

1 l

Braidwood Unit I has recently completed its seventh cycle of operation. The purpose of this letter is to advise you of Comed's review of the Cycle 8 reload under the provisions of 10CFR50.59 and to transmit the Operating Limits Report (OLR) for the upcoming cycle consistent with Generic Letter 88-16.

The Braidwood Unit I core, which consists of NRC approved fuel designs, was designed 1 to operate within approved fuel design criteria, Technical Specifications and related bases  !

such that:

1) core operating characteristics will be equivalent to or less limiting than those previously 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. j[

Consistent with past reloads, the reload licensing analyses performed for Cycle 8 utilized NRC approved methodologies. The fresh fuel loaded in Cycle 8 consists of 85 i VANTAGE 5 fuel assemblies. There are 32 Region 10A assemblies with 4.00 w/o l enrichment and 53 Region 10B assemblies with 3.80 w/o enrichment. The cycle-specific o\

0 L power distribution limits for Cycle 8 are presented in the attached OLR.

,,.,A 9812010000 981116 ;i PDR ADOCK 05000456 P PDRu A Unicom Company

November 17,1998 U.S. Nuclear Regulatory Commission Page 2 Comed has performed a detailed review of the relevant reload licensing documents, the associated bases, and references. Based on that review, a safety evaluation was prepared, as required by 10CFR50.59, which concluded that the reload presents no unreviewed safety questions and required no Technical Specification changes. The Braidwood On-Site review of the reload 10CFR50.59 has been completed.

Finally, further verification of the reload core design is performed during startup testing.

The startup tests are consistent with Technical Specifications and meet the intent of the testing recommended in ANSI 19.6.1.

i If there are any questions regarding this mater, please contact this office.

amothy J. Tulon l Site Vice President i Braidwood Nuclear Generating Station l

Attachment:

Operating Limits Report, Braidwood Unit 1 Cycle 8 cc: Regional Administrator- USNRC, RIII NRC Senior Resident Inspector-Byron Station NRC Senior Resident Inspector-Braidwood Station nrc/98075tjt. doc