ML20094H001

Advises NRC of Util Review of Cycle 6 Reload Under Provisions of Title 10,Code of Fr Part 50 & Transmits Operating Limits Rept for Upcoming Cycle Consistent W/Gl 88-16

ML20094H001
Person / Time
Site:	Braidwood
Issue date:	11/08/1995
From:	Pontious H COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20094H005	List: ML20094H001 ML20094H006
References
GL-88-16, NUDOCS 9511130295
Download: ML20094H001 (2)

Text

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, O>mmonwealth Illison Ownp.iny a 1400 Opus ibcc Dow ners Gnn e,11. 60515 November 8,1995 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001

Subject:

Cycle 6 Operating Limits Report Braidwood Nuclear Power Station, Unit 1 Facility Operating License NPF-72 L NRC Docket No. 50-456 Ladies and Gentlemen:

Commonwealth Edison Company's (Comed's) Braidwood Nuclear Power Station, Unit 1 (Braidwood 1) has recently completed its fifth cycle of operation r.nd is currently preparing for Cycle 6 startup. The estimated Cycle 6 startup date is November 16,1995. The purpose of this letter is to advise the United States Nuclear Regulatory Commission (USNRC) Staff of Comed's review of the Cycle 6 reload under the provisions of Title 10, Code of Federal Regulations, Part 50, Section 59 (10 CFR 50.59) and to transmit the Operating Limits Report (OLR) for the upcoming cycle consistent with Generic Letter 88-1G, " Removal of Cycle-Specific Parameter Limits from Technical specifications," dated October 4,1988.

The Braidwood I core conshts of USNRC approved fuel designs and was designed to operate within approved fura 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 Updated Final Safety Analysis Report (UFSAR) events which could be affected by the reload are within allowable limits.

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. USNRC Document Control Desk November 8,1995 Consistent with past reloads, the reload licensing analyses performed for Cycle 6 utilized USNRC approved methodologies. The fresh fuel to be loaded in Cycle 6 consists of 80 VANTAGE 5 fuel assemblies. There are 16 Region 8A assemblies with 4.60 weight percent uranium-235 (w/o U-235) enrichment and 64 Region 8B assemblies with 4.40 w/o U-235 enrichment. The cycle-specific power distribution limits for Cycle 6 are presented in the enclosed OLR.

Comed has performed a detailed review of the relevant reload licensing documents, the associated bases, and refemnces. Based on that review, a safety evaluation was prepared, as mquired by 10 CFR 50.59, which concluded that the reload presents no unreviewed safety questions an.d requires no Technical Specification changes. The Braidwood On-Site Review of the reload 10 CFR 50.59 has been completed.

Finally, further verification of the reload core design will be performed during startup testing. The startup tests will be consistent with Technical Specifications and testing recommended in American National Standard [American National Standards Institute /

American Nuclear Society (ANSI /ANS)]-19.6.1-1985, " Reload Startup Physics Tests for Pressurized Water Reactors."

Please address any comments or questions regarding this matter to this office.

Very truly yours, ,

[ \

Harold D. Pontiou Jr.

Nuclear Licensing Admmistrator Enclosum cc: H. J. Miller, Regional Administrator - RIII R. R. Assa, Braidwood Project Manager - NRR S. P. Ray, Acting Senior Resident Inspector - Braidwood Office of Nuclear Facility Safety - IDNS