ML20108D856

Advises NRC of Review of Cycle 6 Reload Per 10CFR50.59. Transmits COLR for Upcoming Cycle Consistent W/Gl 88-16, Removal of Cycle-Specific Parameter Limits from Ts

ML20108D856
Person / Time
Site:	Braidwood
Issue date:	04/30/1996
From:	Kaup K COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20108D859	List: ML20108D856 ML20108D867
References
GL-88-16, NUDOCS 9605090086
Download: ML20108D856 (2)

Text

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l 9 Commonwealth Ediwn Company firaidwood Generating Station

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4 liraceville, lL 60 io% I 9 TelHI% HH-2801 April 30,1996 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 2 Facility Operating License Number NPF-77 NRC Docket No. 50-457 l

Ladies and Gentlemen:

Commonwealth Edison Company's (Comed's) Braidwood Nuclear Power Station Unit 2 (Unit 2) has recently completed its 5th cycle of operation and is currently preparing for Cycle 6 startup. The estimated Cycle 6 startup date is May 7,1996. The purpose of this letter is to  ;

advise the United States Nuclear Regulatory Commission (USNRC) of Comed's review of the Cycle 6 reload under the provisions of Title 10, Code of Federal Regulations, Part 50 Section 59 (10CFR50.59) and to transmit the Operating Limits Report (OLR) for the i upcoming cycle consistent with Generic Letter 88-16, " Removal of Cycle-Specific Parameter l Limits from Technical Specifications," dated October 4,1988.

! The Braidwood Unit 2 core consi::ts of USNRC approved fuel designs, and was designed to operate within approved fuel design criteria, Technical Specifications and related bases such l that:

1) core operating characteristics will be equivalent to or less limiting than those previously reviewed and accepted; or l 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 l l affected by the reload are within allowable limits.

! Consistent with past reloads, the reload licensing analyses performed for Cycle 6 used )

l USNRC-approved methodologies. The fresh fuel to be loaded in Cycle 6 consists of 84 l VANTAGE 5 fuel assemblies. There are 68 Region 8A assemblies with 4.60 weight percent l uranium-235 (w/o U-235) enrichment and 16 Region 8B assemblies with 4.40 w/o U-235 enrichment. The cycle-specific power distribution limits for Cycle 6 are presented in the attached OLR. l l

Comed has performed a detailed review of the relevant reload licensing docut-ts, 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 9605090086 960430 N-P1 i PDR ADOCK 05000457 P PDR \)V \

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questions and requires no Technical Specification changes. The Braidwood On-Site Review l of the reload 10CFR50.59 has been completed.

4 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 Standards Institute /American Nuclear Society (ANSI /ANS)-19.6.1-1985,

" Reload Startup Physics Tests for Pressurized Water Reactors."

Please direct any questions or comments regarding this matter to Mr. Douglas S. Huston, Braidwood Nuclear Station Licensing Supervisor at (815)458-2801 extension 2511.

Karl L. Kaup Site Vice President Braidwood Generating Station KLK/DSH/tts

Attachment:

Operating Limits Report, Braidwood Unit 2 Cycle 6 cc: R. Assa, Braidwood Project Manager - NRR H. Miller, Regional Administrator - RIII C. Phillips, Senior Resident Inspector - Braidwood Office of Nuclear Facility Safety - IDNS etisvykoivamps90018 doc