ML20029E469

Cycle 5 Colr.

ML20029E469
Person / Time
Site:	Braidwood
Issue date:	05/06/1994
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20029E467	List: ML20029E466 ML20029E469
References
NUDOCS 9405180356
Download: ML20029E469 (4)

Text

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A'ITA CHMENT 2 11WIC5 Cole Operating Limits Report (COLR) 9405180356 940506 PDR P ADOCK 05000456 PDR

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B RAID WOOD UNIT 1, CYCLE 5 OPERATING LIMIT REPORT - Fxy PORTION This Radial Peaking Factor Limit Report is provided in accordance with paragraph 6.9.l.9 of the Braidwood Unit i Nuclear Plant Technical Specifications.

The Fxy limits for RATED TilERMAL POWER within specified core planes for Cycle 5 shall be:

a: For the lower core region from greater than or equal to 0% to less than or equal to 50%:

1) For all core planes containing bank "D" control rods:

Psy 13.374

2) For all un-rodded core planes:

fey' 11.761 b: For the upper core region from greater than 50% to less than or equal to 100%:

1) For all core planes containing bank "D" control rods:

Fly 12.195

2) For all unrodded core planes:

Fly 11.772 These Fxy(z) limits were used to confirm that the heat flux hot channel factor FQ(z) will be limited to the Technical Specification values of FQ(z)_<_ [ 21][K(z)] for P>0.5 and P

FQ(z)_s [5.00][K(z)] for Ps0.5 assuming the most limiting axial power distributions expected to result from the insertion and removal of control Banks C and D during operation, including the accompanying variations in the axial xenon and power distributions as described in the " Power Distribution Control and Load .

Following Procedures," WCAP-8403, September 1974. Therefore, these Fxy limits provide assurance that the initial conditions assumed in the LOCA analysis and the ECCS acceptance l criteria of 10 CFR 50.46 are met. l l

See the attached figure for the plot of [Ff *Pg ] vs. Axial Core licight.

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FQ( z )

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. ATTACilMENT 3 References i

1. Westinghouse WCAP-9272-P-A, dated October 1985; " Westinghouse Reload Safety Evaluation Methodology," (originally issued March 1978).

2. CECO submittal, J.A. Silady to T.E. Murley dated July 13, 1990; entitled '

" Commonwealth Edison Company Topical Report on Benchmark of PWR Nuclear Design Methods Using The Phoenix-P and ANC Computer Codes, NRC Docket Nos.

50-295/304,50-454/455, and 50-456/457".

3. NRC SER on CECO's Neutronics Topical dated March 11,1991.

4. CECO submittal, F.G. Lentine to II.R. Denton dated July 27, 1983; entitled " Zion Stations Units 1 and 2, Byron Station Units I and 2, Braidwood Station Units 1 and 2, Commonwealth Edison Company Topical, Report on Benchmark of PWR Nuclear Design Methods," NRC Docket Nos. 50-295/304,50-454/455, and 50-456/457.

5. NRC SER on CECO's Neutronics Topical dated December 13,1983. .

6. NRC Letter from S.P. Sands to T.J. Kovach, " Amendment No.23 - Use of VANTAGE 5 Fuel," dated April 19,1990.

7. CECO submittal, S.C. Hunsader to T.E. Murley "Braidwood Stations Unit I and 2 Application to Facility Operating License NPF-72 and NPF-77," dated October 14,1989.  ;

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