ML20078G863
| ML20078G863 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 11/08/1994 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20078G862 | List: |
| References | |
| NUDOCS 9411160223 | |
| Download: ML20078G863 (5) | |
Text
{{#Wiki_filter:. - ATTACHMENT 2 l l BW2C5 Core Operating Limits Report (COLR) 1 l 4 9411160223 941108 PDR P ADOCK 05000457 PDR
BRAIDWOOD UNIT 2, CYCLE 5 RP_ERATING LIMIT REPQBT - Fxy PORTION This Radial Peaking Factor Limit Report is provided in accordance with paragraph 6.9.1.9 of the Braidwood Unit 2 Nuclear Plant Technical Specifications. The Fxy limit for RATED THERMAL POWER within specified core plans 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:
RTP
$2.052
- 2) For all unrodded core planes:
Ff 51.735 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:
Ff $2.052
- 2) For all unrodded core planes:
Ff 51.817 These Fxy(Ij amits weio used to confirm that the heat flux hot channel factor FQ(z) will be limited to the Technical Specification values of Fa(z)s[5.00][K(2)]/orP50.5 and u m. u m-w
~
Fa(z)s[ 2.-50][K(z)]forP>0.5 P 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 criteria of 10 CFR 50.46 are met.
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0 2 4 6 8 10 12 Com Hebht SxhlPohta) BW2C5 Core Operating Limits Report (COLR) Page 2 of 2
d ATTACHMENT 3 References
- 1. Westinghouse WCAP-9272-P-A, dated October 1985; " Westinghouse Reload Safety Evaluation Methodology", (originally issued March 1978).
- 2. Comed 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 Comed's Neutronics Topical (Ref. 2) dated March 11,1991.
- 4. Comed submittal, F.G. Lentine to H.R. Denton dated July 27,1983; entitled " Zion Stations Units 1 and 2, Byron Station Units 1 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 Comed's Neutronics Topical (Ref. 5) 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. Comed submittal, S.C. Hunsader to T.E. Murley "Braidwood Stations Unit 1 and 2 Application for Amendment to Facility Operating License NPF-72 and NPF-77 dated October 14,1989.
l l l Braidwood Unit 2 Cycle 5 Reload Descnption References
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