ML20151R470
| ML20151R470 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 08/01/1988 |
| From: | Withers B WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| WM-88-0200, WM-88-200, NUDOCS 8808120185 | |
| Download: ML20151R470 (3) | |
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LF CREEK
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W4) NUCLEAR OPERATING CO
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l Bart D. Withers Prow and Ctuet Execueve Omcor August 1, 1988 WM 88-0200 U. S. Nuclear Regulatory Commission ATTN:
Document Control Desk Mail Station PI-137 Washington, D. C. 20555
Subject:
Docket No. 50-482 : Wolf Creek Generating Station Cycle 4 Radial Peaking Factor Limit Report Centlemen:
Enclosed is the Wolf' Creek Generating Station Cycle 4 Radial Peaking Factor Limit Report. This report is being submitted pursuant to sec tion 6.9.1.9 o f the Wolf Creek Generating Station Unit No. 1 Technical Specifications.
Very truly yours, Bart D. Withers President and Chief Executive Officer BDW/j ad Ecnisoure ec:
B. L. Bartlett (NRC), w/a D. D. Chamberlain (NRC), w/a R. D. Martin (NRC), w/a P. W. O'Connor (NRC), w/a (2) 8808120185 880801 PDR ADOCK 05000482 l
P PNV i i RO. Box 411/ Burtegton, KS 66839 / Phone: (316) 364-6831 M Equal Opportun4y Enveyor 64FHC.YET
Enclosura to WM 88-0200
, Page 1 of 2 Wolf Creek Unit 1 Cycle 4 Radial Peaking Factor Limit Report This Radial Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.1.9 of the Wolf Creek Nuclear Plant Technical Specifications.
The F XY planes for Cycle 4 shall be:
1.
F less than or equal to 1.80 for aim planes containing bank "D" control rods, and 2.
F less than or equal to 1.65 for all unrodded core planes.
These F (z) limit were used to confirm that the heat flux hot channel factor F (z) will be limited to the Technical Specification values of:
F ( z )< {'2.32 } (K) z) } for P > 0 5 and Q
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F (z)f {4.64} (K(z)} for P i 0.5 assuming the most limiting axial power distributions expected to result from the insertion and removal of control banks B, C,
and D during operation, including the accompanying variations in the axial xenon and power l
distributions as described in the "Power Distribution Control and Load Following Procedures", WCAP-8403, September, 1974.
Therefore, these Fg limits provide assurance that the initial conditions assumed in the LOCA l
I analysis are met, along with the ECCS acceptance criteria of 10 CFR 50.46.
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See Figure I for a plot of {F P g } versus Axial Core Height
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FIGURE 1 M AX (FO PREL) VERSUS AXIAL CORE HEIGHT l
DURING NORMAL CORE OPERATION l
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