ML20082U078
| ML20082U078 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 09/16/1991 |
| From: | Bailey J WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NO-91-0249, NO-91-249, NUDOCS 9109190282 | |
| Download: ML20082U078 (3) | |
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NUCLEAR OPERATING CORPORATION John A Dadey Vote Prevde'it o,-anon.
September 16, 1991 NO 91-0249 U. S. Nuclear Regulatory Corraission AT7N Document Control Desk Mail Station F1-137 Vashington, D. C.
20555 Subject Docket No. 50-482: Wolf Creek Generating Station Cycle 6 Radial Peaking Factor Limit Report Gentlemens Enclosed is the Wolf Creek Generating station Cycle 6 Radial Peaking Factor Limit Report.
This report is being submitted pursuant to section 6.9.1.9 of the Wolf Creek Generating Station Unit No. 1 Technical Specifications.
Very truly yours.
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John A. Fialley Vice President Operations JAll/jra Enclosure cca L. L. Gundrum (NRC), w/a A. T. Howell (NRC), w/a R. D. Hartin (HRC), w/a V. D. Reckley (NRC), w/a i
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!!nclosuie to NO 910249 page1of2 l
Wolf Circk Unit 1 Cycle 6 Itadial Pc iking Factor Limit Report This Radial Peaking Factor 1.imit Report is provided in accordance with paragraph 6.9.1.9 of the Wolf Cieck Generating Station Technical Speci0 cations.
The F,, limits for Rated Thermal Power (341' MWt) within specine core planes for Cycle 6 s, hall be:
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- 1. F,, less than or equal to 1.83 for all planes containing bank *D" control rods, and 2.F,,n less than or equr.1 to 1.66 for all unrodded core planes.
u Please note that the F,, limits stated in the report are not applicable for planes in the top and bottom 15% of the cos e, all grid plane regions, and within 2 percent of the bank "D" control rod position per Technical Specification 4.2.2.2.f.
These F,,(i) limits were used to confirm that the heat aux hot channel factor F (z) will be o
limited to the technical speelucation values of:
F (7) s [Y j [K(7)] for P > 0.5 and u
F (z) s [4.64)[K(r)] for P s 0.5 e
This assumes tiie most limiting axial power distributions expected to result f rom the insertion and removal of control banks "B", "C", and "D" during operation, including the accompanying variations in the axial xenon and power distributions as described in the " Power Distribution Control nnd I.ead Following Procedures", WCAP 8403, September,1974. Therefore, these F,,
limits provide assurance that the initial conditions assumed in the LOCA analysis ate met, along with the ECCS acceptance criteria of 10 CFR 50.46.
Figure 1 provides a plot of [F'. P,,,] versus Axial Core lleight.
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Enclosure to NO 9bO249
',page 2 of 2 FIGURE 1 MAXIMUM (Fq'Prel) VERSUS AXIAL CORE HEIGH 1 DURING NORMAL CORE OPERATION i
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