ML20237G572
| ML20237G572 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 08/17/1987 |
| From: | Bailey J WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| ET-87-0254, ET-87-254, NUDOCS 8708240129 | |
| Download: ML20237G572 (3) | |
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W4#LF CREEK NUCLEAR OPERATING CORPORATION John A. Bailey Moe President Erpneering and Technical Services August 17, 1987 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555 Letter:
ET 87-0254 Re:
Docket No. 50-482 Subj:
Wolf Creek Generating Station Cycle 3 Radial Peaking Factor Limit Report Gentlemen:
Enclosed is the Wolf Creek Generating Station Cycle 3 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, John A. Baile Vice-President Engineering and Technical Services JAB:jad Enclosure cc:
RMartin P0'Connor (2)
JCummins 8708240129 870817 PDR ADOCK 05000482 P
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P.O. Box 411/ Burlington, KS 66839 / Phone: (316) 364-8831 An Equal Opportunity Erngeyer M FHCNET
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t Wolf Creek Unit 1 Cycle 3 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 Generating Station Technical Specifications.
The Fxy limits for Rated Thermal Power (3411 MWt) within specific core planes for Cycle 3 shall be:
1.
Fx[1essthanorequalto1.84forallplanescontaining bank "D" control rods, and Fhflessthanorequalto1.66forallunroddedcoreplanes.
2.
These Fxy (z) limits were used to confirm that the heat flux hot channel factor F (z) will be limited to the Technical Specification values of:
9 F (z) < [
] [K(z)] for P > 0.5 and 9
F (z) < [4.64] [K(z)] for P < 0.5 g
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 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 are met, along with the Emergency Core Cooling System acceptance criteria of 10CFR50.46.
See Figure 1 for a plot of [Fg P 3 versus Axial Core Height.
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10 ft 82 CORE HEICW (FEEI)
FIGURE 1 MAX (FO PREL) VERSUS AXlAL CORE HEIGHT DURING NORMAL CORE OPERATION i
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