ML20012B078

Forwards Cycle 5 Radial Peaking Factor Limit Rept,Per Tech Spec Section 6.9.1.9

ML20012B078
Person / Time
Site:	Wolf Creek
Issue date:	02/14/1990
From:	Bailey J WOLF CREEK NUCLEAR OPERATING CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
90-0037, 90-37, NUDOCS 9003130450
Download: ML20012B078 (3)

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VRISLF CREEK NUCLEAR OPERATING CORPORATION J John A. Beesy -

ve mensen

. Nuclear oposehens February 14,-1990:

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NO 90-0037L U; 8. Nuclear Regulatory Conunission

m

. ATTN: Document Control-Desk--

Mail' Station PI-137

_ Washington ;D.L C.- 20555-Subjects Docket No. 50-482: -Wolf Creek Generating. Station Cycle.

5 Radial Peaking Factor Limit; Report ,

Gentlemen:~

, Endlosed is a Wolf Creek ~ Generating Station Cycle 5 Radial Peaking _ Factor

'

• Limit:-Report. This' report is being submitted pursuant to section 6.9.1.9 of . [.

the-WolfLCreek Generating Station Unit No.-1_ Technical Specifications l.

lVery truly,yours, G .-

John A.. Bailey Vice President- i=

Nuclear Operations JAB /aem Attachment-

- cc : E. J.' Holler (NRC), w/a i - :R. D. Martin (NRC), w/a

. D. V. Pickett'(NRC),_w/a-

-M. E. Skow-(NRC)~..w/a 0

\\\

' Bou 411/ Sursngton, KS 80839 / Phone: (316) 364-8831

- 9003130450 900214 ,

PDR ADOCK 050004@2 An Egsel opportuNty Employer MfMC/WT y,. <g_ FDL

ent'to NO 90-0037~

A'ttIc

                                                  -Wolf Creek Unit 1 Cycle 5                               ,

Radial Peaking Factor Limit Report . This Radial Peaking Factor (F ) Limit Report is provided in accordance with-  ! Paragraph 6.9.1.9 of the Wolf Creek Nuclear Plant Technical Specifications. ) The F 4

      ,                  xy limits for Rated Thermal Power (F xy ,      3411 MWt)   within specific-core planes for Cycle 5 shall bei

1. F less than or equal to 1.81 for all planes containing bank "D" control rods, and I

D 2. F less than or equal to 1.C4 for all unrodded core planes. I L L i:

                  ' These Fxy   limits were used to confirm that the Heat Flux Hot Channel factor-.       ;

F (z) will be limited to the Technical- Specification values of: q , Fq (z) d'( * ] [K(z)] for P > 0.5 and y P l Fq (t) $ [4.64] [K(z)] $ 0.5 f Where P = Power and (K(z)] = the normalized Fq (z). This is 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' l l -power distributions. This information is described in the " Power-Distribution Control and Load Following Procedures", WCAP-8403, September, p 1974. Therefore, these Fxy limits provide assurance that the initial-L- 1 conditions assumed in the LOCA analysis are met, along with the ECCS l' acceptance criteria of 10 CFR 50.46. L See Figure 1 for a plot of the product of the total Heat Flux Hot Channel L Factor and Relative Power. [F .Pg ] versus Axial Core Height

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cp ment to N0[90-0037 {o.4 , ii . L 3-

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0- 2 4 6 8 10 12 ., COREHEIGHT(FEET) y i b t FIGURE 1 MAXIMUM (FO PREL) VERSUS AXIAL CORE HEIGHT DURING NORMAL CORE OPERATION , t e e 0

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