ML20129D006

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Forwards Cycle 1 Radial Peaking Factor Limit Rept, Submitted Per Tech Spec 6.9.1.9
ML20129D006
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 01/04/1985
From: Koester G
KANSAS GAS & ELECTRIC CO.
To: Martin R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
KMLNRC-85-005, KMLNRC-85-5, NUDOCS 8507160393
Download: ML20129D006 (3)


Text

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KANSAS GAS AND ELECTRIC COMPANY THE ELECTAIC COMPANY GLENN L. KOESTER TICE PRESsOENT 8eWCLEam January 4, 1985 i

Mr. R.D. Martin, Regional Administrator

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U.S. Nuclear Regulatory Commission l

Region IV 611 Ryan Plaza Drive, Suite 1000 M~

Arlington, Texas 76011 g

U KMLNRC 85-005 Re:

Docket No. STN 50-482 Subj: Cycle 1 Radial Peaking Factor Limit Report

Dear Mr. Martin:

The attached Cycle 1 Radial Peaking Factor Limit Report is submitted in accordance with Section 6.9.1.9 of the Wolf Creek Generating Station Technical Specifications.

Yours very truly, jfY Y

GLK:bb Attach xc:HRDenton Office of Nuclear Reactor Regulation Attn: Core Performance Branch U.S. Nuclear Regulatory Commission Washington, D.C.

20555 PO'Connor (2)

HBundy 8507160393 850104 d-(f f

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201 N. Market -Wichita. Kansas - Mail Address: RO. Box 208 I Wichita, Kansas 67201 - Telephone: Area Code (316) 261-6451

r Attachment to KMLNRC 85-005 Radial Peaking Facto ~r Limit Report This Radial Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.1.9 of the Wolf Creek Unit 1 Nuclear Plant Technical Spec-

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.ifications.

The F limits for RATED THERMAL POWER within specific core planes for Cycles shall be:

RTP 1.

F less than or equal to 1.71 for all core planes containing

...g i xy bank "D" control rods, and li

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RTP 2.

F less than or equal to 1.55 for all unrodded core planes.

xy These Fxy(z) limits were used to confirm that the heat flux hot channel factor Fg(z) will be limited to the Technical Specification values of:

Fq(z) 5 [2 32] [K(z)] for-P > 0.5'and, p

Fq(z).1 [4.64] [K(2)] for.P $ 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 distri-butions as described in the " Power Distribution Control and Load Following Procedures", WCAP-8403, September, 1974. Therefore, these F limits provide assurancethattheinitialconditionsassumedintheLOCAanalysisaremet, x

along with the ECCS acceptance criteria of 10CFR50.46.

T'PRel] vs. Axial Core Height.

See Figure 1 for a plot of [FQ O

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Attachment to KMLNRC 85-005 FIGURE 1

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