ML20210J866

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Forwards Radial Peaking Factor Limit Rept for Cycle 8 & Elevation Dependent Peaking Factor Versus Core Height Graph for Cycle 8,per Tech Spec Paragraph 6.9.1.11
ML20210J866
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 09/15/1986
From: Mcdonald R
ALABAMA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8610010258
Download: ML20210J866 (3)


Text

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O belling Address Atbims Power Comp ny 600 North 18th Street Post Office Box 2641 Birmingham, Alabama 35291 Telephone 205 783-6090 mh h ag: 5, R. P. Mcdonald Senior Vice President g

Flintndge Building g ghgggg g g tv sou:*wm ecir c s, >w" September 15, 1986 Docket No. 50-348 U. S. Nuclear Regulatory Commission Region II, Suite 3100 101 Marietta Street N.W.

Atlanta, Georgia 30303 Attention:

Region II Administrator Gentlemen:

Joseph M. Farley Nuclear Plant - Unit 1 Radial Peaking Factor-Limit Report Enclosed is the Radial Peaking Factor Limit Report for Cycle 8 of Unit 1.

This report is provided in accordance with Paragraph 6.9.1.11 of the Unit 1 Technical Specifications. Also enclosed is a copy of the elevation dependent peaking factor versus core height graph for Cycle 8 of Unit I which is being submitted in support of the subject report.

If you have any questions, please advise.

Yours very trul l'

s R. P. Mcdonald RPM / JAR:kpc-D-TS5 Enclosure cc: Mr. L. B. Long Mr. L. S. Rubenstein Mr. E. A. Reeves Mr. W. H. Bradford Mr. C. H. Berlinger I I 8610010258 860915 PDR ADOCK 05000348 P

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ENCLOSURE 1

FARLEY UNIT 1 CYCLE 8 RADIAL PEAKING FACTOR LIMIT REPORT l

This Radial Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.1.11 of the Joseph M. Farley Nuclear Plant Unit 1 Technical Specifications.

4 The Fry limits for RATED THERMAL POWER within specified core planes for Cycle 8 shall be:

ba{k"D"'controlrods.

F$P less than or equal to 2.00 for all core planes containing 1.

n 2.

For.all unrodded core planes:

F)TP less than or equal to 1.71 up to core elevations of 6.9 f t.

F}jP less than or equal to 1.76 for core elevations above 6.9 ft.

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

7 Fq(z) < 2.31 [K(z)] for P > 0.5 and, j

P Fq(z) 3 62 [K(z)] for P$0.5 4

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assuming the most limiting axial power distributions expected to result from the insertion and removal of control banks 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,"

l WCAP-8385, September 1974. Therefore, these Fry limits provide assurance that t

the initial conditions assumed in the LOCA analysis are met and the ECCS acceptance criteria limit of 2200*F for Peak Clad Temperature is not exceeded.

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0 FIGURE 1 Maximum F *P,,, versus Core Height During Normal Operation Farley Unit 1 Cycle 8 18 I

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