ML20082A587
| ML20082A587 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/29/1995 |
| From: | Dennis Morey SOUTHERN NUCLEAR OPERATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9504040122 | |
| Download: ML20082A587 (5) | |
Text
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Southern Nuclear Oper: ting Company Post Offica Box 1295 Birmingham, Alabam2 35201 Telephons (205) 868-5131 Southem Nude 3r Operating Company o... uo,.y NrIefr*Ney March 29, 1995 fne southem electnc system Docket No.: 50-364 U. S. Nuclear Regulatory Commission ATTN: Dc-7-T-:= Control Desk Washington,DC 20555 Joseph M. Farley Nuclear Plant-Unit 2 Radial Peakma Factor Limit Report Gentlemen:
Enclosed is the Radial Peaking Factor Limit Report (RPFLR) for Cycle 11 of Unit 2. This report is provided in accordance with Paragraph 6.9.1.11 of the Unit 2 Technical Specifications. "Ihe cunent Technical Specification 6.9.1.11 requires that a RPFLR be submitted before each reload cycle (prior.
to Mode 2). Also mM is a copy of the elevation dependent peaking factor versus core height graph for Cycle 11 of Unit 2, which is being submitted in support of the subject report.
The enclosed Radial Peaking Factor Limit Report was evaluated using the Power Shape Sensitivity Model (PSSM) screemng process to ensure that the cosine shape renmins the limiting power distribution in the large break loss of coolant accident (LOCA) analysis. The PSSM process eliminates the need for applying penalty factors on the F,y(z) surveillance data.
If you have any questions, please advise.
Respectfully submitted,
[ 3 tis Dave Morey
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Enclosure 1
cc: Mr. S. D. Ebneter Mr. B. L. Siegel Mr. T. M. Ross i
l 040149 9504040122 950329
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PDR ADDCK 05000364 P
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TABLE 1 RADIAL PEAKING FACTOR LIMIT REPORT l
I This Radial Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.1.11 of the Joseph M. Farley Unit 2 Technical Specifications, f
The Fxy limits for RATED THERMAL POWER within specified core planes for Cycle 11 shall be:
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I For VANTAGE 5 fuel:
RTP 1.
F,y less than or equal to 2.52 for all core planes containing Bank "D control rods.
2.
For all vrodded core planes:
tGP F,y less than or equal to 1.88.
For Low-Parasitic (LOPAR) fuel:
RTP 1.
F,y less than or equal to 2.37 for all core planes containing Bank "D" control rods.
i 2.
For all unrodded core planes:
RTP F,y less than or equal to 1.76.
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.1 TABLE I (cont.).
RADIAL PEAKING FACTOR LIMIT REPORT Dese 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:
VANTAGE 5 fuel:
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Fq(z) i
[ 235][K(z)] for P > 0.5 and, P
i Fq(z) 1 4.90 [K(z)] for P 10.5 l
1
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I IAw-Parasitic (LOPAR) fuel:
i Fq(z) i
[ 23.2][K(z)] for P > 0.5 and, p
Fq(z) 1 4.64 [K(z)] for P 10.5 I
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 i
and power distributions as described in the " Power Distribution Control and Load Following Procedures,"
WCAP-8385, September 1974. Derefore, these Fxy limits provide assurance that the initial conditions f
assumed in the LOCA analysis are met and the ECCS acceptance criterion limit of 2200*F for peak clad 4
temperature is not exceeded.
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FIGURE 1 a
VANTAGE 5 MAXIMUM (FQT x Prel) VERSUS CORE HEIGHT DURING NORMAL OPERATION 2.5
.l l
~~
4 2.4
,.r.
2.3 A
2.2 A
i i
N 2.1 Cd CL 2.0 g
1.9 g
Ol f4 1.8 m
Z l.7 H 1.6 X
1.5 1.4 1.3 1.2 I
lFXY LIMIT = 1.88
,y i
1.0 0
2 4
6 8
10 12 i
CORE HEIGHT (FEET) h I
i i,
i A-3 m
FIGURE 2 y..
LOPAR MAXIMUM (FOT x Prel) VERSUS CORE HOGHT DURING NORMAL OPERATION 2.5 2.4
.1 '
6 I
2.3 a
b
-h 2.2
/
+7 i
2.1 a
Ed m2.0 n.
x 1. 9 21.8 4
1.7 oE H
i
- 1.6 f
1.5 I
1.4 1.3
- yxy 3131,
'1,33 1.2 1.1
^
t 1.0 0
2 4
6 8
10 l'2 CORE HEIGHT-(FEET) w l
l i
4 9
9 A-4
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