ML20138A398
| ML20138A398 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 02/26/1986 |
| From: | Tucker H DUKE POWER CO. |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8603140222 | |
| Download: ML20138A398 (3) | |
Text
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l DUKE POWER GOMPAhT P.O. BOX 03189 CHARLOTTE N.C. 28242 IIALH. TUCKER TELEPHONE
,4 =l===g g (704) 073-4NH w
February 26, 1986 Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commission l
Region II 101 Marietta Street, NW, Suite 2900 l
Atlanta, Georgia 30323 i
Ret Catawba Nuclear Station Unit 2 Docket No. 50-414 Technical Specification 6.9.1.9 l
Dear Dr. Graces i
Pursuant to Technical Specification 6.9.1.9, please find attached the Radial l
Peaking Factor Limit Report for Catawba Unit 2 Cycle 1.
l Very trul'y yours,
/
9
< fra_
Hal B. Tucker WLHisib l'
Attachment l
cc Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation j
U. S. Nuclear Regulatory Commission Washington, D. C.
20555 l
l Attention:
Carl Berlinger Reactor Systen Branch NRC Resident Inspector l
t Catawba Nuclear Station
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o Radial Peaking Factor Limit Report This Radial Peaking Factor Limit Report is provided in accordance with
' Paragraph 6.9.1.9 of the Catawba Unit 2 Nuclear Plant Technical Specifications.
The F limits for RATED THERMAL POWER within specific core planes for Cycle *[ shall be:
1.
F less than or equal to 1.73 for all core planes c5Xtaining bank"D" control rods, and 2.
F less than or equal to 1.57 for all unrodded c5le planes.
These Fxy(s) limits were used to confirm that the heat flux hot channel factor F (z) will be limited to the Technical Specification values of:
q 2
F (z) < [ 'p ] (K(z)] for P > 0.5 and, q
F (z) ;c (4.64) (K(z)] for P < 0.5 q
assuming the most limiting axial power distributions expected to result from.the insertion and removal of Control Banks B, Q, and D during i
operation, including the accompan;ing variations in the axial xenon and power distributions as described in the " Power Distribution Control and l
Load Following Procedures" WCAP-8403, September, 1974. Therefore.
l these Fxy limits provide assurance that the initial conditions assumed in the LOCA analysis are met, along with the ECCS acceptance criteria cf 10CFR50.46.
See Figure 1 for a plot of (Fq* pre] vs. Axial Core Height I
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3 BOTTOM 10 12 CORE HEIGHT ( FEET)
TOP FIGURE 1 T
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REL DURING NORMAL CORE OPERATION
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