ML20093J638
| ML20093J638 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/23/1984 |
| From: | Tucker H DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8407300227 | |
| Download: ML20093J638 (3) | |
Text
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DUKE POWER GOMPANY P.O. DOX 33180 CHAMLOTTE. N.C. 28242 HALB. TUCKER TELEPHONE vaca eneminant (704) 373-4531 July.23,1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
-20555 Attention:
Ms. E. G. Adensam, Chief Licer. sing Branch No. 4 Re: Catawba Nuclear Station, Unit 1 Docket No. 50-413 Technical Specification 6.9.1.9
Dear Mr..Denton:
Pursuant to Technical Specification 6.9.1.9, please find attached the Radial Peaking Factor Limit Report for Catawba, Unit 1 Cycle 1.
Very truly yours, c4 4 w
Hal B. Tucker-RWO/slb' Attachments cc: Mr. James P. O'Reilly, Regional Administrator Palmetto Alliance U. S.-Nuclear Regulatory Commission 213515 Devine Street Region II Columbia, South Carolina 29205 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Chief,. Core Performanca Branch ~
~
U. S. ~ Nuclear Regulatory Commission Washington', D. C.
20555
.NRC Resident Inspector Catawba Nuclear Station Mr.; Robert' Guild, Esq.
Attorney-at-Law P.-0. Box 12097 Charleston, South Carolina 29412 Mr. Jesse L. Riley
. Carolina Environmental Study Group.
854'Henley Place (Charlotte, North Carolina 29207
-8407300227 840723
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Radial Peaking / actor _ Limit Report
' This Radial Peaking Factor Limit Report is provided in accordance with
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- Paragraph 6.9.1.9 of the. Catawba Unit 1 Nuclear Plant Technical Specifications.
, The F' limits for RATED THERMAL POWER within specific core planes for Cycle *I shal1 be:
~
'1'.
,F less than or equal to 1.73 for all core planes
' cEXtaining bank"D" control tods, and
~
12.
F less than or equal to 1.57 for all unrodded
- c8Ee plaises!
These Fxy(z) limits were used to confirm that the heat flux hot channel
' factor F (z) will be limited to the Technical Specification values of:
q F (z) 1 [2.32] [K(z)]
for P > 0.5 and, Y
q p
F (z) < [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
._op.eration, including the accompanying variations in the axial xenon and power distributions as described in the " Power Distribution Control and Load Following Procedures", WCAP-8403, September, 1974. Therefore, these Fxy limits provide assurance that the initial conditions assumed in'the LOCA analysis are met, along with the ECCS acceptance criteria of 10CFR50.46.
~
See Figure 1 for a plot of [FqPRe] vs. Axial Core Height
E 1
3:
2.4 N
^
^
N I--
-r r
2.2
.=
=
=
~.
r--
, n-t 2
zo
.~
7 o
1.s l
-=
i aw i
C h
1.6 H
'g
=
E i-D 1.4 ;g
_E_
x<
[
E 1.2 1_
i-l_
=
';-~"
1.0 1
0.B
- _= -
z 0
2 4
6 8
10 12 TP CORE HEIGHT ( FEET'.
FIGURE 1 T
NIAXIMUM F
P VERSUS AXIAL HEIGHT Q
REL DURING NORMAL CORE OPERATION
- - ~
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