ML20088A492
| ML20088A492 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 04/05/1984 |
| From: | Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | Burnett R Office of Nuclear Reactor Regulation |
| References | |
| P-84103, NUDOCS 8404120112 | |
| Download: ML20088A492 (3) | |
Text
,
pubiic service company off Conomde 16805 WCR 19 1/2, Platteville, Colorado 80651 April 5, 1984 Fort St. Vrain Unit #1 P-84103 Robert Burnett, Director Office of Nuclear Reactor Regulation Operating Reactors Safeguards Branch Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, D.C.
20555
SUBJECT:
CYCLE 4 BASE REACTIVITY CURVE AND ROD WITHDRAWAL SEQUENCE Gentlemen:
In accordance with the requirements of LC0 4.1.8 of the Fort St.
Vrain Technical Specifications, I am transmitting the Base Reactivity Curve and Rod Withdrawal Sequence for Refueling Cycle 4.
This data is provided for your information.
These changes will become effective with revisions to the System Operating Procedures for refueling cycle 4, currently in progress.
Initial startup is presently planned to consist of training starts for licensed operators, and is planned to occur during mid-April, 1984.
If you have questions regarding this transmittal, please contact me at (303)785-2223.
po -u y Very truly yours, h W $W Don W. Warembourg Manager, Nuclear Production Attachments DWW/dkh f601 8404120112 e40405 gDRADUCK05000 g
cR.M T*
reg T
'e 2
FIGURE-18 BASE REACTIVITY. CURVE CYCLE 4 Cycle 4~ Thermal Burnup (MMwb r s ( t ) )
0.00 0.05 1.00 1.50 2.00- 2.50 3.00 3.50 4.00 4.50 5.00 5.50 6.00 l
'"i uu.uu ; uu.,,o ou no "m. --0.1150
-0.1150_
-0.1125; 5-0.1125
/ i
-0.1100l
,/
_ -0.1100 5-0.1075
-0.1075;
/
,/
5-0.1050 E g -0.1050;
-0.1025
!-0.1025
/
n
-0.1000 :
e
/
- -0 1000 -
/..e
]-0.0975j l-0.0975h S
2 -0.0050 :
/
-0.0950
/
o x
/
_p_0.0925"
,-0.0925; p
r Chairman. [8/SC 0.0900g$
$ -0*0900
/
Arrowd: me.4 d h a 2
m j
cate:.;r - e - 8 4 b-0.0875
-0.0575; f
Ponc 5 5 8 MAR 1-1984
- 0. 0 5 5 0 *-
/
PORC f*eetina ?!o.
---0.0850 rirSc reetina No.
W i
-0.0625
-0.0525 :
l-0.0800 2
-0.0500 m,,
0.00 0.05 1.00 1.50 2.00 2.50 3.00 3.50 4.00 4.50 5.00 5.50 6.'00 80*F CgCle 4 Thermal Burnup (MMwb r s (t ) )
All rods inserted No Xe-135 No Sm-149 All Pa-233 decayed to U-233
PUBLIC SERVICE COMPANY OF COLORADO
- " i.
FORT ST. VRAIN NUCLEAR GENERATING STATION TABLE I l
Control Rod Withdrawal Sequence for Cycle 4 I _
. GROUP.
10 = 000 l ROD PAIRS l GROUP WORTHICUMULATIVEl l.lWITHORAWALl l l SEQUENCE l NUMBER IE = EVENlCOMPRIS1NG GROUP lWHEN PULLED]
GROUP l
ll l
l l
A B
C lIN SEQUENCE l WORTH l
II I
I I
I I
I II I
I I
I I
I ll 1
1 2A*
-l E
I 2
4 6[
0.0485 1
0.0485 l
ll 1
I I
I I
I ll 2
[
4F*
I 0
l 25 31 37 l 0.0139 l
0.0624 I II I
I I
I I
I ll 3
1 4D l
0 1 23 29 35 1 0.0046
[
0.0670 l
l l l
l
[
l i
I II 4
l 1 (0-115) 1 l
1 l
D.0064 l
0.0734 l 1 -l l
l l
1 I
I ll 5
1 4B I
E I 21 27 33 l 0.0109 l
0.0843 I
II I
I I
I I
I I-l 6
l 28 l
0 1
3 5
7l 0.0368 l
0.1211 I
II I
I I
I I
I ll 7
_l 4E l
0 l 24 30 36 [
0.0087
,1 0.1298 I II I
I I
I I
I I -l 8
I 4A I
E l 20 26 32 l 0.0080 l
0.1378 I II I
I I
I I
I ll 9
l 4C l
E l 22 28 34 l 0.0126 l
0.1504 l ll 1
I I
I I
I
-l-l 10 1
3C l
0
.l 10 14 18 l. 0.0200 l
0.1704 l l1 1
I l
l l
1
-l l 11 1
3A-l E
I 8
12 16 l 0.0133 l
0.1837 l
1I I
I I
I I
I
-l l 12 l
3B I
E l
9 13 17 I 0.0196 1
0.2033 I
II I
I I
I I
I ll 13 l
30 1
0 l 11 15 19 I 0.0154 1
0.2187 I
II I
I I
I I
I ll 14 '
11'(115-190)I l
1 1
0.0022 1
0.2209 I
l1 i
1 I
I I
I l
- Run-Back groups FOAM 372 22 3643 L__
d