ML20137D786
| ML20137D786 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 08/29/1984 |
| From: | Andrews R OMAHA PUBLIC POWER DISTRICT |
| To: | Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| LIC-84-267, NUDOCS 8508230040 | |
| Download: ML20137D786 (5) | |
Text
,
Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 402/536 4000 August 29, 1984 LIC-84-267 pq N @ $ [
T) l 9l
!l{[ !;
Mr. J. T. Collins, Administrator
~'
U. S. Nuclear Regulatory Commission hl i.
- j Region IV 611 Ryan Plaza Drive, Suite 1000 ij g ;
SEP-41984 g
Arlington, Texas 76011 L ty l
Reference:
Docket No. 50-285
Dear Mr. Collins:
Fuel Performance Report Pursuant to the requirement of Fort Calhoun Station Unit No.1 Techriical Specification 5.9.3.h., Omaha Public Power District, holder of Generating License DPR-40, submits the attached Fuel Performance Report for Cycle 8.
Sincerely,
- gf7b, d
s Division Manager Nuclear Production RLA/DJM/rh-R Attachment cc:
LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N. W.
Washington, D. C.
20036 Mr. E. G. Tourigny, NRC Project Manager Mr. L. A. Yandell, Senior Resident Inspector 8508230040 840829 PDR ADOCK 05000285
[
P pop 455124 Employmen h qual opportunity
Fort Calhoun Station Cycle 8 Fuel Performance Report
)
Fort Calhoun Station Cycle 8 Fuel Performance Report As required by Fort Calhoun Station Technical Specification 5.9.3, Omaha Pub-lic Power District is submitting a fuel performance summary.
Cycle 7 fuel performance related chemistry data will provide the basis for evaluating the Cycle 8 fuel perforvence. The Cycle 7. data will be utilized because comprehensive fuel assembly examinations were performed at the con-clusion of. this cycle. The lead assenbly from Cycle 7 achieved an average burnup of 52,000 MWD /MTU with no rod perforations or anamalies found during its examination. The lead batch of fuel for Cycle 8 had an average burnup of 37,800 MWD /PUU which is well below the Cycle 7 high burnup denonstration assembly.
Figures 1 and 2 show a comparison of the chemistry data for Cycles 7 and 8.
Figure 1 indicates that the total coolant activity (pCi/gm) for Cycle 8 was about the same as the previous cycle. The end of cycle value was approxi-mately 9% of the Technical Specification (2.1.3(1)b.) limit of 100/Euci/gm.
Figure 2 shows the I-131 equivalent data for Cycles 7 and 8.
The Cycle 8 data shows an increase in the iodine activity level, suggesting that addi-tional fuel failure may have occurred near the end of the cycle. The dose equivalent level was less than 0.17 uCi/gm and is well below the Technical Specification limit of 1.0 uCi/gm. For the part of the cycle where the total coolant activity showed a slight increase, the CEA and power histories were examined. Prior to the activity increase and until the end of the cycle; the CEA's were fully withdrawn and no severe power maneuvers occurred. Addition-ally, throughout the cycle the fuel was operated within the PCI criteria.
The activity increase occurred during normal steady state power operations.
In summary, the Cycle 8 data shows that the fuel achieved burnups within the range of previously examined Cycle 7 fuel, and that comparable fuel perform-ance related chemistry data existed for both cycles, thus demonstrating ex-cellent fuel performance in Cycle 8.
j
mwv-e e O
Oo str l
w I
i l
I I
I I
I I
o I
o I
l d
o I
I LJ
\\
l e
l 8
N e
L's, o
5 b
-g H
l l
C3 I
<C oo 8
E i
z l
ai9
<C l
I i
ali e
C1.
O 2
O i
E C ')
E5 o
L&
s' w
<C
\\l a
Z
\\!
8 H
W Cr l-CL l
B a
1 E
,4 o
8 Cf3 5
l t
8 8
O o
O 8
N 3
a E
N g
G m
w
, 'g O
o
\\
o
's H
s w1
's
(
s M
'g
~
e 1
O III IIf fII IIf i11 1if 11l iIf f11 iff Iff IfI h!
l'h'-L f f 11I o
o.
o.
- o.
o.
o.
o.
o.
- o. -
o.
e.
o.
o.
o.
e.
o.
o.
o.
Y b
w e
wg wg
-v1 we e
- 31 EQU::VA_E\\" ys 3UlNU3 FIGUE 2 Ii31 {pCi/gs) 0.20 M
g..................i
,e 0.15 CYC.E8
~
l /%
0'10
/
N
- CYCLE 7 l
4 m
/
a o'
l 0.05
/
/
o e
0.00 0
1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 CYCLE AVG BURNUP (NWD/NTij)