ML20063J105
| ML20063J105 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 08/17/1982 |
| From: | William Jones OMAHA PUBLIC POWER DISTRICT |
| To: | Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| LIC-82-283, NUDOCS 8209020287 | |
| Download: ML20063J105 (3) | |
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Omaha Public Power District 1623 HARNEY e OMAHA, NE8RASMA 68102 e TELEPHONE 536-4000 AREA CODE 402 August 17, 1982 LIC-82-283
[g; C Mr. J. T. Collins, Administrator b,,# d, N U. S. Nuclear Regulatory Commission
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o 611 Ryan Plaza Drive, Suite 1000
-h Region IV
[
y Arlington, Texas 76011
Reference:
Docket No. 50-285
Dear Mr. Collins:
Cycle 6 Fuel Performance Report In accordance with Fort Calhoun Station Technical Specification 5.9.3(h), please find attached a report entitled " Summary of Irradiated Fuel Performance and Inspection Following Cycle 6 Operation". The report provides a summary of the fuel inspections and fuel performance analysis conducted duiing and following the District's 1981 refueling outage.
Sincer ly,
'lb'A W. C. dgnes Division Manager Production Operations WCJ/TLP:jmm Attachment cc:
LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.
Washington, D.C.
20036 Mr. Lawrence A. Yandell - NRC Senior Resident Inspector I
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8209020287 820817 PDR ADOCK 05000285 P
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SUMMARY
OF IRRADIATED FUEL PERFORMANCE AND INSPECTION FOLLOWING CYCLE 6 OPERATION During and followin inspections of three (3)g the end of Cycle (E0C) 6 refueling outage, irradiated fuel assemblies (D005, G037, and G041), which were returned to the core for Cycle 7, and two (2) ir-radiated assemblies (D038 and D013), discharged prior to the 1981 re-fueling, were performed. The detailed visual inspections of the ir-radiated assemblies were conducted utilizing a periscope in the spent fuel pool.
Burnup characteristics or anomalies inspected for included assembly length, shoulder gap, rod bow, and assembly bow.
Four (4) fuel pins were removed from assembly D005 and were replaced with four (4) pins from discharged assembly D038.
The four (4) pins removed from D005 are presently stored in the spent fuel pool awaiting shipment to Battelle-Columbus for detailed examination as part of the Department of Energy (DOE) extended burnup program.
Non-destructive oxide thickness characterization was also performed on both interior and exterior fuel rods from assemblies D005 and 0038.
The characterization was accomplished using an eddy current testing (ECT) probe (i.e., proximity probe).
The oxide thickness measurements verified that a continued linear relationship between oxide thickness and burnup existed.
This linear relationship between oxide thickness and burnup is considered valid through burnups of 52,000 MWD /MTV. This data was of paramount importance in detennining the acceptability of returning fuel assembly D005 to the reactor for a sixth cycle of ir-radiation, which is expected to result in a burnup to approximately 52,000 MWD /MTU.
The inspection program was temporarily interrupted by a glycol spill in the spent fuel pool, which occurred on October 17, 1981.
Subsequent spent fuel pool cleanup delayed the fuel inspections until resumption in late March,1982. At that time, a detailed TV and peri-scope examination of assembly D013 was conducted and then 0013 was disassembled and ten (10) rods removed.
These rods were examined using the eddy current probe to verify their clad integrity and were then transferred with twelve (12) other rods removed earlier in the inspection l
program to a rod shipment basket in preparation for shipment to Battelle t
for hot cell examination.
The E0C-6 fuel examinations demonstrated the following:
1.
Fuel burnup characteristics identified during the inspections were as expected.
2.
Excellent fuel rod and assembly performance was observed for average burnups of 45 GWD/MTU.
3.
Adequate shoulder gaps exist to permit burnups of greater than 50 GWD/M W.
4.
Cladding oxide film thickness measurements on Cycles 4 and 5 exposed assemblies are in agreement with oxidation models and fuel burnups to 50 GWD/MTU could be accomplished.
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5.
Channel closure of Fort Calhoun Station fuel follows the data trend established in other Combustion Engineering (CE) plants for lower burnups.
- l The detailed examinations conducted at the conclusion of Cycle 6 confinned the excellent perfonnance of the Fort Calow.1 Station fuel assemblies.
This is in agreement with the Cycle 6 reactor coolant radiochemistry data.
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