ML20082B643
| ML20082B643 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 10/17/1983 |
| From: | William Jones OMAHA PUBLIC POWER DISTRICT |
| To: | Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| LIC-83-262, NUDOCS 8311210273 | |
| Download: ML20082B643 (2) | |
Text
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Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 402/536 4000 October 17, 1983 LIC-83-262 Mr. J.
T.
Collins Regional Administrator g z3 E
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Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000
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Reference:
Docket No. 50-285
Dear Mr. Collins:
Fort Calhoun Station Cycle 7 Fuel Performance Report i
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As required by Fort Calhoun Station Technical Specification 5.9.3, Omaha Public Power District is submitting a fuel per-formance summary based on results of the Cycle 7 fuel in-spections.
A comprehensive examination of five fuel assemblies was com-pleted following their discharge from the core at the end of Cycle 7.
The inspections were performed on a high burnup as-sembly, D005, which had achieved an average burnup of 52,000 MWD /MTU and a peak rod burnup of 56,000 MWD /MTU.
This as-sembly had been radiated for six cycles.
Inspections were also conducted on four fuel assemblies which contain rods which had undergone a simulated IN/OUT/IN fuel management scheme.
These pins were inspected to determine the accept-ability of this type of fuel management.
The examination work scope included an assembly visual in-spection and dimensional characterization which was per-formed using a periscope.
Assembly length measurements and assembly shoulder gap measurements were made.
All as-semblies were disassembled and eddy current testing was performed on all rods in D005 and nineteen rods in each of the four assemblies which had simulated the IN/OUT/IN fuel management.
In addition, single rod inspections were per-
'1 formed.
A visual inspection was performed on twenty rods.
Oxide thickness measurements were performed on fourteen rods.
Profilometry was performed on nine rods and length measurements were performed on seven rods.
Eddy current testing showed that there were no leaking roda detected
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8311210273 831017 PDR ADOCK 05000285 Employmen aleopportunity F
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Mr.
J.
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Collins LIC-83-2G2 Page Two among the high burnup assembly rods or among the rods which had been through an IN/OUT/IN fuel management simulation.
The assembly growth and the fuel rod growth were measured.
The results were as expected and are similar to previously reported results.
The shoulder gap measurements showed that sufficient shoulder gap existed to allow future assemblies to achieve' burnup similar to that achieved by assembly D005.
Closure on assembly D005 is predicted to occur in 60,000 to 70,000 MWD /MTU range based on the data taken during three 4
inspections of this assembly.
Oxide film thickness measurements were conducted on a number of rods.
The maximum oxide. film thickness measured was 65 microns and is significantly less than the maximum oxide thickness allowable.
The Cycle ~7-fuel inspections reveal that assembly D005 suc-cessfully completed six cyclos of irradiation with lead rod burnups of 56,000 MWD /MTU with no fuel rod perforations and no anomalies which would indicate deterioration of per-formance capabilities.
Excellent performance was also ob-served in the IN/OUT/IN demonetration fuel assembli'es.
A full report of these inspections will be included as-part of the District's program with the Department of Energy (DOE).
Sincerely, s
i 1
NJ l
W. C. Jones Dividion Manager.
Production Operations WCJ/JCB:jmm cc:
LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire _ Avenue, N.W.
Washington, D.C.
20036.
Mr.
E. G. Tourigny, Project _ Manager Mr.-L.
A..Yandell, Senior Resident Inspector
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