ML19330A577
| ML19330A577 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 07/15/1980 |
| From: | William Jones OMAHA PUBLIC POWER DISTRICT |
| To: | Stello V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8007280601 | |
| Download: ML19330A577 (3) | |
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1623 MARNEY s OMAHA. NESRASMA 68102 e TELEPHONE 536-4000 AREA CO DE 402 July 15, 1980 Mr. Victor Stello, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Reference:
Docket No. 50-285
Dear Mr. Stello:
3 In accordince with the Fort Calhoun Station Technical Specifi-cations, please find enclosed ten (10) copies of a report entitled
" Summary of Irradiated Fuel Inspection Following Cycle 5 Operation".
The report provides a summary of the fuel inspection performed during the District's 1980 refueling outage.
Sincerely, k
W.C.fone.0 s
Division Manager Production Operations
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WCJ/KJM/BJH/PRT:jmm Enclosures.
cc:
NRC Regional Office (2)
NRC Director of MPA (2)
LeBoeuf, Lamb, Leiby & MacRae kool
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8007280_6 O i h
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SUMMARY
OF IRRADIATED FUEL INSPECTION FOLLOWING CYCLE 5 OPERATION During the E0C-5 refueling outage, six irradiated fuel assemblies, which were returned to the core for Cycle 6, and forty discharged as-semblies were inspected. A list of the assemblies inspected is sum-marized in Table 1.
All of the assemblies were visually inspected in the inspection stand, in accordance with ST-FE-1 and SP-FE-1.
The assemblies were examined using a 5:1 zoom underwater TV camera, with video recordings of the data being made.
Shoulder gap, assembly length, and fuel rod channel width data, obtained with the camera zoomed in, were recorded for further analysis in fuel assemblies 0005, G037, G038, G040, and G041.
Assembly D005 was returned to the core for a fifth cycle of irradiation, as part of the Department of Energy (00E) extended burnup program.
The four batch "G" assemblies are being used in the DOE SAVFUEL program in which an in-out-in fuel management scheme is being simulated in several of the fuel pins of these assemblies.
No major abnormalities were observed in the six assemblies inspected which were returned to the Cycle 6 core, although 0005 did exhibit some minor channel gap closure due to fuel rod bowing.
The observed bowing is well within the bounds assumed for the Cycle 6 safety analysis. A detailed report on these assemblies is being issued as part of the DOE program.
Of the forty discharged assemblies visually inspected, one ancmaly was observed. Assembly 0043, an assembly with three cycles of exposure, showed assembly bow--probably due to preferential guide tube growth. No channel gap closure was observed in this assembly, and it appeared no rma t when viewed on the TV monitor.
The differential bow was uniform (in the same direction) over the length of the assembly and thus re-sulted in an upper end fitting displacement of several inches from the assembly centerline. This anomaly appears to be isolated, with no other similar cases being observed.
Of the 46 assemblies examined, no failed fuel pins were observed,
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which is consistent with the low reactor coolant activity levels measured in Cycle 5.
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TABLE 1 FUEL ASSENBLIES INSPECTED A.
Irradiated Assemblies Returned to the Core 1.
0005 2.
E001 3.
G037 4.
G038 5.
G040 6.
G041 B.
Discharged Assemblies 1.
D006 21.
E012 2.
D009 22.
E016 3.
0027 23.
E020 4.
0028 24.
E023 5.
0029 25.
E101 6.
0030 26.
E102 7.
0031 27.
E103 8.
0032 28.
E105 9.
D033 29.
E106
- 10. 0034 30.
E107 11.
D035 31.
E108
- 12. D036 32.
E110 13.
0037 33.
Elli
- 14. D038 34.
E113 15.
D039 35.
E114
- 16. 0040 36.
E116
- 17. D041 37.
E117
- 18. D042 38.
E118 19.
D043 39.
E119
- 20. D044 40.
E120