ML19330A577

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Forwards Summary of Irradiated Fuel Insp Following Cycle 5 Operation Performed During 1980 Refueling Outage.No Major Abnormalties Observed in Six Irradiated Fuel Assemblies Inspected.No Failed Fuel Pins Were Observed
ML19330A577
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
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 3

Dear Mr. Stello:

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

) WCJ/KJM/BJH/PRT:jmm Enclosures.

cc: NRC Regional Office (2)

NRC Director of MPA (2)

LeBoeuf, Lamb, Leiby & MacRae kool _s

///

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.

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Of the 46 assemblies examined, no failed fuel pins were observed, 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