ML20090M675
| ML20090M675 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 04/29/1975 |
| From: | NORTHERN STATES POWER CO. |
| To: | Anthony Giambusso Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9105070403 | |
| Download: ML20090M675 (2) | |
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DA1 E OF DOC DATE ALC'D LTR TWX RPT OTHER Minneapolin, Ninu L.O. Mayer._pr 4-29-75 5-1-75 xxx
ORIG CC OlllER Mr. A. Giambasso 1-signed SENT LOCAL PDit xxx Cl. ASS UNCL ASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
xxxxxx 40 50-263
. DESCRIPTION:
ENCLOSURES:
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Ltr furn Summary Status,of Fuel Report for the Monticello Nuclear Generating Ple'nt. according 4l t o the Tech - Spec s * *...... -
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"i NORTHEMN 5TATES POWER COMPANY MINN E APoble MIN N E GOTA 88401 April 29, 1975
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Mr. A. Giambusso, Director Division of Reactor Licensing M.,,
U. S. Nuclear Regulatory Conunissio
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Washington, DC 20555
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Dear Mr Giambusso:
4 MONTICELLO NUCLEAR GENERATING PIANT s'
Docket No.
50-263 License No. DPR-22
SUMMARY
STATUS OF FUEL REPORT 4
This report is submitted in compliance with Technical Specification 6.7.C.6, "Stmanary Status of Fuel Report," which is required following each refueling.
The Monticello generator was taken off line on January 9,1975, and the re-actor was made subcritical on the fol?owing day.
During the outage 80 Re-load 3 fuel assemblies were inserted into the core to replace initial core fiici.
Cycle 4 commenced as the reactor was again made critical on February 6,1975, and the generator put on line the following day.
The performance of fuel is monitored at the plant by the offgas level during plant operation and by fuel sipping during a refueling ourage. A summary of fuel performance through Cycle 2 is reported in the document entitled, "Monticello Nuclear Generating Cycle 3 Startup Report and Summary Status of Fuel Report," submitted July 19, 1974. As reported, a thorough sipping program at the end of Cycle 2 revealed cladding perforations in a number of initial core fuel assemblies.
The offgas level was found substantially reduced during the initial power ascension in Cycle 3, but prior to reaching rated conditions it became apparent that additional perforations had developed.
Power was restricted rn 907. of rated early in the cycle, decreasing to 757. at the end of Cycle 3 to meet an administrative limit on offgas which was established well below the licensed limit.
During the last refueling outage the 348 initial core fuel assemblies in the core were wet / dry sipped in the fuel pool. A total of 49 leaking assemblies were identified. All 20 Reload-1 (7x7) assemblies and a 257. sample of the 116 Reload -2 (8x8) assemblies were sipped with no lenkers identified.
These findings are consistent with previous cycles.
To date 157 of the initial core fuel assemblics have been classified as leakers; no replacement fuel has failed.
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4779
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