ML20032C836
| ML20032C836 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 09/08/1981 |
| From: | William Jones OMAHA PUBLIC POWER DISTRICT |
| To: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| NUDOCS 8111110780 | |
| Download: ML20032C836 (4) | |
Text
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Omaha Public Power District 1623 MARNEY a OMAHA. NEERASMA 681C2 a TELEPHONE 536 4000 AREA CODE 402 N
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September 8, 1981 N
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b Mr. K. V. Seyfrit, Director t f40V1019815 @
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U.S. Nuclear Regulatory Commission u
Office of Inspection and Enforcement
,7 Region IV s
611 Ryan Plaza Drive, Suite 1000 Q/[
Arlington, Texas 76011 1
Subject:
Fort Calhoun Station Cycle 7 Refueling and Operation
Dear Mr. Seyfrit:
This letter is to inform the Nuclear Regulatory Commission of Omaha Public Power District's (0 PPD) schedule for refueling the Fort Calhoun Station Unit No.1 for Cycle 7 operation.
Current District planning has Cycle 6 operation terminating on or about September 15, 1981.
At that time, an estimated two (2) month refueling outage will begin.
The Cycle 7 core will consist of forty (40) fresh batch I assemblies of 3.50 w/o enrichment. The remainder of the core will be composed of forty (40) batch H fuel assemblies, forty-four (44) batch G assemblies, eight (8) batch F assemblies, and assembly D005 which will be irradiated for its sixth cycle as part o' a DOE high burnup fuel demonstration program.
The loading pattern or Cycle 7 is shown in the attached v
figure.
Based on analyses performed by our nuclear fuel vendor, Exxon Nuclear Corporation, and by the District, it has been determined that:
1.
No Technical Spec'fication changes are required for Cycle 7 operation, 2.
The axial and racial power distribtdicas calculated for Cycle 7 are bounded by the power distributions used to generate the current Technical Specifications, 3.
The control rod reacthity for Cycle 7 is conservative with respect to that used to generate the current Technical Speci-fications, 4.
The Cycle 7 thermal-hydraulic parameters are within the bounds covered by the current Technical Specifications and safaty
- analyses,
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Mr. K. V. Seyfrit September 8, 1981 Page Two i
5.
The tran:ient accidents analyzed for Cycle 7 are bounded by the Cycle 6 safety analyses,
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6.
The anticipated fuel assembly bernups, excluc'ing assembly 0005, do not exceed the limits established in the Cycle 6 safety analyses, q
i 7.
All Cycle 7 parameters which affect the ECCS analysis are conservative with respect to the parameters used in the Cmle 6 ECCS safety analyses, 8.
The new fuel (batch I) to be loaded in Cycle 7 is identical to the batch H fuel which was the new fuel loaded in Cycle 6, 9.
The Cycle 7 safety analyses are based on the Cycle 6 burnup of 11,000 + 500 MWD /MTU and Cycle 6 will be shut down with a burnup within this design burnup " window", and 10.
The Cycle 7 startup physics testing program will be conducted in accordance with the testing program used during the Cycle 6 startup.
The District has concluded that the Cycle 7 refueling and subsequent operation will not:
1.
Increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analyses, 2.
Create the possibility for an accident or malfunction of a different type than any evaluated previously in the safety analyses report, and 3.
Reduce the margin of safety as defined in the basis for any Technical Specification.
Therefore, pursuant to 10 CFR 50.59(a)(1), the District has determined that the Cycle 7 refuelint and operation does not involve a change in the Technical Specification or an unreviewed safety question.
Cmaha Public Power District is planning to irradiate a Combustion Engineering nuclecr fuel assembly for its sixth operating cycle in the Fort Calhoun Cycle 7 core. This irradiation is to provide a small scale demonstration of fuel performance at exposures greater than 50,000 MWD /MTV. The average exposure of this assembly at the start of Cycle 7 will be 45,000 MWD /MTV and is projected to be 52,500 MWD /MTU at the end of this cycle. The high burnup assembly is currently being irradiated in its fifth cycle at rcrt Calhoun.
Following Cycle 6 shutdown, the high burnup assembly (D005) will be examined in detail using the Com-bustion Engineering comprehensive inspection stand.
The D005 assembly will be reconstitute ~ by removing selected high burnup fuel rods and replacing them with fuel rods from discharged batch D assemblies. Only
'Mr. K. V. Seyfrit September 8, 1981 Page Three after the assembly is examined and judged to be suitable for a sixth cycle of irradiation will it be reloaded in ~the Fort Calhoun Cycle 7 Core.
Our confidence that this fuel ' assembly will operate successfully for the full cycle is based on the previous performance of CE nuclear fuel, the favorable poolside inspection results following each of the four previous cycles of operation, and the fact that the assembly power will be about 70 percent of the core average assembly power.
Omaha Public Power District and Combustion Engineering have not yet completed the safety review for the high burnup demonstration assembly in Cycle 7.
The criteria for the Cycle 7 safety analyses are the same as those for the Cycle 6 safety analyses. The irradiation for the higi.
burnup assembly in Cycle 7 is expected to involve no unreviewed safety questions and will require no change in the Technical Specifications.
If further evaluation and completion of the formal review of this de-monstration bundle irradiation by the District staff (to be completed by September 11,1981) does not confirm our preliminary assessment, we will submit further analyses or the demonstration bundle will not be utilized in Cycle 7.
If assembly D005 is not utilized in the Cycle 7 core, an irradiated fuel assembly which has been or would have been discharged from the core will replace D005 :n the Cycle 7 core.
The assembly will -be selected such that the Cycie 7 power distribution will be bounded by the power distribution used i' the Cycle 7 safety analyses.
Sincergly, O
(A W W. C.
ones l
Divisi n Manager Production Operations WCJ/KJM/TLP:jmm cc: Mr. Robert A. Clark, Chief U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Licensing Operating Reactors Branch No. 3 Washington, D.C.
20555 LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.
Washington, D.C.
20036
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Irradiated Fuel Designation xx Cycle 7 Batch Type y-z Cycle 6 Location Fresh Fuel Designation AA Batch BB-CC Assembly Identification
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Fort Calhoun Cycle 7 Loadino Pattern i