ML20076F376
| ML20076F376 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 06/10/1983 |
| From: | Giesler C WISCONSIN PUBLIC SERVICE CORP. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-83-121 NUDOCS 8306140048 | |
| Download: ML20076F376 (10) | |
Text
,
NRC-83-121 WISCONSIN P U B LIC S E RVIC E CO R PO R ATIO N RO. Box 1200, Green Bay, Wisconsin 54305 June 10, 1983 Mr. S. A. Varga, Chief Operating Reactors Branch #1 Division of Licensing U.S. Nuclear Regulatory Commision Washington D.C.
20555
Dear Mr. Varga:
Docket 50-305 Operating License DPR-43 Kewaunee Nuclear Power Plant Cycle IX Reload Safety Evaluation, Revision 1
Reference:
Kewaunee Nuclear Power Plant Reload Safety Evaluation, Kewaunee Cycle IX, dated February 1983, transmitted to S. A. Varga from C. W. Giesler by letter dated February 24, 1983.
Enclosed please find forty (40) copies of the recently revised pages to the Kewaunee Nuclear Power Plant Cycle IX Reload Safety Evaluation (RSE). The initial Cycle IX RSE (referenced above) was completed prior to the shut down of Cycle VIII, and was therefore based on a proposed core reloading pattern designed from an assumed beginning of cycle burnup distribution. The reload pattern has since been optimized, using the actual beginning of Cycle IX burn-up distribution, by removing eight clusters Of depleted burnable poison rods from the initial design. Accordingly, the appropriate pages to the referenced safety evaluation have been revised to reflect the redesigned core pattern.
The conclusions of the safety evaluation are not affected by this change.
Our evaluation has shown that the Cycle IX core design is more conservative than the design utilized in our accident analysis, and therefore does not create an unreviewed safety question.
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O Mr. S. A.~Varga
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Jun'e 10,1983 Page 2 Very truly yours, b[ WM%
C W Giesler Vice President - Nuclear Power 1
ms Enc.
cc - Mr. Robert Nelson, US NRC US NRC, c/o Document Management Branch Washingtcn, D.C.
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Re vo 1 RELOAD SA FETY EVALU ATION FOR KEWAUNEE CYCLE IX Prepared By _ _.[.
- g Date 9'22~S huclear Fuel Engineer
' M'b Date Reviewed By Nucid r Fu Analysis Supervisor
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Date hM-h3 Reviewed By _
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Licensing & Systems Supervisor
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Director - Fuel Services
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Date 8f [7 Approved By _ Manager - Fuel & Fossil Operations
Rev. 1 1 0 IEIEDRHCII93 The Kowaunee Nuclear Power Plant is shutdown for the Cycle 8-9 refueling.
Startup of cycle 9 is forecast for say, 1983.
This report presents an eval".ation of the Cycle 9 reload and demonstrates that the core reload will not adversely affect the safety of the plant.
Those accidents which could potentially be affected by the reload core design are re v iewed.
Details of the calculational model used to generate physics parameters for this Reload Safety Evaluation are described in Reference (1).
Accident Evaluation methodologies applied in this report are detailed in Reference (2).
These reports have been previously reviewed (3).
The current model reliability factors are discussed in section 5 of this report.
An evaluation, by accident, of the pertinent reactor parame-ters is perf ormed by comparing the reload analysis results with the current bounding safety analysis values.
The evaluations performed in this document employ the current Technical Specification (4) limiting safety system setpoints and operating limits including the burnup dependent power peaking limits described in section 2.2 where applicable.
Rev. 1 It has been concluded that the Cycle 9 design is more conservative than results of previously docketed accident analyses.
This conclusion is based on the assumption that there is adherence to plant operating limitations, and Technical Specifications (4),
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1 Ze O COBE DEB 192 2.1 Core Description The reactor core consists of 121 fuel assemblies of 14 X 14 l
design.
The core loading pattern, assembly identification, BCCA bank identification, instrument thimble I.D.,
thermo-couple I.D.,
and burnable poison rod configurations for Cycle 9 are presented in Figure 2.1.1.
Thirty-six new Erron assemblies enriched to 3. 4 w/o U235 will reside with seventy-two partially depleted Exxon and thirteen partially depleted Westinghouse assedblies.
Table 2.1.1 displays the core breakdown by region, enrichment and previous cycle duty.
The Cycle 9 reload core vill employ 32 Burnable Poison Rod Assemblies (BPHA'S) containing 256 fresh and 112 partially depleted burnable poison rods.
Eight clusters of depleted burnable poison rods were removed from the initial design to optimize the loading pattern based on the actual beginning of Cycle 9 burnup distribution.
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- 2. 4 Shutdown Window Since the Cycle 9 BPR configuration was optinized based on the actual beginning of Cycle 9 burnup distribution, the sensitivity analysis of the Cycle 8 shutdown burnup window was replaced by a calculation of peaking factors at the actual Cycle 9 burnup distribution.
The results are presented in Table 2.4.1.
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Rev. 1 Table 2.4.1 Peaking Factor at Actual Beginning of Cycle Burnup IMi______
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