ML19330B683
| ML19330B683 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/29/1980 |
| From: | Crouse R TOLEDO EDISON CO. |
| To: | Novak T Office of Nuclear Reactor Regulation |
| References | |
| 638, NUDOCS 8008050373 | |
| Download: ML19330B683 (2) | |
Text
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TOLEDO
%mme EDISON A.crama P. Cacuse yte Avs. cent NsC43r Docket No.50-346
.c s 233 522i License No. NPF-3 Serial No. 638 July 29, 1980 Director of Nuclear Reactor Regulation Attention:
Mr. Themas M. Novak Assistant Director Operating Reactors Division of Licensing United States Nuclear Regulatory Commission b*ashington, D. C.
20555
Dear Mr. Novak:
This letter partially responds to your request for additional information related to the proposed technical specification changes to support fuel cycle 2 operation of the Davis-Besse Nuclear Power Station, Unit 1.
The attachment addresses items 1 and 3 of your request.
Item 2 is being further discussed with your staff. A final response will be consistent with the results of the current discussions.
Very truly yours, f
Tc'-
RPC:TJM Attachment
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THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISCN AVENUE TOLECO, OHIO 43652 8008050 373
Docket No. 50-346 License No. NPF-3 Serial No.
638 July 29, 1980' Response to Items 1 and 3 of July 23, 1980 NRC Letter for
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Davis-Besse Nuclear Power Station Unit 1 (DB-1)
Item ?
We have not yet received a response to our letter of November 23, 1979 from R. W. Reid (NRC) to L. E. Roe (Toledo Ed) on control rod guide tube wear.
Please provide a schedule for your response and, if the response is to rely on a B&W generic evaluation, identify the generic evaluation report and pro-vide a statement of your concurrence with its findings.
-RESPONSE The evaluation appropriate for DB-1 is provided in Topical Report BAW-1623 (June, 1980) " Control Rod Guide Tube Wear Measurement Program". This was formally transmitted to the NRC from Babcock & Wilcox (J. Taylor) on July 18, 1980.
Toledo Edison concurs with the report findings.
Item 3 Please provide the expected values for the maximum local and maximum assembly burnup for EOC 2 at Davis-Besse Unit 1.
Will fuel rod internal pressures remain below nominal system pressure during normal operation for these projected burnups?
RESPONSE
The expected values for the local and maximum assembly burnup for EOC 2 at DB-1 are 23,900 and 23,300 mwd /mtu, respectively. The fuel rod internal pressure will remain below nominal system pressure during normal. operation for these projected burnups.
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