ML17324A742

Application for Amend to License DPR-74,revising Tech Specs Re Cycle 6 Reload.Fee Paid

ML17324A742
Person / Time
Site:	Cook
Issue date:	03/14/1986
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML17324A745	List: ML17324A742 ML17324A749 ML17324A751
References
AEP:NRC:0916I, AEP:NRC:916I, NUDOCS 8603200290
Download: ML17324A742 (12)

Text

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ACCESSION NN~l6032002'FO DOC: O'ATE!""SE'/03/14 '"NOTARIZED: NO '- ')OCXET FACIL: 50-316 Donald C. Cook Nuclear Power Planti Unit 2i Indiana h 05000316 AUTH. NANE AUTHOR AFFILIATION ALEXICH, N. P. Indiana h Michigan Electric Co.

REC I P. NANE REC I P IENT AFF I L I ATION DENTON> H. R. Of f ice of Nuclear Reactor Regulationi Director (post 851125

SUBJECT:

Application for amend to License DPR-74> revising Tech Specs re Cycle 6 reload. Fee paid.

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IN DIANA 8 M ICH IGAN ELECTRIC CON PAN Y P,O, BOX 16631 COLUMBUS, OHIO 43216 March 14, 1986 AEP:NRC:0916I Donald C. Cook Nuclear Plant Unit No. 2 Docket No. 50-316 License No. DPR-74 PROPOSED TECHNICAL SPECIFICATIONS FOR. THE CYCLE '6 RELOAD Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Denton:

This letter and its attachments constitute an application for amendment to the Technical Specifications (T/Ss) for the Donald C. Cook Nuclear Plant Unit No. 2. This amendment is requested to support the Cycle 6 reload of Unit 2. Cycle 6 is scheduled to begin critical operation June 1, 1986 and will include the third reload fuel batch fabricated by Exxon Nuclear Company (ENC).

Our analysis concerning significant hazards considerations and a summary of the justification for the D. C. Cook Unit 2 Cycle 6 T/S changes are included in Attachment 1. Attachment 2 contains the proposed revised T/S pages.

Attachment 3 is the proprietary version of the safety evaluation for the RdF RTD installation in Unit 2. Attachment 4 contains the Westinghouse Application for Withholding Proprietary Information from Public Disclosure,

<HA CAW-86-017, the accompanying affidavit, and the Proprietary Information

,ming HO Notice for the safety evaluation in Attachment 3. We will be transmitting OO a non-proprietary version of the Westinghouse report by separate letter.

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,NO It is anticipated that this will be sent by March 21, 1986.

aa Attachment 5 contains an ENC letter report describing supplementary 01CI OA calculations to previously submitted analyses for D. C. Cook Unit 2 Cycle 6 OC operation. Attachment, 6 is ENC's Application for Withholding Proprietary Information from, Public Disclosure. ENC will be transmitting a non Cll Pl

6) fi'A -proprietary version of the report in a separate letter by June 1, 1986.

In order to ensure that these materials are available for your review on a timely basis, Attachments 5 and 6 will be submitted directly to you by ENC on March 14, 1985 with their letter No. RAC:022:86. As discussed with your staff on March 13, 1986, changes to the Boron Dilution Accident analysis are still under Corporate review and will be transmitted separately by ENC as a supplement to this report. c& k"m4 gisC A Ci@~g <:A4 x

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Mr. Harold R. Dent AEP:NRC:0916I Attachment 7 contains a summary of allowances which are not addressed by other attachments. This attachment has been provided to assist the reviewers in understanding the development of certain values cited in the proposed Technical Specifications, and supplements information provided in Attachments 3, 5, and previously submitted ENC analyses.

Attachment 8 is a list of previously submitted analyses for D. C. Cook Unit 2 Cycle 6 operation. Attachment 9 is a summary table of the Cycle 6 reload. This table includes information on a number of characteristics of the fuel assemblies that will constitute the Cycle 6 core.

For your convenience in reviewing these changes, we have included as 0 a summary description of all the T/S changes, including references to specific sections 'o'f the Cycle 6'afety analyses where appropriate.

We believe that the proposed changes will not result in (1) a significant change in the types of effluents or a significant increase in the amounts of any effluent that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure.

To the best, of our knowledge, these proposed changes constitute all of those needed to support the Cycle 6 reload with the exception of changes to T/Ss 3/4.1.1.2 and 3/4.1.2.7. These changes are currently being prepared and are expected to be submitted by March 21, 1985. We have, however, included descriptions of these changes in Attachment 10 and included 10 CFR 50.92 analyses for them in Attachment 1. We have included blanks in to indicate the location in the present T/Ss where changes will occur.

These proposed changes will be reviewed by the Plant Nuclear Safety Review Committee (PNSRC) by March 27, 1986 and by the Nuclear Safety Design Review Committee (NSDRC) at their next regularly scheduled meeting. Should their review in any way change this submittal, we will notify you promptly.

In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to Mr. R. C. Callen of the Michigan Public Service Commission and Mr. G. Bruchmann of the Michigan Department of Public Health.

Pursuant to 10 CFR 170.12(c), we have enclosed an application fee of

$ 150.00 for the proposed amendments.

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Mr. Harold R. Dent AEP:NRC:0916I This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.

Ver tr ly you M. P. lexich Vice President SP

'm Attachments cc: John E. Dolan (Proprietary)

W. G. Smith, Jr. - Bridgman (Proprietary)

G. Bruchmann (Propri etary)

R. C. Callen (Proprietary)

G. Charnoff (Proprietary)

NRC Resident Inspector Bridgman (Proprietary)

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INDIANA 8 MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 March 14, 1986 AEP:NRC:0916I Donald C. Cook Nuclear Plant Unit No. 2 Docket No. 50-316 License No. DPR-74 PROPOSED TECHNICAL SPECIFICATIONS FOR THE CYCLE 6 RELOAD Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Denton:

This letter and its attachments constitute an application for amendment to the Technical Specifications (T/Ss) for the Donald C. Cook Nuclear Plant Unit No. 2. This amendment is requested to support the Cycle 6 reload of Unit 2. Cycle 6 is scheduled to begin critical operation June 1, 1986 and will include the third reload fuel batch fabricated by Exxon Nuclear Company (ENC).

Our analysis concerning significant hazards considerations and a summary of the justification for the D. C. Cook Unit 2 Cycle 6 T/S changes are included in Attachment 1. Attachment 2 contains the proposed revised T/S pages.

Attachment 3 is the proprietary version of the safety evaluation for the RdF RTD installation in Unit 2. Attachment 4 contains the Westinghouse Application for Withholding Proprietary Information from Public Disclosure, CAW-86-017, the accompanying affidavit, and the Proprietary Information Notice for the safety evaluation in Attachment 3. We will be transmitting a non-proprietary version of the Westinghouse report by separate letter.

It is anticipated that this will be sent by March 21, 1986.

Attachment 5 contains an ENC letter report describing supplementary calculations to previously submitted analyses for D. C. Cook Unit 2 Cycle 6 operation. Attachment 6 is ENC's Application for Withholding Proprietary Information from Public Disclosure. ENC will be transmitting a non

-proprietary version of the report in a separate letter by June 1, 1986.

In order to ensure that these materials are available for your review on a timely basis, Attachments 5 and 6 will be submitted directly to you by ENC on March 14, 1985 with their letter No. RAC:022:86. As discussed with your staff on March 13, 1986, changes to the Boron Dilution Accident analysis are still under Corporate review and will be transmitted separately by ENC as a supplement to this report. cFc'w, gyp gncA Phanyf:Ag g g0

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Mr. Harold R. Den AEP:NRC:0916I Attachment 7 contains a summary of allowances which are not addressed by other attachments. This attachment has been provided to assist the reviewers in understanding the development of certain values cited in the proposed Technical Specifications, and supplements information provided in Attachments 3, 5, and previously submitted ENC analyses.

Attachment 8 is a list of previously submitted analyses for D. C. Cook Unit 2 Cycle 6 operation. Attachment 9 is a summary table of the Cycle 6 reload. This table includes information on a number of characteristics of the fuel assemblies that will constitute the Cycle 6 core.

For your convenience in reviewing these changes, we have included as 0 a summary description of all the T/S changes, including references to specific sections of the Cycle 6 safety analyses where appropriate.

We believe that the proposed changes will not result in (1) a significant change in the types of effluents or a significant increase in the amounts of any effluent that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure.

To the best of our knowledge, these proposed changes constitute all of those needed to support the Cycle 6 reload with the exception of changes to T/Ss 3/4.1.1.2 and 3/4.1.2.7. These changes are currently being prepared and are expected to be submitted by March 21, 1985. We have, however, included descriptions of these changes in Attachment 10 and included 10 CFR 50.92 analyses for them in Attachment 1. We have included blanks in to indicate the location in the present T/Ss where changes will occur.

These proposed changes will be reviewed by the Plant Nuclear Safety Review Committee (PNSRC) by March 27, 1986 and by the Nuclear Safety Design Review Committee (NSDRC) at their next regularly scheduled meeting. Should their review in any way change this submittal, we will notify you promptly.

In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to Mr. R. C. Callen of the Michigan Public Service Commission and Mr. G. Bruchmann of the Michigan Department of Public Health.

Pursuant to 10 CFR 170.12(c), we have enclosed an application fee of

$ 150.00 for the proposed amendments.

Mr. Harold R. Dent AEP:NRC:0916I This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.

Ver t ly you M. P. lexich Vice President 9)~"'m Attachments cc: John E. Dolan (Proprietary)

W. G. Smith, Jr. - Bridgman (Proprietary)

G. Bruchmann (Proprietary)

R. C. Callen (Proprietary)

G. Charnoff (Proprietary)

NRC Resident Inspector - Bridgman (Proprietary)

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