ML17324B124

Forwards Rev 0 to Steam Generator Repair Rept. Steam Generator Design Changes,Qa Program,Security Aspects & Environ Evaluation Discussed.Table 3.8-1, Repair Project Man-Rem Estimates Withheld (Ref 10CFR2.790(a)(4))

ML17324B124
Person / Time
Site:	Cook
Issue date:	11/07/1986
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML17324B125	List: ML17324B124 ML17334B012
References
AEP:NRC:0980, AEP:NRC:980, NUDOCS 8611140299
Download: ML17324B124 (9)

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ACCESSION NBR: 8611140299 DOC. DATE: 86/11/07 NOTARIZED: YES DOCKET ¹ FAC IL: 50-316 Donald C. Cool; Nuclear Po))jer Plant. Unit 2. Ind iana 5 05000316 AUTH. NANE AUTHOR AFFILIATION ALEXICH, t1. P. Indiana )c michigan Electric Co.

REC IP. )~tANE RECIPIENT AFFILIATION DENTON> H. R. Office of Nuclear Reactor Regulation~ Director (post 851125

SUBJECT:

Fortoards Rev 0 to "Steam Generator Repair Rept. " Steam generator design changesi GA program> securitg aspects environ evaluation discussed. Table 3. 8-1> "Repair Pro Ject Nan-Rem Estimates" withheld (ref 10CFR2. 790(a) (4) ).

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TITLE: QR Submittal: General Distribution NOTES:

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P.O. BOX 16631 COLUMBUS, OHIO 43216 November 7, 1986 AEP:NRC:0980 Donald C. Cook Nuclear Plant Unit No. 2 Docket No. 50-316 License No. DPR-74 STEAM GENERATOR REPAIR REPORT, REVISION 0 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Denton:

Please find enclosed the Steam Generator Repair Report, Revision 0, for the Donald C. Cook Nuclear Plant, Unit 2. As previously discussed with your staff, Unit 2 of the Donald C. Cook Nuclear Plant has experienced secondary side corrosion in a number of tubes in the four steam generators. Various measures have been taken to arrest the corrosion, including plugging of degraded tubes, boric acid addition and reduction of operating temperature. At present, Donald C. Cook Unit 2 is being operated at 80% power as the result of reduced operating temperature.'o increase availability and to return to full-power operation, Indiana & Mi'chigan Electric Company (I&MECo) plans to repair the four Donald C. Cook Unit 2 steam generators by replacement of the lower assemblies.

The steam generator repair project for Donald C. Cook Unit 2, as described in the enclosed Steam Generator Repair Report, is similar to the steam generator repairs completed by the Virginia Electric and Power Company for the Surry Power Station and by Wisconsin Electric Power Company for the Point Beach Nuclear Plant, Unit 1. I&MECo will be using the reactor coolant system pipe-cutting process to remove the Donald C.

Cook Unit 2 steam generators. This process was successfully used for both the Surry and Point Beach steam generator repairs.

O.M fo o The enclosed Steam Generator Repair Report describes the steam generator design changes that are being made to enhance maintenance and reduce secondary side corrosion. The report describes the repair project, quality assurance program, security aspects associated with the repair project and provides safety evaluations of the repaired steam generators "030 0 and associated repair activities. The report also discusses the environmental evaluation, conducted pursuant to the Donald C. Cook Appendix B Environmental Technical Specifications, for the repair project.

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Mr. Harold R. Denton AEP'NRC:0980 These Technical Specifications were used to evaluate the site work that will begin April 1987. This site work includes road and parking lot upgrade and construction of the temporary facilities necessary to support the repair project.

Based on our preliminary safety evaluations contained in the Steam Generator Repair Report, we believe the final safety evaluations will conclude that the repair project will not involve an unreviewed safety question as defined in 10 CFR 50.59. However, the repair project does require substantial advance planning and involves considerable cost to I&MECo. Therefore, please inform us as quickly as possible of any

.comments the staff may have concerning the repair project as described in the enclosed Steam Generator Repair Report. It is important that the repairs commence as soon as possible after the replacement lower assemblies are delivered to the Donald C. Cook Nuclear Plant. The earliest date of delivery is August 1988.

Also, please find enclosed a check in the amount of $ 150, pursuant to 10 CFR 170, for the review of the enclosed Steam Generator Repair Report.

For you convenience an additional 40 copies of the Steam Generator Repair Report are being sent to you under separate cover. Copies of this letter and its attachment 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.

It is requested, pursuant to 10 CFR 2.790(a)(4), that Table 3.8-1 entitled, "Repair Project Man-Rem Estimates" contained in the enclosed Steam Generator Repair Report be withheld from public disclosure until a general contractor for the repair project has been selected. Disclosure of the information contained in Table 3.8-1 is considered privileged commercial information and would compromise the competitive position of I&MECo in the selection of a general contractor.

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.

Very truly yours,

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M. . Ale rch Pgl~

Vice President >~(loL~

edg Enclosure cc: John E. Dolan, w/o encl.

M. G. Smith, Jr. - Bridgman R. C. Callen G. Bruchmann G. Charnoff, w/o encl.

NRC Resident Inspector - Bridgman

STATE OF OHIO COUNTY OF FRANKLIN M. P. Alexich, being duly sworn, deposes and says that he is the Vice President of Licensee Indiana & Michigan Electric Company; that he has read the Steam Generator Repair Report, knows the contents thereof; and that said contents are true to the best of his knowledge and belief.

M. P..A exich Vice President Subscribed and sworn to me this 7th day of November, 1986.

(Notary Public WW< SS<o+ ~(

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IN DI4N4 8 M ICH IG4N ELECTRIC COM P4N Y P>O> BOX 16631 COLUMBUS, OHIO 43216 November 7, 1986 AEP:NRC:0980 Donald C. Cook Nuclear Plant Unit No. 2 Docket No. 50-316 License No. DPR-74 STEAM GENERATOR REPAIR REPORT, REVISION 0 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Denton:

Please find enclosed the Steam Generator Repair Report, Revision 0, for the Donald C. Cook Nuclear Plant, Unit 2. As previously discussed with your staff, Unit 2 of the Donald C. Cook Nuclear Plant has experienced secondary side corrosion in a number of tubes in the four steam generators. Various measures have been taken to arrest the corrosion, including plugging of degraded tubes, boric acid addition and reduction of operating temperature. At present, Donald C. Cook Unit 2 is being operated at 80% power as the result of reduced operating temperature.

To increase availability and to return to full-power operation, Indiana & Michigan Electric Company (I&MECo) plans to repair the four Donald C. Cook Unit 2 steam generators by replacement of the lower assemblies.

The steam generator repair project for Donald C. Cook Unit 2, as described in the enclosed Steam Generator Repair Report, is similar to the steam generator repairs completed by the Virginia Electric and Power Company for the Surry Power Station and by Wisconsin Electric Power Company for the Point Beach Nuclear Plant, Unit l. I&MECo will be using the reactor coolant system pipe-cutting process to remove the Donald C.

Cook Unit 2 steam generators. This process was successfully used for both the Surry and Point Beach steam generator repairs.

The enclosed Steam Generator Repair Report describes the steam generator design changes that are being made to enhance maintenance and reduce secondary side corrosion. The report describes the repair project, quality assurance program, security aspects associated with the repair project and provides safety evaluations of the repaired steam generators and associated repair activities. The report also discusses the environmental evaluation, conducted pursuant to the Donald C. Cook Appendix B Environmental Technical Specifications, for the repair project.

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hr. Harold R. Denton AEP:NRC:0980 These Technical Specifications were used to evaluate the site work that will begin April 1987. This site work includes road and parking lot upgrade and construction of the temporary facilities necessary to support the repair project.

Based on our preliminary safety .evaluations contained in the Steam Generator Repair Report, we believe the final safety evaluations will conclude that the repair project will not involve an unreviewed safety question as defined in 10 CFR 50.59. However, the repair project does require substantial advance planning and involves considerable cost to I&MECo. Therefore, please inform us as quickly as possible of any comments the staff may have concerning the repair project as described in the enclosed Steam Generator Repair Report. It is important that the repairs commence as soon as possible after the replacement lower assemblies are delivered to the Donald CD Cook Nuclear Plant. The earliest date of delivery is August 1988.

Also, please find enclosed a check in the amount of $ 150, pursuant to 10 CFR 170, for the review of the enclosed Steam Generator Repair Report.

For you convenience an additional 40 copies of the Steam Generator Repair Report are being sent to you under separate cover. Copies of this letter and its attachment 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.

It is requested, pursuant to 10 CFR 2.790(a)(4), that Table 3.8-1 entitled, "Repair Project Man-Rem Estimates" contained in the enclosed Steam Generator Repair Report be withheld from public disclosure until a general contractor for the repair project has been selected. Disclosure of the information contained in Table 3.8-1 is considered privileged commercial information and would compromise the competitive position of I&MECo in the selection of a general contractor.

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.

Very truly yours, M. . Ale x.ch Vice President $

edg ,)by'c:

Enclosure John E. Dolan, w/o encl.

W. G. Smith, Jr. - Bridgman R. C. Callen G. Bruchmann G. Charnoff, w/o encl.

NRC Resident Inspector - Bridgman