ML20215A201
| ML20215A201 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/04/1986 |
| From: | Nauman D SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19292G420 | List: |
| References | |
| NUDOCS 8612110204 | |
| Download: ML20215A201 (2) | |
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29218 Nuclear Operations SCE&G December 4,1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C. 20555
Subject:
Virgil C. Summer Nuclear Station Doc cet No.50/395 Operating License No.NPF-12 Steam GeneratorTube Repair
Dear Mr. Denton:
'l In a letter from Mr. D. A. Nauman to Mr. H. R. Denton dated January 16,1986, and as su aplemented in letters dated March 18, May 8, and July 22,1986, South Carolina Electric & Gas Compan (SCE&G) requested an amendment to the Virgil C. Summer Nuclear Station's Te nical Specifications (T.S.), Section 3/4.4.5, " Steam Generators," and its bases. This amendment would allow SCE&G the potential for i
alternatives to tube plugging in the event that subsequent degradation occurs in the steam generator tubes. The proposed T.S. change would permit SCE&G to select a tube repair method, to perform an evaluation in accordance with 10 CFR 50.59, and to utilize the method in the repair of defective steam generator tubes.
Based upon the subsequent technical review, additional clarifying information has been identified for incorporation into the amended T.S. pages. AttachmentIis an updated T.S. revision package, which incorporates the clarifying amendment requested by your stafT.
Included as AttachmentIIis the Combustion Engineering Inc. (CE) Technical Report,"V. C. Summer Steam Generator Tube Re ir Using Leak Ti,ght Sleeves,"
CEN-337-P. This document has been prepa ed b CE to address the issue of experienced degradation. CENpanded steam generator tubes which may have repairing fulldepth hardroll ex 337-P contains information proprietary to CE and is su pported by an affidavit (Attachment III) signed b CE, the owner of the information. The affidavit sets forth the basis on w ich the information may be withheld from public disclosure by the Commission and addresses with specifici the considerations listed in paragraph (b)(4) of Section 2.790 of Title 10 of the Co e of Federal Regulations (10CFR2.790).
Accordingly,it is respectfully requested that the information which is proprietary to CE be withheld from public disclosure in accordance with 10CFR2.790.
Correspondence with respect to the proprietary as pects of the application for withholding or the supporting CE a:Tidavit should reference SC 86-57 and should be addressed to A. E. Scherer, Director, Nuclear Licensing, Combustion Engineering Inc.,1000 Prospect Hill Road, P.O. Box 500, Windsor, Connecticut 06095.
8612110204 861204
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Mr. H. R. Denton Steam GeneratorTube Repair December 4,1986 Page 2 This change does not alter the conclusions of the "No Significant Hazard Determination" previously submitted with the January 16,1986, letter. The req uest has been reviewed and approved by the Plant Safety Review and the Nuclear Safety Review Committees. The application fee for the review of the amendment request has been submitted previously with the January 16,1986, letter from Mr. D. A.
Nauman to Mr. H. R. Denton.
The statements and matters set forth in this submittal are true and correct to the best of my knowledge, information and belief.
Ifyou should have any further questions, please advise.
Very tr.y ou D.A.Naum DBM: DAN:bjh c:
O. W. Dixon, Jr./T. C. Nichols, Jr.
E. H. Crews, Jr.
E. C. Roberts J. G. Connelly, Jr.
D. R. Moore W. A. Williams,Jr.
J. Nelson Grace Group Managers O. S. Bradham C. A. Price C. L. Ligon (NSRC)
R. M. Campbell, Jr.
K. E. Nodland R. A.Stough G. O Percival R. L. Prevatte J. B. Knotts, Jr.
H. G. Shealy NPCF PSRC File v
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