ML20059F137
| ML20059F137 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/28/1993 |
| From: | Rehn D DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19311B168 | List: |
| References | |
| NUDOCS 9311040147 | |
| Download: ML20059F137 (4) | |
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DukeIbwerCompany D. L Rtm Catawba Nudear Generation Department Yue i+esident
~ 800ConcordRoad (Mm8313205 Olhce 4
York. SC29745 (803 AH3426 Fax DUKEPOWER October 28,1993 i
U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C.
20555
Subject:
Catawba Nuclear Station, Unit I-Docket No. 5G-413 Supplement to Technical Specification Amendment Renewal Of Steam Generator Tube Interim Plugging Criteria for Unit 1 Cycle 8 On October 5,1993, Catawba Nuclear Station submitted a proposed Technical Specification Amendment requesting renewal of the voltage-based steam generator tube interim plugging criteria for Unit I for Cycle 8. With this submittal, Catawba enclom.1 WCAP-13854,
" Technical Support for Cycle 8 Steam Generator Tube Interim Plugging Criteria for Catawba Unit 1," September 1993. This WCAP references WCAP-13684 (Proprietary),
" Analysis to Determine Relative Tube / Tube Support Plate Displacements Under Steam Line Break leads for Catawba Unit 1 Steam Generators," March 1993. The information contained in this tube support plate deflection analysis (WCAP-13684) was discussed in a meeting held between the NRC staff, Catawba Nuclear Station personnel, and -
Westinghouse personnel on April 1,1993, but was never formally submitted to the NRC.
This letter represents our formal submittal of this analysis.
When WCAP-13684, " Analysis to Determine Relative Tube / Tube Support Plate Displacements Under Steam Line Break Imads for Catawba Unit 1 Steam Generators," was developed and printed, it was not appropriately marked to delineate proprietary informatica. As a result, Catawba is submitting WCAP-13684, Rev.1, " Analysis to Determine Relative Tube / Tube Support Plate Displacements Under Steam Line Break Loads for Catawba Unit 1 Steam Generators" which properly identifies the proprietary information. This is the only significant difference between WCAP-13684 and WCAP-13684, Rev.1. There are no technical changes to WCAP-13684. Therefore, WCAP-13854, " Technical Support for Cycle 8 Steam Generator Tube Interim Plugging Criteria for Catawha Unit 1," September 1993, should now reft ence WCAP-13684, Rev.1 instead
. of WCAP-13684.
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E October 28,1993.
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l Enclosed are:
1.
5 copies of WCAP-13684, Rev.1, " Analysis to Determine Relative Tube / Tube-Support Plate Displacements Under Steam Line Break Loads for Catawba' Unit 1 Steam Generators" (Proprietary).
2.
5 copies of WCAP-13887, " Analysis to Determine Relative Tube / Tube Support Plate.
Displacements Under Steam Line Break Imads for Catawba Unit 1 Steam Generators" (Non-Proprietary).
Also enclosed are a Westinghouse authorization letter, CAW-93-538, an accompanying affidavit, a Proprietary Information Notice, and a Copyright Notice.
As item 1 above contains information proprietary to Westinghouse Electric Corporation, it is supported by an affidavit signed by Westinghouse, the owner of the information. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR Section 2.790 of the Commission's regulations.
Accordingly, it is respectfully requested that the information which is proprietary. to Westinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.790 of the Commission's regulations.
Correspondence with respect to the copyright or proprietary aspects of the items listed above or the supporting Westinghouse Affidavit should reference CAW-93-538 and should be addressed to Nicholcs J. Liparulo, Manager of Nuclear Safety and Regulatory Activities, Westinghouse Electric Corporation, P.O. Box 355, Pittsburgh, Pennsylvania 15230-0355.
Pursuant to 10 CFR 50.91 (b)(1), the appropriate South Carolina official is being provided a copy of this letter.
Very truly yours, U. % ' /
s D. L. Rehn RKS/
Enclosures j
m Nuclear Regulatory Commission October 28,1993 Page 3 q
xc: Mr. S. D. Ebneter Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900 Atlanta, GA 30323 Mr. Heyward Shealy, Chief Bureau of Radiological Health South Carolina Department of Health &
Environmental Control i
2600 Bull Street Columbia, SC 29201 Mr. R. J. Freudenberger NRC Resident Inspector Catawba Nuclear Station Mr. Robert E. Martin, Project Manager ONRR Mr. William T. Russell, Associate Director Inspection & Technical Assessment ONRR i
American Nuclear Insurers c/o Dottie Sherman, ANI Library The Exchange, Suite 245 270 Farmington Avenue Farmington, CT 06032 M & M Nuclear Consultants 1166 Avenue of the Americas New York, NY 10036-2774 INPO Records Center Suite 1500 1100 Circle 75 Parkway r
Atlanta, Georgia 30339 I
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U. S. Nuclear Regulatory Commission Page 4 i
D. L. Rehn, being duly sworn, states that he is Site Vice-President, Catawba Nuclear Station; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission this revision to the Catawba Nuclear Station ' Technical l
Specifications, Appendix A to License No. NPF-35; and that all statements and matters set forth therein are true and correct to the best of his knowledge.
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Subscribed and sworn to before me this Jf day of O/ ND
,1993.
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