ML20035H147
| ML20035H147 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/22/1993 |
| From: | Tuckman M DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19303F598 | List: |
| References | |
| ET-NRC-93-3868, NUDOCS 9305030205 | |
| Download: ML20035H147 (3) | |
Text
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Duke Pouer Company MS YtxwnN Ca airba hudear Genemnon Drnrtment Vice Presider.t r
600 Concord Road (M3)MI 3205 Othce fork. SC 29745 (M3)UI-3126 ft t DUKEPOWER April 22,1993 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C.
20555
Subject:
Catawba Nuclear Station, Unit 1 l
Docket No. 50-413 l
AdditionalInfonnation Supporting Catawba Unit 1 Operation for the Remainder of Cycle 7 On April 8,1993, Catawba Nuclear Station submitted technical information which quantified main steam line break (SLB) steam generator tube leakage and the associated dose consequences to funher support the Interim Plugging Criteria (IPC) which was granted by the NRC on September 25,1992 for Catawba Unit 1 Cycle 7. This infonnation was supplemented on April 21,1993. This infonnation was discussed with the NRC staff and it was requested that further modifications be made to the calculations and the information be resubmitted. Enclosed is the information requested in the form of Addendum 1 to the infonnation submitted on April 8,1993.
The information related to SLB steam generator tube leakage is proprietary to Westinghouse. Please refer to the attached Westinghouse letter, ET-NRC-93-3868, which requests that this information be withheld from public disclosure. As stated in this letter, Westinghouse expects to fully comply with the requirements for the pmprietary and non-pmprietary versions of the infonnation and an accompanying affidavit when the documents have been pnspared.
In addition, enclosed are Catawba SLB dose analysis methodology and results which utilize the values for SLB steam generator tube leakage from the enclosed Westinghouse repon.
Per discussion held on April 21,1993 between Mr. Matthews of your staff and myself, it is my understanding that Catawba has been given relief from the mid-cycle outage which was n: quired by the Safety Evaluation issued with Technical Specification Amendment 102 to Facility Operating License NPF-35. This decision is contingent upon final submittal all necessary documentation by Catawba. In addition, it is my understanding that a revised Safety Evaluation will be issued which reflects this decisien to permit full cycle operation for Catawba Unit I during Cycle 7.~
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t U. S Nuclear Regulatory Commission j
April 22,1993 Page 2 I declare under penalty of perjury that these statements are true and correct to the best of l
my knowledge.
l Very truly yours, I
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f hW~0ws M. S. Tuckman i
6 5
RKS/
i Enclosums e
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I
l U. S. Nuclear Regulatory Commission i
April 22,1993 i
Page 4 i
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bxc: D. B. Mayes W. A. Haller H. D. Brewer T. E. Cook I
R. C. Futrell i
T. P. Harrall l
l A. S. Bhatnager R. O. Sharpe i
D. V. Ethington i
T. C. Poindexter L. R. Davison NCMPA-1 NCEMC l
PMPA SREC ELL-EC050 Group File: CN-801.01 Master File: 801.01 i
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