ML20138C810
| ML20138C810 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/11/1985 |
| From: | Tucker H DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8510230050 | |
| Download: ML20138C810 (2) | |
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DUKE POWER GOMPANY P.O. HOx 33180 CIIARLOTTE, N.C. 28242 HAL B. TUCKER retzenown vice ransment (704) 373-4531 mm. -.
October 11, 1985 P
l Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 i
Attention:
Ms. E. G. Adensam, Chief j
Licensing Branch No. 4 Re: Catawba Nuclear Station Docket Nos. 50-413 and 50-414
Dear Mr. Denton:
License Condition 17(b) of Facility Operating License NPF-35 requires the submittal of bimonthly reports on the status of the confirmatory research l
program of tests and analyses regarding containme.it response for main steamline break accidents. Attached is the fifth bimonthly report.
Very truly yours,
. /-r
,g Hal B. Tucker WLH/hrp
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Attachment cc:
Dr. J. Nelson Grace, Regional Administrator Palmetto Alliance U. S. Nuclear Regulatory Commission 2135 Devine Street Region II Columbia, South Carolina 29205 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
~NRC Resident Inspector Catawba Nuclear Station Robert Guild, Esq.
P. O. Box 12097 Charleston, South Carolina 29412 Mr. Jesse L. Riley Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 851023005o e51011 PDR ADOCM 05000413
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a Catawba Nuclear Station Main Steamline Break Inside Containment Bimonthly Status Report October, 1985 The draft report on the Catawba I Containment calculations using the COBRA ~NG was received from Numerical Applications Incorporated. Westinghouse is currently completing its review of the report and it will be issued to the utilities and NRC as a WCAP to support the LOTIC-III analysis of ice condenser superheat. The results of the COBRA-NC calculations were presented to Duke Power, the NRC and their consultants; at the end of July. NRC and their con-sultants provided Westinghouse and the utilities with comments and questions on the calculations which have been addressed in the draft report. The COBRA-NC calculations indicate that when the ice condenser drains were modeled; the bulk containment peak temperature was 285*F.
These results have known conser-vations inherent in the calculations and models such that a true best estimate calculation would yield even lower bulk average containment temperatures.
The drain testing has been completed and the data is being reduced and analyzed.
Analysis is also being completed to address the NRC concerns on temperature distributions in the drain liquid sheet and droplets as well as the effects of noncondensibles and scalability of the results to a steam / water environment.
The final drain model for the LOTIC-III computer code is being formulated and will use the test data where ever possible such that a more realistic contain-ment calculation can be obtained from the LOTIC code. These results are being prepared for a separate WCAP on the drain tests, data, and LOTIC model.
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