ML19350D637
| ML19350D637 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 05/07/1981 |
| From: | Maurin L CAROLINA POWER & LIGHT CO. |
| To: | Tedesco R Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.30, TASK-TM NUDOCS 8105180249 | |
| Download: ML19350D637 (1) | |
Text
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LOUISIANA P O W E R & L I G H T! P o BOX 6000. NEW CALEANS. LOUISIANA 70174 242 ottAnoNee sincer
- (504) 366-2345 sus $5sYIU May 7, 1981 W3P81-1232 3-Bl.06 Q-3-A29 Mr. R. L. Tedesco Assistant Director for Licensing Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555
SUBJECT:
Waterford Steam Electric Station - Unit 3 Docket No. 50-382 Small-Break Loss of Coolant Accident Analysis
Dear Mr. Tedesco:
LP&L is currently participating in the C-E Owners Group activities sddressing Item II.K.3.30 of NUREG 0737, " Revised Small-Break Loss of
'loolant Accident Methods to Show Compliance with 10 CFR Part 50, Appendix K."
In this regard, efforts are underway to evaluate the adequacy of the existing small-break LOCA models used by C-E for the Waterford-3 accident analysis. Comparisons with experimental data, including LOFT TEST L3.6, have been favorable.
The Waterford-3 FSAR will be updated in Amendment No. 18 (Mid-May, 1981) by adding the following sentence to the first paragraph on page 1.9-42a (Amend. No.15, (2/81)):
"The final report to justify the adequacy of the present small-break LOCA model will be submitted to the NRC by January 1, 1982."
Yours very truly,
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Assistant Vice President CI Nuclear Operations
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