ML20074A450
| ML20074A450 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/09/1983 |
| From: | Westafer G FLORIDA POWER CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.30, TASK-TM 3F-0583-07, 3F-583-7, TAC-45815, NUDOCS 8305130067 | |
| Download: ML20074A450 (1) | |
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Power COneonariow May 9,1983 3F-0583-07 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 NUREG-0737, Item II.K.3.30 Revised Small-Break Loss-of-Coolant-Accident Methods to Show Compliance with 10 CFR 50, Appendix K
Dear Sir:
On November 1,1982, Babcock & Wilcox Company submitted topical reports BAW-10092P, Revision 3 (CRAFT 2-FORTRAM Program for Digital Simulation of a Multinode Reactor Plant) and BAW-10154P (B&W Small Break LOCA ECCS Evaluation Model).
Florida Power Corporation endorses these reports as our response to the requirements of the subject NUREG Item.
It is our understanding that work on NUREG-0737, Item II.K.3.3D should not be started until NRC approval is received for these two reports.
Sincerely, A
t G. R. Westafer Manager Nuclear Licensing and Fuel Management RMB:mm cc:
Mr. James P. O'Reilly Regional Administrator, Region II Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 2900 Atlanta, GA 30303 8305130067 830509 A0 PDR ADOCK 05000302 aurth street soutn. P O. Box 14042, st. Petersburg. FWida 33733 e 813-866-5151 T'
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