ML20065B013
| ML20065B013 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/15/1983 |
| From: | Baynard P FLORIDA POWER CORP. |
| To: | Lainas G Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0630, RTR-NUREG-630 3F-0283-15, 3F-283-15, NUDOCS 8302220360 | |
| Download: ML20065B013 (1) | |
Text
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M Power CORPORAT8ON February 15, 1983 3F-0283-15 Director of Nuclear Reactor Regulation Attention: Mr. Gus C. Lainas, Assistant Director Safety Assessment 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-0630, Cladding Swelling and Rupture Models for LOCA Analysis
Dear Sir:
In Florida Power Corporation's (FPC) letters dated August 13, 1982 and October 14, 1982, FPC committed to submit a short-term report concerning rupplemental Emergency Core Cooling Systems calculations.
The issuance of this report has been delayed due to the new LOCA kW/ft limits. These LOCA kW/ft limits are currently being calculated for Crystal River 3.
The final report by Babcock & Wilcox will not be completed before March 1, 1983.
FPC will review and submit the report to the NRC on or before April 4,1983.
Sincerely, 0n
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tsy Y. Baynard Assistant to Vice President Nuclear Operations Wheeler (M01)C2-3 cc:
Mr. J. P. O'Reilly 0l Regional Administrator, Region II 9
U.S. Nuclear Regulatory Commission l
101 Marietta Street N.W., Suite 3100 Atlanta, GA 30303 8302220360 830215 DR ADOCK 05000302 p
PDR General Office 3201 inirty-fourin street soutn. P O Box 14042. St Petersburg Florida 33733 813-866-5151