ML20065B013: Difference between revisions

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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      ). f27,ani
>          r. tsy Y. Baynard Assistant to Vice President Nuclear Operations Wheeler (M01)C2-3 cc:    Mr. J. P. O'Reilly Regional Administrator, Region II                                                                9 0l U.S. Nuclear Regulatory Commission                                                            l 101 Marietta Street N.W., Suite 3100 Atlanta, GA 30303 8302220360 830215 p DR ADOCK 05000302 PDR General Office 3201 inirty-fourin street soutn . P O Box 14042. St Petersburg Florida 33733 813-866-5151}}

Revision as of 06:59, 31 March 2020

Notifies That B&W Final Rept Re Supplemental ECCS Calculations Will Not Be Completed Before 830301.Util Will Review & Submit Rept to NRC on or Before 830404
ML20065B013
Person / Time
Site: Crystal River Duke Energy icon.png
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)


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