ML20038A905

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Forwards Revision 1 to Evaluation of Steam Line Break Consequences Associated W/Removal of Rupture Matrix Signals from Emergency Feedwater Valves.
ML20038A905
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 11/17/1981
From: Cross W
FLORIDA POWER CORP.
To: Stolz J
Office of Nuclear Reactor Regulation
Shared Package
ML20038A906 List:
References
3F-1181-23, NUDOCS 8111240423
Download: ML20038A905 (1)


Text

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_Powe._r November 17, 1981 File: 3-0-1-a

  1. 3F-ll 81 -23 Mr. John F. Stolz, Chief Operating Reactors Branch #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 Rupture Matrix Signals

Dear Mr. Stolz:

Enclosed are forty (40) ccpies of Revision 1 to the report " Evaluation of Steam Line Break Consequences Associated With Removal of Rupture Matrix Signals From Emergency Feedwater Valves".

Florida Power Corporation submitted the original report on June 2,1980. The Nuclear Regulatory Commission performed an independent analysis and the re-sults did not agree with this report. Further review of the original analysis revealed an incorrect assumption regarding the mass release rate (exit steam flow rate was assumed rather than the appropriate steam flow rate associated with cold feedwater at 880 gpm). The results of the later analysis were dis-cussed in a telephone conversation and a meeting on July 11, 1980. A Florida Power Corporation letter dated July 16, 1980, documented that the containment design pressure and temperature limits would be reached in 65 minutes and 36 minutes, respectively. The July 16 letter also committed to perform an addi-tional analysis to determine if the reactor would return to critical sooner than 36 minutes. This report " Evaluation of Reactivity Response For a Steam Line Break Event with Unterminated Emergency Feedwater Flow" was submitted September 3, 1981. This revision to the original report completes all docu-mentation to justify the removal of the rupture matrix sign,als.

' O Sincerely, n uha William A. Cross (Q4%f y

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,Q/-gG i i Manager, Nuclear Licensing Q x*,,

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8111240423 811117 ..

Klein(11/16)C3-3 PDR ADOCK 05000302 -

P PDR General Office 3201 Tnirty-fourin street soutn . P O Box 14042. St Petersburg. Florida 33733 813-866 61s1