ML20214J123

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Confirms That RCS Flowrate Elbow Tap Normalization & cross- Calibr Will Be Performed During Every Refueling Outage,Per NRC Request for Clarification Re 860627 Application for Rev to Tech Specs
ML20214J123
Person / Time
Site: Summer 
Issue date: 11/21/1986
From: Nauman D
SOUTH CAROLINA ELECTRIC & GAS CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
NUDOCS 8612010165
Download: ML20214J123 (1)


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29218 Nuclear Operations SCE&G A StamaCorgwy November 21,1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Subject:

Virgil C. Summer Nuclea; Station Docket No. 50/395 Operating License No. NPF-12 Reactor Coolant System Flow

Dear Mr. Denton:

By letter on June 27,1986, South Carolina Electric & Gas Company (SCE&G) requested a revision to the Virgil C. Summer Nuclear Station Technical Specifications. Specifically, this request concerned changes to the Reactor Coolant System (RCS) flowrate measurement uncertainty and the allowable power levels for RCS flowrate less than 100% ofThermal Design Flow.

During the technical review of this submittal, your staff requested clarification, and this letter hereby provides confirmation, that RCS flowrate elbow tap normalization j

and cross-calibration will be performed on an every refueling outage basis.

Should you have any further questions, please contact us at your convenience.

Very truly yours, D.A.Nauman

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