ML18141A159

Forwards VEP-FRD-41, Reactor Sys Transient Analyses Using Retran Computer Code, in Response to Questions Raised at 830921 Meeting Re Methodology Used to Analyze Steam Line Break.Meeting Proposed for Third Wk of Oct 1983

ML18141A159
Person / Time
Site:	Surry
Issue date:	10/06/1983
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Harold Denton, Varga S Office of Nuclear Reactor Regulation
References
521A, NUDOCS 8310140094
Download: ML18141A159 (2)

Text

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e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWA:RT VxcE P:aESIDENT NUCLEAR OPERATIONS October 6, 1983 Mr. Harold R. Denton, Director Serial No. 521A Office of Nuclear Reactor Regulation PSE/WBR:lmf:0743C Attn: Mr. Steven A. Varga, Chief Docket Nos. 50-280 Operating Reactors Branch No. 50-281 Division of Licensing License Nos. DPR-32 U. S. Nuclear Regulatory Commission DPR-37 Washington, D. C. 20555 Gentlemen:

AMENDMENT TO OPERATING LICENSES DPR-32 AND DPR-37 SURRY POWER STATION UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATIONS CHANGE In our letter dated September 13, 1983 (Serial No. 521) Vepco requested an amendment to operating licenses DPR-32 and DPR-37 to allow operation of Surry Unit Nos. 1 and 2 at reduced boron concentrations for the boron injection tank (BIT) and boric acid system.

On September 21, 1983, Vepco met with the NRC to review the submittal.

During the meeting several questions were raised relevant to the methodology used to analyze the steam lihe break assuming the BIT was at zero (0) ppm.

Vepco pointed out that the methodology used for those analyses is discussed in Vepco's topical report VEP-FRD-41 (copy attached) which had been submitted to the NRC in April 1981. We propose a technical meeting with the staff to discuss in detail the analysis methods, codes, assumptions and results, etc.

Vepco would like to hold this meeting in the 3rd week of October 1983. This should give your staff sufficient time to review the referenced topical report and our submittal, and to forward any questions to us for review prior to the meeting.

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

Very truly yours, J!U W. L. Stewart

Enclosure:

(1) Vepco Topical Report VEP-FRD-41 entitled "Reactor System Transient Analyses using the RETRAN Computer Code" dated March 1981.

831014(f094--83100.6 PDR ADOCK 05000280 P PDR

e VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton 2 cc: Mr. James P. 0 Reilly1 Mr. J. Don Neighbors Regional Administrator NRC Project Manager - Surry Region II Operating Reactors Branch No.

Division of Licensing Mr. D. J. Burke Mr. Charles Price NRC Resident Inspector Department of Health Surry Power Station 109 Governor Street Richmond, Virginia