ML20063P170

Forwards Addl Info Re 820715 Application for Amend of Licenses DPR-77 & DPR-79 Concerning Steam Generator Water Level low-low Reactor Trip Setpoint

ML20063P170
Person / Time
Site:	Sequoyah
Issue date:	10/07/1982
From:	Mills L TENNESSEE VALLEY AUTHORITY
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8210130150
Download: ML20063P170 (2)

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TENNESSEE VALLEY HORITY l CHATTANOOG A, TENNESSEE 37401 400 Chestnut Street Tower II October 7, 1982 Mr. Harold R. Denton, Director Office of Nuclese Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Denton:

In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 In a letter dated July 15, 1982 to you (TVA-SQN-TS-31), we submitted a proposed amendment to the Sequoyah Nuclear Plant operating licenses DPR-77 and DPR-79. In an October 5,1982 conference call, members of your staff requested additional information on the r.eed for de proposed amendment.

Enclosed are 40 copies of additional information on the need for this change.

If you have any questions concerning this matter, please get in touch with J. E. Wills at FTS 858-2683 Vary truly yours, 1

TEifNESSEE VALLEY AUTHORITY

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L. M. Mills, Manager Nuclear Licensing Sworn d subscribed before me thi - day of 1982 Notary Public M M W u 1_

My Commission Exoires 9 8 _ &

Enclosure (40) cc: U.S. Nuclear Regulatory Commission Region II Attn: Mr. James P. O'Reilly, Regional Administrator 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 CK Ohc y pyg An Equal Opportunity Empfoyer

EECLOSURE ADDITIONAL INFORMATION ON THE NEED FOR AMENDMENT TO THE SEQUOYAH NUCLEAR PLANT STEAM GENERATOR WATER LEVEL LOW-LOW REACTOR TRIP SETPOINT Steam generator level is difficult to control at low power levels and has caused numerous unneeded reactor +ips. Through June 1982, over 39 percent of the reactor trips occurring on toth Sequoyah units resulted from low-low steam generator levels. Decreasing the steam generator low-low level reactor trip setpoint to 18 percent will therefore provide an increase in low power operational flexibility by increasing the margin to reactor trip and reduce the number of reactor trips and resultant unnecessary challenges to the reactor protection system while maintaining an adequate margin of safety.

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