ML20215B930

Application for Amends to Licenses DPR-77 & DPR-79, Consisting of Tech Spec Change 87-35,adding Requirements for Two Flow Control Valves to Table 3.4-1, RCS Pressure Isolation Valve. Fee Paid

ML20215B930
Person / Time
Site:	Sequoyah
Issue date:	06/10/1987
From:	Domer J TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20215B933	List: ML20215B930 ML20215B938
References
TAC-R00153, TAC-R00154, TAC-R153, TAC-R154, NUDOCS 8706170514
Download: ML20215B930 (2)

Text

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s TENNESSEE VALLEY AUTHORITY CHATTANOOGA, TENNESSEE 374o1 SN 157B Lookout Place JUN 101987 l

TVA-SQN-TS-87-35 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328  ;

9 SF.QUOYAH NUCLEAR PLANT - TECHNICAL SPECIFICATION CHANGE 87-35

References:

1. T. M. Novak's letter to H. G. Parris dated April 5, 1985. " Safety Evaluation Report on Sequoyah Inservice Test Program fo'.a Pumps and Valves (IST)"

2. Letter from M. B. Whitaker to B. Youngblood dated May 10, 1986 (TVA-SQN-TS-68)

In reference 2 TVA requested a technical specification change to Table 3.4-1, " Reactor Coolant System Pressure Isolation Valves." TVA review of Generic Letter 87-06 has indicated the need for this table to remain in the technical specifications. To avoid confusion, this change is being withdrawn and resubmitted so that the table will remain in the technical specifications, and two required valves not in the table will be added.

In accordance with 10 CFR 50.90, we are enclosing a requested amendment to licenses DPR-77 and DPR-79 to change the technical specifications of Sequoyah Nuclear Plant units 1 and 2. The proposed change will add requirements for two flow control valves to Table 3.4-1, " Reactor Coolant System Pressure Isolation Valves."

The proposed technical specification change is identified in enclosure 1. The justification for the proposed technical specification change is provided in enclosure 2. A proposed determination of no significant hazards consideration performed pursuant to 10 CFR 50.92 is provided in enclosure 3.

Enclosed is a check for the $150 amendment application fee required by 10 CFR 170.12.

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p A O j h An Equal Opportunity Employer

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U.S. Nuclear Regulatory Commission d 7

.Please direct questions you may have concerning this issue to Rick W. Meadors at (615) 870-6649.

Very truly yours, 1

TENNESSEE VALLEY AUTHORITY

.[. . .;

vJ.'A. Domsr, Assistant Director I Nuclear Safety and Licensing Sworn to d subsc ed before me this k ay of M f/ 1987 Ahll6t dotary Public

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My Commission Expires /

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Enclosures cc (Enclosures):

Mr. Michael H. Mobley, Director (w/o Enclosures)

Division of Radiological Health T.E.R.R.A. Building 150 9th Avenue, N Nashville, TN 37203 Mr. G. G. Zech, Assistant Director for Inspection Programs Office of Special Projects I. U.S. Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900 Region II ,

Atlanta, Georgia 30323 Mr. J. A. Zwolinski, Assistant Director for Projects

- Division of TVA Projects Office of Special Projects U.S. Nuclear Regulatory Commission 4350 East West Highway EWW 322 Bethesda, Maryland 20814 Sequoyah Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379