ML20235Q434

Application for Amends to Licenses DPR-77 & DPR-79, Consisting of Tech Spec Change Requests 88-24 & 88-02, Revising Unit 1 Surveillance Requirement 4.7.1.2.a to Add pump-specific,differential Pressure Test Values for Pump

ML20235Q434
Person / Time
Site:	Sequoyah
Issue date:	02/23/1989
From:	Michael Ray TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20235Q436	List: ML20235Q434 ML20235Q438
References
NUDOCS 8903020626
Download: ML20235Q434 (3)

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, TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 37401 SN 1578 Lookout Place FEB 231989 TVA-SQN-TS-88-24 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C. 20555 Gentlemen:

In the Matter of ) Docket No. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - TECHNICAL SPECIFICATION CHANGE 88-24 (UNIT 1)

AND ADDITIONAL INFORMATION FOR TECHNICAL SPECIFICATION CHANGE 88-02 (UNIT 2)

Reference:

TVA letter to NRC dated May 26, 1988, "Sequoyah Nuclear Plant (SQN) Unit 2 - Technical Specification Change 88-02" In accordance with 10 CFR 50.90, we are enclosing a requested amendment to license DPR-77 to change the technical specifications of SQN unit 1. The proposed change revises the unit I surveillance requirement (SR) 4.7.1.2.a to add pump-specific, differential pressure test values for each auxiliary feedwater (AFH) pump. The associated bases section of the unit 1 technical specifications is revised for clarification.

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.

The equivalent technical specification change for SQN unit 2 was transmitted by the reference. In response to NRC questions, TVA has reevaluated the methodology used in addressing test instrument error associated with the plant data used to generate the AFH pump curves and system resistance curves. These curves were subsequently used to calculate the AFH differential pressure test values. As a result of this reevaluation, additional margin has been added to the AFH test values to offset uncertainties in the flow and pressure test data. The inclusion of this additional margin results in an increase to the test values submitted by the reference for unit 2. Revised unit 2 pages are provided in enclosure 1 of this letter. Values that reflect the new unit 2 test because the new values are more restrictive than those previously submitted by the reference, the conclusions drawn in the unit 2 significant hazards evaluation remain unchanged. A revised bases section for unit 2 is also included to resolve NRC comments.

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8903020626 890223 ON DR ADOCK 0500 7  ; l An Equal Opportunity Employer

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U.S. Nuclear Regulatory Commission FEB 281989

'Please' direct questions concerning_this issue to Russell R. Thompson at (615).843-7470.

Very Truly Yours, TENNESSEE VALLEY AUTHORITY r

,OA I M. J. R y, Acting Manager c}

Technical. Services Licensing Subscribed ard swo n to b e me on; his. 3 ay of ,1989 Notary PublIc MyCommissionExpiresh [

Enclosures cc: See page 3

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U.S. Nuclear Regulatory Commission g g$ $8@

cc (Enclosures):

Ms. S. C. Black, Assistant Director for Projects.

TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. F. R. McCoy, Assistant Director for Inspection Programs  ;

TVA Projects Division U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Michael H. Mobley, Director (w/o enclosures)

Division of Radiological Health T.E.R.R.A. Building i 150 9th Avenue, N  !

Nashville, Tennessee 37203 Sequoyah Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Snddy Daisy, Tennessee 37379 Amarican Nuclear Insurors Attention: Librarian The Exchange, Suite 245 270 Farmington Avenue Farmington, Connecticut 06032

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