ML20246D527

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Forwards Steam Generator Tubing Insp Results, Re Cycle 3 Insp.No Addl Tubes Plugged During 890227 Inservice Insp.Eddy Current,Row 2 Inner Radius U-bends in Steam Generators & Propagating Fatigue Cracks Also Examined
ML20246D527
Person / Time
Site: Sequoyah 
Issue date: 07/05/1989
From: Michael Ray
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20246D531 List:
References
NUDOCS 8907110358
Download: ML20246D527 (2)


Text

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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA TENNESSEE 37401 5N 157B Lookout Place JUL 5 1989 i

I U.S. Nuclear Regulatory Commission i

ATIN: Document Control Desk Hashington, D.C.

20555 Gentlemen:

In the Matter of

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Docket No. 50-328 Tennessee Valley Authority SEQUOYAH NUCLEAR PLANT (SQN) UNIT 2 - INSERVICE INSPECTION (ISI) 0F UNIT 2 STEAM GENERATOR TUBES As required by SQN Unit 2 Technical Specification 4.4.5.5.b. enclosed are the results of the steam generator tube ISI completed for Unit 2 on February 27, 1989. No additional tubes were plugged during this inspection.

An ISI was performed on 204 tubes in steam generator 1 and 204 tubes in steam

. generator 4.

The ISI result category was classified by TVA as C-1.

Independent of the ISI, TVA performed a self-imposed eddy current examination of all nonplugged, peripheral tubes in all four steam generators and a 20 percent random sample in steam generators 1 and 4.

As a result of these examinations, antivibration bar wear was discovered in steam generators 1 and 3 (approximately 300 additional tubes were examined in both steam generators 1 and 3 to ensure bounding of the affected tubes).

Twelve tubes in steam generator I and one tube in steam generator 3 were affected.

Additionally, all row 2, inner radius U-bends in all steam generators were examined with an optimized probe design (motorized rotating pancake coll), and 50 rotating pancake coil examinations were performed on steam generator 2 at the top of tubesheet expansion / transitions.

TVA also performed examinations for the evaluation of SQN Unit 2 susceptibility to rapidly propagating fatigue cracks.

No commitments are contained in this submittal.

Please direct questions concerning this issue to K. S. Whitaker at (615) 843-7748.

Very truly yours, TENNESSEE VALLEY AUTHORITY h'

Manager,Nuc1[ar"[ Licensing p

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and Regulatory Affairs Enclosure p

cc:

See page 2 g

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An Equal Opportunity Employer

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U.S. Nuclear Regulatory Commission JUI. 5 8 89 cc'(Enclosure):

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

.TVA Projects Division U.S.; Nuclear Regulatory Commission

.One White Flint, North 11555 Rockville Pike 1

Rockville, Maryland. 20852-Mr. B. A. Wilson, Assistant Director for Inspection Programs TVA Projects Division-U.S. Nuclear Regulatory Commission l

Region II.

101 Marietta Street, NW, Suite 2900 Atlanta,. Georgia 30323

.NRC Resident Inspector.-

.Sequoyah Nuclear Plant.

2600 Igou Ferry Road Soddy. Daisy, Tennessee 37379 1

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