ML20211F889

Forwards Sequoyah Nuclear Plant Unit 1 Cycle 9 Refueling Outage, Re Completed SG Activities,Per TSs 4.4.5.5.b & 4.4.5.5.c

ML20211F889
Person / Time
Site:	Sequoyah
Issue date:	08/25/1999
From:	Salas P TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20211F893	List: ML20211F889 ML20211F903
References
GL-95-05, NUDOCS 9908310097
Download: ML20211F889 (3)

Text

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nn Tennessee Vdey Authority, Post Omce Box 2000, Soddy-Da:sy. Tennessee 37379 August 25, 1999 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of ) Docket No. 50-327 i Tennessee Valley Authority )

SEQUOYAH NUCLEAR PLANT (SQN) - SPECIAL REPORT ON STEAM GENERATOR (SG) ACTIVITIES COMPLETED DURING THE UNIT 1 CYCLE 9 (U1C9)

REFUELING OUTAGE

References:

(1) TVA letter to NRC dated October 13, 1998, I "Sequoyah Nuclear Plant (SON) - Unit 1 Steam Generator (SG) Tube Plugging Report and Notification of Unit 1 SG Tube Inspections -

Unit 1 Cycle 9 Refueling Outage" (2) TVA letter to NRC dated December 29, 1998, "Sequoyah Nuclear Plant (SON) - Unit 1 Cycle 10 .

Steam Generator 90-Day Report for Voltage-Based j Alternate Repair Criteria" l l

In accordance with the requirements of SON TSs 4.4.5.5.b and 4.4.5.5.c, TVA is submitting the enclosed report that includes i the results of SG inservice inspections during the UIC9  !

refueling outage and the written followup information for SGs categorized as C-3. i

)

During SON's scheduled U1C9 refueling outage (September-October  !

1998), extensive inservice inspections were conducted in all j four SGs to address active and potential damage mechanisms 9908310097 990825 310'49 1 I

PDR ADOCK 05000327 P PDR ()./x {

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w 2 0 U.S. Nuclear Regulatory Commission Page 2 .

August'25, 1999 -

identified in the-U1C9. Pre-Outage Damage Assessment. The results of the inspections were classified as follows:

SG 1 - SG 2 SG 3 SG 4 Bobbin C-1 C-2 C-2 C-2 TTS~RPC C-2 C-2 C-2 C-2 Freespan Dents C-1 C-1 C-1 C-1 U-Bend + Point C-2 C-2 C-3 C-3 (TTS - top of tubesheet, RPC - rotating pancake coil)

The SON UIC9 SG TubeiPlugging Report required by TS 4.4.5.5.a, the UIC9 90-day report for voltage based alternate repair criteria required by License Condition 2.C. (8) (b), and TVA's commitment to Generic Letter 95-05 were previously submitted to NRC by References 1 and 2, respectively.

If you have any. questions, please call me at (423) 843-7170 or Jim S th at (423) 843-6672.

ed alas Licensing and Industry Affairs Manager Enclosure cc (Enclosure):

Mr. R .~ W . Hernan, Project Manager U.S. Nuclear ~ Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624 Regional Administrator U.S.' Nuclear Regulatory Commission

' Region II Atlanta Federal Reserve 61 Forsyth St., SW, suite 23T85 Atlanta, Georgia 30303-3415 l

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ENCLOSURE TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT (SON)

UNIT 1 UNIT 1 CYCLE 9 REFUELING OUTAGE 12-MONTH STEAM GENERATOR INSPECTION REPORT

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