ML20211F889
| 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: |
| References | |
| GL-95-05, NUDOCS 9908310097 | |
| Download: ML20211F889 (3) | |
Text
y o-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 310'49 I
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2 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
ENCLOSURE TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT (SON)
UNIT 1 UNIT 1 CYCLE 9 REFUELING OUTAGE 12-MONTH STEAM GENERATOR INSPECTION REPORT
(