ML20199J221
| ML20199J221 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/29/1998 |
| From: | Salas P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20199J227 | List: |
| References | |
| NUDOCS 9802050262 | |
| Download: ML20199J221 (2) | |
Text
,
I Tennessee Vaney Authortty, Post Omce Box 2000, Soddy Daisy, Tennessee 37379-2000 January 29, 1998 U.S.
Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D,C.
20555 Gentlemen:
In the Matter of
)
Docket No. 50-328 Tennessee N.lley Authority
)
SEQUOYAH NUCLEAR PLANT (SQN) - SPECIAL REPORT ON STEAM GENERATOR (SG) ACTIVITIES COMPLETED DURING THE UNIT 2 CYCLE 8 (U2C8) REFUELING OUTAGE In accordance with the requirements of SON Unit 2 TS 4.4.5.5 b and License Condition 2.C. (8) (b), TVA is submitting the enclosed report that includes the following:
(1) results of SG in-service inspection, and (2) results of alternate plugging criteria implementation.
During the scheduled SON U2C8 r. fueling outage, extensive in-service inspections were conducted in all four SGs to address active and potential damage mechanisms identified in the U2C8 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 Dented TSP + Point C-1 C-1 C-1 C-1 j
U-Bend + Point C-3 C-3 C-3 C-3 I
F (TTS - top of tubesheet, RPC - rotating pancake coil,
- )
TSP - tube support plate)
C A total of three tubes were in-situ pressure tested (one in SG f
No. 2 and two in SG No. 4) to support a leakage integrity 1.
evaluation for U-bend primary water stress corrosion cracking l
(PWSCC) and top of tubesheet (TTS) PWSCC.
i
'1 V
- ..', v v v. e V
)
9002050262 990129 PDR ADOCK 05000328 i
p PDR I
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N U.S. Nuclear Regulatory Commission Page 2 January 29, 1998 of the enclosure provides the 90-day APC report required by TVA's commitment via License Condition 2.C. (8) (b) to Generic Letter 95-05, and Attachment 2 contains the safety evaluation associated with a loose part in SG No. 2.
The attachments ere prepared by Westinghouse Electric Corporation.
TVA has reviewed the attachments of the enclosure and concurs with the results.
If you have any questions, please call me at (423) 843-7170 or J.
Smith at (423) 843-6672.
? s d.
wnn J"
da as Licensing and Indostry 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 Administrater U.S. Nuclear Regulatory Commission Region II Atlanta Federal Reserve 61 Forsyth St.,