ML033510702
| ML033510702 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/12/2003 |
| From: | Salas P Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML033510702 (3) | |
Text
December 12, 2003 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter
)
Docket No. 50-328 Tennessee Valley Authority
)
SEQUOYAH NUCLEAR PLANT (SQN) - UNIT 2 STEAM GENERATOR (SG)
TUBE PLUGGING REPORT - SG TUBE INSPECTIONS DURING UNIT 2 CYCLE 12 REFUELING OUTAGE A summary report of SG tube plugging during the Unit 2 Cycle 12 refueling outage, as required by SQN Technical Specification (TS) 4.4.5.5.a, is being provided in the enclosure. The inservice inspection of the Unit 2 SG tubes was completed on November 30, 2003. In accordance with SQN TS 4.4.5.5.b, TVA will submit a special report of the results from this inspection on or before November 30, 2004.
Pursuant to the reporting requirements of TS 4.4.5.5.c, NRC was informed of the SG tube inspections that fell into Category C-3. The results were provided during a telephone conference call on December 1, 2003. The Category C-3 follow-up report is being provided by Enclosure 2.
Please direct questions concerning this issue to me at (423) 843-7170 or J. D. Smith at (423) 843-6672.
Sincerely, Original signed by Pedro Salas Site Licensing and Industry Affairs Manager Enclosures
E1-1 ENCLOSURE 1 SEQUOYAH NUCLEAR PLANT UNIT 2 CYCLE 12 (U2C12) REFUELING OUTAGE STEAM GENERATOR TUBE PLUGGING REPORT NUMBER OF TUBES PLUGGED FROM THE U2C12 INSPECTIONS BY STEAM GENERATOR Steam Generator No. 1:
4 Steam Generator No. 2:
16 Steam Generator No. 3:
14 Steam Generator No. 4:
26 Total Number of Tubes Plugged from U2C12 Steam Generator Inspections: 60
E2-1 ENCLOSURE 2 SEQUOYAH NUCLEAR PLANT UNIT 2 CYCLE 12 REFUELING OUTAGE FOLLOW-UP REPORT FOR TECHNICAL SPECIFICATION (TS) 4.4.5.5.c STEAM GENERATOR (SG) CATEGORY C-3 In accordance with TS Section 4.4.5.5.c, TVA previously informed NRC, during a teleconference on December 1, 2003, that Unit 2 SG No. 4 had been categorized as C-3.
The Bobbin inspection was categorized as C-3 for SG No. 4 because greater than 10 percent of the tubes inspected were considered degraded because of axial outside diameter stress corrosion cracking (ODSCC) within tube support plates. SQN TS allows axial ODSCC indications inside tube support plates to remain in service if the indication meets the voltage based repair criteria. TVA conservatively considers the tubes containing axial ODSCC within tube support plates to be degraded, in accordance with TS 4.4.5.4.a.3. A full length inspection of 100 percent of the tubes is performed, as part of the initial inspection scope; therefore, no expansion was required.