ML100550770
| ML100550770 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/19/2010 |
| From: | Krich R Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML100550770 (2) | |
Text
Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402-2801 February 19, 2010 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 10 CFR 50.36(c)(5)
Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 2 Facility Operating License No. DPR-79 NRC Docket No. 50-328
Subject:
Unit 2 Cycle 16 - 90 Day Steam Generator Report for Voltage-Based Alternate Repair Criteria and W* Alternate Repair Criteria In accordance with Sequoyah Nuclear Plant (SQN) Unit 2 Technical Specification (TS) 6.9.1.16.2, SQN is providing the 90 day steam generator (SG) report (Enclosure 1).
The report contains results of voltage-based repair criteria that were applied during the Unit 2 Cycle 16 (U2C16) refueling outage SG inspections (end of Cycle 16 operation). The voltage-based repair criteria are for axial outside diameter stress corrosion cracking at tube support plate intersections. The report contains a condition monitoring assessment that demonstrates that the Generic Letter (GL) 95-05, "Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking," acceptance criteria are satisfied for Unit 2 at the end of Cycle 16 and an operational assessment that demonstrates that the GL 95-05 acceptance criteria is expected to continue to be satisfied through Cycle 17.
In accordance with SQN Unit 2 TS 6.9.1.16.4, SQN is providing the 90 day SG report associated with the application of W* during the U2C16 refueling outage (Enclosure 2).
The cumulative leak rates as calculated for W* Alternate Repair Criteria, the GL 95-05 alternate repair criteria, and all other sources of primary to secondary accident-induced leakage were within the SQN Unit 2 limit (3.7 gallons per minute per SG).
Printed on recycled paper
U.S. Nuclear Regulatory Commission Page 2 February 19, 2010 There are no commitments contained in this letter. If you have any questions concerning this issue, please contact J. W. Proffitt at (423) 843-6651.
Respectfully, R. M. Krric Vice President Nuclear Licensing
Enclosures:
- 1. Steam Generator Report Voltage Based Alternate Repair Criteria Unit 2 Cycle 16 90 Day Report
- 2. Steam Generator W* Alternate Repair Criteria Unit 2 Cycle 16 90 Day Report Enclosures cc (Enclosures):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Sequoyah Nuclear Plant