ML11266A157
| ML11266A157 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/16/2011 |
| From: | Krich R Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML11266A157 (2) | |
Text
Tennessee Valley Authority 1101 Market Street, LP 3R Chattanooga, Tennessee 37402-2801 R. M. Krich Vice President Nuclear Licensing September 16, 2011 10 CFR 50.36(c)(5)
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission 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 17 Day Steam Generator Report for Voltage-Based Alternate Repair Criteria and W* Alternate Repair Criteria The purpose of this letter is to submit the 90-day steam generator report for the Sequoyah Nuclear Plant (SQN), Unit 2. SQN, Unit 2, entered Mode 4 from the Cycle 17 refueling outage on June 18, 2011. SQN, Unit 2, Technical Specifications (TS) 6.9.1.16.2 and 6.9.1.16.4 require the report to be submitted within 90 days after initial entry into Mode 4 following completion of inspections in accordance with the steam generator program. Therefore, this report is due September 16, 2011.
In accordance with SQN, Unit 2, TS 6.9.1.16.2, the Tennessee Valley Authority (TVA) 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 17 (U2C17) refueling outage SG inspections (end of Cycle 17 operation). The voltage-based alternate repair criteria (ARC) 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 17 and an operational assessment that demonstrates that the GL 95-05 acceptance criteria is expected to continue to be satisfied through Cycle 18.
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U.S. Nuclear Regulatory Commission Page 2 September 16, 2011 In accordance with SQN, Unit 2, TS 6.9.1.16.4, the TVA is providing the 90-day SG report associated with the application of W* during the U2C17 refueling outage (Enclosure 2). The cumulative leak rates as calculated for W*, 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.
There are no regulatory commitments associated with this submittal. Should you have any questions, please contact Dan Green at (423) 751-8423.
Respectfully, R. M. Krich
Enclosures:
- 1. Sequoyah 2C17 Voltage-Based ARC 90-Day Report
- 2. Sequoyah 2C17 W-Star 90-Day Report cc (Enclosures):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Sequoyah Nuclear Plant