ML17324B353
| ML17324B353 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  (DPR-077) |
| Issue date: | 12/04/2017 |
| From: | Andrew Hon Plant Licensing Branch II |
| To: | Anthony Williams Tennessee Valley Authority |
| Hon A DORL/LPL2-2 301-415-8480 | |
| References | |
| CAC MF9287, EPID L-2017-LRO-0005 | |
| Download: ML17324B353 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION Mr. Anthony L. Williams IV Site Vice President Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000, OPS 4A-SQN Soddy Daisy, TN 37384-2000 WASHINGTON, D.C. 20555-0001 December 4, 2017
SUBJECT:
SEQUOYAH NUCLEAR PLANT, UNIT 1 - REVIEW OF THE STEAM GENERATOR TUBE INSERVICE INSPECTIONS FOR CYCLE 21 REFUELING OUTAGE IN THE FALL OF 2016 (CAC NO. MF9287; EPID L-2017-LR0-0005)
Dear Mr. Williams:
By letters dated February 13, 2017 (Agencywide Documents Access and Management System Accession No. ML17045A145), Tennessee Valley Authority (TVA) submitted information summarizing the results of the fall 2016 steam generator tube inspections pertormed at the Sequoyah Nuclear Plant (Sequoyah), Unit 1. These inspections were pertormed during Refueling Outage 21.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information TVA provided and concludes it contains the information required by the Sequoyah, Unit 1, technical specifications and that no additional followup is required at this time. The NRC staff review of the steam generator portions of the report is enclosed.
If you have any questions, please contact me at (301) 415-8480 or Andrew.Hon@nrc.gov.
Docket No. 50-327
Enclosure:
NRC Review of Report cc: Listserv Sincerely,
(/--
Andrew Hon, Project Manager Licensing Project Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
OFFICE OF NUCLEAR REACTOR REGULATION REVIEW OF STEAM GENERATOR TUBE INSPECTION REPORT FOR CYCLE 21 SEQUOYAH NUCLEAR PLANT, UNIT 1 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 By letter dated February 13, 2017 (Agencywide Documents Access and Management System Accession No. ML17045A145), Tennessee Valley Authority (the licensee), submitted information summarizing the results of the fall 2016 steam generator (SG) tube inspections performed at Sequoyah Nuclear Plant, Unit 1, during Refueling Outage 21.
Sequoyah Unit 1 has four Model 57 AG replacement SGs that were installed in 2003. Each SG contains 4,983 thermally treated Alloy 690 tubes, which have a nominal outside diameter of
- 0. 75 inches and a nominal wall thickness of 0.043 inches. The tubes were hydraulically expanded into the tubesheet and are supported by several Type 409 stainless steel, lattice grid tube supports. The U-bend portion of the tubes is supported by diagonal and vertical straps.
The licensee provided the scope, extent, methods, and results of their SG tube inspections in the document referenced above. In addition, the licensee described corrective actions (i.e., tube plugging) taken in response to the inspection findings.
Based on a review of the information provided, the staff concludes that the licensee provided the information required by the applicable Technical Specifications 5.5.7, "Steam Generator Program," and Section 5.6.6, "Steam Generator Tube Inspection Report." In addition, the staff concludes that there are no technical issues that warrant followup action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units.
Enclosure
ML173248353 OFFICE DORULPL2-2/PM DORULPL2-2/LA NAME AHon BClayton DATE 12/01/17 12/01/17 DMLR/MCCB/BC" SBloom 11/16/17