ML20117L594
| ML20117L594 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/30/1996 |
| From: | Shell R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20117L596 | List: |
| References | |
| NUDOCS 9609170067 | |
| Download: ML20117L594 (2) | |
Text
nn Tent.essee Valley Authority, Post Office Box 2000, Soddy-Daisy, Tennessee 37379-2000 August 30,1996 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of
)
Docket No. 50-328 Tennessee Valley Authority
)
SEQUOYAH NUCLEAR PLANT (SON)- SPECIAL REPORT ON STEAM GENERATOR (SG) ACTIVITIES COMPLETED DURING THE UNIT 2 CYCLE 7 REFUELING OUTAGE
References:
- 1. TVA letter to NRC dated December 12,1995, "Sequoyah Nuclear Plant (SON) - Technical Specification (TS) Change 95-23, "Alternata Plugging Criteria (APC) for Steam Generator (S/G) Tubing - Unit 2"
- 2. TVA letter to NRC dated March 4,1996,"Sequoyah Nuclear Plant (SON) - NRC Request for Additional Information - Technical Specification (TS) Change 95-23," Alternate Plugging Criteria (APC) for Steam Generator (S/G) Tubing - Unit 2" in accordance with the requirements of SON Unit 2 TS 4.4.5.5.b and TVA commitments from the referenced letters, enclosed is a report that includes the following: (1) results of the SG tube inservice inspection, and (2) results of the APC implementation.
An inservice inspection (bobbin coil) was performed on 100 percent of the tubes in all four SGs. Rotating pancake coil was performed at the top of the tubesheet on SGs No.1-4,49,100,56, and 56 percent, respectively. The inservice inspection results (defined in TS 4.4.5.2) were classified as Category C-2 for each of the four Unit 2 SGs.
SON Unit 2 implemented APC for tube support plates during the Unit 2 Cycle 7 refueling outage. Attachment 1 of this report contains a 90-day APC report that was prepared by Westinghouse Electric Corporation. TVA has reviewed the APC report and concurs with the results. Two tubes were pulled, one each from SGs No. 2 and 3 to support application of APC. The results of the destructive examination are documented in the APC report.
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1 U.S. Nuclear Regulatory Commission Page 2 August 30,1996 contains a S/G tube integrity assessment for U-bend primary water stress corrosion crack indications. Westinghouse performed the structuralintegrity analysis of the three largest indications. TVA has reviewed the results of the analysis and concurs with the conclusion that structuralintegrity was maintained during Cycle 7 operation.
Please direct questions concerning this issue to D. V. Goodin at (423) 843-7734.
Sincerely, An R. H. Shell M
Manager SON Site Licensing Enclosure cc: Mr. R. W. Hernan, Project Manager (w/ Enclosure)
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 Administrator U.S. Nuclear Regulatory Commission Region 11 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711 i