ML20134B139
| ML20134B139 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah |
| Issue date: | 11/04/1985 |
| From: | Wallace P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| NUDOCS 8511110298 | |
| Download: ML20134B139 (8) | |
Text
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l j'
TENNESSEE VALLEY AUTHORITY l
Sequoyah Nuclear Plant Post Of fice Box 2000 Soddy Daisy, Tennessee 37379 I-November 4, 1985 U.S. Nuclear Regulatory Commission j
. Document Control Desk l
Washington, DC 20555 I
Gentlemen:
l TENNESSEE VALLEY AUTHORITY - SEQUOYAH NUCLEAR PLANT UNIT 2 - DOCKET NO.
I 50-328 - FACILITY OPERATING LICENSE DPR SPECIAL REPORT 85-08 The enclosed special report provides the results of the unit 2 steam generator tube inservice inspection completed on November 4, 1984. This report is submitted in accordance with Sequoyah unit 2 Technical Specifi-cations 4.4.5.5 and 6.9.2.
Very truly yours, TENNESSEE VALLEY AUTHORITY h--
P. R. Wallace Plant Manager Enclosure cc (Enclosure):
J. Nelson Grace,_ Regional Administrator U.S. Nuclear Regulatory Commission Suite 2900 101 Marietta Street,'NW Atlanta, Georgia 30323 Records Center Institute of Nuclear Power Operations Suite 1500 1100 circle 75 Parkway Atlanta, Georgia 30339 NRC Inspector, NUC PR,-Sequoyah D
g OY
.1983-TVA 5OTH ANNIVERSARY
- An Equal Opportunity Employer -
SEQUOYAll UNIT 2 SECOND REFUELING OUTAGE November 1984 Steam Generator Inspection Results Contents Table 1 Inspection Summary Table 2 Steam Generator 1 Inspection Summary Iable 3 Steam Generator 4 Inspection Summary Table 4 Tubesheet map of row 1 & 2 tubes inspected Table 5 Tubesheet map of tubes tested in defect exam Table 6 Tubesheet map of tubes included in AVB area exam a
RCB:DR 10/31/85
TABLE 1 SEQUOYAH UNIT 2 SECOND REFUELING OUTAGE November 1984 Steam Generator Inspection Summary S/G 1 S/G 4 Total tubes inspected 720 728 Tubes recording pluggable defects Q 40% wall loss) 0 0
Tubes recording degradation I
(< 39% wall loss) 0 0
1 RCB:DR 10/31/85 b
e.
TABLE 2 SEQUOYAH UNIT 2 SECOND REFUELING OUTAGE November 1984 Steam Generator 1 Inspection Summary ASME Code Exams No. Tubes Full length defect exams (CTS-HTS) 308 AVB area exams (C7 TSP-HTS) 94 Total ASME code exams 402 Non-ASME Code Exams No. Tubes Partial length defect exams (H7 TSP-HTS) 130 Special row I & 2 U-bend tests 188 Total Non-ASME code erams 318 Total tests conducted in S/C 1 720 tubes Tubes recording pluggable defects Qt 40% wall loss) 0 Tubes recording degradation (1 39% wall loss) 0 RCB:DR 10/31/85 L_
TABLE 3 SEQUOYAH UNIT 2 SECOND REFUELING OUTAGE November 1984 Steam Generator 4 Inspection Summary ASME Code Exams No. Tubes Full length defect exams (CTS-HTS) 316 AVB area exams (C7 TSP-HTS) 94 Total ASME code exams 410 Non-ASME Code Exams No. Tubes Partial length defect exams (H7 TSP-HTS) 130 Special row 1 & 2 U-bend tests 188 Total non-ASME code exams 318 Total tests conducted in S/G 4 728 tubes Tubes recording pluggable defects
(> 40% wall loss) 0 Tubes recording degradation
(< 39% wall loss) 0 RCB:DR 10/31/85
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