ML20045A667
| ML20045A667 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/04/1993 |
| From: | Fenech R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9306110176 | |
| Download: ML20045A667 (6) | |
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Tennessee Valley Authority. Post Of< ice Box 2000. Soddy-Daisy. Tennessee 37379-2000 i
Robert A. Fenech Vice President. Sequoyah Nuclear Plant June 4, 1993 U.S. Nuclear Regulatory Commission i
ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of
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Docket No. 50-327 Tennessee Valley Authority
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.SEQUOYAH NUCLEAR. PLANT (SQN) - UNIT 1 STEAM GENERATOR (SG) TUBE PLUGGING As required by SQN Technical Specification 4.4.5.5.a,'this submittalf provides notification of SG tube plugging during the Unit 1 Cycle 6 refueling outage. The in-service inspection of the-SG tubes was l
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completed on May. 27, 19.93.
TVA will submit a special report of the results of this inspectim on or'before May 27, 1994.
[ contains a summary of the tubes plugged in Unit 1 during. this outage. The summary statement of the commitment contained in this letter is provided in Enclosure 2.
Please direct questions concerning this issue to D. V. Goodin at (615) 843-7734.
Sincerely, d-tA Robert-A. Fenech i
Enclosures cc: See page 2 D
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.4' U.S. Nuclear Regulatory Commission Page 2 June 4. 1993.
t Enclosures-cc-(Enclosures):
Mr. D. E. LaBarge, Project Manager U.S. 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 II 101 Marietta Street, NW, Suite 2900 Atlanta,-Georgia 30323-2711 s
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. ENCLOSURE 1
.SEQUOYAH NUCLEAR _ PLANT.
UNIT 1 CYCLE 6 REFUELING OUTAGE-
- s STEAM GENERATOR TUBE PLUGGING
SUMMARY
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4' Steam Gcnarator Tuba Plugging, List Sequoyah Nuclear Plant Unit 1 Cycle 6 EG Eni Cal Location Reason for Plugging 1
12 69 HTS - 0.09 SCI' PWSCC 21 55 HTS - 1.69
-SAI PWSCC 24 37
44 34 C01 + 0.22 48 COLD LEG WASTAGE 2
11 26 HTS - 0.13 SCI' PWSCC 13 24 HTS - 0.10 SCI PWSCC 26 52 HTS - 0.13 SCI PWSCC 3
80 H07 + 6.12 SCI PWSCC 4
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9 75 HTS - 0.03 SCI PWSCC 15 64 HTS - 2.65 SAI PWSCC 16 48 HTS - 0.09 SCI
.PWSCC 20 87 H02 + 0.28 SAI ODSCC 45 36 C01 + 0.0 47 COLD LEG WASTAGE 46 50 C02 + 0.12 47 COLD LEG WASTAGE-21 64 H01 + 0.56
~SAI ODSCC-15 67 H02 - 0.19 SAI ODSCC 4
9 33 HTS - 0.22 SCI' PWSCC 11 26 HTS - 0.17 SCI PWSCC HTS - 0.18 SCI
-PWSCC; 11 27 HTS - 0.11 SCI PWSCC 12 41 HTS - 0.08 SCI PWSCC 13 27 HTS - 0.02 SCI PWSCC' 14 25 H01 + 0.55 SAI-ODSCC 15 28 HTS - 0.08 SCI PWSCC 15 30 HTS - 0.02 SCI' PWSCC-15 40 HTS - 0.11 SCI PWSP1 16 26 HTS - 0.16 SCI PWSLd 22 42 HTS - 0.05 SCI PWSCC 28 59 AV3 + 0.0 42 AVB WEAR 9
30 H02 + 0.54 SAI ODSCC-
.10 36 H01 + 0.76 SAI ODSCC 21 44 H01 + 0.65 SAI ODSCC 36 59 H01 + 0.76 SAI ODSCC 38 35 H01 + 0.65 SAI ODSCC 28 32 HTS - 0.43 SAI PWSCC f
- i. 'IDIALS SG 1L - 4 (27 cumulative).
3 (31 cumulative)
SG 2 SG 3 - 12 (60 cumulative)
SG 4
--18 (63' cumulative)
TOTAL - 37 (181 cumulative)
DEE.INITIONS AV2 Second antivibration bar above hot leg AV3 Third antivibration bar above hot leg AVB Antivibration bar C01 First support plate - cold leg CO2 Second sr., ort plate - cold leg Hol
-First support plate - hot leg H02 Second support plate - hot leg H07 Seventh support plate - hot leg HTS Top of tube sheet - hot leg SAI Single axial indication SCI Single circumferential indication PWSCC Primary water stress corrosion cracking ODSCC Outside diameter stress corrosion cracking
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7 LIST OF COMMIIMENTS TVA.will submit a special report of'the results of-the Unit 1 Cycle 6 steam generator in-service inspection on or before May 27, 1994.
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