ML20096A604
| ML20096A604 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/04/1992 |
| From: | Joshua Wilson TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9205110147 | |
| Download: ML20096A604 (6) | |
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May 4, 1992 U.S. Nuclear Regulatory Commission ATTN Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of
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Docket No. 50-328 Tennessee Valley Authority
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SEQUOYAH NUCLEAR PIANT (SQN) - UNIT 2 STEAM GENERATOR (SG) TUBE PLUGGING As required.by SQN Technical Specification 4.4.5.5.a. this submittal provides notification of SG tube-plugging during the Unit 2 Cycle 5 refueling outage. The in-servico inspection of the FG tubes was completed on April 19, 1992.
TVA will submit a special report of the results of this inspection on or before April 19, 1993. contains a summary of the tubes plugged in Unit 2 during this outage. The summary statement of the commitment contained in this letter is provided in Enclosure 2.
Please direct questiona concerning this issue to D. V. Goodin at (615) 843-7734.
Sincerely, hk 3 L
- f. L. Wilson I
Enclosures l
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9205110147 920504
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4 U.S. Nuclear Regulatory Commission Page 2 May 4, 1992 cc (Enclosures):
Mr. D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou ferry Road Soddy Daisy, Tennessee 37379
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Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 l
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ENCLOSURE 1 t '
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UNIT-2 CYCLE 5 REFUELING 0UTAGE-SIEAM GENERATOR TUBE' PLUGGING
SUMMARY
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f Steam Generator (SG) Tube Plugging List
-Sequoyah Nuclear Plant Unit 2 Cycle 5 SG
' Row Col Location Reason for Plugging 1
8 54 HTS - 0.57 SAI PWSCC 33 56 AV3 + 0.0 44 AVB wear 33 58 AV2 + 0.0 42 AVB wear AV3 + 0.0 42'
'AVB wear
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34 47 AV3 + 0.0 39 AVB wear 46 46 Col + 0.12 37 Cold leg wastage 2
19 HTS - 0.09 COI PWSCC 8
60 HTS - 2.49 MAI PWSCC 11 3
Col - 0.22 38 Cold leg wastage 12 67 HTS - 0.05 COI PWSCC 13 79 HTS - 0.34 SAI PWSCC 25 -
-45 HTS - 0.50 SAI PWf..C
-26 12 H01 + 0.0 15 5 0.D. indication 29 34 AV3 + 0.0 40
'VB wear 30 51 HTS - 1.12 SAI iWSCC
'31 13 Col + 0.0 37 Cold leg wastage 32 59 AV2 + 0.0 42 AVB wear 34 77 Col - 0.30 39 Cold leg wastage 35 18' CO2 + 0.0 45 Cold leg wastage 43' 33 Col + 0.21 57 Cold leg wastage
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36 Col + 0.0-57 Cold leg wastage 1
3 12 54 HIS - 0.75 SAI PWSCC 11 2 61 HTS - 2.19-
=SAI PWSCC 15 70 HTS - 1.09
'SAI PWSCC 18 25 HTS - 0.91 SAI~
PWSCC l
22 31 HTS - 0.45 SAI PWSCC 122 33 HTS - 2.54-SAI PWSCC 25
-32 HTS - 2.48 SAI PWSCC 34 44' AV3 + 0.0 43 AVB wear
-35 77 C01 - 0.20 66 Cold leg wastage 36 77 Col - 0.20 35 Cold leg wastage-
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CO2 + 0.0 39 Cold leg wastage' 30:
25'
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'C01 + 0.0' 45 Cold leg. wastage 38 22 CO2 4 0.0 45 Cold leg wastage l
-___:_r-_-_.___-_-____-__--___-__=___2-_-_-__---___________-_-
TOTALS SG 1 - 5 (104 cumulative)
SG 2 - 19 (119 cumulative)
SG 3 - 12 (108 cumulative)
SG h
_2 (103 cumulative)
TOTAL - 38 DEFINITIONS AV2 Second anti-vibration bar above hot leg AV3 Third anti-vibration bar above hot leg AVB Anti-vibration bar
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C01 First support plate - cold leg CO2 Second support plate - cold leg H01 First support plate - hot leg s
HTS Top of tube sheet - hot leg SAI Single axial indication COI Circumferential indication MAI Multiple axial indication PWSCC Primary water stress corrosion cracking
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J-LIST OF COMMITMENTS l
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TVA will submit a special report of the results of the Unit 2 Cycle 5 3'
1 steam generator in-service inspection on or before April 19, 1993.
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