ML19257B905
Letter Sequence Other | |
|---|---|
TAC:12657, (Open) | |
Initiation
Administration Questions
Results
Other: 05000282/LER-1984-010-01, :on 841029,steam Generator Tube Leakage Occurred.Probably Caused by Intergranular Attack in Tubesheet Crevice Region.Leaking Tubes Plugged.Several Tubes Will Be Removed for Analysis, 05000306/LER-1980-003, Forwards LER 80-003/01T-0, 05000306/LER-1980-003-01, /01T-0:on 800109,while Conducting Eddy Current Examination of Steam Generator,Row 1 Column Hot Leg Tube Found Defective.Caused by Wearing of Tube Lane Blocking Device Against Tube.Device Modified to Prevent Movement, ML19257B905, ML19323G175, ML19323G177, ML19323G178, ML20083E895, ML20093C128, ML20137Y839 | |
MONTHYEARML19257B9051980-01-10010 January 1980
[Table View]RO 80-03:during Eddy Current Insp of Steam Generator 21, Defect Discovered in One Tube.Caused by Movement of One Tube Lane Blocking Devices Against Outside Surface of Tube, 17 Inches Above Tubesheet.Tube Will Be Plugged Project stage: Other 05000306/LER-1980-003-01, /01T-0:on 800109,while Conducting Eddy Current Examination of Steam Generator,Row 1 Column Hot Leg Tube Found Defective.Caused by Wearing of Tube Lane Blocking Device Against Tube.Device Modified to Prevent Movement1980-01-23023 January 1980 /01T-0:on 800109,while Conducting Eddy Current Examination of Steam Generator,Row 1 Column Hot Leg Tube Found Defective.Caused by Wearing of Tube Lane Blocking Device Against Tube.Device Modified to Prevent Movement Project stage: Other 05000306/LER-1980-003, Forwards LER 80-003/01T-01980-01-23023 January 1980 Forwards LER 80-003/01T-0 Project stage: Other ML19323G1781980-02-29029 February 1980 Steam Generator Chemistry Study Project stage: Other ML19323G1771980-03-10010 March 1980 Exam of Prairie Island 2 Inconel Alloy 600 Steam Generator Tube. Portions Withheld (Ref 10CFR2.790) Project stage: Other ML19323G1751980-04-25025 April 1980 Nondestructive Exam of Prairie Island 2 Steam Generator Tubing Project stage: Other ML19318C3481980-06-27027 June 1980 Submits Application to Withhold Westinghouse Research Rept 80-5D9-PRARI-R1, Examination at Prairie Island 2 Inconel Alloy 600 Steam Generator Tube, (Ref 10CFR2.790).Affidavit Supporting Request Encl Project stage: Request ML20083E8951983-12-19019 December 1983 Repts Steam Generator Tube Plugging Following Recent Outages.Info Will Be Expanded Upon in Inservice Insp Rept & Updated FSAR Will Be Modified Project stage: Other ML20093C1281984-10-0101 October 1984 Provides Status of Steam Generator Tube Plugging Effort. During Recent Inservice Insp of Unit 2,33 Tubes Plugged in Steam Generators 21 & 22.Further Info Will Be Submitted in Inservice Insp Rept Project stage: Other 05000282/LER-1984-010-01, :on 841029,steam Generator Tube Leakage Occurred.Probably Caused by Intergranular Attack in Tubesheet Crevice Region.Leaking Tubes Plugged.Several Tubes Will Be Removed for Analysis1984-11-28028 November 1984
Project stage: Other ML20137Y8391985-10-0202 October 1985 Submits Steam Generator Tube Plugging Info,Per Tech Spec 4.12.E.1.Results of Inservice insp:19 Tubes Plugged, Including 7 Tubes in Steam Generator 21 & 12 Tubes in Steam Generator 22 (1.6% & 3.2%,respectively) Project stage: Other 1980-04-25 |
| ML19257B905 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 01/10/1980 |
| From: | Tierney F NORTHERN STATES POWER CO. |
| To: | |
| References | |
| TAC-12657, NUDOCS 8001210204 | |
| Download: ML19257B905 (1) | |
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Text
NIBD NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT RR #2 Welch,. TIN 35089 January 10, 1980 Mr. James G. Keppler, Director Region II! 0f fice of Inspection and Enforcement US Nuclear Regulatory Conraission 799 Roosevelt Road Glen Ellyn, IL 60137 Attention:
R. F. Warnick Reportable Occurrence No. 80-3 Eddy current inspection of No. 21 Steam Generator at Unit 2 refueling revealed a defect in one tube.
The tube vill be plugged. Visual inspecuan revealed that the defect was caused by movement of one of the tube lane blocking devices against the outside surface of the tube about 17 inches above the tubesheet. Additional tubes in this region are being examined.
The nature of the defect is such that it appears that failure, had it occurred, would have produced minor leakage as opposed to tube rupture.
Sincerely, Y.
..{
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Tie,yney, Jr.
Plant Man'ager Prairic Island Nuclear Plant FPT/jd cc:
L. O. Mayer Director, MIPC (2) c/o Distribution Services Branch, DDC, ADM C. D. Feierabend 1774 '320 foob e,ta 80012102(>f 3
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