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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
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MONTHYEARML19257B9051980-01-10010 January 1980 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 ML19291C1991980-01-15015 January 1980 Supplemental Info to RO 80-3.One Tube Defective on Steam Generator Hot Leg 21.One Tube Defective & Ten Tubes Degraded on Cold Leg 21.Hot Leg 22 to Be Inspected.Four Tubes Defective & 42 Degraded on Cold Leg 22.Cause Unknown Project stage: Supplement 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 ML19318C3441980-06-27027 June 1980 Forwards Westinghouse Rept 80-509-PRAIR-R1, Examination at Prairie Island 2 Inconel Alloy 600 Steam Generator Tube, Resulting from 800212 Meeting Re Jan 1980 Insp.Rept Withheld (Ref 10CFR2.790).Util Encl Project stage: Meeting 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
- 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
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
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Northem States Power Company 414 Nconet Mall Minneapohs. Minnesota 55401 Telephone (612) 330-5500 October 1, 1984 Director Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLAITE Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Steam Generator Tube Plugging In accordance with Technical Specification 4.12.E.1, the following steam
. generator tube plugging information is provided for the information of the NRC Staff.
Following the recent inservice inspection of the Unit 2 steam generators, thirty-three tubes were plugged. Nineteen tubes were plugged in steam generator 21 and fourteen in steam generator 22. The percentage of tubes plugged is 1.4% and 2.8% in steam generators 21 and 22, respectively.
l This information will be expanded upon in the Inservice Inspection Report l
for each unit. Also Tables 4.3-13 and 14 of the Prairie Island Updated Safety Analysis Report will be updated in the next revision.
If you have any questions concerning this information please call.
I d' h w.
David Musolf Manager-Nuclear Support rvices DMM/EFE/ dab c: Regional Administrator-III NRR Project Manager, NRC Resident Inspector, NRC G Charnoff 8410100370 841001 PDR ADOCK 05000282 G
PDR
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