Letter Sequence Meeting |
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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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Text
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NSP NORTHERN STATES POWER COMPANY MIN N E A POU S. MIN N E SOTA 55401 June 27, 1980 Director of Nuclear Reactor Regulation U S Nuclear Regluatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-306 License No. DPR-60 Examination of Prairie Island 2 Inconel Alloy 600 Steam Generator Tube-Westinghouse Researh Report-30-5D9-PRARI-R1 On March 20, 1980, the NRC issued a " Summary of Meeting Held on February 12, 1980 to discuss the January 1980 Unit 2 Steam Generator Tube Inspection" for the Prairie Island Nuclear Generating Plant.
The NRC Staf f conclusions
- 3 and #4 on page 3 of the Summary contain the recommendations that (a) the presentations by NSP and Westinghouse should be documented and R0-80-03 should be supplemented in about 3 weeks to include the latest results and (b) the additional data from the continuing Westinghouse study should be submitted in about 3 months. Update Licensee Event Reports were submitted to I6E Region III as follows: P-RO-80-03, Rev I on March 6, 1980 and P-RO-80-03, Rev 2 on May 23, 1980. Revision 2 to the Licensee Event Report contains a note that Exhibit B is considered to be proprietary information and will be submitted as a separate document to the Director of Nuclear Reactor Regula-tion as being exempt from disclosure.
Enclosed are 5 copies of the proprietary report " Examination of Prairie Island 2 Inconel Alloy 600 Steam Generator Tube".
Also attached is an
" Application for Withholding Proprietary Information from Public Disclosure" and the Affidavit of Dennis E Gilberts which states the basis for exemption from public disclosure of the enclosed document.
It is requested that this document be withheld from public disclosure in accordance with 10CFR Section 2.790.
,M o.
L 0 Mayer, PE Manager of Nuclear Support Services LOM/jh cc J G Keppler (w/o attachments)
G Charnoff (w/o attachments)
Contains 10CFR 2.790 Proprietary Information b5 h
8 00 7gy g
