ML19350D665
| ML19350D665 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/13/1981 |
| From: | Mayer L NORTHERN STATES POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19350D666 | List: |
| References | |
| NUDOCS 8105180315 | |
| Download: ML19350D665 (1) | |
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Northern States Power Company
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'Q244:@dfotr QS y,nneapoks. Minnesota 55401
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Direef.or of Nuclear Reactor Regulation U " Wuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-306 License No. DPR-60 Unit 2 Steam Generator Eddy Current Test Report Attached for your review are four copies of the report. " Inservice Inspection -
Examination Summary, Eddy Current, Prairie Island Nuclear Geserating Plant Unit 2, February 24 to March 8, 1981." This is a summary of the ed ; current tests conducted during the Spring 1981 refueling outage of Prairie Island Unit 2.
As previously reported in Licensee Event Report 81-02 dated March 13, 1981 a number of degraded or defective tubes were identified. The attached report supplements the information provided in Licensee Event Report 31-02 and provides information requested by the NRC Staff on March 23, 1981 in a telecopy from Robert E Martin, our Project Manager.in the Division of Licensing. This informa-tion is provided in Appendix D of the report.
It should be noted that Appendix D contains a minor error in page numbering in that pages 4 and 5 have been transposed.
Four copies of the original color photographs presented in Appendix C of the report are being mailed directly to Mr Martin in a separate shipment. An additional copy of the original color photographs will be mailed to Mr J G Keppler, Director, Region III Of ff.ce of Inspection and Enforcement.
This report is being submitted in accordance with the Prairie Island ASME Code Section XI In service and Testing Program submitted to the Commission for review on Feburary 1,1978 (revisad through Revision 5 dated September 3,1980). As noted in that prectram, submittal of the attached summary is intended to satisfy the inspection reporting requirements contained in IWA-6220 of Section XI of the ASME Code.
Detailed inservice inspection report s are available at our General Of fice for review by the Region III Of fice of Inspection and Enforcement.
Please contact us if you have any questions concerning this inspeccion or our findings related to the Unit 2 steam generator tube degradation.
A L 0 Mayer, PE Manager of Nuclear Support Services LOM/DMM/jh cc J G Keppler (2 copies of attachment)
H Baron, Chief Boiler Inspector, State of Minnesota (1 copy of attachment)
S Tack, Hartford Insurance (2 copies of attachment)
G Charnoff (w/o attachment)
NRC R sident Inspector (w/o attachment) 810518 Jgg!