ML20114B671

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Forwards Inservice Insp - Exam Summary,Prairie Island Nuclear Generating Plant - Unit 2,840905-1002. Results Indicate Integrity of Sys Maintained
ML20114B671
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 01/22/1985
From: Musolf D
NORTHERN STATES POWER CO.
To:
Office of Nuclear Reactor Regulation
Shared Package
ML20114B672 List:
References
NUDOCS 8501290413
Download: ML20114B671 (2)


Text

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Northem States Power Company 414 Nicollet Mall Minneapohs Minnesota 55401 Telephone (612) 330-5500 January 22, 1985 ,

Director Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND HUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Unit 2 Inservice Inspection Summary Report Attached for your review are four copies of the report, " Inservice Inspection - Examination Summary, Prairie Island Nuclear Generating Plant - Unit 2, September 5,1984 thru October 2,1984". This is the third inservice inspection conducted for inspection period three.

This report identifies the components examined, the examination methods used, the examination number and summarizes the examination results of each of the following areas:

1. Plant Systems a) Pressure retaining components and supports of the reactor coolant and associated systems classified as ASME Class 1 and ASME Class 2.

b) Seismic Bolting Program.

2. Eddy Current Examination of Steam Generator Tubing. Nineteen tubes j in No. 21 steam generator and fif teen tubes in No. 22 steam generator were mechanically plugged.

The evaluation of the results from the inservice examinations indicated that the integrity of the systems has been maintained.

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8501290413 850122 PDR ADOCK 05000282 A G PDR p t '

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Dir cf NRR January 22, 1985 N States Power Company Page 2 1

This report is being submitted in accordance with the Prairie Island ASME Code Section XI Inservice and Testing Program. As noted in that program,  !

submittal of the attached summary is intended to satisfy the inspection reporting requirements contained in IWA-6220 of Section XI of the ASME i Code.

Dd Ow, David Musolf Manager - Nuclear Support Services DMH/EFE/ dab c: Regional Administrator-III, NRC (2 copies of attachment)

NRR Project Manager, NRC (1 copy of attachment)

Resident Inspector, NRC (w/o attachment)

G Charnoff (w/o attachment)

H Baron, Chief Boiler Insp. , State of MN (1 copy of attachment)

S Tack, Hartford Ins. (1 copy of attachment)

Attachment i

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