ML20128E567

From kanterella
Jump to navigation Jump to search
Forwards Inservice Insp-Exam Summary Prairie Island Nuclear Generating Plant-Unit 1,850114-0222,First 10-Yr Final Rept, Summarizing Results for Pressure Retaining Components & Supports,Reactor Pressure Vessel & Seismic Supports
ML20128E567
Person / Time
Site: Prairie Island Xcel Energy icon.png
Issue date: 05/21/1985
From: Musolf D
NORTHERN STATES POWER CO.
To:
Office of Nuclear Reactor Regulation
Shared Package
ML20128E570 List:
References
NUDOCS 8505290417
Download: ML20128E567 (2)


Text

(

~

Northem States Power Company 414 Nicollet Mall Minneapons. Minnesota 55401 Telephone (612) 330 5500

)

May 21, 1985 Director Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Unit 1 Inservice Inspection Summary Report Attached for your review are four copies of the report, " Inservice Inspection - Examination Summary, Prairie Island Nuclear Generating Plant - Unit 1. January 14, 1985 thru February 22, 1985". This is the last inservice inspection conducted for inspection period three of the first ten year interval.

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.

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

2.

Reactor pressure vessel examinations.

3.

Bolting of seismic supports classified as ASME Class 1.

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

8505290417 850521 A

DR ADOCK 05000282 On.

t PDR

)\\

k

..- +

Dir of NRR MAy 21, 1985 Page 2 Northem States Power Company This report is being submitted in accordance with Prairie Island ASME Code Section XI Inservice Inspection 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 Code..

dL.

David Musolf Manager - Nuclear Support Se ices DMM/EFE/le 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 Tact, Hartford Ins. (1 copy of attachment)

Attachment