ML20012E426

Forwards Inservice Insp-Exam Summary 900103-0219 Refueling Outage 13,Insp Period 2,Second Interval. Exam Plan Focused on Pressure Retaining Components & Supports of RCS & Associated Sys,Fsar Augmented Exams & Eddy Current Exam

ML20012E426
Person / Time
Site:	Prairie Island
Issue date:	03/28/1990
From:	Parker T NORTHERN STATES POWER CO.
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20012E427	List: ML20012E426 ML20012E429
References
NUDOCS 9004050114
Download: ML20012E426 (1)

Text

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414 Hicollet Mall Minneapolis, Minnesota 65401 1927 Telephone (612) 330 6500 March 28,'1990 ASME Code Section XI IWA 6220 Director Of fice of Nuclear Reactor Regulation Attn: Document Control Desk

'US Nuclear Regulatory Commission PRAIRIE ISLAND NUCLEAR CENERATING PLANT Docket No. 50 262 License No. DPR-42 50 306 DPR 60 Unit 1 Inservice Inspection Summary Report Refueline Outage No. 14

-Attached for your information are four copies of the report, " Inservice Inspection Examination Summary, January 3,1990 to February 19, 1990,

' Refueling Outage Number 13, Inspection Period 2, Second Interval." This is a summary of the examinations performed during the last refueling outage of the Prairie Island Nuclear Generating Plant Unit No. 1.

This report identifies components examined, the examination methods used, the examination number, and summaries the results. The examination plan focused on 1) the pressure retaining components and their supports of the reactor coolant system and' associated systems classified as ASME Class 1 and ASME Class 2, 2) FSAR Augmented Examinations, and 3) Eddy current examination of the Steam Generator. All anomalies were either corrected or an engineering evaluation was performed to accept "as in" conditions.

'This report is being submittd in accordance with the Prairie Island ASME Code Section XI Inservice Inspection and Testing Program. As noted in that Program, submittal of the attached summary report is intended to satsify the inspection reporting requirments contained in IWA 6220 of the ASME Boiler and Pressure Vessel Code.

Please contact us if you have any questions related to the information presented in this report.

ThomasMParkr Manager Nuclear Support Services c: Regional Administrator-III, NRC (2 copies of attachment)

NRR Project Manager, NRC (1 copy of attachment)

NRC Resident Inspector (w/o attachment)

C Charnoff (w/o attachment)

A Justin, Chief Boiler Inspector, State of MN (1 copy of attachment)

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

Attachment e

9004050114 900328 i

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