ML20066C918
| ML20066C918 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 01/07/1991 |
| From: | Parker T NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20066C919 | List: |
| References | |
| NUDOCS 9101110317 | |
| Download: ML20066C918 (7) | |
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- Northem States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401 1027 Telephone (612) 330 5500 January 7, 1991 ASME Code Section XI IWA 6220 Director Office of Nuclear Reactor Regulation Attn: Document Control Desk US Nuclear Regulatory Commission PRAIRIE ISLAND CLEAR GENERATINC PLANT Docket No. 50 2 Licenae No. DPR 42 50 306 DPR-60 Unit 2 Inservice Inspection Summary Report Refueling Outage No. 14 Attached for your information are four copies of the report, " Inservice Inspection Examination Summary, August 29, 1990 to October 2, 1990, Refueling Outage Number 14 Inspection Period 2, Second Interval" and four copies of the ASME Section XI Repair / Replacement Summary report.
The Inservice Inspection Examination Summary report is a summary of the examinations performed during the last refueling outage of the Prairie Island Nuclear Generating Plant Unit No. 2. The. ASME Section XI Repair / Replacement Summary report is a summary of the repairc and replacements to ASME Code Class 1, 2 and 3 components and systems during the last refueling outage of the Prairie Island Nuclear Generating Plant Unit No. 2. The Inservice Inspection Summary report identifies components examined, the examination rathods used, the examination number, and sumraaries 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. The ASME Section XI Repair / Replacement Summary report identifies work request number and summaries the work. The Inservice Inspection Summary Report is being submitted in accordance with the Prairie island ASME Code Section XI Inservice Inspection and Testing Program. The submittals of the attached summary reports are intended to satisfy the inspection reporting requirements contained in IWA-6220 of the [ ASME Boiler and Pressure Vessel Code. l 0 l 9101110317 910107 l PDR ADOCK 05000282 \\( -O PDR
0Yh .3 Northem States Power Company January 7,1991 Page 2 Please contact us if you have any quest 10:u related to the information presented in these reports. r Thomas M Parker Manager Nuclear Support Services c: Regional Administrator-III, NRC (2 copies _of attachments) NRR Project Manager, NRC;(1 copy o_f; attachment) NRC Resident Inspector (w/o attachment) J Silberg.(w/o attachment)- A Justin, Chief Boiler Inspector, : State of MN (1 copy of attr.chment) S Tack,' Hartford Ins. (1 copy of attachment) Attachment l-I f'l s~ .,-r--, ,~< .-~~~._4-
s 5 - 4 - 4 . PRAIRIE ISLAND NUCLEAR GENERATIHo PLANT
- NORTHERN STATES POWER COMPANY 1
= A TITLE: NUMBER: QJ s gg SQD% ASME SECTION XI SP 1795 i 9VENg REPAIR / REPLACEMENT
SUMMARY
[2795] e l,$ REV: 0 'y lM5 1.0 PURPOSE This surveillance activity is performed to review work requests for the purpose of documenting all ASME repairs / replacements. The details of the repairs / replacements are found in the individual work packages, This SP activity will result in a summary of the repairs / replacements and meets the. requirements of N1 ACD 5.4. 6.4.5 which states "a summary report SHALL be submitted to Manager Nuclear ' Support Services subsequent to each outage for all repairs / replacements conducted since the previous outage " 2.0 SCOPE OF REVIEW 2.1 The review and summary description is limited to repairs / replacements governed by ASME Section XI. 2.2 The review and summary description of Igpgrg are: 2.2.1 Those made to the pressure retaining boundary of components and their supports which involve metal removal or welding when no new base material is added. 2.2.2 Heat exchanger tube or tube sheet bore hole plugging. 2.2.3 Welds joining replacements to existing systems. 2.3 The review and summary of the modifications or alterations are: 2.3.1 Spare and renewal components, appurtenances,' subassemblies, or parts of a component or system. 2.3.2 Additions of components such as valves that are'within the scope of ASME Section XI. 2.3.3 System changes such'as rerouting of piping that are within the scope of ASME Section XI. 1
. PRAIRIE ISLAND NUCLEAR OENERATING PLANT HoRTHERN STATES POWER COMPANY, j6{ ' TITLE: NUMDER: '4 ' Q D y' ASME SECTION XI SP 1795 'n W Q E 4r ! ' REPAIR / REPLACEMENT
SUMMARY
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Page 2 of 5 ~" y 3.0 INSTRUCTIONS t 3.1 Following review of the work instructions (WRs)l make entries onto the attached table. 3.2 Following the completion of start of the unit after refueling, submit table to Manager Nuclear Technical Services. l l t ( l i l l
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