Text

Inservice Inspection Summary Report, Interval 3, Period 3, Refueling Outage Dates 09-10-04 Fuel Cycle 22: 12-7-2002 to 11-23-04
	ML050910245
Person / Time
Site:	Prairie Island
Issue date:	02/22/2005
From:	Solymossy J; Nuclear Management Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	FOIA/PA-2010-0209, L-PI-05-013
	Download: ML050910245 (266)
	v • d • e

Ir N

Prairie Island Nuclear Generating Plant Committed to NuearExcelln Operated by Nuclear Management Company, LLC FE 2 2005 L-PI-05-013 10 CFR 50.55a U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET NO. 50-282 LICENSE NO. DPR-42 UNIT 1 INSERVICE INSPECTION

SUMMARY

REPORT, INTERVAL 3, PERIOD 3, REFUELING OUTAGE DATES: 9-10-2004 TO 11-23-2004 FUEL CYCLE 22:12-7-2002 TO 11-23-2004 During the 2004 Prairie Island Unit 1 refueling outage, an inservice inspection (ISI) examination for the third period of the third interval was conducted. Attached for your information is a copy of the ISI examination summary report for this period.

The summary report is being submitted in accordance with the Prairie Island American Society of Mechanical Engineers (ASME) Code Section XI Inservice Inspection Program and is intended to satisfy the inspection reporting requirements contained in IWA-6220 of the ASME Boiler and Pressure Vessel Code.

The report identifies components examined, the examination methods used, the examination number, and summarizes the results. All anomalies were either corrected or an engineering evaluation was performed to accept "as-is" conditions. A description of the corrective work and the corresponding work request numbers are provided in the ASME Section XI Repair/Replacement portion of the report.

This letter contains no new commitments and no revisions to existing commitments.

Please contact Jack Leveille (651-388-1121, Ext. 4142) if you have any questions related to this lett Jos ezh . Solymossy A A fice President, Prqi ie Isla Nuclear Generating Plant Oq7 cc: (see next page) 1717 Wakonade Drive East

Welch, Minnesota 55089-9642 Telephone: 651.388.1121

Page 2 NUCLEAR MANAGEMENT COMPANY, LLC cc: Regional Administrator, USNRC, Region IlIl Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector- Prairie Island Nuclear Generating Plant Chief Boiler Inspector, State of MN Enclosure (1) 1717 Wakonade Drive East . Welch, Minnesota 55089-9642 Telephone: 651.388.1121

ENCLOSURE NUCLEAR MANAGEMENT COMPANY, LLC PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET NO. 50-282 February 2005 INSERVICE INSPECTION

SUMMARY

REPORT INTERVAL 3, PERIOD 3 REFUELING OUTAGE DATES: 9-10-2004 TO 11-23-2004 UNIT 1, FUEL CYCLE 22: 12-7-2002 TO 11-23-2004 (attachment contains a table of contents) 263 pages follow

XCEL ENERGY PRAIRIE ISLAND NUCLEAR GENERATING PLANT 1717 WAKONADE DRIVE EAST WELCH, MINNESOTA 55089 OPERATED BY:

NUCLEAR MANAGEMENT COMPANY, LLC 700 FIRST STREET HUDSON, WISCONSIN 54016 INSERVICE INSPECTION

SUMMARY

REPORT INTERVAL 3, PERIOD 3 REFUELING OUTAGE DATES: 9-10-2004 TO 11-23-2004 UNIT 1, FUEL CYCLE 22: 12-7-2002 TO 11-23-2004 COMMERCIAL SERVICE DATE: DECEMBER 16,1973 Prepared By:'AU/i UA44A AA lPtpPr6eram Engineer, Nuclear Management Company SRvedB Date :././t tl o Reviewed By: Date: <21 1//O Repair/Replacyfnent Program Engineer, Nuclear Management Company Ron Clow, Reviewed By: f e t Date: . c/Z/.

Program En ering Manager, N clear Management Company Scott M Approved By: Date: !Yl1ZO&

Director of Engineering, Nuclear Management Compaq y Terry Silverberg

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1 CYCLE 22

SUMMARY

REPORT Table of Contents Number of Pages Section 1. Discussion 3 Section 2. Form NIS-1, Owner's Report for Inservice Inspections 3 Section 3. ISI Examinations 21 Section 4. IWE Examinations 3 Section 5. Pressure Tests 5 Section 6. Snubber Inservice Testing and Preservice Examinations 2 Section 7. Steam Generator Eddy Current Examination Results 13 Section 8. Repair/ Replacement Activities for Fuel Cycle 22 211

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT I CYCLE 22

SUMMARY

REPORT Section 1. Discussion

1.0 INTRODUCTION

This summary report identifies the components examined, the examination methods used, the examination number and summarizes the examination results performed during the 3rd period of the 3rd interval, unit 1 fuel cycle 22. The 3rd inspection interval is based on the examination requirements of the ASME Boiler and Pressure Vessel Code Section Xl, 1989 Edition with no addenda.

2.0 PERSONNEL Visual and nondestructive examinations were performed by Nuclear Management Company, Lambert Macgill and Thomas (LMT), ABB and Zetec Inc. Framatome Technologies was contracted to perform independent evaluation of the eddy current steam generator data.

Wesdyne was contracted to perform 10-year reactor vessel examinations. The Hartford Steam Boiler Inspection and Insurance Company of Connecticut, provided the Authorized Inspection services. Examination personnel certifications are maintained on file by Nuclear Management Company.

3.0 INSPECTION

SUMMARY

Examination results indicate that plant system's integrity has been maintained.

Section 4 contains the Class MC components examined, the examination number, and summary of the examination results performed during unit 1 cycle 22. The first interval, September 9, 1996 to May 8, 2008 is based on the examination requirements of ASME Section XI 1992 Edition and 1992 Addenda, and 10 CFR 50.55a dated Tuesday, September 30, 1997.

Section 5 contains the pressure test results. All indications of leakage were evaluated and corrective measures performed as required by IWB-3142 and IWA-5250. Five leaking Code Class 2 component were accepted by analytical evaluation as allowed by ASME Section Xl IWB-3142.4. These evaluations are being submitted as required by subparagraph IWB-3144(b).

Snubber inspection results are contained in Section 6. No snubber failures were identified.

During the refueling outage, 11 and 12 steam generators were replaced. All repair/

replacement activities completed during the cycle are documented on Form NIS-2 in Section 8.

4.0 EXAMINATION REPORTS, EQUIPMENT AND MATERIALS The inservice inspection reports in Sections 3 and 4 contain references to procedures, equipment and materials used to complete the specific examinations. Copies of the examination reports, examination procedures, and equipment records are available from Nuclear Management Company.

Section 1. Discussion Page 1

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1 CYCLE 22

SUMMARY

REPORT Sections 3 and 4 contain several abbreviations which are identified below:

CAP = Corrective Action Process CE = Condition Evaluation GEO = Geometry, evaluation of a indication OPR = Operability Recommendation IN = Information Notice IND = Indication requires further evaluation NAD = No Apparent Defects SE = Safety Evaluation WO = Work Order 5.0 IWE INDICATIONS REQUIRING REPORTING Exam report - 2004V103 Two indications were found during the inspection of penetration C6B, 12 Main Steam line penetration. The first indication found was an arc strike or electrical arc. This indication is rejectable per the ASME Section Xl subsection IWE-3510.2, acceptance standard of other signs of distress and the recording criteria in H10.3 Appendix A. The second indication is blistering paint, which also meets the acceptance standard and recording criteria referenced above.

Indication #1 The majority of the electrical arc indication is on the non-code class portion of the penetration with only a small portion of the discoloration from the strike on the weld connecting the penetration sleeve to the containment wall. Due to the location of the arc strike this is not a structurally significant indication. This is an isolated indication not service related and there is no reason to suspect degradation in inaccessible areas. The inspection performed was adequate to evaluate the indication no supplemental inspections are required.

Indication #2 The second indication is blistering paint inside of containment. The coatings degradation is limited to the penetration and the immediate area around the penetrations. The heat from the Main Steam piping causes blistering of the paint and is nonstructural in nature. The inspection performed is sufficient to evaluate the condition no supplemental inspections are required. The coatings failure is nonstructural in nature therefore no corrective actions are required to maintain the integrity of the structure.

The Main Steam and Feedwater penetrations are the only components that would subject the coating to similar temperature conditions and no other areas would be likely to have a similar condition. None of these areas are in inaccessible locations. The Safety Related Coatings Program has previously identified the degraded coating and removal of the blistering paint has been done in the past. The area noted during this inspection is in a location the painters could not reach. The other Main Steam and Feedwater penetrations have been inspected in accordance with the Containment Inspection Program in prior outages with no indications found. Due to the prior inspections of like penetrations and previous paint removal no additional inspections are required.

Summary The arc strike is an isolated incident not requiring additional inspections. Due to the prior inspections of like penetrations not identifying blistering paint no additional inspections are required.

Section 1. Discussion Page 2

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1 CYCLE 22

SUMMARY

REPORT Because neither of the indications are structural in nature no corrective action is required.

Successive inspections of this area will be performed as required IWE-3122.4.

Section 1. Discussion Page 3

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1 CYCLE 22

SUMMARY

REPORT Section 2. NIS-1 (3 pages)

Section 2. NIS-1 Page 1

Page I of 2 NIS-1'-

OWNER'S REPORT FOR INSERVICE INSPECTIONS (As required by the Provisions of the ASMIE Code Rules)

1. Oxner Nuclear Management Company, 700 First Street, Hudson, Wisconsin 54016 (Name and Address of Owner)

2. Plant Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive E., Welch, Minnesota 55089 (Name and Address of Plant)

3. Plant Unit .

4. Oxwner Certificate ofAuthorization (if required) N/A

5. Commercial Service Date 12/16/1973

6. National Board Number for Unit N/A : !

7. Components Inspected Component or Manufacturer or Manufacturer or Installer State or Province National Board No.

Appurtenance Installer Serial No. No.

II Reactor Coolant Pump Westinghouse W515 12 Reactor Coolant Pump Westinghouse W516 .. - -

II RIIR Heat Exchanger Joseph Oats & Sons 1817-IA .. 340 12 RIIR Heat Exchanger Joseph Oats & Sons 1817-lB 341 II RIIR Pump Byron Jackson .

12 RIIR Pump Byron Jackson 11 Safety Injection Pump Bingham 12 Safety Injection Pump Bingham _

II Accumulator Tank Delta Southern 41038-70-1 2554 12 Accumulator Tank Delta Southern 41038-70-2 2555 11 Boric Acid Tank Navco _ _

Reactor Vessel Creuot-Loire 686 NINN 200-51 -

Pressurizer Westinghouse 1111 68-20 11 Steam Geeriator Framatome ANP 0V/P1291 161 12 Steam Generator Framatome ANP GV/P1292 162

8. Examination Dates 1217/2002 to 11/23/2004

9. Inspection Period Identification: (3rd Period) 5/26/1999 to 12/20/2004

10. Inspection Interval Identification: (3rd Interval) 12/17/1993 to 12/20/2004

11. Applicable Edition of Section XT 1989 Addenda none iWe. .u-

Page 2 of 2 NIS-1

12. Date/Revision of Inspection Plan: 5/21/04, Revision 1

13. Abstract of Examinations and Tests. Include a list ofexaininations and tests and a statement concerning status of wtork required fort Inspection Plan.

See Sections 3 through 7

14. Abstract of Results of Examinations and Tests.

See Sections 3 through 7

15. Abstract of Corrective Measures.

See Sections 3 through 6 We certify that a) the statemenits made in this report are correct, b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI, and c) corrective measures taken conform to the rules of the ASME Code,Section XI.

Certificate ofAuthorization No. ( if applicable) N/A Expiration Date Date _ l Signed Bys By__

)%wner CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectores and the State or provinces of and employed by .0 ,cexeoSTEA' 8 lMISPrIO & rsce Co o.f Hnxfbvbi ct-. have inspected the components described in this Owner's Report during the peroid f x O to .!3 t4cY 0,4 , and state that to the best ofmy knowledge and belief, the Owner has performed examinations and tests and taken corrective measures described in this Owzner's Report in accordance with the inspection plan and as required by the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes and any warranty, expressed or implied, concerning the examinations, tests, and corrective measures described in this Ovwner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions Mi l %j1qe pFi 'kRS Atm U Ilspetor's Signature National Board, State, Province, and Endorsements Date

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1 CYCLE 22

SUMMARY

REPORT Section 3. ISI Examinations (21 pages)

Section 3. ISI Examinations Page I

Page 2 of 21 Section 3. ISI Examinations Plant: Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089 Plant Unit: I Owner Certificate of Authorization (If Req.): N/A Owner: Xcel Energy Commercial Service Date: December 16, 1973 Operated by: Nuclear Management Company National Board Number for Unit: N/A Summary No. Comp ID Comp Desc. Cateoory Item Procedure Method/Sheet/Results System ISO Num Exam Date Class 1 300037 W-7 Valve - Pipe B-J 89.21 SWI NDE-PT-1 PT 2004P037 NAD RC ISI 1B 10/8/2004 Comments: Pre-service to WO# 0305017.

300038 W-6 Pipe - Valve B-J B9.21 SWI NDE-PT-1 PT 2004P038 NAD RC ISI-11B 10/8/2004 Comments: Pre-service to WO# 0305017.

300102 H-1A . SnubberA F-A F1.10c SWI NDE-VT-2.0 VT 2004V090 NAD VC ISI-1F 10/5/2004 Comments: Pre-service to WO# 0309296 300126 H-1A .SNUBBERA F-A F1.10c SWI NDE-VT-2.0 VT 2004V058 NAD Si ISI-2 9/28/2004 Comments: Pre-service to WO# 0309307 300147 H-7 RESTRAINT LUGS F-A F1.10a SWI NDE-VT-2.0 VT 2004V047 NAD RH ISI-3A 9/20/2004 300211 H-4 HYDR SNUBBER/CLAMP F-A F1.10c SWI NDE-VT-2.0 VT 2004V116 NAD RC ISI-5A 9130/2004 Comments: Pre-service to WO# 0309286 300212 H-1A SnubberA/Clamp F-A F1.10c SWI NDE-VT.2.0 VT 2004V048 NAD RC ISI-SA 9/2312004 Comments: Pre-service to WO# 0309287 300275 W-14 SAFE END TO PRESS B-F 85.40 SWI NDE-PT-1 PT 2004P001 NAD RC ISI-5C 9/15/2004 SWI NDE-UT-2 UT 2004U055 NAD RC I1_51C 10/20/2004 300276 H-5 RUPTURE RESTRAINT F-A F1.10b SWI NDE-VT-2.0 VT 2004V032 NAD *RC ISI51)5 9/19/2004 300282 H-4 SIESMIC RESTRAINT F-A F1.10b SWI NDE-VT-2.0 VT 2004V021 NAD RC ISI-5D) 9/16/2004 300318 H-1 . RUPTURE RESTRAINT F-A F1.10b SWI NDE-VT-2.0 VT 2004V022 NAD RC ISI-7 9/16/2004 300502 W-1 VALVE - PIPE B-J B9.21 SWI NDE-PT-1 PT 2004P039 NAD VC IS1-l1D 10/14/2004 Comments: Pre-service to WO# 0408070.

300518 W-5 SAFE END - NOZZLE B-F B5.10 SWI NDE-PT-1 PT 2004P061 NAD RC ISI-12C 11/2/2004 UT-Vendor UT 2004VE028 NAD RC ISI-12C 10/26/2004 300523 W-5 Safe end - nozzle B-F B5.70 SWI NDE-UT-2 UT 2004U061 GEO RC ISI-12A 10/25/2004 SWI NDE-PT-1 PT 2004P050 NAD RC ISI-12A 10/23/2004 Comments:: Pre-service to W,'# 0310442 3 . .0 300528 W-1 Nozzle - Safe End B-F 85.70 SWI NDE-UT-2 UT 2004U062 GEO RC ISI-12B 10/25/2004 SWI NDE-PT-1 PT 2004P048 NAD RC ISI-12B 10/23/2004 Comments: Pre-service to WO# 0310442 I

Page 3 of 21 Section 3. ISI Examinations Plant: Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089 Plant Unit: 1 Owner Certificate of Authorization (If Req.): N/A Owner: Xcel Energy Commercial Service Date: December 16, 1973 Operated by: Nuclear Management Company National Board Number for Unit: N/A Summary No. Comp ID Comp Desc. Cateaorv Item Procedure Method/Sheet/Results System ISO Num Exaim Date 300538 W-5 SAFE END - NOZZLE B-F 85.10 SWI NDE-PT-1 PT 2004P062 NAD RC ISI-13C 11/3/2004 UT-Vendor UT 2004VE029 NAD RC ISI-13C 10/26/2004 300543 W-5 Safe End - Nozzle B-F B5.70 SWI NDE-PT-1 PT 2004P045 NAD RC ISI-13A 10/22/2004 SWI NDE-UT-2 UT 2004U059 GEO RC ISI-13A 10/23/2004 Comments: Pre-service to WO# 0310445 300548 W-1 Nozzle - Safe End B-F B5.70 SWI NDE-PT-1 PT 2004P042 NAD RC ISI-13B 10/22/2004 SWI NDE-UT-2 UT 2004U060 GEO RC ISI-13B 10/23/2004 Comments: Pre-service to WO# 0310445.

300612 B-1 VALVE BOLTING B-G-2 B7.70 SWI NOE-VT-1.0 VT 2004V099 NAD RH ISI-19A 10/4/2004 SWI NDE-VT-1.0 VT 2004VW65 IND RH ISI-19A 10/3/2004 Comments: 2004V065 rejected 6 studs. Studs replaced per WO# 0407227. Repair Replacement Plan# 1-22-087.

300779 H-7 HYDR SNUBBER/CLAMP F-A F1.10c SWI NDE-VT-2.0 VT 2004V097 NAD RC ISI-26 10/5/2004 Comments: Pre-service to WO# 0309302 300782 H-4 HYDR SNUBBER/CLAMP F-A F1.10c SWI NDE-VT-2.0 VT 2004V108 NAD RC ISI-26 10/6/2004 Comments: Pre-service to WO# 0309303 300783 H-8 HYDR SNUBBER/CLAMP F-A F1.10c SWI NDE-VT-2.0 VT 2004V109 NAD RC ISI-26 10/6/2004 Comments: Pre-service exam to WO# 0309304 300788 H-2 HYDR SNUBBER F-A F1.10c SWI NDE-VT-2.0 VT 2004V059 NAD RC ISI-26 10/2/2004 Comments: Pre-service to WO# 0309306 300894 B-i FLANGE BOLTING B-G-2 B7.50 SWI NDE-VT-1.0 VT 2004V126 NAD RC ISI-29B 10/9/2004 300895 B-1 FLANGE BOLTING B-G-2 B7.50 SWI NDE-VT-1.0 VT 2004V121 NAD RC ISI-29A 10/9/2004 300898 NOZZLE - SAFE END B-F B5.40 SWI NDE-UT-2 UT 2004U056 NAD RC ISI-29A 10/20/2004 SWI NDE-PT-1 PT 2004P002 IND RC ISI-29A 9/15/2004 Comments: UT examination coverage limited to 66.23% due to configuration. PT examination coverage 100%. PT Indication found to be Code acceptable.

300918 B-2 VALVE BOLTING B-G-2 B7.70 SWI NDE-VT-1.0 VT 2004V124 NAD Si ISI-30B 10/8/2004 300923 W-7 SAFE END - NOZZLE B-F B5.10 UT-Vendor UT 2004VE030 NAD RC ISI-30B 10/26/2004 SWI NDE-PT-1 PT 2004P060 NAD RC ISI-308 11/3/2004 300945 H-1 HYDR SNUBBER F-A F1.10c SWI NDE-VT-2.0 VT 2004V046 NAD RC ISI-31 9/22/2004 Comments: Pre-service exam to WO# 0310022

Page 4 of 21 Section 3. ISI Examinations Plant: Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089 Plant Unit: I Owner Certificate of Authorization (If Req.): N/A Owner Xcel Energy Commercial Service Date: December 16, 1973 Operated by: Nuclear Management Company National Board Number for Unit: N/A Summary No. Comp ID Comp Desc. Categorv Item Procedure Method/Sheet/Results System ISO Num Exam Date 300993 H-1 SPRING HANGER F-A F1.10c SWI NDE-VT-2.0 VT 2004V029 NAD SI ISI-33B 9/20/2004 301031 R.V.NUTS NUTS (1-16) B-G-1 B6.10 SWI NDE-VT-1.0 VT 2004V043 NAD RV ISI-37 9/22/2004 301034 Marmon Clamp A MARMON CLAMP @ 120 B-G-2 B7.10 SWI NDE-VT-1.0 VT 2004V228 NAD RV ISI-38 11/19/2004 Comments: Pre-service to WO# 0408797 301078 W-2 Tubesheet to Head B-B B2.60 SWI NDE-UT-16A UT 2004U033 NAD VC ISI-44 9/24/2004 Comments: UT examination coverage limited to 32.29%. Relief Request# 5, Revision 2.

301089 LIGAMENTS1-4E LIGAMENTS B-G-1 B6.40 UT-Vendor UT 2004VE031 NAD RV ISI-48 10/26/2004 Comments: Partial exam (ligaments 26 - 48) 301090 W-1 FLANGE / VESSEL B-A B1.30 UT-Vendor UT 2004VE033 NAD RV ISI-48 10/2612004 301091 W-2 UP SHELL / LOW SHELL B-A B1.11 UT-Vendor UT 2004VE034 NAD RV ISI-48 10/26/2004 301092 W-3 LOW SHELL (INTER.) B-A 61.11 UT-Vendor UT 2004VE035 IND RV ISI48 10/2612004 Comments: 2004VE035 Identified indications. Indications were allowable by code.

I.SI 301093 W-4 LOW SHELL / LOW HEAD B-A 61.11 UT-Vendor UT 2004VE036 NAD RV ISI48 10126/2004 301094 W-5 RING / DISC B-A 61.21 UT-Vendor UT 2004VE037 NAD RV ISI-48 1012612004 301096 Lug @ 90 Support Lug © 90 B-K 610.10 UT-Vendor UT 2004VE032 NAD RV ISI-50 10/2612004 301098 N-6 Inlet Nozzle to Vessel Weld Loop A B-D B3.90 UT-Vendor UT 2004VE038 NAD RV ISI-50 10/26/2004 301099 N-6 IR Inlet Nozzle (Inner Radius) to Vessel Weld Loop B-D B3.100 VT-Vendor VT 2004VE055 NAD RV ISI-50 10/26/2004 Comments: Code Case N-648-1 301100 N-7 Outlet Nozzle to Vessel Weld Loop A B-D B3.90 UT-Vendor UT 2004VE040 IND RV ISI-50 10/26/2004 Comments: UT examination coverage limited to 76.38%

301101 N-7 IR Outlet Nozzle (Inner Radius) to Vessel Weld Lo B-D B3.100 VT-Vendor VT 2004VE056 NAD RV ISI-50 10/26/2004 Comments: Code Case N-648-1 301102 -N-8: SI Nozzle to Vessel Weld Loop A B-D B3.90 'UT-Vendor UT 2004VE054 IND RV ISI-50

10/26/2004 UT-Vendor UT 2004VE042 IND RV ISI-50 10/26/2004 Comments: UT examination coverage limited to 59.26%. All indications identified are Code acceptable.

301103 N-8 IR SI Nozzle (Inner Radius) to Vessel Weld Loop A B-D B3.100 VT-Vendor VT 2004VE057 NAD RV ISI-50 10/26/2004 Comments: Code Case N-648-1 302501 V-1 VALVE INT SURFACES B-M-2 B12.50 SWI NDE-VT-3.0 VT 2004V060 NAD RH ISI-19A 10/3/2004 302901 B-1 FLANGE BOLT B-G-2 B7.50 [SI-VT-1.0 VT 2004V018 NAD VC ISI-27D 2/26/2003

Page 5 of 21 Section 3. ISI Examinations Plant: Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089 Plant Unit: 1 Owner Certificate of Authorization (If Req.): N/A Owner: Xcel Energy Commercial Service Date: December 16, 1973 Operated by: Nuclear Management Company National Board Number for Unit: N/A Summary No. Comp ID Comp Desc. Category Item Procedure Method/Sheet/Results System ISO Num Exam Date Comments: Pre-service examination from WO# 0300670. Previous indication identified on Report # 2002V497. CAP027781.

302952 V-2 VALVE INT SURFACES B-M-2 B12.50 SWI NDE-VT-3.0 VT 2004V122 NAD Si ISI-30B 10/8/2004 SWI NDE-VT-3.0 VT 2004V127 NAD Si ISI-30B 10/10/2004 Comments: 2004V122 IS1 exam. 2004V127 examined new internals prior to replacement per WO# 0407938.

302977 N-9 Inlet Nozzle to Vessel Weld Loop B B-D B3.90 UT-Vendor UT 2004VE044 NAD RV ISI-50 10/26/2004 302978 N-9 IR Inlet Nozzle (Inner Radius) to Vessel Weld Loop B-D B3.100 VT-Vendor VT 2004VE058 NAD RV ISI-50 10/26/2004 Comments: Code Case N-648-1 302979 N-10 Outlet Nozzle to Vessel Weld Loop B B-D B3.90 UT-Vendor UT 2004VE046 IND RV ISI-50 10/26/2004 Comments: UT examination coverage limited to 78.47%. All indications identified are Code Acceptable.

302980 N-10 IR Outlet Nozzle (Inner Radius) to Vessel Weld Loc B-D B3.100 VT-Vendor VT 2004VE059 NAD RV ISI-50 10/26/2004 Comments: Code Case N-648-1 302981 N-11 Si Nozzle to Vessel Weld Loop B B-D B3.90 UT-Vendor UT 2004VE048 IND RV ISI-50 10/26/2004 Comments: UT examination coverage limited to 59.26%. All indications identified are Code acceptable.

302982 N-11 IR Si Nozzle (Inner Radius) to Vessel Weld Loop 6B-D B3.100 VT-Vendor VT 2004VE060 NAD RV ISI-50 10/26/2004 Comments: Code Case N-648-1 303032 N-31R NOZZLE - HX B-D B3.160 SWI NDE-VT-1.0 VT 2004VO50 NAD VC ISI-44 9/24/2004 Comments: Relief Request No. 5, Revision 2 303033 N-41R HX - NOZZLE B-D B3.160 SWI NDE-VT-1.0 VT 2004VO51 NAD VC ISI-44 9/24/2004 Comments: Relief Request No. 5, Revision 2 305417 VESSEL VT INTL SURFACES B-N-1 B13.10 VT-Vendor VT 2004VE050 NAD RV ISI-48 10/26/2004 305701 V-1 Valve Int Surfaces (Installed RC-10-1 as of 11/1 B-M-2 B12.50 SWI NDE-VT-3.0 VT 2004V224 NAD RC ISI-29A 11/9/2004 Comments: Pre-service to WO# 0310234 305702 B-2 Valve Bolting (Installed RC-10-1 as of 11115/04) B-G-2 B7.70 SWI NDE-VT-1.0 VT 2004V222 NAD RC ISI-29A 11/9/2004 Comments: Pre-service to WO# 0310234 305703 V-1 Valve Int Surfaces (Installed RC-10-2 as of 11/1 B-M-2 B12.50 SWI NDE-VT-3.0 VT 2004V225 NAD RC ISI-29B 10/11/2004 Comments: Pre-service to WO# 0310234 305704 B-2 Valve Bolting (Installed RC-10-2 as of 11/15/04) B-G-2 B7.70 SWI NDE-VT-1.0 VT 2004V223 NAD RC ISI-29B 11/9/2004

Page 6 of 21 Section 3. ISI Examinations Plant: Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089 Plant Unit: 1 Owner Certificate of Authorization (If Req.): N/A Owner. Xcel Energy Commercial Service Date: December 16,1973 Operated by: Nuclear Management Company National Board Number for Unit: N/A Summary No. Comp ID Comp Desc. Category Item Procedure Method/Sheet/Results System ISO Num Exam Date Comments: Pre-service to WO# 0310234 311034 Marmon Clamp EMARMON CLAMP @ 240 B-G-2 B7.10 SWI NDE-VT -1.0 VT 2004V229 NAD RV ISI-38 1111 912004 Comments: Pre-service to WO# 0408797 315300 RV-2 Int Attachment -Beltline B-N-2 813.50 VT-Vendor VT 2004VE051 NAD RV ISI-48 10/26/2004 315400 RV-i Int. Attachment Beyond Beltline B-N-2 813.60 VT-Vendor VT 2004VE052 IND RV ISI-48 1012612004 Comments: Indications evaluated to be acceptable per CE006062 315500 RV-4 Core Support Structure B-N-3 B13.70 VT-Vendor VT 2004VE053 IND RV ISI-48 10/26/2004 Comments: Indications evaluated to be acceptable per CE006062 320102 H-1B SnubberB F-A F1.10c SWI NDE-VT -2.0 VT 2004WV89 NAD VC ISI-IF 10/5/2004 Comments: Pre-service to WO# 0309297 320145 H-3/1A Ini. Attach[DOUBLE SPRING] B-K 610.20 SWI NDE-PT -1 PT 2004P035 NAD RC ISI-3A 10/5/2004 320147 H-7/lA Int. Attach[Restraint Lugs) B-K 610.20 SWI NDE-PT r-1 PT 2004P036 NAD RH ISI-3A 10/512004 320215 H-l11A Int. Attach[RCP #11 Column 1-A] B-K B10.30 SWI NDE-PT -1 PT 2004P033 IND RC ISI-14 9/29/2004 Comments: 2004P033 identified 5 indications. All 5 indications were found to be Code acceptable.

320233 H-6B 'B' SNUBBER/CLAMP F-A F1.10c SWI NDE-VT -2.0 VT 2004V049 NAD RC 1SI-5B 9/24/2004 Comments: Pre-service to WO# 0309285 320285 H-9B 'B" Snubber/Clamp F-A F1.10c SWI NDE-VT -2.0 VT 2004V045 NAD RC ISI-5D 9/21/2004 Comments: Pre-service exam to WO#0309288 320484 H-311A Int. Attach[ANCHOR SUPPORT] B-K B10.20 SWI NDE-PT -1 PT 2004P034 IND VC ISI-1ID 1015/2004 SWI NDE-PT -1 PT 2004P047 NAD VC IS11ID 10/26/2004 Comments: 2004P034 identified an indication. Initiated CAP 039246. Repaired per WO# 0408112 and reexamined, with no indications per Report No. 2004P047. Since the flaw was removed, no successive examinations are required to be performed. Expanded scope was performed on ISI Summa ry No. 320962 on Report No. 2004P041.

320595 H-511A Int. AttachIRUPTURE RESTRAINT LUG) B-K B10.20 SWI NDE-PT -1 PT 2004P040 NAD Si ISI-i8 10/16/2004 Comments: Expanded scope from 320993 320962 H-311A Int. Attach[RUPTURE RESTRAINT] B-K 810.20 SWI NDE-PT -1 PT 2004P041 NAD VC ISI-32A 10/16/2004 Comments: Expanded scope from 320484 320993 H-I/A Int. Attach[SPRING HANGER] B-K B10.20 SWI NDE-PT-1 PT 2004P046 NAD Si ISI-33B 10/23/2004 SWI NDE-PT-1 PT 2004P027 IND Si ISI-33B 1015/2004

Page 7 of 21 Section 3. ISI Examinations Plant: Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089 Plant Unit: 1 Owner Certificate of Authorization (If Req.): N/A Owner: Xcel Energy

Commercial Service Date: December 16, 1973 Operated by: Nuclear Management Company National Board Number for Unit: N/A Summary No. ComD ID Comp Desc. Cateaorv Item Procedure Method/Sheet/Results SVstem ISO Num Exam Date

I - '__ _-- ____

Comments: 2004P027 identified an indication. Initiated CAP 039244. Repaired per WO# 0408114 and reexamined with no indications per Report No. 2004P046. Since the flaw was removed, no successive examinations are required to be performed. Expanded scope was performed on ISI Summary No. 320595 on Report No. 2004P040.

321031 R.V. NUTS NUTS (17-32) B-G-1 B6.10 SWI NDE-VT-1.0 VT 2004V044 NAD RV ISI-37 9/24/2004 321034 Marmon Clamp CMARMON CLAMP @ 360 B-G-2 B7.10 SWI NDE-VT-1.0 VT 2004V230 NAD RV ISI-38 11/19/2004 Comments: Pre-service to WO# 0408797 321738 H-1/IA Int. Attach[BASE] B-K B10.10 SWI NDE-MT-1 MT 2004M008 NAD RC IS1-4 1 9/29/2004 350200 H-13 SG # 11 Column I F-A F1.40 SWI NDE-VT-2.0 VT 2004V159 NAD SG lSl-43C 10/26/2004 Comments: Pre-service to WO# 0310433 350201 H-14 SG # 11 Column 2 F-A F1.40 SWI NDE-VT-2.0 VT 2004V172 NAD SG ISI-43C 10/26/2004 Comments: Pre-service to WO# 0310433 350202 H-15 SG # 11 Column 3 F-A F1.40 SWI NDE-VT-2.0 VT 2004V173 NAD SG ISI.43C 10/26/2004 Comments: Pre-service to WO# 0310433 350203 H-16 SG # 11 Column 4 F-A F1.40 SWI NDE-VT-2.0 VT 2004V167 NAD SG ISI-43C 10/26/2004 Comments: Pre-service to WO# 0310433 350204 H-13 SG # 12 Column I F-A F1.40 SWI NDE-VT-2.0 VT 2004V161 NAD SG IS1-43D 10/26/2004 Comments: Pre-service to WO# 0310435 350205 H-14 SG # 12 Column 2 F-A F1.40 SWI NDE-VT-2.0 VT 2004V174 NAD SG ISI-43D 10/26/2004 Comments: Pre-service to WO# 0310435 350206 H-15 SG # 12 Column 3 F-A F1.40 SWI NDE.VT-2.0 VT 2004V160 NAD SG ISI-43D 10/26/2004 Comments: Pre-service to WO# 0310435 350207 H-16 SG # 12 Column 4 F-A F1.40 SWI NDE-VT-2.0 VT 2004V175 NAD SG lS1-43D 10/26/2004 Comments: Pre-service to WO# 0310435 350216 H-2 RCP # 11 Column 2-B F-A F1.40 SWI NDE-VT-2.0 VT 2004V232 NAD RC ISI-14 11/22/2004 Comments: Pre-service to WO# 0408894 350219 H-2 RCP # 12 Column 2-B F-A F1.40 SWI NDE-VT-2.0 VT 2004V231 NAD RC ISI-34 11/22/2003 Comments: Pre-service to WO# 0408894 370027 SP 1403 Reactor Vessel Closure Head Bare Metal Visual BACC GL88-05 SP 1403 VT 2004V227 NAD RV 9/16/2004

Page 8 of 21 Section 3. ISI Examinations Plant: Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089 Plant Unit: I Owner Certificate of Authorization (If Req.): N/A Owner: Xcel Energy Commercial Service Date: December 16,1973 Operated by: Nuclear Management Company National Board Number for Unit: N/A Summary No. Comp ID Comp Desc. Category Item Procedure Method/Sheet/Results System ISO Num Exam Date Comments: Augmented Exam 390100 W-4A . . Elbow - Safe End B-J 89.11 SWI NDE-UT-1 1 UT 2004U068 NAD RC ISI-12A 10/25/2004 SWI NDE-PT-1 PT 2004P051 NAD RC ISI-12A 10123/2004 SWI NDE-UT-16A UT 2004U067 GEO RC ISI-12A 1012512004 Comments: Pre-service to WO# 0310442 390101 W-1A Safe End - Pipe B-J 89.11 SWI NDE-PT-1. PT 2004P049 NAD RC ISI-12B 10/2312004 SWI NDE-UT. 1I UT 2004U069 NAD RC 1SI-12B 10/25/2004 SWI NDE-UT-16A UT 2004U070 GEO RC ISI-12B 1012512004 Comments: Pre-service to WO# 0310442 390102 W4A Elbow-Safe End B-J 89.11 SWI NDE-PT-1 PT 2004P044 NAD RC ISI-13A 10/22/2004

.. SWI NDE-UT-16A UT 2004U065 GEO RC ISI-13A 10/23/2004 SWI NDE-UT-11 UT 2004U066 NAD RC ISI-13A 10123/2004 Comments: Pre-service exam to WO# 0310445. UT examination coverage limited to 87.75% due to OD profile of cast stainless steel elbow. PT examination coverage 100%.

390103 W-1A Safe End - Elbow B-J 89.11 SWI NDE-UT-1 1 UT 2004U064 NAD RC ISI-13B 10/23/2004 SWI NDE-UT-16A UT 2004U063 GEO RC ISI-13B 1012312004 SWI NDE-PT-1 PT 2004P043 NAD RC ISI-13B 10/22/2004 Comments: Pre-service to WO# 0310445 390121 W-1 Head - Cylindrical Ring B-B 82.40 UT-Vendor UT 2004VE062 NAD SG ISI-43E 1/8/2004 390122 W-2 Cylindrical Ring - Tubesheet 8-B B2.40 UT-Vendor UT 2004VE063 GEO SG ISI-43E 1/8/2004 390141 W-1 Head - Cylindrical Ring B-B B2.40 UT-Vendor UT 2004VE064 GEO SG ISI-43F 1/5/2004 390142 W-2 Cylindrical Ring - Tubesheet B-B 82.40 UT-Vendor UT 2004VE065 GEO SG ISI-43F 1/5/2004 390160. N-51R - Inlet Nozzle Inner Radius B-D B3.140 SWI NDE-VT-1.0 VT 2004V012 NAD SG ISI-43E 9/312004 Comments: Code Case N-619. Pre-service to WO# 0310231

.390161 N-61R Outlet Nozzle Inner Radius B-D B3.140 SWI NDE-VT-1.0 VT 2004V020 NAD SG ISI-43E 9/3/2004 Conmments: Code Case N-619. Pre-service to WO# 0310231 390162 N-51R Inlet Nozzle Inner Radius B-D B3.140 SWI NDE-VT-1.0 VT 2004V013 NAD SG ISI-43F 9/3/2004 Comments: Code Case N-619. Pre-service to WO# 0310231 390163 - N-61R Outlet Nozzle Inner Radius B-D B3.140 SWI NDE-VT-1.0 VT 2004V014 NAD SG ISI-43F 9/3/2004 Comments: Code Case N-619. Pre-service to WO# 0310231

Page 9 of 21 Section 3. ISI Examinations Plant: Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089 Plant Unit: 1 Owner Certificate of Authorization (If Req.): N/A Owner: Xcel Energy Commercial Service Date: December 16, 1973 Operated by: Nuclear Management Company National Board Number for Unit: N/A Summary No. Comp ID Comp Desc. Category Item Procedure Method/Sheet/Results System ISO Num Exam Date

390164 B-1 Inlet Manway Bolts B-G-2 B7.30 SWI NDE-VT-1.0 VT 2004V039 NAD SG ISI-43E 9/22/2004 SWI NDE-VT-1.0 VT 2004V183 NAD SG IS43E 11/5/2004 Comments: Both pre-service to WO# 0310231. 2004V039 completed after a stud was damaged (CAP039576) 390165 B-2 Outlet Manway Bolts B-G-2 B7.30 SWI NDE-VT-1.0 VT 2004V040 NAD SG ISI-43E 9/22/2004 Comments: Pre-service to WO# 0310231 390166 B-1 Inlet Manway Bolts B-G-2 67.30 SWI NDE-VT-1.0 VT 2004V042 NAD SG ISI-43F 9/22/2004 Comments: Pre-service to WO# 0310231 390167 B-2 Outlet Manway Bolts B-G-2 B7.30 SWI NOE-VT-1.0 VT 2004V041 NAD SG ISI-43F 9122/2004 Comments: Pre-service to WO# 0310231 Class 2 301107 W-1LS2D NOZZLE - RED. ELBOW C-F-2 C5.50 SWI NDE-UT-1A UT 2004U074 GEO MS ISI-51A 11/1/2004 MT-Vendor MT 2004VE022 NAD MS ISI-51A 10/31/2004 Comments: Pre-service to WO# 0310229 301108 W-11LSUD PIPE-PIPE C-F-2 C5.50 SWI NDE-UT-1A UT 2004U007 NAD MS ISI-51A 9/21/2004 SWI NDE-MT-1 MT 2004M004 NAD MS ISI- 51A 9/21/2004 301112 W-3LS2DU PIPE - ELBOW C-F-2 C5.50 SWI NDE-UT-1A UT 2004U075 NAD MS ISI-51A 11/1/2004 MT-Vendor MT 2004VE023 NAD MS ISI-51A 10/31/2004 Comments: Pre-service to WO# 0310229 301132 H-2 SEISMIC RESTRAINT F-A F1.20a SWI NDE-VT-2.0 VT 2004V216 NAD MS ISI-51A 11/11/2004 Comments: Pre-service to WO# 0310229 301134 H4 SEISMIC RESTRAINT F-A F1.20a SWI NDE-VT-2.0 VT 2004V194 NAD MS ISI-51A 11/8/2004 Comments: Pre-service to WO# 0310229 301149 W-2LS2U2D PIPE - 58 ELBOW C-F-2 C5.50 SWI NDE-UT-1A UT 2004U022 NAD MS ISI-51B 9/27/2004 SWI NDE-MT-1 MT 2004M006 NAD MS ISI-51 B 9/27/2004 301150 W-3LSD2U 58' ELBOW - PIPE C-F-2 C5.50 SWI NDE-UT-1A UT 2004U021 NAD MS ISI-51 B 9/27/2004 SWI NDE-MT-1 MT 2004M005 NAD MS ISI-51B 9/27/2004 301151 W4 PIPE - ELBOW C-F-2 C5.51 SWI NDE-UT-1A UT 2004U018 NAD MS ISI-51 C 9/23/2004 SWI NOE-MT-1 MT 2004M001 NAD MS ISI-51C 9/16/2004 301215 W-6 PIPE - ELBOW C-F-2 C5.51 SWI NDE-UT-1A UT 2004U009 GEO FW ISI-52 9/22/2004

Page 10 of 21 Section 3. ISI Examinations Plant: Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089 Plant Unit: I Owner Certificate of Authorization (If Req.): N/A Owner: Xcel Energy Commercial Service Date: December 16,1973 Operated by: Nuclear Management Company National Board Number for Unit: N/A Summary No. ComD ID Comp Desc. Category Item Procedure =

Method/Sheet/Results =

System ISO Num

Exam Date SWI NDE-MT-1 MT 2004M003 NAD FW ISI-52 9/21/2004 301216 W-7 -ELBOW - PIPE C-F-2 C5.51 SWI NDE-MT-1 MT 2004M002 NAD FW ISI-52 9/21/2004 SWI NDE-UT-1A UT 2004U008 GEO FW ISI-52 912212004 301238 W-21 ELBOW TO PIPE C-F-2 C5.51 MT-Vendor MT 2004VE018 NAD FW ISI-52 11/2/2004 SWI NDE-UT-1A UT 2004U078 NAD FW ISI-52 10/6/2004 Comments: Pre-service to WO# 0310228 301240 W-26 Sweepolet - Pipe C-F-2 C5.81 MT-Vendor MT 2004VE021 NAD FW ISI-52 10/8/2004 Comments: Pre-service to WO# 0310228 301242 W-22 PIPE TO NOZZLE C-F-2 C5.51 SWI NDE-UT-1A UT 2004U084 NAD FW ISI-52 11/6/2004 MT-Vendor MT 2004VE017 NAD FW ISI-52 11/5/2004 Com'ments: Pre-service'to WO# 0310228 301245 W-25 Pipe'- Sweepoiet C-F-2 C5.51 SWI NDE-UT-1A UT 2004U053 NAD AF ISI-52 10/16/2004 MT-Vendor MT 2004VE020 NAD AF ISI-52 10/12/2004 Comments: Pre-service to WO# 0310228 301247 W-24 Flued Head - Pipe C-F-2 C5.51 MT-Vendor MT 2004VE019 NAD AF ISI-52 10/23/2004 SWI NDE-UT-1A UT 2004U057 GEO AF ISI-52 10/23/2004 Comments: Pre-service to WO# 0310228 301253 H-9 ANCHOR ELBOW F-A F1.20a SWI NDE-VT-2.0 VT 2004V187 NAD FW ISI-52 11/7/2004 Comments: Pre-service to WO# 0310228 301254 H-8 ANCHOR ELBOW F-A F1.20a SWI NDE-VT-2.0 VT 2004V189 NAD FW ISI-52 11/7/2004 Comments: Pre-service to WO# 0310228 301572 WA1LS2D NOZZLE - RED. ELBOW C-F-2 C5.50 SWI NDE-UT-1A UT 2004U073 GEO MS ISI-68A 11/1/2004

- . . MT-Vendor MT 2004VE025 NAD MS ISI-68A 10/30/2004 Comments: Pre-service to WO# 0310229 301577 W-3LS2UD PIPE - ELBOW C-F-2 C5.50 MT-Vendor MT 2004VE027 NAD MS ISI-68A 10/29/2004 SWI NDE-UT-1A UT 2004U071 NAD MS ISI.68A 10/31/2004 Comments: Pre-service to WO# 0310229 301595 H-1 SEISMIC RESTRAINT F-A F1.20a' SWI NDE-VT.2.0 VT 2004V214 NAD Ms ISI-68A 11/11/2004

Page 11 of 21 Section 3. ISI Examinations Plant: Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089 Plant Unit: 1 Owner Certificate of Authorization (If Req.): N/A Owner: Xcel Energy Commercial Service Date: December 16, 1973 Operated by: Nuclear Management Company National Board Number for Unit: N/A Summary No. Comp ID Comp Desc. Category Item Procedure Method/SheetUResults System ISO Num Exam Date Comments: Pre-service to WO# 0310229 301596 H-3 SEISMIC RESTRAINT F-A F1.20a SWI NDE-VT-2.0 VT 2004V193 NAD MS ISI-68A 111812004 Comments: Pre-service to WO# 0310229 301640 H-6A Snubber A F-A F1.20c SWI NDE-VT-2.0 VT 2004V057 IND MS ISI-68B 9/28/2004 Comments: Indication not in scope of Section Xi Program. Evaluation per snubber program (CAP039042) 301642 H-2A Snubber A F-A F1.20c SWI NDE-VT-2.0 VT 2004V128 NAD MS ISI-68C 10/13/2004 Comments: Pre-service to WO# 0407307 301667 W-26 Flued Head to Pipe C-F-2 C5.51 SWI NDE-UT-1A UT 2004U058 GEO AF ISI-69 10/23/2004 MT-Vendor MT 2004VE006 NAD AF ISI-69 10(23/2004 Comments: Pre-service to WO# 0310228 301690 W-21 ELBOW TO PIPE C-F-2 C5.51 MT-Vendor MT 2004VE002 NAD FW ISI-69 11/2/2004 SWI NDE-UT-1A UT 2004U081 NAD FW ISI-69 11/5/2004 Comments: Pre-service to WO# 0310228 301692 W-23 Pipe - Sweepolet C-F-2 C5.51 SWI NDE-UT-1A UT 2004U054 NAD AF ISI-69 10/1612004 MT-Vendor MT 2004VE004 NAD AF ISI-69 10/3/2004 Comments: Pre-service to WO# 0310228 301694 W-24 PIPE TO NOZZLE C-F-2 C5.51 SWI NDE-UT-1A UT 2004U080 NAD FW ISI-69 11/5/2004 MT-Vendor MT 2004VE005 NAD FW ISI-69 11/5/2004 Comments: Pre-service to WO# 0310228 301697 W-22 Sweepolet to Pipe C-F-2 C5.81 MT-Vendor MT 2004VE003 NAD FW ISI-69 10/14/2004 Comments: Pre-service to WO# 0310228 301704 H-8 ANCHOR ELBOW F-A F1.20a SWI NDE-VT-2.0 VT 2004V185 NAD FW ISI-69 11/6/2004 Comments: Pre-service to WO# 0310228 301705 H-7 ANCHOR ELBOW F-A F1.20a SWI NDE-VT-2.0 VT 2004V186 NAD FW ISI-69 11/6/2004 Comments: Pre-service to WO# 0310228 301706 H-5 ANCHOR ELBOW F-A F1.20a SWI NDE-VT-2.0 VT 2004V188 NAD FW ISI-69 11/6/2004 Comments: Pre-service to WO# 0310228

Page 12 of 21 Section 3. ISI Examinations Plant: Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089 Plant Unit: 1 Owner Certificate of Authorization (If Req.): N/A Owner: Xcel Energy Commercial Service Date: December 16,1973 Operated by: Nuclear Management Company National Board Number for Unit: N/A Summary No. Como ID Comp Desc. Cateaorv Item Procedure Method/Sheet/Results System ISO Num Exam Date

-- - I __ _ _ I I 302967 H-2A . SnubberA F-A F1.20c SWI NDE-VT-2.0 VT 2004V006 NAD MS ISI-51C 5/25/2004 Comments: Pre-service to WO# 0200346 302983 H-1 SNUBBER 1 F-A FIAO0 SWI NDE-VT-2.0 VT 2004V203 NAD SG IS1-43C 11/5/2004 Comments: Pre-service to WO# 0310431 302984 H-2 SNUBBER 2 F-A F1.40 SWI NDE-VT-2.0 VT 2004V178 NAD SG ISI-43C 11/5/2004 Comments: Pre-service to WO# 0310431 302986 H-3 SNUBBER 3 F-A F1.40 SWI NDE-VT-2.0 VT 2004V176 NAD SG IS1-43C 11/5/2004 Comments: Pre-service to WO# 0310431 302987 H-4 SNUBBER 4. F-A F1.40 SWI NDE-VT-2.0 VT 2004V177 NAD SG ISI-43C 11/5/2004 Comments: Pre-service to WO# 0310431 302992 H-9 TOP SUPPORT GIRDER F-A F1.40 SWI NDE-VT-2.0 VT 2004V204 NAD SG IS1-43C 11/10/2004 Comments: Pre-service to WO# 0310431 303004 H-i SNUBBER 1 F-A F1.40 SWI NDE-VT-2.0 VT 2004V179 NAD SG IS1-43D 11/4/2004 Comments: Pre-service to WO# 0310432 303005 H-2 SNUBBER 2 F-A F1.40 SWI NDE-VT-2.0 VT 2004V180 NAD SG IS1-43D 11/4/2004 Comments: Pre-service to WO# 0310432 303006 H-3 SNUBBER 3 F-A F1.40 SWI NDE-VT-2.0 VT 2004V181 NAD SG S15143D 11/4/2004 Comments: Pre-service to WO# 0310432 303007 H-4 SNUBBER 4 F-A F1.40 SWI NDE-VT-2.0 VT 2004V182 NAD SG IS1-43D 11/4/2004 Comments: Pre-service to WO# 0310432 303012 H-9 TOP SUPPORT GIRDER F-A FI.40 SWI NDE-VT-2.0 VT 2004V205 NAD SG S15143D 11/10/2004 Comments: Pre-service to WO# 0310432 303079 W-18LSU PIPE - WELDOLET C-F-2 C5.80 SWI NDE-MT-1 MT 2004M009 NAD MS 1S1-51C 10/18/2004 305055 H-1 ROD/CLAMP F-A F1.20a SWI NDE-VT-2.0 VT 2004V141 NAD Si ISI-lO0B 10/15/2004 Comments: Expanded scope from Summary No. 305071.

305057 H-3 BOX HANGER F-A F1.20b SWI NDE-VT-2.0 VT 2004V133 NAD Si ISI-1008 10/15/2004

Page 13 of 21 Section 3. ISI Examinations Plant: Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089 Plant Unit: 1 Owner Certificate of Authorization (If Req.): N/A Owner: Xcel Energy Commercial Service Date: December 16, 1973 Operated by: Nuclear Management Company National Board Number for Unit: N/A Summary No. Comp ID Comp Desc. Category Item Procedure Method/Sheet/Results System ISO Num Exam Date Comments: Expanded scope from Summary No. 305071.

305069 H-4 Seismic Anchor F-A F1.20b SWI NDE-VT-2.0 VT 2004V140 NAD Si ISI-100A 10/15/2004 Comments: Expanded scope from Summary No. 305071.

305070 H-5 Double Rigid Hanger F-A F1.20a SWI NDE-VT-2.0 VT 2004V149 IND Si ISI-100A 10/15/2004 Comments: 2004V149 identified additional parts that did not appear on drawing. CAP039671 documents the discrepancy.

305071 H-6 BOX HANGER F-A F1.20b SWI NDE-VT-2.0 VT 2004V184 NAD Si ISI-100A 11/6/2004 SWI NDE-VT-2.0 VT 2004V118 IND Si ISI-100A 10/8/2004 Comments: 2004V118 identified a clearance issue. Initiated CAP 039248. Repaired per WO# 0408118 and reexamined with no indications per Report No. 2004V184. Expanded scope was performed on ISI Summary Nos. 305107, 305069, 305057, 305055, 305070, 325070, 305106 and 305069 305105 H4 SEISMIC ANCH./SADDLE F-A F1.20b SWI NDE-VT-2.0 VT 2004V119 NAD Si ISI-99A 10/8/2004 305106 H-5 PIPE CLAMP F-A F1.20b SWI NDE-VT-2.0 VT 2004V148 IND Si ISI-99A 10/15/2004 Comments: Expanded scope from Summary No. 305071.

305107 H-6 SEISMIC/CLAMP/LUGS F-A F1.20b SWI NDE-VT-2.0 VT 2004V139 NAD Si ISI-99A 10/15/2004 Comments: Expanded scope from Summary No. 305071.

305193 W-1 PEN 28A -REDUCER C-F-1 C5.21 SWI NDE-PT-1 PT 2004P030 NAD Si ISI-97A 9/21/2004 SWI NDE-UT-16A UT 2004U023 NAD Si ISI-97A 9/22/2004 305194 W-2 REDUCER - PIPE C-F-1 C5.21 SWI NDE-PT-1 PT 2004P016 NAD Si ISI-97A 9/17/2004 SWI NDE-UT-16A UT 2004U024 NAD Si 1SI-97A 9/19/2004 305195 W-3 PIPE - PIPE C-F-1 C5.21 SWI NDE-PT-1 PT 2004P015 NAD Si ISI-97A 9/17/2004 SWI NDE-UT-16A UT 2004U025 NAD SI ISI-97A 9/19/2004 305196 W-4 PIPE - 45 ELBOW C-F-1 C5.21 SWI NDE-PT-1 PT 2004P014 NAD SI ISI-97A 9/17/2004 SWI NDE-UT-16A UT 2004U026 NAD SI ISI-97A 9/19/2004 305197 W-5 45 ELBOW - PIPE C-F-1 C5.21 SWI NDE-PT-1 PT 2004P013 NAD SI ISI-97A 9/17/2004 SWI NDE-UT-16A UT 2004U027 NAD Si ISI-97A 9/19/2004 305198 W-6 PIPE - 45 ELBOW C-F-1 C5.21 SWI NDE-PT-1 PT 2004P019 NAD Si ISl-97A 9/18/2004 SWI NDE-UT-16A UT 2004U028 NAD Si ISI-97A 9/19/2004 305199 W-7 45 ELBOW - PIPE C-F-1 C5.21 SWI NDE-UT-16A UT 2004U032 NAD SI ISI-97A 9/19/2004 SWI NDE-PT-1 PT 2004P018 NAD SI ISI-97A 9/18/2004 305200 W-8 PIPE - RED TEE C-F-1 C5.21 SWI NDE-UT-16A UT 2004U019 NAD Si ISI-97A 9/22/2004 SWI NDE-PT-1 PT 2004P032 NAD Si ISI-97A 9/23/2004 305201 W-9 RED TEE - REDUCER C-F-1 C5.21 SWI NDE-UT-16A UT 2004U020 NAD Si ISI-97A 9/22/2004 SWI NDE-PT-1 PT 2004P009 NAD Si ISI-97A 9/17/2004 305202 RED TEE - PIPE C-F-1 C5.21 SWI NDE-UT-16A UT 2004U011 NAD Si ISI-97B 9/18/2004

Page 14 of 21 Section 3. ISI Examinations Plant: Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089 Plant Unit: 1 Owner Certificate of Authorization (If Req.): N/A Owner Xcel Energy Commercial Service Date: December 16, 1973 Operated by: Nuclear Management Company National Board Number for Unit: NIA Summary No. Como ID Comp Desc. Cateaorv Item Procedure Method/Sheet/Results System ISO Num Exam Date

- __ - - . - SWI NDE-PT-1 PT 2004P012 NAD Si ISI-97B 9/17/2004 Comments: Ut examination coverage limited to 50% due to configuration. PT examination coverage 100%.

305203 W-2 PIPE - ELBOW C-F-1 C5.21 SWI NDE-UT-16A UT 2004U012 NAD Si ISI-97B 9118/2004 SWI NDE-PT-1 PT 2004P010 NAD Si ISI-97B 9/17/2004 305204 W-3 ELBOW - PIPE C-F-1 C5.21 SWI NDE-UT-16A UT 2004U016 NAD Si ISI-97B 911812004 SWI NDE-PT-1 PT 2004P011 NAD Si ISI-97B 9/17/2004 305205 W-4 PIPE - ELBOW C-F-1 C5.21 SWI NDE-UT-16A UT 2004U015 NAD Si ISI-97B 9/18/2004 SWI NDE-PT-1 PT 2004P008 NAD Si ISI-97B 9/17/2004 305206 W-5 ELBOW - PIPE C-F-1 C5.21 SWI NDE-UT-16A UT 2004U017 NAD Si ISI-97B 9/18/2004 SWI NDE-PT-1 PT 2004P007 NAD Sl ISI-97B 9/17/2004 305207 W-6 PIPE - ELBOW C-F-1 C5.21 SWI NDE-PT-1 PT 2004P017 NAD Si ISI-97B 9/17/2004 SWI NDE-UT-16A UT 2004U013 NAD Si ISl-97B 9/1812004 305254 H-3 Double Spring Hanger F-A F1.20c SWI NDE-VT-2.0 VT 2004V030 NAD Si ISI-98A 9/20/2004 305260 W-3 PIPE - ELBOW C-F-1 C5.21 SWI NDE-PT-1 PT 2004P024 NAD Si ISI-98A 9/17/2004 SWI NDE-UT-16A UT 2004U029 NAD Si ISI-98A 9/19/2004 305261 W-4 ELBOW - 45 ELBOW C-F-1 C5.21 SWI NDE-PT-1 PT 2004P025 NAD Si ISI-98A 9/1712004 SWI NDE-UT-16A UT 2004U030 NAD Si ISI-98A 9/19/2004 305262 W-5 45 ELBOW- PIPE C-F-1 C5.21 SWI NDE-PT-1 PT 2004P026 NAD Si ISI-98A 9/17/2004 SWI NDE-UT-16A UT 2004U031 NAD SI ISI-98A 9/19/2004 305332 W-19 PIPE - ORIFICE C-F-1 C5.30 SWI NDE-PT-1 PT 2004P005 NAD Si ISI-98C 9/16/2004 305333 W-20 ORIFICE - PIPE C-F-1 C5.30 SWI NDE-PT-1 PT 2004P006 NAD Si ISI-98C 9/16/2004 305340 W-27 VALVE - PIPE C-F-1 C5.30 SWI NDE-PT-1 PT 2004P004 NAD Si ISI-98C 9/16/2004 305344 W-31 PIPE - VALVE C-F-1 C5.30 SWI NDE-PT-1 PT 2004P003 NAD Si ISl-98C 9/16/2004 305637 H-8 Spring F-A F1.20c SWI NDE-VT-2.0 VT 2004V191 NAD AF ISI-52A 11/7/2004 Comments: Pre-service to WO# 0310228 305640 H- 1 Pipe Restraint F-A F1.20b SWI NDE-VT-2.0 VT 2004V190 NAD AF ISI-52A 11/6/2004 Comments: Pre-service to WO# 0310228 305651 H-10 . Double Spring F-A F1.20c SWI NDE-VT-2.0 VT 2004V217 NAD AF ISI-69A 11/11/2004 Comments: Pre-service to WO# 0310228 V 2 1 305652 H-1I Pipe Restraint F-A F1.20b SWI NDE-VT-2.0 VT 2004V215 NAD AF ISI-69A 11/11/2004 Comments: Pre-service to WO# 0408542 I . : ; I ,.

315635 W-11 PIPE TO FLUED HEAD C-F-2 C5.61 SWI NDE-UT-1A UT 2004U077 GEO AF ISI-52A 11/6/2004 SWI NDE-MT-1 MT 2004M010 NAD AF ISI-52A 11/5/2004

Page 15 of 21 Section 3. ISI Examinations Plant: Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089 Plant Unit: 1 Owner Certificate of Authorization (If Req.): N/A Owner: Xcel Energy Commercial Service Date: December 16, 1973 Operated by: Nuclear Management Company National Board Number for Unit: N/A Summary No. Comp ID Comp Desc. Cateqory Item Procedure Method/Sheet/Results System ISO Num Exam Date Comments: Pre-service to WO# 0310228 315667 W-13A Pipe to Pipe C-F-2 C5.61 SWI NDE-UT-1A UT 2004U083 GEO AF ISI-69A 11/5/2004 SWI NDE-MT-1 MT 2004M011 NAD AF ISI-69A 11/5/2004 Comments: Pre-service to WO# 0310477 315668 W-15A PIPE TO FLUED HEAD C-F-2 C5.61 SWI NDE-MT-1 MT 2004M012 NAD AF ISI-69A 11/5/2004 SWI NDE-UT-IA UT 2004U082 NAD AF ISI-69A 11/5/2004 Comments: Pre-service to WO# 0310228 315839 H-1 Single Sliding Base F-A F1.20a SWI NDE-VT-2.0 VT 2004V129 NAD Cs ISI-91D 10/14/2004 315855 W-6 Pipe - Elbow C-F-1 CX.XX SWI NDE-PT-1 PT 2004P056 NAD CS ISI-91C 10/15/2004 SWI NDE-UT-16A UT 2004U046 NAD CS ISI-91C 10/16/2004 Comments: Pre-service to WO# 0303946 315856 W-7 elbow - tee C-F-1 CX.XX SWI NDE-PT-1 PT 2004P057 NAD Cs ISI-91C 10/15/2004 SWI NDE-UT-16A UT 2004U050 NAD CS ISI-91C 10/16/2004 Comments: Pre-service to WO# 0303946 315857 W-8 PIPE TO VALVE(CS-16) C-F-1 CXXX SWI NDE-UT-16A UT 2004U051 NAD CS ISI-91C 10/16/2004 SWI NDE-PT-1 PT 2004P059 NAD CS ISI-91C 10/16/2004 Comments: Pre-service to WO# 0303946 315862 W-13 elbow - tee C-F-1 CXXX SWI NDE-UT-16A UT 2004U048 NAD CS ISI-91C 10/16/2004 SWI NDE-PT-1 PT 2004P053 NAD CS ISI-91C 9/27/2004 Comments: Pre-service exam to WO# 0303946 315863 W-14 PIPE TO VALVE(CS-17) C-F-1 CXXX SWI NDE-PT-1 PT 2004P054 NAD Cs ISI-91C 10/14/2004 SWI NDE-UT-16A UT 2004U049 NAD CS ISI-91C 10/16/2004 Comments: Pre-service to WO# 0303946 315866 H-1 Single Rigid Base F-A F1.20a SWI NDE-VT-2.0 VT 2004V156 NAD CS ISI-91C 10/23/2004 Comments: Pre-service to WO# 0303946 315867 H-2 Single Rigid Base F-A F1.20a SWI NDE-VT-2.0 VT 2004V153 NAD CS ISI-91C 10/16/2004 Comments: Pre-service exam to WO# 0303946 315868 H-1 CS Pump 11 Support A F-A F1.40 SWI NDE-VT-2.0 VT 2004V168 NAD Cs ISI-90A 11/3/2004

Page 16 of 21 Section 3. ISI Examinations Plant: Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089 Plant Unit: 1 Owner Certificate of Authorization (If Req.): N/A Owner Xcel Energy Commercial Service Date: December 16, 1973 Operated by: Nuclear Management Company National Board Number for Unit: N/A Summary No. Comp ID Comp Desc. Cateqory Item Procedure Method/Sheet/Results System ISO Num Exam Date SWI NDE-VT-2.0 VT 2004V055 NAD Cs ISI-90A 9/27/2004 Comments: 2004V055 for ISI on 9127/04. 2004V168 as pre-service to WO# 0303949 on 11/3/05.

315869 H-2 CS Pump 11 Support B F-A F1.40 SWI NDE-VT-2.0 VT 2004V054 NAD Cs ISI-90A 9/27/2004 SWI NDE-VT-2.0 VT 2004V169 NAD CS ISI-90A 11/3/2004 Comments: 2004V054 was completed for ISI credit on 9/27104. 2004V169 was completed 11/3/04 as pre-service to WO# 0303949 315870 H-1 CS Pump 12 Support A F-A F1.40 SWI NDE-VT-2.0 VT 2004V170 NAD CS ISI-90B 11/3/2004 Comments: Pre-service to WO# 0303949 315871 H-2 CS Pump 12 Support B F-A F1.40 SWI NDE-VT-2.0 VT 2004V171 NAD CS ISI-90B 11/3/2004 Comments: Pre-service to WO# 0303949 315933 H-2 Seismic Restraint F-A F1.20a SWI NDE-VT-2.0 VT 2004V031 NAD RH ISI-55A 9/21/2004 315936 H-1 Single Spring Base Support F-A F1.20c SWI NDE-VT-2.0 .VT2004V052 NAD RH ISI-55C 9/27/2004 315941 H-3 Anchor F-A F1.20b SWI NDE-VT-2.0 VT 2004WV53 NAD RH ISI-55D 9/27/2004 315980 H-2 Single Spring Hanger F-A F1.20c SWI NDE-VT-2.0 VT 2004V056 NAD CS ISI-91A 9/27/2004 321643 H-5/IA Int. Attach[SUPPORT BRACKET-CV-31099] C-C C3.40 SWI NDE-MT-1 MT 2004M007 NAD MS ISI-68B 9/28/2004 322967 H-2B Snubber B F-A F1.20c SWI NDE-VT-2.0 VT 2004V007 NAD MS ISI-51C 5/28/2004 Comments: Pre-service to WO# 0200344 325254 H-3/IA Int. Attach[Double Spring Hanger] C-C C3.20 SWI NDE-PT-1 PT 2004P029 NAD Si ISI-98A 9/20/2004 325255. H-4/lA Int. Attach[FLOOR RESTRAINT] C-C C3.20 SWI NDE-PT-1 PT 2004P028 NAD Si ISI-98A 9/17/2004 325933 H-2/IA Int. AttachlSeismic Restraint] C-C C3.20 SWI NDE-PT-1 PT 2004P031 NAD RH ISI-55A 9/21/2004 390104 H-17 Support Rod F-A F1.40 SWI NDE-VT-2.0 VT 2004V206 NAD SG ISI-43C 11/10/2004 Comments: Pre-service to WO# 0310431 390105 H-18 Support Rod F-A F1.40 SWI NDE-VT-2.0 VT 2004V207 NAD SG ISI-43C 11/10/2004 Comments: Pre-service to WO# 0310431 390106 H-19 Support Rod F-A F1.40 SWI NDE-VT-2.0 VT 2004V208 NAD SG ISI-43C 11/10/2004 Comments: Pre-service to WO# 0310431 390107 H-20 Support Rod F-A F1.40 SWI NDE-VT-2.0 VT 2004V209 NAD SG IS1-43C 11/10/2004 Comments: Pre-service to WO# 0310431 390108 H-17 Support Rod F-A F1.40 SWI NDE-VT-2.0 VT 2004V210 NAD SG ISI-43D 11/10/2004

Page 17 of 21 Section 3. ISI Examinations Plant: Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089 Plant Unit: 1 Owner Certificate of Authorization (If Req.): N/A Owner: Xcel Energy Commercial Service Date: December 16, 1973 Operated by: Nuclear Management Company National Board Number for Unit: N/A Summary No. Comp ID Comp Desc. Category Item Procedure Method/Sheet/Results System ISO Num Exam Date Comments: Pre-service to WO# 0310432 390109 H-18 Support Rod F-A F1.40 SWI NDE-VT-2.0 VT 2004V211 NAD SG ISI-43D 11/10/2004 Comments: Pre-service to WO# 0310432 390110 H-19 Support Rod F-A F1.40 SWI NDE-VT-2.0 VT 2004V212 NAD SG ISI-43D 11/10/2004 Comments: Pre-service to WO# 0310432 390111 H-20 Support Rod F-A F1.40 SWI NDE-VT-2.0 VT 2004V213 NAD SG ISI-43D 11/10/2004 Comments: Pre-service to WO# 0310432 390123 W-3 Tubesheet- Shell C-A C1.30 SWI NDE-UT-3 UT 2004U087 NAD SG ISI-43E 11/8/2004 Comments: Pre-service to WO# 0310231 390128 W-8 Top Head - Head C-A C1.20 SWI NDE-UT-3 UT 2004U086 NAD SG ISI-43E 11/8/2004 Comments: Pre-service to WO# 0310231 390129 N-1 Nozzle - Shell C-B C2.21 SWI NDE-UT-3 UT 2004U091 NAD SG ISI-43E 11/8/2004 MT-Vendor MT 2004VE012 NAD SG ISI-43E 11/8/2004 Comments: Pre-service to WO# 0310231 390130 Ni-IR Nozzle Inner Radius C-B C2.22 SWI NDE-UT-8 UT 2004U089 NAD SG ISI-43E 11/8/2004 Comments: Pre-service to WO# 0310231 390143 W-3 Lower Shell - Tubesheet C-A C1.30 SWI NDE-UT-3 UT 2004U088 NAD SG ISI-43F 11/8/2004 Comments: Pre-service to WO# 0310231 390148 W-8 Top Head - Shell C-A C1.20 SWI NDE-UT-3 UT 2004U085 NAD SG ISI-43F 11/8/2004 Comments: Pre-service to WO# 0310231 390149 N-1 Nozzle - Shell C-B C2.21 SWI NDE-UT-3 UT 2004U092 NAD SG ISI-43F 11/8/2004 MT-Vendor MT 2004VE007 NAD SG ISI-43F 1117/2004 Comments: Pre-service to WO# 0310231 390150 N-AR Nozzle Inner Radius C-B C2.22 SWI NDE-UT-8 UT 2004U090 NAD SG ISI-43F 11/8/2004 Comments: Pre-service to WO# 0310231 390170 W-2ALSDU Pipe - Pipe C-F-2 C5.50 SWI NDE-UT-1A UT 2004U076 GEO MS ISI-51A 11/1/2004 MT-Vendor MT 2004VE024 NAD Ms ISI-51A 10/31/2004

Page 18 of 21 Section 3. ISI Examinations Plant: Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089 Plant Unit: 1 Owner Certificate of Authorization (If Req.): N/A Owner: Xcel Energy Commercial Service Date: December 16, 1973 Operated by: Nuclear Management Company National Board Number for Unit: N/A Summary No. Comp ID Comp Desc. Cateaorv Item Procedure Method/SheetVResults System ISO Num Exam Date Comments: Pre-service to WO# 0310229 390171 W-2ALSDU Pipe - Pipe C-F-2 C5.50 SWI NDE-UT-1A UT 2004U072 NAD MS ISI-68A 10/30/2004 MT-Vendor MT 2004VE026 NAD MS ISI-68A 10/29/2004 Comments: Pre-service to WO# 0310229 390975 W-7A tee - pipe C-F-1 CX.XX SWI NDE-UT-16A UT 2004U005 NAD CS ISI-9iC 9/18/2004 SWI NDE-PT-1 PT 2004P022 NAD - Cs ISI-91C 9/18/2004 Comments: Pre-serrvice to WO# 0303946 390976 W-17 pipe - tee C-F-1 CX.XX SWI NDE-PT-1 PT 2004P023 NAD CS ISI-91C 9/18/2004

... '.'- o: . ..- . .... ....

SWI NDE-UT-16A UT 2004U006 NAD CS ISI-91C 9/19/2004 Comments: Pre-service to WO# 0303946 390977 W-18 vaive - pipe . , C-F-1 CX.XX SWI NDE-UT-16A UT 2004U052 NAD CS ISI-91C 10/16/2004 SWI NDE-PT-1 PT .2004P058 NAD CS ISI-91C 10/14/2004 Comments: Pre-service exam to WO# 0303946. UT examination coverage limited to 50% due to configuration. Component exempt from the requirements of ASME Section Xl, 1989 Edition (current Code for the 3rd Interval Plan); however, the site chose to perform a pre-service examination since the Class 2 thin wall piping becomes In scope with the implementation of RI-ISI during the 4th Interval.

390978 W-13A tee - pipe C-F-1 CX.XX SWI NDE-UT-16A UT 2004U002 NAD CS ISI-91C 9/19/2004 SWI NDE-PT-1 PT 2004P021 NAD CS ISI-91C 9/18/2004 Comments: Pre-service to WO# 0303946 390979 W-19 pipe - tee C-F-1 CX.XX SWI NDE-PT-1 PT 2004P020 NAD CS ISI-91C 9/18/2004 SWI NDE-UT-16A UT 2004U004 NAD CS ISI-91C 9/19/2004 Comments: Pre-service to WO# 0303946 390980 W-20 valve - pipe C-F-1 CX.XX SWI NDE-UT-16A UT 2004U045 NAD CS ISI-91C 10/16/2004 SWI NDE-PT-1 PT 2004P052 NAD CS ISI-91C 9/24/2004 Comments: Pre-service exam to WO# 0303946. UT examination coverage limited to 50% due to configuration. Component exempt from the requirements of ASME Section Xl, 1989 Edition (current Code for the 3rd Interval Plan); however, the site chose to perform a pre-service examination since the Class 2 thin wall piping becomes in scope with the Implementation of RI-ISI during the 4th Interval.

390981 W-5A Pipe - Pipe C-F-1 CX.XX SWI NDE-PT-1 PT 2004P055 NAD CS ISI-91 C 10/1512004 SWI NDE-UT-16A UT 2004U047 NAD CS ISI-91 C 10/16/2004 Comments: Pre-service to WO# 0303946 392104 H-17/IA Int. Attach. (Support Rod) C-C C3.10 MT-Vendor MT 2004VE013 NAD SG ISI-43C 11/812004

Page 19 of 21 Section 3. [SI Examinations Plant: Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089 Plant Unit: 1 Owner Certificate of Authorization (If Req.): N/A Owner: Xcel Energy Commercial Service Date: December 16, 1973 Operated by: Nuclear Management Company National Board Number for Unit: N/A Summary No. Comp ID Comp Desc. Cateqory Item Procedure Method/Sheet/Results System ISO Num Exam Date Comments: Pre-service to WO# 0310431 392105 H-18/lA Int. Attach. (Support Rod) C-C C3.10 MT-Vendor MT 2004VE014 NAD SG ISI-43C 11/8/2004 Comments: Pre-service to WO# 0310431 392106 H-19/lA Int. Attach. (Support Rod) C-C C3.10 MT-Vendor MT 2004VE015 NAD SG ISI-43C 11/8/2004 Comments: Pre-service to WO# 0310431 392107 H-20/1A Int. Attach. (Support Rod) C-C C3.10 MT-Vendor MT 2004VE016 NAD SG ISI-43C 11/8/2004 Comments: Pre-service to WO# 0310431 392108 H-17/ilA Int. Attach. (Support Rod) C-C C3.10 MT-Vendor MT 2004VE008 NAD SG ISI-43D 11/2004 Comments: Pre-service exam to WO# 0310431 392109 H-18/lA Int. Attach. (Support Rod) C-C C3.10 MT-Vendor MT 2004VE009 NAD SG ISI-43D 1117/2004 Comments: Pre-service exam to WO# 0310431 392110 H-19/lA Int. Attach. (Support Rod) C-C C3.10 MT-Vendor MT 2004VE010 NAD SG ISI-43D 11/7/2004 Comments: Pre-service exam to WO# 0310431 392111 H-20/lA Int. Attach. (Support Rod) C-C C3.10 MT-Vendor MT 2004VE011 NAD SG ISI-43D 11/7/2004 Comments: Pre-service to WO# 0310431 Class 3 301051 H-1 Support A F-A F1.40 SWI NDE-VT-2.0 VT 2004V034 NAD AF ND-1-3-253A 9/21/2004 301052 H-2 Support B F-A F1.40 SWI NDE-VT-2.0 VT 2004V033 NAD AF ND-1 253A 9/21/2004 301080 H-1 Support A F-A F1.40 SWI NDE-VT-2.0 VT 2004V083 NAD CC ND-1-3-216A 10/5/2004 301081 H-2 Support B F-A F1.40 SWI NDE-VT-2.0 VT 2004V084 NAD CC ND-1-3-216A 10/5/2004 301104 H-1 Support A F-A F1.40 SWI NDE-VT-2.0 VT 2004V081 NAD CC ND-1-3-216B 10/5/2004 301106 H-2 Support B F-A F1.40 SWI NDE-VT-2.0 VT 2004V082 NAD CC ND-1-3-216B 10/5/2004 301115 H-1 Support A F-A F1.40 SWI NDE-VT-2.0 VT 2004V110 NAD CW ND-1-3-15C 10/6/2004 312351 CWH-502 Rigid Hanger F-A F1.30a SWI NDE-VT-2.0 VT 2004V155 NAD CW ND-1-3-15 10/19/2004 SWI NDE-VT-2.0 VT 2004V091 IND CW ND-1-3-15 10/6/2004 Comments: 2004V091 indicated CWH-502 carries no load. WO# 0408117 restored the support to its original configuration. CAP039255 & CAP039351.

312352 CWH-515 Sway Strut F-A F1.30b SWI NDE-VT-2.0 VT 2004V150 NAD CW ND-1-3-15 10/8/2004

Page 20 of 21 Section 3. ISI Examinations Plant: Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089 Plant Unit: 1 Owner Certificate of Authorization (If Req.): N/A Owner: Xcel Energy Commercial Service Date: December 16, 1973 Operated by: Nuclear Management Company National Board Number for Unit: N/A Summary No. Comp ID Comp Desc. Category Item Procedure

Method/Sheet/Results System ISO Num Exam Date Comments: Expanded scope from Summary No. 312409.

312353 CWH-516 Sway Strut F-A F1.30b SWI NDE-VT-2.0 VT 2004V138 NAD CW ND-1-3-15 10/16/2004 Comments: Expanded scope from Summary No. 312409.

312354 CWH-600 Restraint F-A F1.30b SWI NDE-VT-2.0 VT 2004V142 NAD CW ND-1-3-16 10/16/2004 Comments: Expanded scope from Summary No. 312409.

312408 CWH-503 Spring F-A F1.30c SWI NDE-VT-2.0 VT 2004V158 NAD CW ND-1-3-15 10/15/2004 Comments: Expanded scope from Summary No. 312409 312409 CWH-504 Seismic Restraint F-A F1.30b SWI NDE-VT-2.0 VT 2004V152 NAD CW ND-1-3-15 10/19/2004

'! ' ISWI NDE-VT-2.0 Vr 2004V117 IND CW ND-1-3-15 10/6/2004 Comments: 2004V117 identified a loose jam nut. Initiated CAP 039254. Tightened per WO# 0408116 and reexamined with no indications per Report No. 2004V152. Expanded scope was performed on ISI Summary Nos. 312415, 312353, 312408, 312412, 312410, 312469, 31289, 312354, 312352 and 315063 312410 CWH-505 Double Rod - F-A F1.30b SWI NDE-VT-2.0 Vr 2004V144 NAD CW ND-1-3-15 10/17/2004

- -,; ,I* - . SWI NDE-VT-2.0 VT 2004V130 IND CW ND-1-3-15 10/15/2004 Comments: Expanded scope from Summary # 312409. 2004V130 found no load on both rods. CAP039316. WO# 0408141 repaired conditions. No indications noted on 2004V144.

312412 CWH-517 Strut- F-A F1.30b SWI NDE-VT-2.0 VT 2004V131 IND CW ND-1-3-15 10/15/2004 SWI NDE-VT-2.0 Vr 2004V145 NAD CW ND-1-3-15 10/17/2004 Comments: Expanded scope from Summary # 312409. 2004V131 Identified loose lock nut. CAP039317. Tightened lock nut per WO# 0408143. No indications on 2004V145.

312413 CWH-525A Floor Restraint F-A F1.40 SWI NDE-VT-2.0 VT 2004V11 1 NAD CW ND-1-3-15 10/612004 312415 CWH-526A Floor Restraint F-A F1.40 SWI NDE-VT-2.0 VT 2004V143 NAD CW ND-1-3-15 10/15/2004 Comments: Expanded scope from Summary No. 312409 312419 CWH-525B Floor Restraint F-A F1.40 SWI NDE-VT-2.0 Vr 2004V112 NAD CW ND-1-3-16 10/6/2004 312465 CWH-210 Slide Base F-A F1.30a SWI NDE-VT-2.0 VT 2004V101 NAD CW ND-1-3-23 10/6/2004 312469 - CWH-315 Strut/Clamp F-A F1.30b SWI NDE-VT-2.0 VT 2004V135 NAD CW ND-1-3-24 10/16/2004 Comments: Expanded scope from Summary No. 312409.

312489' CWH-311 Strut /Clamp F-A F1.30b SWI NDE-VT-2.0 Vr 2004V137 NAD CW ND-1-3-24 10/1612004 Comments: Expanded scope from Summary No. 312409.

312633 CWH-374 Snubber/Clamp&Lugs F-A F1.30c ISI-VT-2.0 VT 2004V019 NAD CW ND-1-3-92 1/17/2003 Comments: Pre-service to WO# 0200327 312654 CWH-418 Rod F-A F1.30a SWI NDE-VT-2.0 VT 2004V095 NAD CW ND-1-3-93 1015/2004

Page 21 of 21 Section 3. ISI Examinations Plant: Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089 Plant Unit: 1 Owner Certificate of Authorization (If Req.): N/A Owner: Xcel Energy Commercial Service Date: December 16, 1973 Operated by: Nuclear Management Company National Board Number for Unit: N/A Summary No. Comp ID Comp Desc. Category Item

=

Procedure Method/Sheet/Results System ISO Num =

Exam Date 312655 CWH-419 Strut /Clamp F-A F1.30a SWI NDE-VT-2.0 VT 2004V096 NAD cW ND-1-3-93 10/5/2004 312664 CWH-413 Strut/Clamp F-A F1.30a SWI NDE-VT-2.0 VT 2004V093 NAD ND-1-3-94 10/5/2004 312770 CCH-194 Anchor F-A F1.30b SWI NDE-VT-2.0 VT 2004V025 NAD CC ND-1-3-223 9/17/2004 312846 AFWH-24 Rod F-A F1.30a SWI NDE-VT-2.0 VT 2004V028 NAD AF ND-1-3-249 9/17/2004 312892 RAFWH-101 U-BoltU LO CLR F-A F1.40 SWI NDE-VT-2.0 VT 2004V075 NAD AF ND-1-3-265B 10/4/2004 315063 CWH-901 Box Restraint F-A F1.30b SWI NDE-VT-2.0 VT 2004V151 NAD CW ND-1 15A 10/18/2004 Comments: Expanded scope from Summary No. 312409.

321051 H-1/lA Int. Attach[Support A] D-A D1.30 SWI NDE-VT-1.0 VT 2004V035 NAD AF ND-1 253A 9/21/2004 321052 H-2/IA Int. Attach[Support B] D-A D1.30 SWI NDE-VT-1.0 VT 2004V036 NAD AF ND-1-3-253A 9/21/2004 321080 H-1/lA Int. Attach[Support A] D-A D1.10 SWI NDE-VT-1.0 VT 2004V085 NAD CC ND-1-3-216A 10/5/2004 321081 H-2/IA Int. Attach[Support B] D-A D1.10 SWI NDE-VT-1.0 VT 2004V086 NAD CC ND-1 216A 10/5/2004 321104 H-1/IA Int. Attach[Support A] D-A D1.30 SWI NDE-VT-1.0 VT 2004V087 NAD CC ND-1-3-216B 10/5/2004 321106 H-2/IA Int. Attach[Support B] D-A D1.30 SWI NDE-VT-1.0 VT 2004V088 NAD CC ND-1-3-2165 10/5/2004 321115 H-1/lA Int. Attach [Support A] D-A 01.30 SWI NDE-VT-1.0 VT 2004V113 NAD CW ND-1-3-15C 10/6/2004 322409 CWH-504/lA Int. Attach[Seismic Restraint] D-A D1.20 SWI NDE-VT-1.0 VT 2004V092 NAD CW ND-1-3-15 10/6/2004 322413 CWH-525A/IA Int. Attach[Floor Restraint] D-A D1.10 SWI NDE-VT-1.0 VT 2004V114 NAD CW ND-1-3-15 10/6/2004 322419 CWH-525B/IA Int. Attach[Floor Restraint] D-A D1.10 SWI NDE-VT-1.0 VT 2004V115 NAD CW ND-1-3-16 10/6/2004 322465 CWH-210/IA Int. Attach(Slide Base] D-A D1.20 SWI NDE-VT-1.0 VT 2004V100 NAD CW ND-1-3-23 10/6/2004 322531 CWH-21 8/lA Int. Attach[Spring] D-A 01.20 SWI NDE-VT-1.0 VT 2004V120 NAD CW ND-1-3-47 10/9/2004 322654 CWH-41 8/IA Int. Attach[Rod] D-A 01.20 SWI NOE-VT-1.0 VT 2004V094 NAD CW ND-1 93 10/5/2004 322692 SVH-55/IA Int. Attach[Floor Restraint] D-A D1.20 SWI NDE-VT-1.0 VT 2004V077 NAD MS ND-1-3-178 10/4/2004 322709 CCH-33/lA Int. Attach[Double Rod] D-A D1.20 SWI NDE-VT-1.0 VT 2004V078 NAD CC ND-1-3-218 10/4/2004 322712 CCH-36/lA Int. Attach[Seismic Anchor] D-A D1.20 SWI NDE-VT-1.0 VT 2004V079 NAD CC ND-1-3-218 10/4/2004 322743 CCH-374/lA Int. Attach[Strut] D-A D1.20 SWI NDE-VT-1.0 VT 2004V026 NAD CC ND-1-3-219 9/18/2004 322846 AFWH-24/IA Int. Attach[Rod) D-A 01.20 SWI NDE-VT-1.0 VT 2004V024 NAD AF ND-1-3-249 9/18/2004 322868 AFWH-2311A Int. Attach[Rodi D-A D1.20 SWI NDE-VT-1.0 VT 2004V023 NAD AF ND-1-3-251 9/18/2004 332771 CCH-298/lA Int. Attach(Sliding Base) D-A D1.20 SWI NDE-VT-1.0 VT 2004V027 NAD CC ND-1 223 9/18/2004 Class NC 350107 FW-1 18 Pipe to Pipe HELB USARAI SWI NDE-UT-iA UT 2004U034 NAD FW ISI-HELB-1 9/28/2004 Comments: Augmented Examination 350120 FW-167 Pipe to Pipe HELB USAR Al SWI NDE-UT-IA UT 2004U035 GEO FW ISI-HELB-2 9/28/2004 Comments: Augmented Examination 350142 MS-19 Valve to Pipe HELB USAR Al SWI NDE-UT-1A UT 2004U036 GEO Ms ISI-HELB-3 9/30/2004

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1 CYCLE 22

SUMMARY

REPORT Section 4. IWE Examinations (3 pages)

Section 4. IWE Examinations Page 1

Page 2 of 3 Section 4. IWE Examinations Plant: Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089 Plant Unit: 1 Owner Certificate of Authorization (If Req.): N/A Owner Xcel Energy Commercial Service Date: December 16, 1973 Operated by: Nuclear Management Company National Board Number for Unit: N/A Summary No. Comp ID Comp Desc. Category Item Procedure Method/Sheet/Results System ISO Num Exam Date Class MC 400039 S-38 Accessible Surface Area E-A E1.12 SWI NDE-Vr-1.1 vr 2004V063 IND PC ISI-301 1013/2004 Comments: Follow up exam previously evaluated under NCR 19991420. No change from previous exam.

400045 S-44 Accessible Surface Area E-A E1.12 SWI NDE-Vr-1.1 VT 2004V062 IND PC ISI-301 101312004 Comments: Follow up exam previously evaluated under NCR 19991420. No change from previous exam.

400046 S-45 Accessible Surface Area E-A E1.12 SWI NDE-Vr-1.1 VT 2004V061 IND PC ISI-301 10/3/2004 Comments: Follow up exam previously evaluated under NCR 19991420. No change from previous exam.

400050 S-49 Accessible Surface Area E-A E1.12 SWI NDE-VT-1.1 VT 2004V064 IND PC ISI-301 10/3/2004 Comments: Follow up exam previously evaluated under NCR 19991420. No change from previous exam.

400069 S-64C Accessible Surface Area E-A 21.12 SWI NDE-VT-2.1 VT 2004V202 NAD PC ISI-302 1119/2004 400083. S-.73 Accessible Surface Area E-A E1.12- SWI NDE-Vr-2.1 Vr 2004V070 NAD PC ISI-304 1014/2004 400084 S-73A Accessible Surface Area E-A E1.12 SWI NDE-VT-2.1 VT 2004V073 NAD PC ISI-304 1014/2004 400085 S-74 Accessible Surface Area E-A E1.12 SWI NDE-VT-2.1 Vr 2004V071 NAD PC ISI-304 10/4/2004 400122 S-99 Accessible Surface Area E-A E1.12 SWI NDE-VT-2.1 Vr 2004V195 NAD PC ISI-309 11/9/2004 400264 Cl Accessible Surface Area E-A E1.12 SWI NDE-VT-2.1 VT 2004V066 IND PC ISI-304 1014/2004 Comments: Evaluated under CAP09736 400270 C6B Accessible Surface Area E-A E1.12 SWI NDE.V1-2.1 VT 2004V103 IND PC ISI-305 1016/2004 Comments: Evaluated under CAP039736 400283 C16 Accessible Surface Area E-A E1.12 SWI NDE-Vr-2.1 VT 2004V072 NAD PC ISI-304 1014/2004 400347 C45 Accessible Surface Area E-A E1.12 SWI NDE-VT-2.1 VT 2004WV69 NAD PC ISI-304 10/4/2004 400355 C49A Accessible Surface Area E-A E1.12 SWI NDE-VT-2.1 Vr 2004VW67 IND PC ISI-304 10/4/2004 Comments: Evaluated under CAP039736 400356 - C49B Accessible Surface Area E-A E1.12 SWI NDE-Vr-2.1 VT 2004V074 NAD PC ISI-304 10/4/2004 400467 G67 Moisture Barrier E-D E5.30 SWI NDE-Vr-2.1 Vr 2004V198 IND PC ISI-303 11/9/2004 SWI NDE-Vr-2.1 Vr 2004V218 NAD PC ISI-303 11/13/2004 400470 G70 Moisture Barrier E-D E5.30 SWI NDE-VT-2.1 VT 2004V197 IND PC ISI-303 11/9/2004 SWI NDE-VT-2.1 VT 2004V219 NAD PC ISI-303 11/13/2004 405534. C3 Accessible Surface Area E-A . E1.12 SWI NDE-VT-1.1 Vr 2004V105 IND PC ISI-305 10/6/2004 Comments: Follow up exam previously evaluated under NCR 19991420. No change from previous exam.

405576 C34D Accessible Surface Area E-A E1.12 SWI NDE-Vr-1.1 VT 2004V106 NAD PC ISI-305 1016/2004

Page 3 of 3 Section 4. IWE Examinations Plant: Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089 Plant Unit: 1 Owner Certificate of Authorization (If Req.): N/A Owner: Xcel Energy Commercial Service Date: December 16, 1973 Operated by: Nuclear Management Company National Board Number for Unit: N/A Summary No. Comp ID Comp Desc. Categi 1°ry Item Procedure Method/Sheet/Results System ISO Num Exam Date Comments: Follow up exam. No change from previous exam.

405587 C36E Accessible Surface Area E-A E1.12 SWI NDE-VT-1.1 VT 2004V107 IND PC ISI-305 10/6/2004 Comments: Follow up exam previously evaluated under NCR 19991420. No change from previous exam.

405608 C42A Accessible Surface Area E-A E1.12 SWI NDE-VT-1.1 VT 2004V098 NAD PC ISI-304 10/4/2004 405611 C42D Accessible Surface Area E-A E1.12 SWI NDE-VT-1.1 VT 2004V104 NAD PC ISI-305 11/2/2004 405614 C42F Accessible Surface Area E-A E1.12 SWI NDE-VT-1.1 VT 2004V154 NAD PC ISI-307 10/11/2004 405626 C46A Accessible Surface Area E-A E1.12 SWI NDE-VT-2.1 VT 2004V125 IND PC ISI-307 10/9/2004 Comments: Follow up exam previously evaluated under NCR 19991420. No change from previous exam.

405630 C60 Accessible Surface Area E-A E1.12 SWI NDE-VT-1.1 VT 2004V201 NAD PC ISI-302 411/9/2004 405644 S-68 Accessible Suface Area E-A E1.12 SWI NDE-VT-2.1 VT 2004V010 NAD PC ISI-303 9/1/2004 SWI NDE-UT-10 UT 2004U001 NAD PC ISI-303 9/1/2004 Comments: Normally inaccessible area made accessible for special inspection.

405652 G32 Moist Barrier E-D E5.30 SWI NDE-VT-2.1 VT 2004V200 IND PC ISI-301 11/9/2004 SWI NDE-VT-2.1 VT 2004V220 NAD PC ISI-301 11/13/2004 405663 G65 Moist Barrier E-D E5.30 SWI NDE-VT-2.1 VT 2004V226 NAD PC ISI-302 11/16/2004 SWI NDE-VT-2.1 VT 2004V199 IND PC ISI-302 11/9/2004 405665 G68 Moist Barrier E-D E5.30 SWI NDE-VT-2.1 VT 2004V068 IND PC ISI-303 9/23/2004 SWI NDE-VT-2.1 VT 2004V166 NAD PC ISI-303 11/2/2004 405666 G71 Moist Barrier E-D E5.30 SWI NDE-VT-2.1 VT 2004V196 IND PC ISI-303 11/9/2004 SWI NDE-VT-2.1 VT 2004V221 NAD PC ISI-303 11/13/2004 406023 C37A Accessible Surface Areas E-C E4.12 SWI NDE-UT-10 UT 2004U037 NAD PC ISI-307 10/11/2004 406024 C37B Accessible Surface Areas E-C E4.12 SWI NDE-UT-10 UT 2004U038 NAD PC ISI-307 10/11/2004 406025 C37C Accessible Surface Areas E-C E4.12 SWI NDE-UT-10 UT 2004U039 NAD PC ISI-305 10/11/2004 406026 C37D Accessible Surface Areas E-C E4.12 SWI NDE-UT-10 UT 2004U040 NAD PC ISI-305 10/11/2004 406027 C38A Accessible Surface Areas E-C E4.12 SWI NDE-UT-10 UT 2004U041 NAD PC ISI-307 10/11/2004 406028 C38B Accessible Surface Areas E-C E4.12 SWI NDE-UT-10 UT 2004U042 NAD PC ISI-307 10/11/2004 406029 C38C Accessible Surface Areas E-C E4.12 SWI NDE-UT-10 UT 2004U043 NAD PC ISI-305 10/11/2004 406030 C38D Accessible Surface Areas E-C E4.12 SWI NDE-UT-10 UT 2004U044 NAD PC ISI-305 10/11/2004

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1 CYCLE 22

SUMMARY

REPORT Section 5. Pressure Tests The following scheduled pressure tests were conducted during unit 1 cycle 22. All indications of leakage were evaluated and corrective measures performed as required by IWB-3142 and IWA-5250.

SYSTEM -CATEGORYIITEM ,..i;tjt . -PROCEDURE i ASME Xi WORK COMPLETION

' - -CODE : ;ORDER - . DATE

. CLASS .:

Reactor Coolant B-P/1815.10, B15.20. B15.30. SP 1070 1 0305162 11/22/2004 B15.40. B15.50. B15.60, B15.70 Reactor Coolant B-P/ B15.10, B15.20, B15.30, SP 1392 1 0305295 11/22/2004 B15.40, B15.50, B15.60.

B15.70 Caustic Addition D-B/ D2.10 SP 1168.7 3 0200239 12/3/2003 Cooling Water C-H/ All SP 1168.8 2 0200240 11/20/2003 Cooling Water D-B/ All SP 1168.8A 3 0200241 12/11/2003 Auxiliary Control Room Chilled D-B/ All SP 1168.9 3 0200242 4/25/2003 Water Safety Injection C-H/All SP 1168.13 2 0200223 3/15/2003 Chemical & Volume C-H/All SP 1168.16 2 0200227 6/212003 Control Feedwater C-H/ All SP 1168.17 2 0200228 1/2/2003 BAST C-FH All SP 1168.21 2 0200230 12110/2004 Five class 2 component were accepted by analytical evaluation as allowed by ASME Section Xi IWB-3142.4. These evaluations are submitted below as required by subparagraph IWB-3144(b).

SP 1168.10, Class 2 Component (CE 001599) IWB-3142.4 Acceptance by Analytical Evaluation The purpose of this evaluation is to address leakage through the body to cap gasket area of check valve RH-3-1. RH-3-1 is the check valve to the suction of 12 RHR pump from the RCS hot legs. During the phase 11cooldown, it was noted that there was slight weepage at this location. Due to plant conditions, the valve was not repaired during the outage. However, the carbon steel studs and nuts were replaced with stainless steel per EEC 1190 and Work Order 0211382.

To evaluate the acceptability of operating during the next cycle with this leakage this evaluation looks at expected plant conditions (normal, transient and post-accident) and evaluates the affect from potential leakage.

Expected Conditions:

Section 5. Pressure Tests Page I

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT I CYCLE 22

SUMMARY

REPORT RH-3-1 could be exposed to the following conditions during normal operations and transient or post-accident conditions:

Normal Operation:

During cooldown and heat-up operations, the RHR loop is operated at a RCS pressure less than 425 psig and temperature less than 350 0F. This check valve is directly in this flow path and could be exposed to these conditions. The actual pressure conditions at the check valve are the sum of the RCS pressure plus the static head between the RCS and the valve (less than 100 feet assuming the pressurizer is water solid). Therefore, the total pressure at the valve would be less than 475 psig. This condition would only exist for a short time period at the most on the order of several hours. During this time frame, the concern for leakage through this valve gasket area would be lost inventory.

Transient Operation:

This only discusses system transient operation and not plant transient operation. Plant transient operation is discussed in the post-accident condition discussion. Transient conditions could be overpressure or over temperature conditions. For overpressure conditions, system pressure is limited to the setpoint (plus accumulation) for relief valve RH-8-1. This pressure condition would be for a very short time period as valves MV-32164, 32165, 32230 and 32231 would close at a pressure of 425 psig. Note that the valve (including studs) is designed for these overpressure conditions. The concern would only be increased leakage through the gasket area during this short time period. The concern for leakage would be lost inventory.

Post-Accident Operation:

During a SGTR (ES 3.1, 3.2, 3.3) or small break LOCA (ES 1.1), the RHR system could be used to complete the cooldown of the unit. The conditions that RH-3-1 would be exposed to are bounded by those during a normal cooldown operation. This would also be applicable to transients such as an Appendix R fire or a seismic event or any other event that required the unit to be taken to cold shutdown. During this time frame, the concern for leakage through this valve gasket area would be lost inventory.

During post-LOCA recirculation, RH-3-1 is exposed to the sump fluid. The limiting pressure during this operation is design containment pressure of 46 psig plus the static head difference between the sump liquid and the valve (no more than 40 feet = 17 psig). Thus, a bounding pressure would be 63 psig. Leakage through this gasket area during this recirculation operation could affect off-site and control room personnel dose.

Leakage acceptance criteria:

Per SP 1082, this valve is leak tested with the remainder of the RHR recirculation loop. The total leakage from this SP is included with total leakage from the CS and the Si systems. The acceptance criteria for this combined total leakage is 2 gph. SP 1082 is performed with the RCS pressurized to 350 psig. This testing is discussed in program procedure H31 and is to meet a NRC commitment. As discussed above, this pressure is very conservative as the maximum pressure at the valve during post-LOCA recirculation system is 63 psig. Assuming that a correction of the flow being proportional to the square root of the pressure would mean Section 5. Pressure Tests Page 2

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1 CYCLE 22

SUMMARY

REPORT that 2 gph at 63 psig is equivalent to 4.7 gph at 350 psig. As noted previously, leakage during post-LOCA recirculation operation affects off-site and control room personnel dose. Per NUREG 0578, the dose analysis uses this as an input to determine accident consequences.

The 2 gph leakage acceptance criteria will bound any leakage considerations for any (normal or post-accident) phase 11cooldown. That is, at 2 gph for a few hours (at most), the inventory lost is negligible. Note that the make-up capability of a single charging pump is 60 gpm; so make-up for the lost inventory is not an issue. For example, assume the valve leaks at this rate for one week (a very conservative time duration). This would correspond to 2 gph

24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

7 days = 336 gallons. This is not a concern from a make-up capability or flooding concern. Note that this assumes that the 2 gph is from this valve entirely and the remainder of the recirculation system has zero leakage. Inactual operation, the leakage criteria for the valve is the difference between the 2 gph and the total system leakage.

During normal power operation, the pressure on the valve is due to static head difference between the height of water in the RWST and the valve. At minimum water level in RWST, this height difference is approximately 75 feet (32 psig). Thus, assuming a constant leakage hole size, the 2 gph leakage at 350 psig corresponds to a maximum allowable leakage criteria of 0.18 gph at normal full power operation. This will be factored into a periodic check (starting out more frequent with the frequency extending to monthly, if possible) during normal operation.

This check is a good idea to detect gross leakage and to clean-up any boric acid; however, it is not a completely valid predictor of leakage under post accident conditions as there is no thermal component. Note that this assumes that the 2 gph is from this valve entirely and the remainder of the recirculation system has zero leakage. Inactual operation, the leakage criteria for the valve is the difference between the 2 gph and the total system leakage.

The other concern is the affect that boric acid could have on the check valve. The check valve body and cap are stainless steel and stainless steel studs and nuts have been installed this outage per EEC 1195 and W00211382. Per Procedure H2 and EPRI 1000975 stainless steel is very resistant to corrosion from boric acid at low concentrations (less than 10% per procedure H2). Even at boric acid high concentrations, stainless steel does not rapidly corrode. For example, per H2, Attachment 1,at 3000 F and 30 percent concentration, the expected wastage is estimated at 2 mils/year. The boric acid in the RHR system is no higher that 2%(-3500 ppm) based on maximum RWST boric acid concentration. Thus, even with a leakage, there is no significant risk of degradation of the studs, nuts, valve body or cap that would result in a challenge to structural integrity.

The other potential concern is the leakage of boric acid on other equipment. A walkdown was performed to identify any components that such leakage could affect. This small amount of leakage through the cap joint area would run around the pipe and drip down from the pipe. As shown in the attached pictures, there are very few items in the vicinity of the check valve.

Furthermore, as shown there are no items of concern directly below the check valve that could be affected by small amounts of boric acid leakage. Therefore, this is not a significant concern either.

==

Conclusion:==

Based on the above discussion, it is acceptable to defer the repair of a small amount of leakage from check valve RH-3-1 provided the following actions are taken:

Section 5. Pressure Tests Page 3

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1 CYCLE 22

SUMMARY

REPORT

1. Leakage from the valve is observed with RCS pressure at approximately 350 psig and the leakage is totaled with the other recirculation system leakages and the total is verified to be less than 2 gph.

2. A periodic check is established during normal operation to verify that the leak rate has not increased. The frequency for this periodic check should initially be shorter (i.e.,

weekly). Based on observed (e.g., no leakage or very slight leakage), it could be extended to monthly checks.

SP 1168.21, Class 2 Component (CAP 040187) IWB-3142.4 Acceptance by Analytical Evaluation Description During the performance of SP 1168.21, the Boric Acid Storage Tank (BAST) System Pressure Test, on 12/10/04 per WO# 0200230 four (4) relevant boric acid indications were noted as follows:

1) BA on the discharge flange area of the 11 Boric Acid Transfer Pump (BATP). This leak appeared to originate from a tube fitting cap on the pump case and propagated up to barely contact the pump discharge flange bolting. There were no signs of discharge flange leakage. This leak is dry and appears to be inactive. WRC# A71433 was initiated to clean BA, repair the fitting, and VT-3 the bolting. [update: WO 0201617 replaced fitting - 1/28/05]

2) BA on the suction side of the 12 BATP case and suction drain valve body, VC-15-154.

This leak appeared to originated from a tube fitting cap on the pump case and wicked down the pump case to the drain valve. This leak is dry and appears to be inactive.

WRC# A71434 was initiated to clean BA, repair the fitting, and inspect the suction gasket. [update: WO 0409745 repaired the cap - 1/18/05]

3) BA on the bonnet of VC-15-156. This BA is from a SS tube fitting leak above the subject valve (non-Code tubing). The valve itself does not appear to have a leak. The BA is dry and crystalline. WRC# A71443 was initiated to clean the BA and repair the tubing above. [update: WO 0409744 replaced valve - 1/18/05]

4) BA on the body of the 2PI-108 isolation valve, 21 BA filter inlet. The valve diaphragm appears to be the source of this minor leak. The leak is dry and appears to be inactive.

WRC# A73709 was initiated to clean the BA, tighten the bonnet nuts, or replace the diaphragm.

There are no signs or corrosion products or loss of pressure retaining wall thickness.

Evaluation All of these affected components are constructed from non-susceptible materials such as 304 SS, 316 SS, etc. They are all heat traced, so the nominal surface temperature is about 175F.

They are all exposed to the atmosphere, so oxygen is present with the crystalline BA and oxygen would be present if the leaks become active (wet).

Section 5. Pressure Tests Page 4

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1 CYCLE 22

SUMMARY

REPORT Per EPRI Technical Report 1000975, Boric Acid Corrosion Guidebook, Revision 1, for various test scenarios and conditions "... corrosion rates for the stainless steel materials were all negligible." This is stated several times in section 4 of the report.

The operating and BA exposure conditions of the above components are similar to the conditions described in the EPRI report and will result in negligible corrosion rates. Based upon these similarities and past operating experience at PI with the BAST/BATP equipment, it is a reasonable expectation that the current conditions are acceptable until such time that repairs are implemented per the referenced WRCs.

Section 5. Pressure Tests Page 5

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT I CYCLE ---- - -22 ---

SUMMARY

REPORT Section 6. Snubber Inservice Testing and Preservice Examinations Inspection results showed no visual snubber failures. All snubbers that underwent functional testing had satisfactory results, therefore no scope expansion was required.

SNUBBER # . Pi # . FUNCTIONAL . FUNCTIONAL Pl #- PREINSTALLATION VT-3 EXAM

.REMOVE D TEST WO AS: TEST .- REPLACED TEST WO . WO

-FOUND .,, .: RESULTS. . :.

1-RLWDH- Pl-396 306999 SAT PI-526 306999 309300 1-RLWDH- Pl-92 306999 SAT PI-265 306998 309301 2243 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

1-RCVCH-1457 Pl-251 306999 SAT Pl-289 306998 309292 1-RHCH=14 Pl-267 306999 SAT Pl-109 306998 309298 1-RCRH-34 Pl-535 306999 SAT Pl-365 306998 310022 1-RBDH-389 Pl-4 306999 SAT Pl-159 306998 309282 1-RBDH-388 Pl-168 306999 SAT Pl-287 306998 309281 1-RBDH-415 PI-345 306999 SAT Pl-78 306998 309283 1-RCCH-375 Pl-447 306999 SAT Pl-218 306998 309284 1-RCRH-12B Pl-27 306999 SAT Pl-280 306998 309285 1-RCRH-21 PI-250 306999 SAT Pl-310 306998 309286 1-RCRH-23A Pl-30 306999 SAT Pl-281 306998 309287 1-RCRH-5B Pl-26 306999 SAT Pl-247 306998 309288 1-RCSH-83A Pl-46 306999 SAT Pl-313 306998 309289 1-RCSH-83B Pl-22 306999 SAT Pl-42 306998 309290 1-RCVCH-1483 Pl-191 306999 SAT Pl-180 306998 309293 1-RCVCR-1484 Pl-253 306999 SAT Pl-214 306998 309294 1-RCVCH-1871 Pl-40 306999 SAT PI-412 306998 309295 1-RCVCH- Pl-296 306999 SAT Pl-399 306998 309296 907A P__-399___306998____30929_

9-RCVCH- Pl-131 306999 SAT Pl-110 306998 309297 907 8B_ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _

1-RHCH-15 Pl-554 306999 SAT Pl-261 306998 309299 1-RPCH-121 Pl-375 306999 SAT Pl-386 306998 309302 1-RPCH-139 Pl-108 306999 SAT Pl-239 306998 309303 1-RPCH-140 Pl-417 306999 SAT PI-195 306998 309304 1-RPCH-160 Pl-327 306999 SAT Pl-521 306998 0309305 1-RPCH-23 Pl-343 306999 SAT Pl-385 306998 309306 1-SIRH-23A Pl-81 306999 SAT Pl-5 306998 309307 Section 6. Snubber Inservice Testing and Preservice Examinations Page 1

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISL AND UNIT 1 CYCLE 22

SUMMARY

REPORT SNUBBER # Pl # FUNCTIONAL .. FUNCTIONAL Pi # PREINSTALLATION VT-3 EXAM REMOVED - TEST WO AS, TEST. --- REPLACED TEST WO WO

FOUND RESULTS 1-WDRH-29A Pi-94 306999 SAT PI-377 306998 309308 1-WDRH-29B Pl-532 306999 SAT Pl-382 306998 309309 1-WDRH-35 Pl-364 306999 SAT Pl-415 306998 309310 1-RCRH-27A Pl-50 306999 SAT Pl-536 306998 310023 1-RCRH-27B Pl-583 306999 SAT PI-493 306998 310024 1-RCRH-51 Pl-337 306999 SAT Pl-35 306998 310025 1-RCRH-52 Pl-136 306999 SAT Pl-572 306998 310026 1-RCRH-48A Pl-564 407300 SAT Pl-564 306998 407300 1-MSH-68A Pl-531 407307 SAT Pl-531 306998 407307 1IS/GO1 SG20 309311 SAT SG15 309185 309311 12S/G01 SG04 309378 SAT SG18 211888 309378 Section 6. Snubber Inservice Testing and Preservice Examinations Page 2

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1 CYCLE 22

SUMMARY

REPORT Section 7. Steam Generator Eddy Current Examination Results During the refueling outage, 11 and 12 steam generators were replaced. The steam generator tube preservice inspections were completed by Framatome ANP in December of 2003 and January of 2004 and have been included in this report.

Section 7. Steam Generator Eddy Current Examination Results Page I

20440-8 (1/2001)

A FRAMATOME ANP ENGINEERING INFORMATION RECORD Document Identifier 51- 5039649 - 00 Title Technical Summary of Steam Generator Eddy Current Examinations for Prairie Island Nuclear Generating Plant Unit 1, December 2003-Pre-service Baseline Inspection PREPARED BY: REVIEWED BY:

Name C. L. Gardner Name T.A. Ribaric Signature A 5 Date 02/13/04 Signature _ _ _ Date 02/13/04 Technical Manager Statement: Ti c Initials _____ __

Reviewer is Independent.

Remarks:

This document presents a textual synopsis describing the various eddy current examinations that comprised the pre-service baseline inspection of the Prairie Island Unit 1 replacement steam generators which occurred in December 2003/January 2004, and the results thereof.

Page 1 of 12

1.0 Introduction The Prairie Island Nuclear Generating Plant, located near Red Wing, Minnesota, is owned by Xcel Energy and operated by Nuclear Management Company (NMC). Replacement steam generators for Unit 1, in operation since 1973, have been purchased and a pre-service baseline eddy current examination was performed by Framatome ANP in Chalon, France. This report summarizes the results of that examination. The table and figures included in this report summarize the examinations performed in each steam generator and the results thereof. Specific tube information and results are found within the full report of which this technical summary is a part.

2.0 Component Description Prairie Island Unit I will operate two Framatome ANP Model 56/19 recirculating steam generators designated as S/G 11 and S/G 12. Each contains a bundle of 4,868 U-bend tubes arranged into 55 rows and 114 columns. The tubing is made of Inconel 690 thermally treated alloy. The design dimensions of all tubing are of 0.750" nominal outside diameter and 0.043" nominal wall thickness.

The tubes are supported by eight alloy 410 stainless steel quatrefoil-hole tube support plates measuring 1.18" in thickness. Tubes intersect up to nine alloy 405 alloy anti-vibration bars (AVB) that are located in the U-bend region of the generators. Tubing U-bend radii range from 2.700" (Row 1) to 58.995" (Row 55). Tube pitch is 1.0425" and square. The tubesheets measure 21.835" in thickness.

The tubes are hydraulically expanded throughout the entire tubesheet depth.

3.0 Scope The examination scope is summarized in the table below. The totals include neither redundant tube examinations nor inadvertent ("out of scope") tests. With the exception of eight tubes, the pre-service rotating coil inspection for Rows 1-9 U-bend regions was performed in July of 2002 at Gavle, Sweden and is not discussed in this summary (see the reference in Section 7.4, below). A discussion for each steam generator follows in Section 5, below.

Examination Technique Leg Probe Extent S/G 11 S/G 12 Bobbin Probe Single-pass full length Hot 61OUL TECTEH 225 982 Single-pass full length Cold 61OUL TE11TEC 4187 3430 Multiple-pass full length both 61OUL various 456 456 (Total) 4868 4868 Rotating Probe I/L TTS (+3"/-3') Hot j 61OPP TSHTSH 4868 4868 C/L TTS (+3"/-3") Cold 61OPP TSCTSC 4868 4868 Rows 1-9 U-bend Hot 56OPP 08H08C 4 4 Special Interestt both various various 331 517

Tntil tuhes -r.4inaexaminatinn were i1022 in each stem oenerntnr all hut thnqe listed here were tested duri- n naprevi.. incneftin.

t Based upon location and signal character, either 610PP, 600MB, or 560PP was used. Special interest locations examined within the other RPC test programs are not included inthe total.

Technical Summary of Steam Generator Eddy Current Examinations 51-5039649-00 Prairie Island Nuclear Generating Plant Unit 1, December 2003 Pre-service Baseline Inspection Page 2 of 12

4.0 Methodology The examinations, personnel, and equipment were in compliance with the requirements of the Framatome ANP, Incorporated (FANP) Quality Assurance Manual, the 1989 Edition of Section XI of the ASME Boiler and Pressure Vessel Code (no addenda), the documents referenced in Section 7.1 through 7.3, below, the applicable customer technical specifications, and industry standards.

A site specific eddy current procedure (referenced in Section 7.1, below) including Examination Technique Specification Sheets (ETSSs) were developed by FANP and reviewed and approved by the utility.

Technicians qualified to either Level I or Level II performed the steam generator tubing examinations.

Personnel qualified to a minimum of Level IIA evaluated the data. Personnel qualified to Level III performed the resolution process.

All of the Level IIA and Level III data analysis personnel were QDA-qualified in accordance with Appendix G of the EPRI PWR Steam Generator Guidelines, revision 6 (referenced in Section 7.3, below). The data analysts attended site-specific analysis guidelines training and were qualified using site-specific written and practical examinations prior to the commencement of the examinations.

All examination data undervent two separate analyses. The analyses remained independent of one another and were referred to as "primary" and "secondary" analysis. To maintain independence, analysts of the two parties worked in separate data rooms. The primary party analysis was performed by manual review of the data; the secondary party analysis utilized computer software to initially screen the data, followed by manual review and editing. The computer screening parameters used during the inspection are discussed in the document referenced in Section 7.2, below. The results of these two evaluations were compared and the discrepancies resolved in accordance with the eddy current procedure.

An independent Level III/QDA analyst monitored the analysis process, including the review of all indications reported by an analyst that were deleted during resolution.

The final results of the data analysis were retrieved by data management personnel and loaded into the Framatome Data Management System (FDMS). The system was used to check the results for accuracy and to ensure all tubes were examined to the proper extent. In addition, FDMS was used to track the examination progress, provide daily status reports, and perform data manipulations for queries, tubesheet mapping applications, trend analyses, and final reporting. A second system, Eddynet Inspection Management System (EIMS), was utilized for analysis functions only.

The examination data were transmitted via the Local Area Network (LAN) and recorded on hard-disk drives. In parallel, the data was copied to separate magneto-optical disks for permanent storage by the customer. Following data analysis, all evaluation results and calibration setups were written to the disks allowing all processes of the examination to exist in a retrievable format on a single storage medium.

Technical Summary of Steam Generator Eddy Current Examinations 51-5039649-00 Prairie Island Nuclear Generating Plant Unit 1, December 2003 Pre-service Baseline Inspection Page 3 of 12

The examinations were performed with the Zetec system. The eddy current instrument used was the Zetec MIZ-30A remote data acquisition unit. Version 1.4 of the Zetec Eddynet lI i software was employed for data acquisition; version 1.6 was used for analysis. The essential variables employed for each examination technique are documented within the procedure on the ETSSs. The ETSSs described the following, as a minimum:

the technique's applicability

the tube material type and dimensions

the probe manufacturer, type, size, and length

the probe extension cable type and length

the examination hardware and software

the examination frequencies and coil connections

the data digitizing rates and probe speeds

the scan direction

the data recording method

the calibration standards

the data acquisition and analysis calibration requirements

the data analysis screening, reporting and recordingrequirements The eddy current techniques employed during the inspection were bobbin coil and rotating probe coil (RPC). The examinations met the requirements of techniques qualified in accordance with Appendix H of the document referenced in Section 7.3, below.

The bobbin coil technique was used in both S/Gs to perform the standard ASME code examination for flaw detection. This technique was applied to the full length for all tubes examined during this outage.

The nominal bobbin probe speed was 40 inches per second (ips), though a lower speed of 24 ips was used for inspecting Rows 1 through 4 to achieve the required data quality in tight-radius U-bends; in all cases a sample rate of 30 points per inch (ppi) was maintained.

The bobbin coil examinations were performed with Zetec probes as specified by the ETSS at frequencies of 550, 280, 140, and 35 kHz, each operated in both the differential and absolute test modes. In addition to the four base frequencies, 550/140 kHz differential and 280/140 kHz absolute tube support plate (TSP) suppression mixes were used to enhance evaluation at TSP and AVB intersections. These examinations were performed in accordance with ETSS #1.

A motorized rotating probe coil (MRPC) technique was used to examine top-of-tubesheet expansion transition areas in both the hot- and cold-legs as well as to characterize bobbin indications in straight sections of tubing. The technique utilized Zetec probes with three coils. The +Point coil was operated at frequencies of 300, 200, 100, and 35 kHz and provided the prime means of MRPC analysis. A 0.115" diameter pancake coil (operated at the aforesaid frequencies), and a 0.080" diameter shielded high frequency coil (operated at 600, 300, and 200 kHz) were also present. The probes were operated at minimum sampling rates of 25 ppi in the axial direction and 30 ppi in the circumferential direction for the examination. The examinations were performed in accordance with ETSS #2.

A single-coil flexible motorized rotating probe was used to examine the U-bend regions of Rows I through 9 tubes as well as to characterize bobbin indications in bent sections of tubing. The technique utilized Zetec probes with a +Point coil, which was operated at frequencies of 400, 300, 200, and 100 kHz. The probes were operated at minimum sampling rates of 30 ppi in the axial direction and 30 ppi in the circumferential direction for the examination. The examinations were performed in accordance with ETSS #3.

Technical Summary of Steam Generator Eddy Current Examinations 51-5039649-00 Prairie Island Nuclear Generating Plant Unit 1, December 2003 Pre-service Baseline Inspection Page 4 of 12

The bobbin probe was chosen for the examination because it is the ASME code-required technique and it provides a fast method for examination of the entire tube. The +Point coil was chosen for the examination because it is an industry qualified technology for the detection of cracking mechanisms.

It also provides superior detection of circumferentially oriented flaws and crack-like flaws in the presence of material geometry variations relative to the bobbin probe.

The +Point coil has been qualified for detection in all regions of the generator for both outer diameter (OD) and inner diameter (ID) indications, including dented regions. The 0.080" high-frequency plus point coil was chosen for its capabilities to provide enhanced detection of small ID indications. The

0. 1 15" pancake coil was used for supplemental information.

5.0 Results and Imperfection Types This section discusses the examinations performed in each steam generator and the types of imperfections detected. Figures A through D show the total number of signals per category. BLG denotes a bulge or localized tube diameter increase. DNG denotes a "ding" representing a localized tube diameter reduction. MBM ("manufacturing burnish mark") denotes a shallow volumetric signal indicative of manual "buffing" of an OD blemish during tube manufacture. NQI ("non-quantifiable indication") represents a signal considered by industry practice to be repairable unless diagnosed differently with a rotating coil test. OXP ("over-expansion") indicates a hydraulic expansion transition at a location beyond the nominal terminus at the top of tubesheet. PDS ("pilger drift signal") represents a tube manufacturing condition caused by the pilgering mandrel. "%" represents a case where a percent of wall loss was reported. GMD ("geometric distortion") is an RPC code denoting an ID surface blemish. PVN ("permeability variation") was used for RPC exams where the tubing displayed non-nominal magnetic permeability values. SVI ("single volumetric indication")

represents an RPC result indicative of wall-loss. A discussion of the indication codes and the methodology for classifying these indications are found in the eddy current procedure.

5.1 Steam Generator 11 A 100% full-length bobbin coil examination (4868 tubes) was performed. Data were acquired from either tube end and consisted of both single-pass examinations and, for low-row tubes, dual-pass partial exams.

A 100% top-of-tubesheet RPC examination was performed in both the hot-leg and the cold-leg (4868 tubes, 9736 examinations). The minimum extent for these tests was from 3.00 inches below the secondary tubesheet face to 3.00 inches above the face. This extent includes the tubing hydraulic expansion transition and future (potential) sludgepile region.

A U-bend RPC examination was performed on the four low-row tubes in S/G 11 that had not been tested during an earlier inspection. The extent of these tests included the entire bent portion of the tubing and the uppermost support plate intersections adjacent to it.

A diagnostic ("Special Interest") RPC examination was performed for every signal reported during the bobbin coil examination unless the location was within another scheduled RPC test extent.

Technical Summary of Steam Generator Eddy Current Examinations 51-5039649-00 Prairie Island Nuclear Generating Plant Unit 1, December 2003 Pre-service Baseline Inspection Page 5 of 12

SIG 11 Bobbin Results:

Figure A: Summary of SIG 11 Bobbin Examination Results 30 24 25 20 en

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10 7 6 5

0 211 1 1

I BLG MBM NQI OXP PDS Indication Codes Figure A, above, is a bar graph depicting the results of the bobbin examination of S/G 11 by signal type. Six of the seven indication codes are represented; DNG indications, totaling 286 in S/G 11, have been omitted for the sake of clarity. The total number of 339 indications were distributed among 323 tubes; the balance of 4565 tubes have a bobbin result of NDD ("no defects detected"). Specific results for tubes with indications and results for all tubes examined in S/G 11 can be found in the full report.

Technical Summary of Steam Generator Eddy Current Examinations 51-5039649-00 Prairie Island Nuclear Generating Plant Unit 1, December 2003 Pre-service Baseline Inspection Page 6 of 12

SIG 11 MRPC Results Figure B: Summary of SIG 11 MRPC Examination Results 5

5 -

4 4

1 - ------- - 1 GMD PVN SVI Indication Codes Figure B, above, is a bar graph depicting the results of all RPC examinations of S/G 11 by signal type.

The total number of 10 indications were distributed among 9 tubes; the balance of 10,061 locations tested have an RPC result of NDD ("no defects detected", used for pre-scheduled exams) or NDF ("no defect found", used for addressing special interest locations). Specific results for tubes with indications and results for all tubes examined in S/G 11 can be found in the full report.

SIG 11 Repairable Indications:

There were no indications found in S/G 11 that would prevent tubes from reaching service for technical reasons. However, the contractual agreement between the utility and the component supplier states that tubes are to be "rejected" in the following circumstances:

a) for any signal measuring 7% wall-loss or greater b) for any ding signal measuring 1.00 volt or greater in amplitude c) for any burnish mark signal measuring 0.50 volts or greater in amplitude d) for other signals measuring 2.00 volts or greater in amplitude (except PDS)

According to these criteria the following 6 tubes were found to be in non-conformance:

R07-C47 .... category "b)": DNG R18-C04 .... category "d)": OXP R29-C89 .... category "d)": BLG R47-C35 .... category "a)": 15%

R47-C44 .... category "b)": DNG R55-C50 .... category "b)": DNG Technical Summary of Steam Generator Eddy Current Examinations 51-5039649-00 Prairie Island Nuclear Generating Plant Unit 1, December 2003 Pre-service Baseline Inspection Page 7 of 12

5.2 Steam Generator 12 A 100% full-length bobbin coil examination (4868 tubes) was performed. Data were acquired from either tube end and consisted of both single-pass examinations and, for low-row tubes, dual-pass partial exams.

A 100% top-of-tubesheet RPC examination was performed in both the hot-leg and the cold-leg (4868 tubes, 9736 examinations). The minimum extent for these tests was from 3.00 inches below the secondary tubesheet face to 3.00 inches above the face. This extent includes the tubing hydraulic expansion transition and future (potential) sludgepile region.

A U-bend RPC examination was performed on the four low-row tubes in S/G 12 that had not been tested during an earlier inspection. The extent of these tests included the entire bent portion of the tubing and the uppermost support plate intersections adjacent to it.

A diagnostic ("Special Interest") RPC examination was performed for every signal reported during the bobbin coil examination unless the location was within another scheduled RPC test extent.

SIG 12 Bobbin Results:

Figure C: Summary of SIG 12 Bobbin Examination Results 30 30 25-20 -18 Ea 15 -

5 W 0 0 0 0 --

BLG MBM NQI OXP PDS %

Indication Codes Figure C, above, is a bar graph depicting the results of the bobbin examination of S/G 12 by signal type. Six of the seven indication codes are represented; DNG indications, totaling 473 in S/G 12, have been omitted for the sake of clarity. The total number of 529 indications were distributed among 504 tubes; the balance of 4364 tubes have a bobbin result of NDD ("no defects detected"). Specific results for tubes with indications and results for all tubes examined in S/G 12 can be found in the full report.

Technical Summary of Steam Generator Eddy Current Examinations 51-5039649-00 Prairie Island Nuclear Generating Plant Unit 1, December 2003 Pre-service Baseline Inspection Page 8 of 12

SIG 12 MRPC Results:

Figure D: Summary of SIG 12 MRPC Examination Results 5 -

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° GMD PVN SVI Indication Codes Figure D, above, is a bar graph depicting the results of all RPC examinations of S/G 12 by signal type. A single indication was reported; the balance of 10,256 locations tested have an RPC result of NDD ("no defects detected", used for pre-scheduled exams) or NDF ("no defect found", used for addressing special interest locations). Specific results for tubes with indications and results for all tubes examined in S/G 12 can be found in the full report.

SIG 12 Repairable Indications:

There were no indications found in S/G 12 that would prevent tubes from reaching service for technical reasons. However, the contractual agreement between the utility and the component supplier states that tubes are to be "rejected" in the following circumstances:

a) for any signal measuring 7% wall-loss or greater b) for any ding signal measuring 1.00 volt or greater in amplitude c) for any burnish mark signal measuring 0.50 volts or greater in amplitude d) for other signals measuring 2.00 volts or greater in amplitude (except PDS)

According to these criteria the following 5 tubes were found to be in non-conformance:

R37-C95 .... category "d)": BLG R44-C23 .... category "b)": DNG R45-C25 .... category "b)": DNG R53-C46 .... category "b)": DNG R55-C55 .... category "b)": DNG Technical Summary of Steam Generator Eddy Current Examinations 51-5039649-00 Prairie Island Nuclear Generating Plant Unit 1, December 2003 Pre-service Baseline Inspection Page 9 of 12

6.0 Miscellany The following information is included herein as it is not documented elsewhere.

6.1 Database Comment Codes During the course of the inspection it became convenient to add certain comments to the database of results for administrative reasons. The following codes were used in the "utility" fields of reporting lines during the inspection:

INR Denotes that the current data was reviewed in reference to an indication from earlier ECT data acquired at the tube mill, and that the said indication is not now reportable (being either under a reporting threshold or interpreted differently).

INF Similarly, an historical indication is not present at all in the current data (the indication was a transient signal phenomenon and not related to the tubing itself).

HL-CL FLIP In one instance, a tube was installed in the steam generator reversed from its identified leg orientation at the tube mill. This was evidenced by comparing the ECT data.

IDOK Used as a declaration that a tube's identity has been verified; performed when there existed the potential (at least in theory) that the tube number had been mis-encoded.

PLP Describes the superficial bobbin signal character ("possible loose part") that resulted in an RCL ("re-test clarification") being reported. In fact, all of the signals that resulted in this code disappeared upon re-test.

SSA Describes the superficial RPC signal character ("secondary side anomaly") that resulted in an RCL being reported. Upon re-test, the result was NDD.

300 Explanatory code for an RBD ("re-test bad data") as the result of the probe being used in excess of 300 tubes. The contract between the utility and the steam generator supplier effectively limited bobbin probe life to this value.

MV The eddy current procedure instructs that all tubes requiring repair have an additional identity verification. Machine Vision (a means of determining tube identification independent of the robotic encoders) may be used for the purpose. The code was used for tubes in non-conformance with the contract instead of PID because it was undetermined which, if any, of the tubes would actually be plugged.

POSTID BUFF Identifies an RPC re-test (of an SVI) after attempts were made to buff or polish the ID of the tube at the indication's location. No change was noted, however.

AVB SPT Identifies bobbin re-tests (and special interest RPC as a result of the re-tests) of 24 tubes in each generator after support members for the AVBs had been placed in their final position (making tube contact near each AVB intersection).

6.2 Examinations with a Magnetically Biased Probe During the course of the rotating coil examinations a small number of tubes exhibited signals consistent with magnetic permeability variations. It was determined that the inspection of these tubes would benefit from re-testing with a magnetically biased ("mag-bias") rotating +Point coil probe.

Although the coils of the mag-bias probe (600MB) used for this examination are identical to that of the standard (61OPP) probe, the biasing magnets have the potential to affect the signal output. It was observed during the examination that the signal character of the mag-bias +Point coil compared favorably to the standard, non-biased coil. The following illustration shows the two probes produce equivalent results for tube wall degradation and that the mag-bias probe eliminates the permeability variation and therefore meets its intended purpose. The technique qualification for the non-biased coil is easily extended to the mag-biased coil for this application.

Technical Summary of Steam Generator Eddy Current Examinations 51-5039649-00 Prairie Island Nuclear Generating Plant Unit 1, December 2003 Pre-service Baseline Inspection Page 10 of 12

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Caliration Sfdard (610PP) Calibration Standbd (600MB) i+0jej N1 IndicationI Tube110PP) Indication In Tube it(600MB) 0 Figure E Technical Summary of Steam Generator Eddy Current Examinations 51-5039649-00 Prairie Island Nuclear Generating Plant Unit 1, December 2003 Pre-service Baseline Inspection Page 11 of 12

7.0 References 7.1 Framatome ANP Procedure 54-ISI-406-01, "Pre-Service Eddy Current Inspection of Prairie Island Steam Generator Tubing", issued 30 December, 2003.

7.2 Framatome ANP Document 51-5037900-00, "CDS Development and Qualification for Prairie Island Unit I Replacement Steam Generators Baseline Examination", issued 11 December, 2003.

7.3 EPRI Technical Report 1003138, "Pressurized Water Reactor Steam Generator Examination Guidelines: Revision 6" (Requirements), dated October, 2002.

7.4 Framatome ANP Document 51-5019819-02, "Prairie Island Unit I Replacement Steam Generators U-bend +Point Examination", issued 18 November, 2002.

Technical Summary of Steam Generator Eddy Current Examinations 51-5039649-00 Prairie Island Nuclear Generating Plant Unit 1, December 2003 Pre-service Baseline Inspection Page 12 of 12

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1 CYCLE 22

SUMMARY

REPORT Section 8. Repair/ Replacement Activities 92 NIS-2 forms are attached which identify Prairie Island Unit 1 Repair/ Replacement Activities during fuel cycle 22.

- DESCIPTIONCODE -

COMPONENTNAE

'ITEM# CLASS SYSTEM 1-22-002 11 SI Pump Unit 0208641, Replaced 11 SI pump motor unit 3 ZE Cooler 0115067, 01ZXO1 cooler coils.

1-22-004 VC Pipe Support (3") 0300064 Replaced bolt assembly. 2 VC 1-22-005 CL Piping 0201494 Fabricate and install 2-CL-17 and 3 CL replaced flange fasteners.

1-22-006 CL Piping 0201492 Fabricate and install 2-CL-18. 3 CL Replace flange bolting.

1-22-007 CL Piping 0202731 Replaced fasteners. 3 CL 1-22-008 11 Charging Pump 0211989 Replaced fasteners. 2 VC Suction Piping 1-22-009 11 BATP Discharge 0211454 Replaced bonnet. 2 VC Valve 1-22-010 12 Charging Pump 0300993 Replaced charging pump packing 2 VC assemblies.

1-22-011 Letdown Line Relief 0302844, EEC- Replaced valve. 2 VC Valve 1250 1-22-012 12 BATP 0301238, SPCE- Replaced the mechanical seal 2 VC ME-0453, EEC- gland plate.

1266 .

1-22-013 13 Chg. Pmp. Dischg. 0211233 Replaced flange fasteners. 2 VC Relief 1-22-014 11 Chg. Pmp. Dischg. 0211231 Replaced flange fasteners. 2 VC Relief 1-22-015 11 Boric Acid Transf. 0210079, SPCE- Replaced the mechanical seal 2 VC Pump ME-0453 gland plate - Suction end.

1-22-016 11 Boric Acid Transf. 0211311, SPCE- Replaced the mechanical seal 2 VC Pump ME-0453 gland plate - Discharge end.

1-22-017 CL supply to D2 pipe 0304407 Replaced 2 sections of 6" pipe. 3 CL 1-22-018 12 BATP 0304096, EEC- Replaced the mechanical seal 2 VC

_ 1266 gland plate and backing plate. . -

1-22-021 Charging Pump 0303035 Replaced plungers in spare 2 VC Packing Assy. charging pump packing assemblies.

1-22-024 Snubber 0004270 Replaced piston and cylinder. yes SN 1-22-025 Snubber 0004271 Replaced piston. yes SN 1-22-026 Snubber 0101496 Replaced piston and cylinder. yes SN 1-22-028 Snubber 0201883 Replaced piston. yes SN 1-22-029 Snubber 0201884 Replaced piston. yes Snubber 1-22-030 Snubber 0201885 Replaced piston. yes SN 1-22-031 Snubber 0201887 Replaced piston. yes SN 1-22-032 Charging Pump 0309814 Replaced plungers and gland 2 VC Packing Assy. plate in spare charging pump packing assemblies.

Section 8. Repair/ Replacement Activities Page 1

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1 CYCLE 21

SUMMARY

REPORT 1-22-033 11 CL Strainer 0300326 Replaced valve and flange 3 CL Backwash Valve (2") bolting.

1-22-039 12 BATP 0309640, SPCE- Replaced the mechanical seal 2 VC ME-0453, EEC- gland plate.

1266 1-22-040 121 Cont. Rm ChId. 0300884 Replace flange fasteners. 3 ZH Wtr. Pmp Disch. Flow Ind.

1-22-041 Spare Charging Pump 0312062 Replaced packing assemblies. 2 VC Packing Assemblies 1-22-042 Spare CS Pump 0400361, EEC Replaced mechanical seal and 2 CS 1076 gland plate and gland fasteners.

1-22-043 Charging Pump 0400185 Replaced plungers in spare 2 VC Packing Assy. charging pump packing assemblies and gland plates.

1-22-044 RHR to 11 CS Orifice 0309942, EEC- Replaced flange fasteners. 2 RH 1389 .

1-22-045 RHR to 12 CS Orifice 0309967, EEC- Replaced flange fasteners. 2 RH 1389 1-22-046 12 RHR Pump Dschg. 0309713, EEC Replaced flange fasteners. 2 RH Check 1190 1-22-048 11 RHR Pump 0310689, EEC Replaced flange fasteners. 2 RH Suction Check 1190 1-22-049 Snubbers 1, 2, 3, & 4 0310359, Removed spring hangers and 1 SG 0310432, DCP associated hardware and 03RC02 mounting beams, installed vertical supports, replaced mounting fasteners of the SG snubbers and upper lateral support ring flanges as necessary.

1-22-050 Vertical Supports 0310357, Removed spring hangers and I SG 0310431, DCP associated hardware and 03RC02 mounting beams, installed vertical supports, replaced mounting fasteners of the SG snubbers and upper lateral support ring flanges as necessary.

1-22-051 Rupture Restraint 0310470, DCP Permanent removal of the RCS 1 RC 03RC02 cross over leg rupture restraints.

1-22-052 Rupture Restraint 0310468, DCP Permanent removal of the RCS 1 RC 03RC02 cross over leg rupture restraints.

1-22-053 Spring Hanger 0310333, Removed and reinstalled portions 2 SB 0310556, DCP of the steam generator blowdown 03SG01 piping and permanently removed a spring hanger. Modified Support RBDH-387.

1-22-054 Sway Strut 0310334, Removed and reinstalled portions 2 SB 0310557, DCP of the steam generator blowdown 03SG01 piping. Replaced a spring hanger with 2 rigid restraints. Modified the wall bracket for a spring hanger. Replaced a section of 2" piping and one 90 deg. el..

Modified 2" line support.

Section 8. Repair/ Replacement Activities Page 2

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT I CYCLE 21

SUMMARY

REPORT 1-22-055 Old Steam Generator 0310373, Replaced the primary side of the 1 RC 0310445, Steam Generator.

0310437, DCP 03RC02, DCP 03SG01 1-22-056 Old Steam Generator 0310372, Replaced the primary side of the 1 RC 0310442, Steam Generator.

0310436, DCP 03RC02, DCP 03SGOI 1-22-057 Original Steam 0310379, Piping was removed and 2 MS, SG Generator 0310472, reinstalled in support of the 0310229, installation of the secondary side 0310231, DCP of the replacement steam 03SGOI generator. The rigid restraint was modified to remove the rigid band.

Weld build up in the counterbore was also performed.

1-22-058 Original Steam 0310375, Piping was removed and 2 SG, MS Generator 0310471, reinstalled in support of the 0310229, installation of the secondary side 0310231, DCP of the replacement steam 03SG01 generator. The rigid restraint was modified to remove the rigid band.

1-22-059 Aux. Feed line 3-AF- 0310381, Piping was removed and replaced 2 AF, FW 11 3010474, in support of the installation of the 0310228, DCP secondary side of the 03SG01 replacement steam generator.

1-22-060 Aux. Feed line 3-AF- 0310383, Piping was removed and 2 AF, FW 12 3010477, reinstalled in support of the 0310228, DCP installation of the secondary side 03SG01 of the replacement steam

.generator.

1-22-061 Column 1 0310360, Modified the support column I SG 0310433, DCP swivel adapter and bumper 03RC02 blocks.

1-22-062 Column 1 0310363, Modified the support column 1 SG 0310435, DCP swivel adapter and bumper 03RC02 blocks.

1-22-063 12 RHR Discharge 0309712, EEC- Replaced body to bonnet 2 RH Pump Line valve 1359 fasteners.

1-22-064 11 RHR HX Tube Inlet 0209698, EEC- Replaced body to bonnet 2 RH 1359 fasteners.

1-22-065 11/12 RC PMP Dch 0304370, EEC- Replaced relief valve for IST 2 VC relief valve 1310 testing.

1-22-066 SG Snubber Block 0309378 Replaced valve block. 2 SG Valve 1-22-067 SG Snubber Block 0309311 Replaced valve block. 2 SG Valve 1-22-068 Steam Gen. 3" 0309476, Install external recirc. piping and 2 SG external recirc. Line 0309477, valve.

DCP03SGO5 _ _ _

1-22-069 Steam Gen. 3" 0309476, Install external recirc. piping and 2 SG external recirc. Line 0309478, valve.

DCP03SGO5 Section 8. Repair/ Replacement Activities Page 3

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT I CYCLE 21

SUMMARY

REPORT 1-22-070 12 RHR Crossover 0309711, EEC- Replaced body to bonnet 2 RH Inlet 1505 fasteners.

1-22-071 11 RHR HX Outlet 0310190, EEC- Replaced body to bonnet 2 RH 1505 fasteners.

1-22-072 12 MD AFW PMP 0302035 Replaced body to bonnet 3 AF ISuct. fasteners.

1-22-073 11 CC Heat 0309410, Replaced end flanges and covers, 3 CC Exchanger 0309412, attached lifiting lugs to the end 0306712 covers, and performed shell weld repairs as necessary to remove pitting of internal surfaces.

1-22-074 CC Heat Exchanger 0200466, Attached lifting lugs to the end 3 CC end cover plates 0309418, covers that will be installed at the 0405720 next refueling outage.

1-22-075 12 Containment FCU 0403586 Replaced flange fasteners. 3 CL 1-22-076 11 Excess Letdown 0300316, EEC- Replaced flange to head 1 VC HX 1196 fasteners.

1-22-077 122 CR Chilled Wtr. 0300828 Replaced discharge flange 3 ZH

_ Pmp. fasteners.

1-22-078 6" Containment Spray 0303945, Added recirculation lines to 2 CS Piping 0303946, Containment Spray piping.

0303949, Removed piping support.

DCP03CS02 Replaced support bolting on 11 &

12 CS pumps.

1-22-079 11 SG MS HDR Relief 0403587, EEC- Replace flange fasteners. 2 MS Valve 1096 1-22-080 11 Containment Spray 0301139 Replaced mechanical seal 2 CS Pump icluding gland plate.

1-22-081 12 BATP 0407196, SPCE- Replaced the mechanical seal 2 VC ME-0453 gland plate.

1-22-082 11 MSIV 0407276 Replaced disc. 2 MS 1-22-085 Spring Hanger 0407291 Reassembled spring hanger. 2 AF 1-22-086 11 RHR Heat 0407778 Replaced flange fasteners. 2 RH l Exchanger 1-22-087 RCS Lp B hot leg 0407227 Replaced body to bonnet I RH RHR Sup. fasteners.

1-22-088 11 Charging Pump 0401076 Replaced charging pump packing 2 VC assemblies.

1-22-089 12 BATP 0407257 Replaced the mechanical seal 2 VC gland plate and 1 casing fastener assembly.

1-22-090 AF piping 0407376 Corrected piping configuration for 3 AF rupture disc holding flanges.

1-22-091 Charging line isolation 0305017 Replaced valve. 1 RC valve 1-22-093 Main Steam Line WO-0407875 Weld build up of eroded area. 2 MS 1-22-094 Main Steam Line WO-0407874 Weld build up of eroded area. 2 MS 1-22-095 RCP Seal Rtm. 0400020 Replaced body to bonnet 2 VC Isolation Valve fastener.

1-22-096 Cooling water line 0407857 Replaced Fan Coil Unit piping 3 CL spool piece with new pipe and

. fittings.

Section 8. Repair/ Replacement Activities Page 4

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 1 CYCLE 21

SUMMARY

REPORT 1-22-097 Hi/Lo Head SIS to 12 0407938, EEC- Replaced the disc assembly. I St RX Vessel Nozzle 1546 Check Valve 1-22-099 11 Seal Wtr Injection 0408070 Replaced Check Valve. 1 VC Check (2")

1-22-101 1Seal Water HX Inlet 0408126, EEC- Replaced the valve bonnet and 2 VC 1554 fasteners.

1-22-102 VC System Hanger 0408112 Repair of weld on integral 1 VC attachment.

1-22-103 Si System Hanger 0408118 Repaired box support. 2 Si 1-22-104 Si System Hanger 0408114 Repair of weld on integral 1 Si attachment.

1-22-105 12 BATP 0408152, SPCE- Replaced the mechanical seal 2 VC ME-0453 gland plate.

1-22-107 13 Charging Pump 0408547 Replaced assemblies 19, 20, 21 2 VC with rebuilt assemblies 7, 8, and 9.

1-22-108 Rx Head Conoseal 0408797 Replaced Marmon Clamp, 1 RV

34 Fasteners, and Male Flange, and Jackscrews.

1-22-110 1 Pressureizer PORV 0408838 Replaced plug and body to bonnet 1 RC control valve fasteners.

1-22-111 11 and 12 RCP 0408894, ECN Tack welded shims in place. 1 RC tension/copmpression 03RC02-ECN-01 tie rods 1-22-112 MS Safety Valve 0309936, EEC- Replaced studs and installed 2 MS 11096 Superbolt nuts.

Section 8. Repair/ Replacement Activities Page 5

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-054

.9. Remarks This work is in suport of the Unit 1 Steam Generator Replacement Project.

CERTIFICATE OF COMPLIANCE We certify that the statements made In the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp Certificate of Authorization No. *' 4 Expiration Date

. Signed . ASME Program Enqineer Date _______ _ _

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnprtn n - and employed byHSR lnsp rnd Ins DCo of Connetticrit of Hartford Conn. have inspected the components described in this Owner's Report during the period o41JevAJoLI to 03JAAIcOS , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xi.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

J ,g-. )2' Commissions _ _ _raGs A J__l _ _ _ _

Inspectors'Siinature <) National Board, Province and Endorsements Date 4 LS(in.<;

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-054

1. Owner Nuclear Management Company, LLC Date 12/14/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0310334, 0310557, DCP 03SG01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by SGT Ltd.

Type Code Symbol Stamp NPT Name 400 S. Tyron St. Suite 2100, Charlotte, NC 28285 Authorization N-3090-1 Expiration Date 6/4/07 Address

4. Identification of System SB Code Class 2

5. (a) Applicable Construction Code B31.1 1998 Edition Addenda Code Case (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Spring Hanger Basic Engineering RBDH-378 Removed Sway Strut Grinnel RBDH-378A Installed l }

Sway Strut Grinnel RBDH-378B Installed Spring Hanger support RBDH-373 Corrected l SGB line 2-SB-2 2-SB-2 Corrected Line Support RBDH-3 Corrected i I

7. Description of Work Removed and reinstalled portions of the steam generator blowdown piping. Replaced a spring hanger with 2 rigid restraints. Modified the wall bracket for a spring hanger. Replaced a section of 2" piping and one 90 deg. el.. Modified 2" line support.

8. Tests conducted: Hydrostatic HIS Pneumatic l Nominal Operating Pressure l Exempt I 0

Other l Pressure 1360 psi Test Temp. 84 F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

1

9. Remarks PRAIRIE ISLAND NUCLEAR GENERATING PLANT

. FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY This work is in suport of the Unit 1 Steam Generator Replacement Project.

ITEM 1-22-053 I

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp ,.//4 ..

Certificate of Authorization No. J4//,9 Expiration Date Signed . ASME Program Engineer Date /2// 4_

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnp6-nt; and employed byHSR lnsp 2nd Ing Co of Connerticut of Hartford Conn. have inspected the components described in this Owner's Report during the period ohoIUAjOkA to 03.1AM d!; , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions de6 ,fo25 but mJd g Ienector's Signa re : National Board, Province and Endorsements Date /lo:s

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-053

1. Owner Nuclear Management Company, LLC Date 12/1412004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name

- 1717 Wakonade Dr. E, Welch Minnesota 55089 0310333, 0310556, DCP 03SGO1

- Address Repair Organization P.O. No., Job No., etc

3. Work Performed by SGT Ltd.

Name NaeType Code Symbol Stamp NPT 400 S. Tyron St. Suite 2100, Charlotte, NC 28285 Authorization N-3090-1 Address Expiration Date 6/4/07

4. Identification of System SB Code Class 2

5. (a)Applicable Construction Code B31.1 1998 Edition Addenda Code Case (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer NaVI Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Spring Hanger Basic Engineering RBDH-385 Removed O SG BD piping 2-SB-1 Removed L.

SG BD piping 2-SB-1 Installed L Spring Hanger Basic Engineering RBDH-387 Corrected

7. Description of Work Removed and reinstalled portions of the steam generator blowdown piping and permanently removed a spring hanger. Modified Support RBDH-387.

8. Tests conducted: Hydrostatic r3 Pneumatic n Nominal Operating Pressure g Exempt g 0

Otherrl Pressure 1360 psi Test Temp. 84 F Other. n/a t . - !

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND'NUCL'EAR GENERATING PLANT' FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-052

9. Remarks This work is insupport of the Unit 1 Steam Generator Replacement.

CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp .. .

Certificate of Authorization No. *//a _ _ Expiration Date Signed (7. ASME Program Engineer Date _ __? _____ _

Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnrcntnt and employed byHSR Insp and Ins Qo of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period ?' MAs o4 to Os JAqJ s , and state that to the best of my knowledge and belief,-the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor, his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions x8 Qc6is Addj qsrl~

Inspectors Sibnature National Board, Province and Endorsements Date AnSLalM bCS , q KJ

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-052

1. Owner Nuclear Management Company, LLC Date 12/16/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0310468, DCP 03RC02 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by SGT Ltd.

Name NaeType Code Symbol Stamp NPT 400 S. Tyron St. Suite 2100, Charlotte, NC 28285 Authorization N-3090-1 Address Expiration Date 6/4/07

4. Identification of System RC Code Class 1

5. (a)Applicable Construction Code n/a n/a Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Rupture Restraint H-1 Removed Rupture Restraint H-2 Removed _

7. Description of Work 'Permanent removal of the RCS cross over leg rupture restraints.

8. Tests conducted: Hydrostatic - Pneumatic 0 Nominal Operating Pressure Ej Exempt i Other [] Pressure psi Test Temp. °F Other n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1)size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM -NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-051

9. Remarks This work is in support of the Unit 1 Steam Generator Replacement.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp -

Certificate of Authorization No //j Expiration Date Signed ASME Proqram Engineer Date _-_ __ _/__/_

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of - Minnontn and employed byHSR Insp and Ins Co of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period j4fto4 to..

bSJq4oS -, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Irs EiQ tor's Signatur Commissions 4t IUS MA 4 :1A National Board, Province and Endorsements va *s V_%A

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNERIS REPORT FOR REPAIR/ REPLACEMENT ACTIVITY' ITEM 1-22-051

1. Owner Nuclear Management Company, LLC Date 12116/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0310470, DCP 03RC02 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by SGT Ltd.

Name NaeType Code Symbol Stamp NPT 400 S. Tyron St. Suite 2100, Charlotte, NC 28285 Authorization N-3090-1 Address Expiration Date 6/4/07

4. Identification of System RC Code Class 1

5. (a) Applicable Construction Code n/a n/a Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Rupture Restraint H-1 Removed _ II Rupture Restraint H-2 Removed EJ

7. Description of Work Permanent removal of the RCS cross over leg rupture restraints.

8. Tests conducted: Hydrostatic 2 Pneumatic - Nominal Operating Pressure g Exempt i Other [3 Pressure psi Test Temp. °F Other n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

I I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-050

9. Remarks These activities are in support of the 11 Steam Generator Replacement Project.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp Certificate of Authorization No. t/,J Expiration Date Signed , ASME Program Engineer Date /2_________

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnp-ntq and employed byHSR lnsp-and Ins Co of Connrctictit of Hartford Conn. have inspected the components described in this Owner's Report during the period 02 Ju4 atI to

_1_t___o_ _ , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and correctivejmeasure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commission: s isS IlOSS AA, (AA ms DateIn srftecr's SQatureI ' , - NB Pao Daten r tt LI A 47 , Vn" , -

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-050 I

1. Owner Nuclear Management Company, LLC Date 1211412004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0310357, 03310431, DCP 03RC02 Address Riepair Organization P.O. No., Job No., etc

3. Work Performed by SGT Ltd.

Name Name Type Code Symbol Stamp NPT 400 S. Tyron St. Suite 2100, Charlotte, NC 28285 AuthorizatlhDon N-3090-1 Expiration Date 6/4107 Address I

4. Identification of System SG Code Class s 1

5. (a) Applicable Construction Code AISC 9th Edition, ASME , 1995 Edition Vill Addenda 96 Code Case (b) Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None _ . .

6. Identification of Components

[Component Name I Manufacturer l Manufacturer I Nat'l Bd #

7. Description of Work Removed spring hangers and associated hardware and mounting beams, installed vertical supports, replaced mounting fasteners of the SG snubbers and upper lateral support ring flanges as necessary.

8. Tests conducted: Hydrostatic E Pneumatic 0 Nominal Operating Pressure El Exempt i Other[]- - Pressure psi TestTemp. °F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. xI1 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3)each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT

FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY

- ITEM 1-22-049

9. Remarks These activities are in support of the 12 Steam Generator Replacement Project.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp I/z Certificate of A oExpiration Date Signed ASME Program Engineer Date __ _4_, __ _

Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnpntn and employed byHSR Insp and Ins Co of Connenrtintjt of- - Hartford Conn. have inspected the components described in this Owner's Report during the period 02oJu.s cA to

___ Me___4 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owners Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Inspector's ignature Commissions IB A-qclS f4JI.

ft19l4 National Board, Province and Endorsements Date V Ins2' i

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-049

1. Owner Nuclear Management Company, LLC Date 12/16/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0310359, 0310432, DCP 03RC02 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by SGT Ltd.

Type Code Symbol Stamp NPT Name 400 S. Tyron St. Suite 2100, Charlotte, NC 28285 Authorization N-3090-1 Address Expiration Date 6/4/07

4. Identification of System SG Code Class

5. (a) Applicable Construction Code AISC 9th Edition, ASME , 1995 Edition Vill Addenda 96 Code Case (b) Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Yr Built Corrected, ASME Removed, or Code Installed Stamp Snubbers 1, 2, 3, & 4 Corrected I Spring Hangers Vertical Supports Upper Lateral Support

7. Description of Work Removed spring hangers and associated hardware and mounting beams, installed vertical supports, replaced mounting fasteners of the SG snubbers and upper lateral support ring flanges as necessary.

8. Tests conducted: Hydrostatic LI Pneumatic 0 Nominal Operating Pressure E Exempt 3 Other [] Pressure psi Test Temp. ° F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 'in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-048

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made In the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp Av 9 4-Certificate of Authorization No. / /2 Expiration Date Signed zASME Poqram Engineer Date __ __0_/_a_

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of MinnPnt -.- and employed byHSR Insp ;nd Insc Co of Connectictit of Hartford Conn. have inspected the components described in this Owner's Report during the period _S8'JV04 to

/QJalS , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI. - -

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a l6ss of any kind arising fronior connected with this inspection.

Commissions AAgO1S A)I mm cI9.9/

In ector's Signbture . : National Board, Province and Endorsements Date _ _ _ _ _ _ _ /?9 __5 K]' J

AL PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY0 ITEM 1-22-048

1. Owner Nuclear Management Company, LIC Date 11130/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0310689, EEC 1190 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name Type Code Symbol Stamp N/A Same Authorization NMA Address Expiration Date N/A

4. Identification of System RH Code Class . V 2

5. (a) Applicable Construction Code B16.5 ,, Edition Addenda Code Case (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer NatVl Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 11 RHR Pump Suction Check RH-3-2 Corrected El_

7. Description of Work Replaced flange fasteners.

8. Tests conducted: HydrostaticE Pneumaticn Nominal Operating Pressure Exemptsa Other Pressure Io'0 psi TestTemp. oel- F Other: 1s NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT-FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-046

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp Certificate of Au N A/ Expiration Date Signed . ASME Program Engineer Date /O/___

Owner or Owners Designee Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnqnt- - and employed byH-4 ln;p nnri lnt Cn of ConnnPtirnft of Hartford Conn. have inspected the components described in this Owner's Report during the period 6J6j.U 0o4 to

/3 omen oq ,and state that to the best of my knowledge and belief, the Owner Was performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressedor implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Inpector's Signatur .

Cdmrhissions 4,I "4A&/'

National Board, Province and Endorsements Date eL.4A ' n

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY.

ITEM 1-22-046

1. Owner Nuclear Management Company, LLC Date 10/11/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0309713, EEC 1190 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System RH Code Class 2

5. (a) Applicable Construction Code B16.5 , Edition Addenda Code Case (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer- Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 12 RHR Pump Discharge Check Crane RH-3-3 Corrected _

7. Description of Work Replaced flange fasteners.

8. Tests conducted: Hydrostatic M PneumaticLI Nominal Operating Pressure ExemptDJ Other Cl Pressure psi Test Temp. 0F Other NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Fr FORM NIS-2 OWNER'S REPORT FOR REPAIRI REPLACEMENT ACTIVITY

9. Remarks ITEM 1-22-045 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp A/4-Certificate of Authorization No. A/1 Expiration Date Signed 6 2 f . ASME ProgramEngineer Date _ _ _ _ __ _

Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of - Minneots and employed byHsR-nsp nd Ing Co of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period ,23 Juot. 04 to

________ , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI. - -

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

I ?QQZI) ~ Commissions &TB~SAl i t29i

'0 tspector's tnature- National Board, Province and Endorsements Date 49 . ,.Zioq

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-045

1. Owner Nuclear Management Company, LLC Date 11/29/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 - of 2

- Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0309967, EEC 1389 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name Type Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date N/A

4. Identification of System RH Code Class 2

5. (a)Applicable Construction Code B16.5 - Edition Addenda Code Case (b) Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components lComponent Name l Manufacturer l Manufacturer l Nat'l Bd l Other ID Yr Built I Corrected, ASME IlName ISerial #

RHR to 12 CS Orifice I I

7. Description of Work Replaced flange fasteners.

8. Tests conducted: Hydrostatics PneumatIcD Nominal Operating Pressure g Exempt J Other E] Pressure psi Test Temp. 0 F Other:

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS'2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-044

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp- - A-Certificate of Aut0. -/,Expiration Date Signed . ASME Program Engineer Date ______

Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State -or Province of___ min__ _n ~ _ _ -_ _ and employed byHSR lnsp and In. Co of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period - 64JVLOtQ to 14ccro+ , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from 6Fconnected with this inspection.

Commissions A (A Mq2,4 Insp ct Signature tj National Board, Province and Endorsements Date (Arhb M I, A

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/. REPLACEMENT ACTIVITY ITEM 1-22-044

1. Owner Nuclear Management Company, LLC Date 10111/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0309942. EEC-1389 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name NaeType Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date N/A

4. Identification of System RH Code Class 2

5. (a) Applicable Construction Code B16.5 Edition Addenda Code Case (b) Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xi Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp RHR to 11 CS Orifice Corrected _

7. Description of Work Replaced flange fasteners.

8. Tests conducted: Hydrostatic E PneumaticD Nominal Operating Pressure Z Exempt /

Other g Pressure psi Test Temp. °F Other-NOTE: Supplemental sheets in form of lists. sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

_ _ I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-043

9. Remarks n/a CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp .4114 Certificate of Authon;zaiy No. _Expiration Date Signed ,ASMEProgramEngineer Date C/,a 'o Owner or Owners Designee. Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnint' and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period OGAPE6'I to 2. MAw o64 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

L nspectors Sign ure Commissions As IQGus AmI MA OnV4 National Board, Province and Endorsements

! Date /I QClo4 I

I a-PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR-REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-043

1. Owner Nuclear Management Company, LLC Date 5/20/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0400185 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner NaeType Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code n/a n/a Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Natl Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Charging Pump Packing Assy. AJAX Spare 1969 Corrected L

7. Description of Work Replaced plungers in spare charging pump packing assemblies and gland plates.

8. Tests conducted: Hydrostatic 7, PneumaticD Nominal Operating Pressure r Exempt ,

Other : Pressure psi Test Temp. °F Other: n/a NOTE: Supplemental sheets in form of lists. sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-042 I

9. Remarks n/a CERTIFICATE OF COMPLIANCE We certify that the statements made In the report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp 4//j Certificate of Authorin No. 4//4 . Expiration Date Signed , ASME Program Engineer Date _ _ _ __

Owner or Owneres Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of MinnPont and employed byHeF lnsp and Ing Co of ronnecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 1s!MA Yoq to 1oJoJcs , and state that to the best of my knowledge and belief, the Ownerhas performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector- nor-his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described. in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

9 Ct2 commissions Ifil'?A11A OJOjT21-f

/hspector's ignature National Board, Province and Endorsements Date 5S

0 PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM N'IS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-042

1. Owner Nuclear Management Company, LLC Date 1/7/2005 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0400361, EEC 1076 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name NaeType Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date N/A

4. Identification of System CS Code Class 2

5. (a) Applicable Construction Code n/a n/a Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xi Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer NatI Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Spare CS Pump Ingersoll Rand 770 7 1971 Corrected D

7. Description of Work Replaced mechanical seal and gland plate and gland studs.

8. Tests conducted: Hydrostatic M Pneumatic Nominal Operating Pressure E Exempt r1Z Other Pressure psi Test Temp. 0 F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

FR NPRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT fOR-REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-041

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made In the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp S4I//A-Certificate of Authorization No. *'/A : Expiration Date -_._-_-_._-

Signed (Xv, ASME Program Engineer Date __o_____

Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or. Province of Minnpcnfa and employed byiSR Insp and Ins Co of Connnctictit of Hartford Conn. have inspected the components described in this Owner's Report during the period .OMAi o'u( to IDSCPo4 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xi.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

- rJ--ector'sir Dectate lSig natue Cup tu.nn&Q atAeNaioalBord - Commissions--

I . ..: ' ,

1e QcLs w Prvnce -- IC2.'l24noreet an

. National Board, Province and Endorsements Date gaoph6A ID ,_

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-041

1. Owner Nuclear Management Company, LLC Date 9/10/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E,Welch Minnesota 55089 0312062 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name Type Code Symbol Stamp NIA Same Authorization NMA Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a)Applicable Construction Code n/a n/a Edition Addenda n/a Code Case n/a (b)Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Spare Charging Pump Packing Corrected Assemblies

7. Description of Work Rebuilt packing assemblies.

8. Tests conducted: Hydrostatic n Pneumatic[] Nominal Operating Pressure [] Exempt W/

Other Cl Pressure psi Test Temp. OF Other:

NOTE: Supplemental sheets inform of lists, sketches, or drawings may be used, provided (1)size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report isincluded on each sheet, and (3)each sheet is numbered and number of sheets is recorded at the top of this form.

FORM NIS-2 OWNER'S REPORT:FOR'REPAIRI REPLACEMENT ACTIVITY ITEM 1-22-040

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp A14/

Certificate of Authorization No. W Expiration Date Signed .ASMEProgramEngineer Date. _______

Owner or Owners Designee, Title CERTIFICATE OF, INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by theNational Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnpqntq : and employed by HSB Insp. and Ins. Co. of Connecticut - -of -- Hartford Conn. have inspected the components described in this Owner's Report during the period c6 Fa6 0q to 3) 40&eo4 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this- certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

-~ O.C) --- Comhmissions 4 j&q AAuI Ins' ecr's Signature National Board, Province and Endorsements Date 4,L4 3t /

Li

n FOR NI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22.040

1. owner Nuclear Management Company. LI-C Date 8130/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet I of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0300884 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name Type Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date N/A

4. Identification of System ZH Code Class 3

5. (a)Applicable Construction Code B31.1 1967 Edition Addenda Code Case (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section X! Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Natli Bd Other 1D Yr Built Corrected, ASME Name Serial Removed, or Code Installed Stamp 121 Cont. Rm ChId. Wtr. Pmp Dieterich Corrected E Disch. Flow Ind.

7. Description of Work Replace flange fasteners.

8. Tests conducted: H-ydrostaticl PneumaticCj Nominal Operating Pressure ElExempt Other El Pressure psi Test Temp. 0OF Other~

NOTE., Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 In.x 11 in., (2)

Information In items 1 through 6 on this report is included on each sheet, and (3) each sheet Is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-039

9. Remarks n/a CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp Certificate of AuthorizationNo. Expiration Date Signed ASME Program Engineer Date ___/___

Owner or Owners Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of X -Minnpcnt: and employed byHsRRlnsp and ins Co nf Connertitt of Hartford Conn. have inspected the components described in this Owner's Report during the period o4JLo t4 to ROJULO4 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xi.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions i S A4t 1 4 1C Ins e Signature National Board, Province and Endorsements Date 9 1ir Ad Aft) ,

Kid0

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR- REPAIR/. REPLACEMENT ACTIVITY ITEM 1-22-039

1. Owner Nuclear Management Company. LLC Date 7/29/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0309640, SPCE-ME-0453, EEC-1266 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a)Applicable Construction Code n/a n/a Edition Addenda n/a Code Case n/a (b)Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'I Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 12 BATP Goulds 145-612 Corrected

7. Description of Work Replaced the mechanical seal gland plate.

8. Tests conducted: Hydrostatic L PneumaticE Nominal Operating Pressure g ExemptLi Other Li Pressure psi Test Temp. OF Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1)size is 8 1 /2 in. x 11 in., (2) information in items I through 6 on this report is included on each sheet, and (3)each sheet is numbered and number of sheets is recorded at the top of this form.

I PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY

9. Remarks ITEM 1-22-033 n/a CERTIFICATE OF COMPLIANCE We certify that the statements made In the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp A_//4 Certificate of Authorization No. 4/,12 Expiration Date Signed , ASME Program Engineer Date _ /3/_/°I Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of HIrtfnrf Cnnn have inspected the components described in this Owner's Report during the period J5 JA1J o04 to 6 sPk O0 '

and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described In the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

gK 1W Q

' ) Inspector's Sd~ature

- Commissions Al S-SAt-3 MA 41C~k-1 National Board, Province and Endorsements Date tiJ 0, , . ,m qM r

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-033

1. Owner Nuclear Management Company, LLC Date 3/31/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0300326 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner N-m Name Type Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date N/A

4. Identification of System CL Code Class 3

5. (a)Applicable Construction Code B31.1 1967 Edition Addenda n/a Code Case n/a (b)Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 11 CL Strainer Backwash Valve Jamesbury CV-31652 1970 Removed L (2")

11 CL Strainer Backwash Valve (2") 1 Jamesbury I CV-31652 I1999 Installed I

7. Description of Work Replaced valve and flange bolting.

8. Tests conducted: Hydrostatic PneumaticD Nominal Operating Pressure j Exempt3 Other El Pressure psi Test Temp. OF Other: n/a NOTE: Supplemental sheets inform of lists, sketches, or drawings may be used, provided (1)size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3)each sheet Isnumbered and number of sheets is recorded at the top of this form.

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY

9. Remarks ITEM 1-22-032 I

CERTIFICATE OF COMPLIANCE We certify that the statements made In the report are correct and this conforms to the requirements of the ASME Code. Section Xi.

Type Code Symbol Stamp 4//I 4 Certificate of Authorization No. Expiration Date Signed , ASME Program Engineer Date I_ ______

L-O0wner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by /sAsC r of Hartford Conn have inspected the components described in this Owner's Report during the period i'Eck to 2oFffc4 I and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

4tU0A - .9C Commissions As 12485 AM, mA aict1 IU Inspector's SigAature National Board, Province and Endorsements Date Date 0fM Ug24 - , 9rv--,

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-032

1. Owner Nuclear Management Company, LLC Date 12/10/2003 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0309814 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name NaeType Cede Symnbol Stamp N/A Same Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code n/a n/a Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) ApplIcable Section XI Code Cases None

6. Identification of Components Component Name I Manufacturer Manufacturer I Nat'l Bd # Other ID Yr Built I Corrected, l ASME

7. Description of Work Replaced plungers and gland plate in spare charging pump packing assemblies.

8. Tests conducted: Hydrostatic Li Pneumatic[] Nominal Operating Pressure [ Exempt Other E] Pressure psi Test Temp. OF Other:

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 In. x 11 in., (2) information in items 1 through 6 on this report Is Included on each sheet, and (3)each sheet Is numbered and number of sheets Is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT:FOR REPAIR/ REPLACEMENT ACTIVITY-ITEM 1-22-031

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp -_

Certificate of Authorization No. - Expiration Date Signed - ASME Program Engineer -.Date /d/4 __

Owner or Owners Designee. Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnihatn -and employed byHSR Insp and Ins Co of Connectictit of Hartford Conn. have inspected the components described in this Owner's Report during the period i(.ltuo3 to

_____s , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector'nor his employer makes any warranty, expressedor implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from'or connected with this inspection.

fi!Q, ad Commissions ' sRSmllS mA olq2t4 rnspector's S gnature - National Board, Province and Endorsements Date &OCOA co3 , Q4

)J

AL PRAIRIEISLAND NUCLEAR GENERATING PLANT-FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-031

1. Owner Nuclear Management Company, LLC Date 10/11/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E,Welch Minnesota 55089 0201887 Address Repair OrganizaUon P.O. No., Job No., etc

3. Work Performed by Owner Name Name Type Code Symbol Stamp NMA Same Authorization N/A Address Expiration Date N/A

4. Identification of System SN Code Class yes

5. (a)Applicable Construction Code B31.1 1967 Edition Addenda n/a Code Case n/a (b)Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Snubber Basic Engineers P1-386 1969 Corrected _

7. Description of Work Replaced piston.

8. Tests conducted: HydrostaticE PneumaticW Nominal Operating Pressure E ExemptE Other Pressure psi Test Temp. 0F Other: Snubber will be functionally tested after reassembly. Test results will be attached to the work order.

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1through 6 on this report is included on each sheet, and (3)each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2-OWNER'S`REPORT FOR F REPAIR/ REPLACE MENT ACTIVITY ITEM 1-22-030

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made In the report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp Certificate of Autho .Lo. Expiration Date Signed , ASME Program Engineer Date __ _ _ __O_ _

Owner or Owners Designee, Tite CERTIFICATE OF INSERVICE JNSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of - Minn fqt' and employed byHs3 Insp and Inc; Co of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period /4Ju4 As to a/ Aooe , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI. -

By signing this certificate neither the Inspector-nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions ,Q2 AoJ ffelLq Uhspector's Sigature National Board, Province and Endorsements.

Date Id I I

PRAIRIE ISLAND NUCLEAR GENERATING PLANT

FORM NIS-2 OWNER'S REPORT- FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-030

1. Owner Nuclear Management Company, 11C Date 10/11/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet I of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0201885 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name Type Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date N/A

4. Identification of System SN Code Class yes

5. (a)Applicable Construction Code B31.1 1967 Edition Addenda n/a Code Case n/a (b)Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c)Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Snubber Basic Engineers P1-399 1970 Corrected I

7. Description of Work Replaced piston.

8. Tests conducted: Hydrostatic J PneumaticE Nominal Operating Pressure Exemptns Other Pressure psi TestTemp. OF Other: Snubber will be functionally tested after reassembly. Test results will be attached to the work order.

NOTE: Supplemental sheets inform of lists, sketches, or drawings may be used, provided (1)size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3)each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM -NIS-2 OWNER'S REPORT-FOR-REPAIRI REPLACEMENT ACTIVITY ITEM 1-22-029

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp.*--

Certificate of Authorization No. 4/ Expiration Date Signed . ASME Program Engineer Date _________

Owner or Owners Designee Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of- Minnpntq -*and employed byHBR Insp and Ins Co of Connenticut of HartfordConn. have inspected the components described in this Owner's Report during the period 17APROs to

_________I , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes *any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owners Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

P0 Commissions A qass Ad MlP19a I ector's Signature - National Board, Province and Endorsements Date 7

(

PRAIRIE ISLAND NUCLEAR GENERATING PLANT l FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-029

1. Owner Nuclear Management Company, LLC Date 10/11/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0201884 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name Type Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date NMA

4. Identification of System Snubber Code Class yes

5. (a) Applicable Construction Code B31.1 1967 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components l Component Name Manufacturer Manufacturer I Natl Bd # l Other ID l Yr Built Corrected, l ASME Snubber

7. Description of Work Replaced piston.

8. Tests conducted: Hydrostatic F PneumatlcZ Nominal Operating Pressure D Exempt L Other 3 Pressure psi Test Temp. OF Other: Snubber will be functionally tested after reassembly. Test results will be attached to the work order.

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items. 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT-ACTIVITY ITEM 1-22-028

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report ire correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp A//A Certificate of Authorization No. i/ Expiration Date Signed . ASME Program Engineer Date _________

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding'a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State-or Province of __MinnP___ n_ - and employed byHsBR Insp :nd Ins Cn of Connentircut of Hartford Conn. have inspected the components described in this Owner's Report during the period o3AAPo3 to 03JA4AS , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI. -

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions nI D Ai ,n /92N '

tectors Sigiture . National Board, Province and Endorsements Date

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-028

1. Owner Nuclear Management Company, LIC Date 10/11/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E,Welch Minnesota 55089 0201883 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name Type Code Symbol Stamp NA Same Authorization N/A Address Expiration Date NMA

4. Identification of System SN Code Class yes

5. (a)Applicable Construction Code B31.1 1967 Edition Addenda n/a Code Case n/a (b)Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Snubber Basic Engineers P1-303 1969 CorrectedL

7. Description of Work Replaced piston.

8. Tests conducted: Hydrostatics PneumaticLI Nominal Operating Pressure g ExemptO Other 5 Pressure psi Test Temp. §F Other Snubber will be functionally tested after reassembly. Test results will be attached to the work order.

NOTE: Supplemental sheets in fbmm of lists, sketches, or drawings may be used, provided (1)size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3)each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT-FOR REPAIR! REPLACEMENT ACTIVITY ITEM 1-22-026

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made In the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp All*

Certificate of AuthorlzIvo. 4 Expiration Date Signed ASME Program Engineer Date / / 3 Owner or Owners Designee, Title ,

I I I CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 13J40oS to I3JA165S , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor, his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

I 4:te *-W- 0Commissions or's Signat

&I&?Sos MA, lqw National Board, Province and Endorsements Date AtA4 I Uo

I -If PRAIRIE ISLAND NUCLEAR GENERATING PLANT

-FORM NIS-2 OWNER'S REPORT-FOR REPAIR/ REPLACEMENT ACTIVITY1 ITEM 1-22-026

1. Owner Nuclear Management Company, LLC Date 1/13/2005 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0101496 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System SN Code Class yes

5. (a) Applicable Construction Code B31.1 1967 Edition Addenda nla Code Cases n/a (b) Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Natl Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Snubber Basic Engineers P1-499 1969 Corrected T. Description of Work Replaced piston and cylinder.

B. Tests conducted: HydrostaticZ PneumaticD Nominal Operating Pressure n Exempt 2 Other Pressure psi Test Temp. 0F Other: Snubber will be functionally tested after reassembly. Test results will be attached to the work order.

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITYl ITEM 1-22-025

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made In the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp -

Certificate of Authorization No. _4// Expiration Date -_-

Signed . ASME Program Engineer Date ILI___3_____ _

Owner or Owner's Designee,Title . . -

CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of MinnPvl- - and employed byHsR lnqp and Ing Co of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 31 ca. to ILI o-xow ,Iand state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector-nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or conniected with this inspection.

Commissions A.. l2

'(petor's Sig'iature . National Board, Province and Endorsements Date mom . 14 ,

KV

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY-ITEM 1-22-025

1. Owner Nuclear Management Company, LIC Date 10/13/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0004271 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name Type Code Symbol Stamp N/

Same Authorization N/A Address Expiration Date N/A

4. Identification of System SN Code Class yes

5. (a)Applicable Construction Code B31.1 1967 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Snubber Basic Engineers P1.476 1969 Corrected E_

7. Description of Work Replaced piston.

8. Tests conducted: Hydrostatic[] Pneumatic[ Nominal Operating Pressure [] Exemptij Other S] Pressure psi Test Temp. °F Other Snubber will be functionally tested after reassembly. Test results will be attached to the work order.

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT- FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-024

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp )/a-4 Certificate of Authoriza o Av 4 Expiration Date - __

Signed ($2". ASMEPrwram Engineer Date ___________

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or* Province of - MinnA:tn and employed byHSB lnqp and Ins Co of Conner-ticut of Hartford Conn. have inspected the components described in this Owner's Report during the period So or 2. to I5 rOrCT , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl. -

By signing this certificate neither the' Inspector nor his employer makes any 'warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissioins A-1 qn4 5 ,I9L, P-r I spector's Si.ature National Board, Province and Endorsements Date is , j2r

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-024

1. Owner Nuclear Management Company, LLC Date 10113/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0004270 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name Type Code Symbol Stamp N/A Same Authorization NMA Address Expiration Date NMA

4. Identification of System SN Code Class yes

5. (a)Applicable Construction Code B31.1 1967 - Edition Addenda n/a Code Case n/a (b)Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xi Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Snubber Basic Engineers P1-429 1969 Corrected _

7. Description of Work Replaced piston and cylinder.

8. Tests conducted: Hydrostatic[] Pneumatic[ Nominal Operating Pressure [ ExemptE]

Other si Pressure psi Test Temp. 0F Other Snubber will be functionally tested after reassembly. Test results will be attached to the work order.

NOTE: Supplemental sheets inform of lists, sketches, or drawings may be used, provided (1)size is 8 1 /2 in.x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3)each sheet is numbered and number of sheets is recorded at the top of this form.

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY

9. Remarks ITEM 1-22-021

]

n/a CERTIFICATE OF COMPLIANCE We certify that the statements made In the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp t//47 Certificate of Authorization No / Expiration Date Signed / , ASME Program Engineer Date / 1 __/_d_

Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesotn and employed by f-ISRC T of HartfnrHr renn have inspected the components described in this Owner's Report during the period 17J-M 03 to 'i(, IAKt - I and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xi.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

4NUAO L)

p. c.

Inspectors Sigrtalure Commissions JRe fift,&S JLwI n"J niitM National Board, Province and Endorsements Date J 113

I' PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-021

1. Owner Nuclear Management Company, LLC Date 6/14/2003 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0303035 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name NaeType Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code n/a n/a Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer I Nat'l Bd # Other ID Yr Built I Corrected, ASMEl

7. Description of Work Replaced plungers in spare charging pump packing assemblies.

S. Tests conducted: HydrostaticE Pneumatic[] Nominal Operating Pressure n Exempt Other n Pressure psi Test Temp. 0F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1)size is 8 1 /2 In. x 11 in., (2)

Information in items 1 through 6 on this report is Included on each sheet, and (3) each sheet is numbered and number of sheets Is recorded at the top of this form.

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-018

9. Remarks n/a CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp ////W Certificate of Authorization No. //AL Expiration Date Signed , ASME Program Engineer Date _ _ _ __ _

Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by I4 S C-7 of Hartford Conn. have inspected the components described in this Owner's Report during the period J4SJuI os to

,0, tJougvA, , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xi.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from'or connected with this inspection.

0tACCD C2 commissions I L. rI oI s AI,- niA ,9l' Ispector's Slnaue National Board, Province and Endorsements f1A r ttI . ,A

n PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-018

1. Owner Nuclear Management Company, LLC Date 7/10/2003 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0304096, EEC-1266 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name Type Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a)Applicable Construction Code n/a n/a Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None

6. Identification of Components i Component Name I Manufacturer l Manufacturer I NatVl Bd # l Other ID l Yr Built I Corrected, l ASME

7. Description of Work Replaced the mechanical seal gland plate and backing plate.

8. Tests conducted: Hydrostatic[] PneumaticWi Nominal Operating Pressure C Exempto Other , Pressure psi TestTemp. aF Other: Operational leakage test NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

I I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-017

9. Remarks n/a CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp Certificate of Authorization No. Expiration Date Signed ,ASME Program Engineer Date _ _ _ __ _

OwnerorOwner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HISR Cr of Hartford Conn. have inspected the components described in this Owner's Report during the period .jo3u os to G?)AuO3 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xi.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Gd(fr#h U) oA AD cQi Inspector's SignatO

.- _ Commissions & lQo0S AmJ tog q192, S

National Board, Province and Endorsements Date Mle A.- A

-I l s * * -* ,. q63--

I Fn PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIRI REPLACEMENT ACTIVITY ITEM 1-22-017

1. Owner Nuclear Management Company, LLC Date 6/30103 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0304407 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name NaeType Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date N/A

4. Identification of System CL Code Class 3

5. (a) Applicable Construction Code B31.1 1967 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases N416-1

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # OtherlD Yr Built Corrected, ASME l Name Serial # Removed, or Code Installed Stamp CL supply to D2 pipe j6-CL.30 Corrected 0

7. Description of Work Replaced 2 sections of 6" pipe.

8. Tests conducted: Hydrostatics Pneumaticn Nominal Operating Pressure Exemptn Other 7 Pressure psi Test Temp. F Other A system leakage test as allowed by Code Case N-416 will be conducted after the repair.

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3)each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-016

9. Remarks n/a CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp A1 Certificate of Authorization No0. _____________Expiration Date Signed ,ASME Program Engineer Date vS/13-A Owner or Owners Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by 158 Cr of Hartford Conn. have inspected the components described in this Owner's Report during the period 23Ju4 Os to 03 JU AJ oI , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection. -

i f .- 'Ae Commissions ,s1%1 '5P3r (nr J19sq J Inspector'sSign.ture National Board, Province and Endorsements Date - ,

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-016

1. Owner Nuclear Management Company, LLC Date 5/20/03 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0211311, SPCE-ME-0453 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner NaeType Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a)Applicable Construction Code n/a n/a Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xi Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Natl Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 11 Boric Acid Transf. Pump Goulds 145-611 Corrected

7. Description of Work Replaced the mechanical seal gland plate - Discharge end.

8. Tests conducted: Hydrostatic[] Pneumatic[] Nominal Operating Pressure [ Exemptvj Other [] Pressure psi Test Temp. F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY-ITEM 1-22-015

9. Remarks n/a CERTIFICATE OF COMPLIANCE.

We certify that the statements made inthe report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp 14 Certificate of Authorization Expiration Date Signed .ASME Program Engineer Date ____________S___

Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECT ION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by Hs.Sp Lr of Hartford Conn. have inspected the components described in this Owner's Report during the period 43 JUAJ 03 to 033 JwUA OS and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connedted with this inspection.

'O. (-)g /

171 -,~Commissions .-,I /9&P5 A"J1 N.-J t,2,2y Inspector's Signatdre National Board, Province and Endorsements Date

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-015

1. Owner Nuclear Management Company, LLC Date 5/20/03 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0210079, SPCE-ME-0453 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name NaeType Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code n/a n/a Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xi Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 11 Boric Acid Transf. Pump Goulds 145-611 Corrected _

7. Description of Work Replaced the mechanical seal gland plate - Suction end.

8. Tests conducted: Hydrostatic D, PneumaticD Nominal Operating Pressure 1Exempt Other 0 Pressure psi Test Temp. F Other n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3)each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY

9. Remarks ITEM 1-22-014 1

. I.

CERilFICATE OF COMPLIANCE We certify that the statements made In the report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp 2/-

Certificate of Authorizatio Ex14piration Date _____________

Signed AS1~ME Program Engineer Date ~~'9____

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 2V mAgoo3 to tkMA4 nyA and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section (l.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

(+/-:~.-...Anna x ) knspector's Signature Commissions - Nationa A4d ,P ron andq AE National Board, Province and Endorsements Date 7/2 I : tyn f

-.- .(J ......

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-014

1. Owner Nuclear Management Company, LLC Date Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0211231 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name NaeType Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code B31.1 1989 Edition Addenda n/a Code Case n/a (b) Appilcable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 11 Chg. Pmp. Dischg. Relief Crosby VC-28-1 Corrected _

7. Description of Work Replaced flange fasteners.

8. Tests conducted: Hydrostaticg Pneumaticfl Nominal Operating Pressure D Exempt Other f Pressure psi Test Temp. °F Other. n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3)each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT-FOR REPAIR/-REPLACEMENT.ACTIVITY

9. Remarks ITEM 1-22-013 I

CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this conforms to the- requirements of the ASME Code.Section XI.

Type Code Symbol Stamp Certificate of Auth.Expiration Date Signed ,ASME Program Engineer Date _________ _____

Owner or Owners Designee ,Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by 14S8 Cr of Hartford Conn. have inspected the components described in this Owner's Report during the period 41 nAvo? to caw-ro. , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

J-Nu'AAiF) Q.4

-Inqpector's Signatud Commissions SUBI c As - na ?nJ /9219 National Board, Province and Endorsements Date - 41c .

f- H PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR! REPLACEMENT ACTIVITY ITEM 1-22-013

1. Owner Nuclear Management Company, LLC Date 5/19/2003 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0211233 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name NaeType Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a)Applicable Construction Code B31.1 1989 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial Removed, or Code Installed Stamp 13 Chg. Pmp. Dischg. Relief Crosby VC-28-3 Corrected

7. Description of Work Replaced flange fasteners.

8. Tests conducted: Hydrostatic ! Pneumatic Nominal Operating Pressure Exempt V Other Pressure psi Test Temp. OF Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

L FORM NIS-2 *OWNER'S

9. Remarks PRAIRIE ISLAND NUCLEAR.GENERATING PLANT,'

REPORT FOR. REPAIR!

REPLACEMENT

... I ....

ITEM ACTIVITY 1-22-012 I

n/a CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this conforms to the requirements of the ASME Code. Section Xi.

Type Code Symbol Stamp Certificate of Auhriaio oExpiration Date Signed, ASME Program Engineer Date ________

,Owner or Owners Designee Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by lusIs cr of Hartford Conn, have inspected the components described in this Owner's Report during the period Is sfP 03 to is' seP6- , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xi.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

m Monsol f An.

-_: Commissions S A'wr 0-m

(?.t4l V

UInspector's Signasure National Board, Province and Endorsements Daltte

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT'FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-012

1. Owner Nuclear Management Company, LLC Date 3/31103 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0301238, SPCE-ME-0453, EEC-1266 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name NaeType Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code n/a n/a Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer NaVI Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 12 BATP Goulds 792A190-2 145-612 Corrected

7. Description of Work Replaced the mechanical seal gland plate.

8. Tests conducted:. Hydrostatic l Pneumatics Nominal Operating Pressure Exempt #

Other [] Pressure psi Test Temp. F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER &'REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-011

9. Remarks nla CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp Certificate of AuthorizatioExpiration Date Signed g , ASME Program Engineer Date _ _____ ,

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by 1-Ii3 Cr of Hartford Conn. have inspected the components described in this Owner's Report during the period )IQA)o

/8 to

/7 S_--P3 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions _& Iuns ,I qI gL Inspector's Sign ure National Board, Province and Endorsements Date I ap'4A L -, on K\J

I RI-PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-011

1. Owner Nuclear Management Company. LLC Date 6/181O3 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0302844, EEC-1250 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name NaeType Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code B31.1 1967 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Letdown Line Relief Valve Crosby JB-25-SPEC VC-25-2 1970 Removed Letdown Line Relief Valve Crosby 2J3-JLT-JBS-E1 VC-25-2 2002 Installed 15 SK

7. Description of Work Replaced valve.

8. Tests conducted: Hydrostatic Pneumatic. Nominal Operating Pressure Exempt /I Other [] Pressure psi Test Temp. 0F Other n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

I I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT -FOR . :... ;1 REPAIR/ . REPLACEMENT I. .

. .. .- .... ~.

.I ACTIVITY ITEM 1-22-010

9. Remarks n/a CERTIFICATE OF COMPLIANCE We certify that the statements made In the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp 4//-

Certificate of Authorization No. /4 Expiration Date Signed , ASMEProgram Engineer Date 1 _e3_.

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by of Hartford Conn. have inspected the components described in this Owner's Report during the period 2Lo lu& 0i to t.o Jon oi , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

- I Commissions Ar C1OS A$ M A J/9f ire National Board, Province and Endorsements

4. ,. .

0 I

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-010

1. Owner Nuclear Management Company, LLC Date 3/14103 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0300993 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner NameType Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date NMA

4. Identification of System VC Code Class 2

5. (a)Applicable Construction Code n/a n/a Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 12 Charging Pump Ajax 145-042 1969 Corrected

7. Description of Work Replaced charging pump packing assemblies.

8. Tests conducted: 'Hydrostatic- W PneumatlcD Nominal Operating Pressure a ExemptIV Other [ Pressure psi Test Temp. F Other: n/a NOTE: Supplemental sheets in forn of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

I I PRAIRIE ISLAND NUCLEAR GENERATING PLANT' FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY

9. Remarks ITEM 1-22-009 I

nia CERTIFICATE OF COMPLIANCE We certify that the statements made Inthe report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp Certificate of Authori atin-o. A l10 . . Expiration Date __ _ _ __ _ _ __ _ _ _ __ _ _ __ _ _ __ _ _ _

Signed ,ASME;Program Engineer Date / 9, ______

Owner or Owneres Designee , itle CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minhesota and employed by : of Hartford Conn. have inspected the components described in this Owner'slReport during the period 20 J-A oos to 20 Jug ot , and state that to the best of myjknowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and correcti ve measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

.. .~ Inspector'sC(ShJ

$ _B,

/1 A. o A )

j-nature

Commissions -JO fo'0s AAM MflJ ,%,92g-National Board, Province and Endorsements

_)

Date -_ 'f.

-1 I "I-go W-3 . . --

U I

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-009

1. Owner Nuclear Management Company, LLC Date 2110/03 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0211454 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name NaeType Code Symbol Stamp N/A Same Authorization NMA Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a)Applicable Construction Code B31.1 1967 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Mantifacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial# I Removed, or Code Installed Stamp 11 BATP Discharge Valve Grinnell VC-11-126 1970 Corrected [

7. Description of Work Replaced bonnet.

8. Tests conducted: Hydrostatic j Pneumatic7 Nominal Operating Pressure Exempt Other E] Pressure PsI Test Temp. F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

I

9. Remarks PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-008 nla CERTIFICATE OF COMPLIANCE We certify that the statements made In the report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp IV4'6' Certificate of Authorization No. aV Expiration Date-Signed & 4a<i. 4 ASME Program Engineer Date P - / Ao Owner or Owner's Designee lTitle CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by AIS8 Cjr of Hartford Conn. have inspected the components described in this Owner's Report during the period QSJUAJo3 to d95 JuM 0 3 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions' -is &VS A*-..' ' ri1A t0j 9 39 National Board, Province and Endorsements 0 IS 1") _.-- __. I

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-008 1I Owner Nuclear Management Company, LLC Date 2110/2003 Name 22 Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E. Welch Minnesota 55089 0211989 Address Repair Organization P.O. No., Job No., etc 31 Work Performed by Owner Type Code Symbol Stamp NIA Name Same Authorization NIA Address Expiration Date N/A

4. Identification of System VC Code Class 2 5i (a) Applicable Construction Code B31.1 1967 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacemi lent Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None 6; Identification of Components Component Name Manufacturer Manufacturer Natl Bd # Other ID Yr Built l Corrected, I ASME Name Serial #

11 Charging Pump Suction Piping NAVCO

7. Description of Work Replaced fasteners.

8. Tests conducted:, Hydrostatic i Pneumatics Nominal Operating Pressure F1 Exempt E/ f Other [ Pressure psi Test Temp. °F Other: n/a NOTE: Supplemental sheets in form of lists. sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S.REPORT FOR REPAIR/ REPLACEMENT ACTIVITY

9. Remarks ITEM 1-22-007 I

n/a CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp Certificate of Authorization No. 4-/ Expiration Date Signed ASME Program Engineer Date _ / ,__ _

Owner or Owner's Designee. Title .

CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by A'S83 C7 of Hartford Conn. have inspected the components described in this Owner's Report during the period /AS69o0 to

/___S____ . and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

(+/-NiAinOA 0 0-9 _ Commissions JA t 9-cm,, - AJ, -

National Board, Province and Endorsements Inspector's Sigahture DaL la :,, , ,'b0 '

K)J

l PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-007 II Owner Nuclear Management Company, LLU Date 1/23/03 Name 2 Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0202731 Address Repair Organization P.O. No., Job No., etc 3L Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Expiration Date N/A Address 4i Identification of System CL Code Class 3 5i (a)Applicable Construction Code B31.1 1967 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacemi lent Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None 6; Identification of Components Component Name Manufacturer Manufacturer rNatlBd# 1OtherlD Yr Built ICorrected, IASME Name Serial #

CL Piping NAVCO

7. Description of Work Replaced fasteners.

8. Tests conducted: HydrostaticQ PneumaticD Nominal Operating Pressure F] ExemptV Other F Pressure psi Test Temp. 0F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY

9. Remarks ITEM 1-22-006 I

CERTIFICATE OF COMPLIANCE We certify that the statements made In the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp A1/a Certificate of Authorization No. A144 Expiration Date Signed , ASME Program Engineer Date _ _____ I _ ___

Owner or Owneres Designee Tite CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by *&s C7 of Hartford Conn have inspected the components described in this Owner's Report during the period 2(eFcio1 to s25IAeoq and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

(J, e ,1,^s 09 (7)

. 4, _. e Inspector's Signature Commissions JR { 025ary2I 5 2g National Board, Province and Endorsements Ed2y Date _ L74Al w

(

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-006

1. Owner Nuclear Management Company, LLC Date 2/11/2002 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0201492 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name NaeType Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date N/A

4. Identification of System CL Code Class 3

5. (a) Applicable Construction Code b31.1 1989 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components l Component Name I Manufacturer Manufacturer I Nat'l Bd # Other ID Yr Built Corrected, ASME l

7. Description of Work Fabricate and install 2-CL-18. Replace flange bolting.

8. Tests conducted: Hydrostatic Pneumatic[] Nominal Operating Pressure I Exempt El Other [I Pressure 200 psi Test Temp. Amb. OF Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 In.x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORTf FOR REPAIR/ REPLACEMENT ACTIVITY

. .. .. . . . t -j , a4j - ........

ITEM 1-22-005

9. Remarks n/a CERTIFICATE OF COMPLIANCE We certify that the statements made Inthe report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp Certificate -ofAuth rz~~>Expiration Date_______________

Signed /) ~eL.ASME Program Engineer Date_____

Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by Pt)hEtrl 6 (N' of Hartford Conn. . X have inspected the components described in this Owner's Report during the period 1t 1 70 to

,_and state that to the best of my knowledge and belief, the Owner'has Oerformed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of prope I of ny kind arising from or connected with this inspection.

Commissions (Q(\)X-o 39 6 /JiV, T IVAEC

'--Inspector's Sign ure National Board, Province and Endorsements Date (/(0o3

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-005

1. Owner Nuclear Management Company, LLC Date 2/11/02 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0201494 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name NaeType Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date N/A

4. Identification of System CL Code Class 3

5. (a)Applicable Construction Code B31.1 1989 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No'Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # OtherID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp CL Piping NAVCO 2-CL-17 Corrected [

7. Description of Work Fabricate and install 2-CL-17 and replaced flange fasteners.

8. Tests conducted: Hydrostatic Pneumatic[] Nominal Operating Pressure [] Exemptn Other [ Pressure 200 Psi Test Temp. ambient F Other n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY

9. Remarks ITEM 1-22-004 1

n/a CERTIFICATE OF COMPLIANCE We certify that the statements made In the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp 4/zVA Certificate of Author lo. ,z. 4Expiration Date Signed , ASME Program Engineer Date 2/X915.14 _____

Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by ilsa cr of Hartford (Crnn have inspected the components described in this Owner's Report during the period Z2 S6Pa3 to 5sPd3 I and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

ZQ e40AAVO ) Oa Commissions d'6 CLS A41t o , 292!t

(/ nspector's SigrnatJkre National Board, Province and Endorsements I / *(.ok _

Date (=~So rat A A, _

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-004

1. Owner Nuclear Management Company, LLC Date 1/9/03 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0300064 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name NaeType Code Symbol Stamp N/A Same Autthorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code B31.1 1967 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp VC Pipe Support (3X) BE 1-CVCH- 1970 Corrected 1680

7. Description of Work Replaced bolt assembly.

S. Tests conducted: Hydrostatic [ PneumaticOl Nominal Operating Pressure r Exempt i Other [ Pressure psi Test Temp. °F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 In. x 11 in., (2)

Information in items 1 through 6 on this report Is included on each sheet, and (3) each sheet Is numbered and number of sheets Is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT -I FORM NIS-2 OWNER'S REPORT FORREPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-002

9. Remarks n/a CERTIFICATE OF COMPLIANCE We certify that the statements made In the report are correct and this conforms to the requirements of the ASME Code. Section Xl.

Type Code Symbol Stamp A-9 Certificate of Authorization No. a/a Expiration Date te Signed , <'4c' . ASME Program Engineer Date e;Z / 7 , _°O3 Owner or Owners Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by A/Sif j7- of Hartford Conn. have inspected the components described in this Owner's Report during the period 9/s/e2 to

_______ _ ,_and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of prope e or s of any kind arising from or connected with this inspection.

_ _ _ _ _ - _ - _ - _ - _ Commissions US vF72 /z-C7w',*,.W3 F6g-Ca)

Inspector's Signature - , National Board, Province and Endorsements Date . . _

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-002

1. Owner Nuclear Management Company, LLC Date 9118/2002 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E. Welch Minnesota 55089 0208641, 0115067, 01ZX01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name Type Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date N/A

4. Identification of System ZE Code Class 3

5. (a) Applicable Construction Code B31.1 1989 Edition Addenda n/a Code Case (b) Applicable Edition of Section Xl Utilized for Repalr/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer iManufacturer l Nat'l Bd # Other ID Yr Built Corrected, ASME Name l Serial Removed, or Code Installed Stamp 1 SI Pump Unit Cooler Krack 174-151 1971 Removed LI 11 SI Pump Unit Cooler Krack 174-151 1990 Installed El

7. Description of Work Replaced 11 SI pump motor unit cooler coils.

8. Tests conducted: Hydrostatic L Pneumaticn Nominal Operating Pressure i Exempt (]

Other [ Pressure 83 psi Test Temp. 44 F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-055-

1. Owner Nuclear Management Company, LLC Date 1211412004 Name

2. Plant Praire Island Nuclear Generating Plant -Sheet I of 2 Name

-1717 Wakonade Dr. E, Welch Minnesota 55089 - 0310373, 0310445, 0310437, DCP 03RC02, DCP 03SGO1 Address - - - - Repair Organization P.O. No., Job No., etc

3. Work Performed by SGT Ltd. Type Code Symbol Stamp NPT Name 400 S. Tyron St. Suite 2100, Charlotte, NC 28285 - Authorization N-3090-1

- Address - - Expiration Date 6/4107

14. Identification of System RC - Code Class 1

5. (a)Applicable Construction Code ASME IlIl , 1995 Edition Addenda 1996 -. - - .Code Case nla (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1989 With No Addenda' (c) Applicable Section Xl Code Cases N.416-2

6. Identification of Components Component Name Manufacturer Manufacturer NatVI Bd # Other ID Yr Built Corrected, ASME Name Serial # - . Removed, or Code

___ _ ___ ___ __ __ __ ___ __ __ ___ _ ___ __ Installed Stam p Old Steam Generator Westinghouse 1102 68-25 134-012 1968 Removed New Steam Generator Framatome GV/P1292 134-012 2003 Installed

7. Description of Work Replaced the primary side of the Steam Generator.

8. Tests conducted: Hydrostatic D Pneumatic n Nominal Operating Pressure - Exempt E]

Other -,Pressure 2235 psi Test Temp. NOT o F Other: n/a - - - .-

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

i , , l . ; 'I _ - - -.. .. . *A .

I'if

9. Remarks PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY This work is in support of the Unit 1 Steam Generator Replacement.

ITEM 1-22-055 I

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp ,/2 Certificate of Authoriz . ./do Expiration Date Signed (. , ASME Program Engineer Date A2//{ /y _

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnocrtn and employed byHRR lnsp nd Ilng Co of ronnprficut of Hartford Conn. have inspected the components described in this Owner's Report during the period l&JQLbq to

__ _A__OS , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions

' Lpector's Signature National Board, Province and Endorsements Date -A n 141

FORM N-1 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR VESSELS*

% As Required by the Provisions of the ASIAE Code,Section III, Division I Pg.1 of 4

s

_ _ _ __ .

1. M3nufactured and certified by FRAMATOME ANP - Usine dc Chalon St. Marcel 7nne Industrielle et nnuart 5-rti -71 SRORAINT MA RCET. - FR AwCE (Name and address of N Certificate Holder)

2. Manufactured for NORTHERN STATES POWER COMPANY:

(Name and address of Purchaser) 1717 WAKONADE DRIVE EAST-WELCH. MINNESOTA 55089-USA

3. Location of installation PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT I 1717 WAKONADE DRIVE EAST-WELCH, MINNESOTA 55089- USA (Name and address)'.' EE-G-DB-0568-B1

4. Type Vertical Heat Exchanecr 'GVPI 29i N/A EE-.G-DB-0572 -D 162 2004 (hork. or ver.) (tank, jacketed, heat. ex.) (Cert. Holder .erial nW) (CRN) (&'awing WI) (Nat1 Bd.n') (year buit)

5. ASME Code, Section 1II,Division 1 1995 1996 1 See Remarks # 19 (edition) (addenda date) (class) - (code case no.)

Items 6-10 Inclusive to be completed for single wall vessels, Jackets ofJacketed vessels, or shtlls of heat exchangers

6. Shell Set Supplementary sheet (page 3 of 4) - -68 3" (rarl *er nsj) (tensie streigth) (nan%Nrkness. (in.D (nirrndesign thkkness Cf.) (easto Cttb kc.} (tenob5 toverai) (ft SInc.))

- 7. Seams (lAn NALA- , ,WA- :. Yes Full (long..) (HT'.) (R7) (eff.%) (9grth) (H ') (RT) (n' of courses)

8. Heads SA 508 Gr3 Cl 2 90 KSi NIA N/A

((a) matl spec. n') (tensile strength) ((b) mat I spec. n (year built) (tensle stength) l l I I ^,2 .

l I Conical I

Slde to Location (top, Thickness Corro! slon Crown. Knuckle Eliiptical Apex Hemispherical Flat Pressure bottom. ends) Allowa nce Radius Radius Ratio Radius Diameter (convex or Angle concave) a - Top 3.54' 0.06- NIA N/A 211 N/A N/A N/A Concave I (b) Bottom N/A N/A NIA N/A N/A IWA N/A N/A N/A N/A.. , Ote .,.f~tnn N/A If removable, bolts used _v., ,s,, ec;>ucg y (matl, spec., rn', size, quantty) (describe or attach sketch)

9. Jacket closure: N'A (describe as ogee &weld, bar, etc. It bar, give dimensions, describe or sketch)

10. Design pressure' 1085 atmax.temp. 600 Min.pressure-testtemp. 70 Fneu, hydro. or comb. Test pressure

1357 (psi)* .-'F?. . (F) (Ps')

Items 11 and 12 to be completed for tube sections .. *. -

t 1.Tubesheets: SA 508 Gr 3 C 2 129.42- 21.46' Welded

- - (stationary, matll spec. n-) (dia. In.(subject to press.)) (thickness (in.)) (attachment (welded, bolted))

- I NA . .A - -. A N/A (floating. mati spec. n') (dia. (In.)) . (thickness (in.)) (attachment)

12. Tubes: SB 163 UNS 06690 0.75- 0.043' 4868 YU (matcI spec C') (00 (in.)) (thickness (inches or gage)) - (n) (type (straight or u))

Items 13 to 16 Inclusive to be completed forinner chambers offacketed vessels, or channels otheat exchangers

13. Shell: SA 508 Gr3 Cl 2 90 Ksi .. 5.66 5.4' 124.40' 15.35' matnL specnn9 (tensile stngtb) (nom #kkness In - () n design Mckness (h)) (5a. IDrn.)) (engthoveral) (ft&

hn))

14. Seams: N/A INIA -. NM - Sinale/Double Yes Full (long.(welded.Dbl..single) (HT'(yesorno) - (RT,) (efl.) (girth) . (T) (n- of courses)

15. Heads SA 508 Gr3 a 2 o KSI . . N WA

((a) matl spec. n-) (tensile strength) ((b) matl spec. N-)) (tensile strength) ((c)) rral spec n') (tensile strength)

Location Thickns n Radius Crown Knuckle Radius RatIo II Apex

-Elliptical ConicalAngle II Hemispherical Radius Flat Diameter (conrvessure convex I I I t II concave)

I (a) Top, bottom, ends I I I I , *I* *- .,," e I ': I I (b)Channel (c) Floating 1

I 5.29' N/A 1

I N/A N/A -N/A N/A J

N/A N/A I NiA NA I

I 65.26' N/A N/A N/A I Concave N/A I

I If removable, bolts used

A -.- .Otherfasfen!ng WNA (matl spec. nW. ske. quantfty) (describe orattach sketch)

16. Design pressure- 2485 at 650 Min. pressure-testtemp.: 70 Pneut.ydro.orconib.Testpres-ure 3107 (PSI) ('F) ~ (Ff) (psi)

Ifta ha o:e w c ie, b.

I If posmtweld beat treated. 2List other intemnal or extemnal pressure wiith coincident temperature vwhen applicable.

'Supplemental Information In form of lists, sketches, or drawings may be used provided (1) size is a ' xl1, (2) Informaton in items 1

. . through 4 on this Data Report Is Included on each sheetl (3) each sheet Is numbered and number of sheets Is recorded at top of this form.

1 (7198) )This form (E00038) may be obtained from the Order Dept., ASidE. 22 Law Drive, Box 2sco, Fairrield. NJ 07007-2300

FORM N-1 (Back - Pg 2 of 4) f Certificate Holders' Serial No GVIPI 292

17. Nozzles, inspection and safety valve openings: See supplementary sheet page 4 of 4

18. Supports: Skirt Mg Lugs N Legs N/A Other 4 su[pDort pads Attached Integral with channel head (yes or no) (quantity) (quantity) (describe) (where and how)

19. Remarks:

Code cases ares N-20-3 . N-71-16 . N411-1 . 2142. 2143. N4tl1-1 Primary hydrotest performed in shop: see attached N2 Data Reports GV/PI 292 (PIF) & GVIPI 292 (PSF)

Secondary hvdrotest performed on site: see attached N2 Data ReDort SG 12 - SIC 006 Girth weld SICO06 performed on site - N Stamp performed on site NCA-8322.b CERTIFICATION OF DESIGN JOSELITO O.CALLEVigna Design Specification certified by _ _ _ _ __ _ _ P.E. State virginia Reg. n 024373 Design Report certified by IHARRYT. HARRISON P.E StateVirginia Reg. n 040201255 CERTIFICATE OF SHOP COMPLIANCE We certify that the statements made in this report are correct and that this nuclear vessel confo s to the rules for construction of the ASME Code, Section IlIl, Division 1.

N Certificate of Authorization N N-2771 Expires January 29. 2006 Date '5 &,)Q ,r b d4 Name FRAMATOME ANP Signed (NCertificate Holder) (Authorized re sentative)

CERTIFICATE OF SHOP INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NEW-YORK and employed by ROYAL INSURANCE of CHARLOTTE. NORTH CAROLINA have inspected the component described in this Data Report on F-. 'ZOQ< and state that to the best of my knowledge and belief, the Certificate Holder has constructed this component Inaccordance with the ASME Code, Section Ill, Division 1.

By signing this certificate neither the inspector nor his employer makes any warranty, expressed or Implied, concerning the component described in this Data Report. Furtherm e neither the inspector nor his employer shall be liable in any manner for any ersonal injury or property damigpr a I opny kind arising from or connected with this Inspection.

Date t 0 *o..-

Signed St§-fA _

LI(j

_MU e t (Autthorzed Nuclear Inspec)

A____ _

__AdAA Commissions A.N NY5258-NB 12223 (Nall, Bd. (Ind. endorsements) and state or prov. And n)

CERTIFICATE OF FIELD ASSEMBLY COMPLIANCE We certify that the statements on this report are correct and that the field assembly construction of arts of this nuclear vessel conforms to the rules of construction of the ASME Code, Section 1II, Dvision 1.

NCertificate of Authorization n N-2771 Expires Januar 29. 2006 Date A \.dL.ame FRAMATOME ANP Signed IM t MN, C e r t i -fica -- o~lde)*-lhrer~cette V- 1-1 7 . -r. -. 1- -1 CERTIFICATE OF FIELD ASSEMBLY INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NEW YORK and employed by ROYAL INSURANCE of CHARLOTTE. NORTH CAROLINA have compared the statements In this Data Report with the described component and state that parts referred to as data items X-A 3.2 '0 4 not included in the certificate of shop inspection, hive been inspected by me on and that to the best of my knowledge and belief the Certificate Holder has constructed and assembled this component in accordance with the ASME Code, Section 1II,Division 1..

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the component described In this Data Report. Furthermo ,neither the inspector nor his employer shall be liable in any manner for an ersonal injury or proper ty or a of any kind arising from or connected with this inspection.

Da teX( Signed tVY' DI QO I Commissions A.N NY 5258 -NB 12223 (Auht-ored Nuclear Insopectorb (Nat'l 8d. (nd endorsements) and state or prov. and n-)

SUPPLEMENTARY SHEET 2

CERTIFICATE HOLDERS' DATA REPORT As Required by the Provisions of the ASME Code Section III, Division I Certificate Holder's Serial Nos. GV/PI 292 Pg. 3 of 4

1. Manufactured and certified by FRAMATOME ANP- Usine de Chalon/Saint Marcel

. (Name and address of Certifcate Holder)

Zone Industrielle ct Vrtuaire sud-71380 SATNT MARCEL - FRANCE

2. Manufactured for NORTHERN STATES POWER COMPANY (Name and address of Purchaser) 1717 Wakonade Drive East - WELCH, MiNNESOTA 55089 - USA

3. Location of Installation PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT I 1717 WAKONADE DRIVE EAST - WELCH. MINNESOTA 55089- USA tName and address)

4. Type Vertical Heat Exchanger GVJPI 292 N/A EE-G-DB-0572 -D 162 2004 (horlz. or vert) (tank, Jacketed, heat. ex.) (Cert. Holder serial n) (CRN) (drawing n') (Nat -Bd.n') (year built) 6 - Shell TABLE 1-SHELL MATERIAL Data Items Shell Mate'I ', Tensile' Nominal Minimum design dia. ID by Line N' designation atenspec. s thkes thickness (inch.)

-ft & inch.)

N, strength (inch.) ikesfnh) -(t&ic.

Lower shell SA 508 Gr3 Cl 2 90 KSi 2.73 2.6 10' 9.42-ntrmediate SA 508 Gr3 Cl 2 '90 KSi ' 2.73 2.6 10' 9.42-6 Conical shell SA 508 Gr3 Cl 2 90 KSi 3.72 3.6 14'0.32-Nozzle shell SA 508 Gr3 Cl 2 90 KSI 3.39 3.27 14' 0.32' Upper shell SA 508 Gr3 Cl 2 90 KSi 3.39 3.27 14' 0.32-k . i. -

Date l \ 'Name 'FCcx" &V Amp W_' Ps Sign~ed i"%

(Certificate Holder) ----: (Authorizea eiiresentative)

Date -q &)Ov Z 4 ... .. . . .

..A ;c. - r#- r' Signed (0 Q Commissions A. ,. r(12223 ' D "2f (Authorized Nuclear Inspector) INatl Board (Inc. Endorsements), State, Province and No)

. CI , I 1 I ! ` .1 ' I_", I '

i - ..

SUPPLEMENTARY SHEET CERTIFICATE HOLDERS' DATA REPORT As Required by the Provisions of the ASME Code Section III, Division 1 Cn-rtifir-alp Hnldke-t -Rowfal Nn-t- GV/PI 292 Pa. 4 of 4

1. Manufactured and certified by FRAMATOME ANP - Usine de Chalon/Saint Marcel (Name and address of Certificate Holder)

Zone Industrielle et portuaire sud- 71380 SAINT MARCEL - FRANCE

2. Manufactured for NORTHERN STATES POWER COMPANY (Name and address of Purchaser) 1717 Wakonade Drive East - WELCH, MINNESOTA 55089 - USA

3. Location of Installation PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT I 1717 WAKONADE DRIVE EAST - WELCH, MINNESOTA 55089-USA (Name and address) EE-G-DB-0568*1B

4. Type Vertical Heat Exchanger GV/PI 292 N/A EE-G-DB.0572 -D 162 2004 (hort.orvert.) (tank.Jacketed heatex.) (Cert.Holderserialn-) (CRN) (drawing n') (Natl Bd.n ) (year built) 17 - Nozzle inspection and safety valve opening Table 2 - Nozzles and Access Openings Purpose Quantity Dia. or Size Type flow Material Thickn Reinforcement Location

_ _ _ _ _ ___ _ _ _ _ _ _ _ _ attached c ns M aterialTh Mae al _ _ _ _ _

Prmary 2 18I Integral Integral SA 508 GO Cl 2 6.4" Integral Channel manwys egr fored A ~Gr3head Primary inlet 1 31.61" Integral Integral SA 508 Gr3 Cl 2 and 3.5"/12" Integral Channel

_ __ _ __ _ ogd SA 182 F316LIN 3.3' _ _ head___

Primary outlet 1 31.61" Integral otera SA 508 Gr3 Cl2 and 3.57 12' Integral hea

_____forged SA182 F316 LN 3.3" head___

SFA-5.5 AWS Lower shell Ifandholes 6 8" Built up Welded SFA-5.23 AWS 5.25 - Built up and

. F9P4-EEF2N-F2N shell nstrentationp InsruenatonFull 0.72 Set on penetration SA 105 0.64" N/A Lower and Nozzle shell comer weld shell Instrumentation Full Upper shell tap 1" 3 0.91" Set on penetration SA 105 0.67" N/A and Nozzle

_comer weld shell Blowdown Blowown 2 1.939" apsFullSet on penetration . SA 105 0.78" N/A Tubesheet 2" comer weld SecodaryFull m anwayy 2 18" Set in penetration SA 508 Gr3 Cl 2 . 6.78" Integral Upper shell manways ~~~~~~~~butt weld _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Full Feedwater 1 13.94' Set in penetration SA 508 GO3 Cl 2 6.t"1/1.6" Integral Nozzle shell

________ ___ ____butt weld Full Recirculation 1 2.63" Set in penetration SA 508 Gr3 Ca2 1.97/3.8" N/A Nozzle shell

_ _butt weld Steam Outlet 1 32" Integral Integral SA 508 Gr3 Cl 2 2.2"IlO.7 Integral Top head

__ _ _ __ __ __ _ _ __ __ __ _ _ _ _ _ _ _ __ _ ______ forged _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Date 9t LI Name FRAMATOM (Certi'icate Holder)

ANP Signed _

(Authorized rep seotatlve)

Date I( V\JoU. 2oC 4-Signed h i Commissions A NU. c\Ja QI22 f\e b'26 (Authorized Nuclear Inpector) [Natl Board (Inc. Endorsements). State, Province and Nol

I . I-

. i FORM N-2 CERTIFICATE HOLDERS' DATA REPORT FOR IDENTICAL NUCLEAR PARTS AND APPURTENANCES*

As Required by the Provisions of the ASME Code,Section III Not to Exceed One Day's Production Pg. 1 of .. 2

1. Manufactured and certified by SGT Ltd. 400 South Tryon Street Charlotte NC 28285 inamne end oddren of NPT Certificte Holder)

2. Manufactured for FRAMATOME ANP-Usine de Chalon St. Marcel Zone Industrielle et portuaire Sud - 71380 Saint Marcel - France

-name and address of purchaser)

3. Location of installation Prairie Island Nuclear Generating Plant Unit 1 1717 Wakonade Drive East Welch, MN 55089 ER80S-D2 (name and address)

4. Type BTMPPIINGV4020 E8018-NM2 90 ksin-nimum N/A 2004 ldrawing no.) (matL spec. no.) ftensil. strength) (CRN) lyear built)

5. ASME Code,Section III, Division 1: 1995 1996 1 N/A (edition) laddenda date) (classd (Code Case no.)

6. Fabricated in accordance with Const. Spec. (Div. 2 only) N/A Revision Date

- Re(no)

7. Remarks: Site Girth weld between conical shell and nozzle shell

8. Nom. thickness fin.) 3.39 Min. design thickness (in.) 3.27 Din. ID (ft & in.) 14' -0 5116" Length overall (ft & in.) N/A

9. When applicable, Certificate Holders' Data Reports are attached for each item of this report:

National National Part or Appurtenance Board No. Part orAppurlenance Board No.

Serial Number in Numerical Order Serial Number in Numerical Order (1) SG 12-S/C006 NIA (26)

(2) (27)

(3) (28)

(4) (29)

(30)

(6) 131)

(7) (32)

(8) (33)

(9) (34)

(10) (35)

(11) (36)

(12) (37)

(13) (38)

(14) (39)

(15) (40)

(16) (41)

(17) (42)

(18). (43)

(19] (44)

(20) (45)

(21) (46)

(22) (47)

(23) 148)

(24) (49)

(25) (50)

10. Design pressure 1085 psi. Temp. 600 eF. Hydro. test pressure 1357 psi /70'F at temp. IF (when applicable)

Supplemental information in the form of lists, sketches, or drawings may be used provided (1)size is 8'/2 x II.,(2) information in hemrs 2 and 3 on this Data Report is included on each sheet, (3)each sheet is numbered and the number of shees is recorded at the top of this form.

(7t98) . This form (E00040) may be obtained from the Order Dept, ASME. 22 Law Drive, Box 2300, Fairfield, NJ 07007-2300.

FORM N-2 (Back - Pg 2 of 2 )

Certificate Holder's Serial Nos. SG 12-S/C006 through CERTIFICATION OF DESIGN Design specifications certified by Joselito 0. Calle P.E. State Virginia Reg. no. 024373 twhen appilcabl)

Design report' certified by Harry T. Harrison P.E. State Virginia Reg. no. 040201255 when.r applicable)

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and that this ithes weld conforms to the rules of construction of the ASME Code,Section III, Division 1.

NPT Certificate of Authorization No. N-30901 Expires May 31, 2005 Date q . OL -..Name SGT Ltd.

(NNT Cartificate HolderSie Signed 2aa u ut &tiava CERTIFICATE OF INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of M11"ULUTA andemployedby f/Atr1aDi WreAN R/il¢I1 l' " 41 CoWvw FEWA&f7 Of fl.)rPru , cT have inspected these hems described in this Data Report on ' / f/a'i ,and state that to the best of my knowledge and belief, the Certificate Holder has fabricated these pans or appurtenances in accordance with the ASME Code, Section 111,Division 1. Each part listed has been authorized for stamping on the date shown above.

By signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, concerning the equipment described in this Data Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

Date el Signed _ZU4rA. a gd-kI (Airtlioried Nucler Inapeaor)

Commissions A18 /IL3 't-1t hAI' 2Od'21 -CEC JNWtL Od.lind. andoersementn) and etate or prov. and no.1

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-056

1. Owner Nuclear Management Company, LLC Date 12/14/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0310372, 0310442, 0310436, DCP 03RC02, DCP 03SG01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by SGT Ltd.

Type Code Symbol Stamp NPT ~

Name 4Na0m0 S Aut oriz tio nN -3090 -1 400 S. Tyron St. Suite 2100, Charlotte, NC 28285 Authorization N-3090-1 - -

Address - Expiration Date - 6/4/07

4. Identification of System RC - Code Class 1

5. (a) Applicable Construction Code ASME Ill 1995 Edition Addenda 1996 Code Case n/a (b) Applicable Edition of Section Xi Utilized for RepalrlReplacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases N-416-2

6. Identification of Components Component Name Manufacturer Manufacturer NatVl Bd # Other ID Yr Built Corrected, ASME Name - Serial # Removed, or Code Installed Stamp Old Steam Generator Westinghouse 1101 68-24 134-011 1968 Removed New Steam Generator Framatome GV/P1291 134-011 2003 Installed

7. Description of Work i Replaced the primary side of the Steam Generator.

8. Tests conducted: Hydrostatic El- Pneumatic El Nominal Operating Pressure i Exempt El Other - Pressure 2235 psi Test Temp. . NOT °F

Other: n/a

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 12 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

I fl-I9. Remarks PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY This work is in support of the Unit I Steam Generator Replacement.

ITEM 1-22-056 I

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp //,#

Certificate of Authorization No. id/A Expiration Date Signed _ ,6 e*f , ASME Program Engineer Date 1/%?/6 _ _ _y Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of MinnP-nt` and employed byHSR Insp qnd In-s Co of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 13Jut oq to 2JWAoS , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

.&nDA I (_jyectors SigL4aJure Commissions XS IqS 4At# M4alq National Board, Province and Endorsements I "I Date Da t e -A - i.f ii

FORM N-1 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR VESSELS*

As Required by the Provisions of the ASME Code,Section III, Division 1 FPa.1 of 4

1. Manufactured and certified by FRAMATOME ANP - Usine de Chalon St. Marcel Zone Industrielle et portuaire Sud - 71380 SAINT MARCEL - FRANCE (Name and address of N Certificate Holder)

2. Manufactured for NORTHERN STATES POWER COMPANY (Name and address of Purchaser) 1717 WAKONADE DRIVE EAST - WELCH. MINNESOTA 55089 - USA

3. Location of installation PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT I 1717 WAKONADE DRIVE EAST - WELCH. MINNESOTA 55089- USA

(Name and address) EE-G-DB-0568-B

4. Type Vertical Helt Exchanier GV/PI 291 N/A EE-G-DB-0572-D 161 2004 (honz. or verL.) (tank, jacketed, heat. ex.) (Cert. Holder serial n-) (CRN) (drawing nW) (Nar sd.n') (year buit)

5. ASME Code, Section 1II,Division 1 1995 1996 1. See Remarks # 19 (edition)- . (addenda date) (class) (code case no.)

Items 6-10 Inclusive to be completed for single wall vessels,Jackets ofJacketed vessels, orshells of heat exchangers

6. Shell See Supplementary sheet (page 3 of 4) - - 68 3" (mal spec.n-.) (tensite streigih) (nonm thickness. (n)) - (errdesign thitcness rij) (da.10 Cit & kc)) (engh (-rrall) (t & nc.)

7. Seams N/A N - ,- Sinele Yes Full (long..) (HT'.) (RT) (eff.%) , I(girth) FH T ) (RT) In' of courses)

8. Heads SA 508 Gr3 Cl 2 90 KSi N/A - N/A

(((a) mat.1 spec. n') (tensle strength)- - ((b) mat I spec. n (year butt) (tensile strength)

Side to Locaticn (top, Thickness Corrosion Crown Knuckle'. Elliptical Conical HemispherIcal Flat Pressure bottom, ends) Allowance Radius Radius . Ratio. Apex Angle Radius Diameter (convex or

- concave) a Top 3.54' 0.06' NIA N/A 2/1 NIA N/A N/A Concave b Bottom N/A I N/A NJA N/A N/A tWA N I NIA N/A N/A

. - . . I .

N/A -N/A If removable, bolts used _Other fastening.

(matil, spec., n', size, quantity) (describe or attach sketch)

9. Jacket closure: N/A (describe as ogee & weld, bar. etc. If bar, give dimensions, describe or sketch)

10. Design pressure2 1085 at max. temp. 600 Min. pressure-test temp. 70 Pneu hydro, or comb. Test pressure 1357 (psi) (IF) -(F) (psi)

Items t ?and 12 to be completed for tube sectIons : .

11. Tubesheets: SA 508 Gr 3 Cl 2 129.42-. . . 21.46' . Welded (stationary, mart, spec. n') (dia. In.(subject to press.)) (thickness (n.)) (attachment (welded, bolted))

N/A - NtA NI. N/A (floatigimat'l spec. n') (dlh. (in.)) - (th0k7ness (in.)) (attachment)

12. Tubes : SB 163 UNS 06690 0.75' . 0.043' 4868 -J (mat.1 spec n) (OD (in.)) (thIckness (hiches or gage)) (n') (type (straIght or U))

Items 13 to 16 Inclusive to be completed for Inner chambers ofJacketed vessels, or channes of heat exchangers 13.Shell: SA508Gr3CI2 90 Ksl 5.66 5.4 . 124., 40` e15.35 5 (mart. sepecn) (tensile strength) (nom,.thiklness (IM)) (min.design rtid On.)) (ta. II (in.)) (lengthoveWl (Ita hI- . -

14. Seams: N/A N/A - A: : Sinole/Dcuble Yes Ft ill - .: 1 (ong. (welded. Dbl., single) (HT' (yes or no) (RT) (elT.%) (girth) FT (R',T) (nofcourses)

15. Heads SA 508 Gr3 Cl2 90 KSI N/A N A- - NIA e . .

((a) matl spec. nW (tensile strength) ((b) matl spec. N')) (tensie strength) -(c)) matl spec n') - (tensile strength)

Loain Tikes Crown Knuckle Elliptical -Conical Hemispherical Flat Side to Pressure Locaion Thic':ncss Radius Radius Ratio Apex Angle Radius Diameter Slde or (a) Top, bottom, ends . )

(b) Channel 5.29 N/A N/A N/A -NIA - 65.26' N/A Concave (c) Floaing N/A NIA N/A NIA N/A NIA N/A N/A If removable, bolts used : Other fastening (marl spec. nW, size, quantty) (describe or attach sketch)

16. Design pressure 2 2.485 at 650 Min. pressure-test temp. 70 r Pneu, hydro, or comb. Test pressure 3107 (psi) , (-F) . . . - - ( F) -- (psi)

If postweld heat treated. 2List other intemal or extemal pressure with coincident tem erature when appicable.

'Supplemental information inform of lists. sketches,"ordrawings maybe used provided(1) sIze isB%x ll, (2)information initems i through 4 on this Data Report IsIncluded on each sheet, (3)each sheet Isnumbered and number of sheets is recorded at top of this form.

(7/98) This form (E00038) may be obtained fronm the Order Dept., ASME. 22 Law Drive, Box 2300, Fairfield, NJ 07007;2300

FORM N-1 (Back - Pg 2 of 4)

Certificate Holders'Seral No GVIPI 291

17. Nozzles, inspection and safety valve openings: See supplementary sheet page 4 of 4 Purpose How Reinforcement Lcto (inlet, outlet, drain, etc.).. antity lDia.OrSizel Type Attached Thickness Material MMal

18. Supports: Skirt No Lugs N/A Legs N/A Other 4 support pads Attached Integral with channel head (yes or no) (quantity) (quantity) (describe) (where and how)

19. Remarks:

Code cases ares : N-20-3. N-71-16 . N411-1 . 2142. 2143. N401-1 Primary hydrotest performed in shop: see attached N2 Data Reports GV/PI 291 (PIF) & GV/PI 291 (PSF)

Secondary hydrotest oerformed on site: see attached N2 Data Report SG 11 - SIC006 Girth weld S/C006 performed on site - N StamD Performed on site NCA-8322.b CERTIFICATION OF DESIGN Design Specification certified by _ OSELITO O.CALLE P.E. State Virginia Reg. no 024373 Design Report certified by IIARRYT. HARRISON P.E. sate Virginia Reg. no 040201255 CERTIFICATE OF SHOP COMPLIANCE We certify that the statements made in this report are correct and that this nuclear vessel conform the rules for construction of the ASME Code, Section 1I1,Division 1.

N Certificate of Auth rization N. N-2771 Expires January 29. 2006 Date Q\ 2.oL Qz .LOJ Name FRAMATOME ANP Signed___

(NCertificate Holder) (Authorized represebtatve)

CERTIFICATE OF SHOP INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NEW-YORK and employed by ROYAL INSURANCE of CHARLOTTE. NORTH CAROLINA have inspected the component described in this Data Report on 02 Q ?clVeb 04- and state that to the best of my knowledge and belief, the Certificate Holder has constructed this component in accordance with the ASME Code,Section III, Division 1.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the component described in this Data Report. Furthenpore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or proper pge or a ltsl of any kind arising from or connected with this Inspection.

Date q CJ etJ o Signed (_/" W IN" Commissions AN NY 5258- NB 12223 (Authorized Nuclear Intector) (Nail. Bd. (inct endorsements) and state or prov. And n)

CERTIF!CATE OF FIELD ASSEMBLY COMPLIANCE We certify that the statements on this report are correct and that the field assembly construction of ails of this nuclear vessel conforms to the rules of construction of the ASME Code,Section III, Division 1.

N Certificte of Authqn;atlon n N-2771 Expires January 29. 2006 Date L9\ Lt¢hame FRAMATOME ANP Signed (N Certificate Holder) (Authorize representative)

CERTIFICATE OF FIELD ASSEMBLY INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NEW YORK and employed by ROYAL INSURANCE of CHARLOTTE. NORTH CAROLINA have cginpared the statements in this Data Report with the described component and state that parts referred to as data items 0( NJovt 2oo4. not included in the certificate of shop Inspection, have been Inspected by me on and that to the best of my knowledge and belief the Certificate Holder has constructed and assembled this component In accordance with the ASME Code,Section III, Division 1.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the component described in this Data Report. Furthermojq, neither the inspector nor his employer shall be liable in any manner for any personal Injury or property d r a loss f ny kind arising from or connected with this Inspection.

Date C[AT0 u'Signed { fYt'9ePV§z Commissions A.N NY 5258-NB312223 (AuthortibfLuclear Inspection) . (Nail 8d. (ncd endorsements) and state or prov. and n)

-SUPPLEMENTARY SHEET CERTIFICATE HOLDERS' DATA REPORT As Required by the Provisions of the ASME Code.Section III, Division I Certificate Holders Serial Nos. GV/PI 291 Pg. 3 of 4

1. Manufactured and certified by FRAMATOME ANP - Usine de Chalon/Saint Marcel (Name and address of Certificate Holder)

Zone Industrielle et Dortuaire sud - 71380 SAINT MARCEL- FRANCE

2. Manufactured for NORTHERN STATES POWER COMPANY (Name and address of Purchaser) 1717 Wakonade Drive East - WELCH, MINNESOTA 55089 - USA

3. Location of Installation PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT I 1717 WAKONADE DRIVE EAST-WELCH, MINNESOTA 55089- USA iNarIIW anO adUress) urr-U-i0n-uWo-0

4. Type Vertical Heat Exchangr GV/P1 291 N/A EE-G-DB-0572-D 161 2004 (hortz or vert) (tank, jacketed, heat. ex.) (Cert Holder serial n) (CRN) (drawing n') (an Bd.n') (year buift) 6 - Shell TABLE 1 - SHELL -MATERIAL Data Items Shell Tensile Nominal Minimum design dia. I D by Line N designation spec. N strength n thickness (inch.) (ft & Inch.)

Lower shell SA 508 Gr3 Cl 2 90 KSi 2.73 2.6 10' 9.42 Iner shell i SA 508 Gr3 Cl 2 _

90 KSi 2.73 2.6 10' 9.42- l 6 10' 9.42' and Conical shell SA 508 Gr3 Cl 2: 90 KSi 3.72 3.6 10;42 Nozzlpershell SA 508 Gr3 Cl 2 >90 KSi 3.39 3.27 14' 0.32 Nozzle shell SA 508 Gr3 Cl 2' 90 KSi 3.39 3.27 14' 0.32 Date5 AwriLb~LI Name htT'WEI, Signed WA :e et.erincate rolrder) x (Authorize representative)

If, .

Date q N)bL. C> 'I Signed (IO&Zkg (Authorized Nuclear Insp6ctor)

. Commissions, A.ft. tNO3(222.1 INatl Board (Inc. Endorsements). State. Province and No]

SUPPLEMENTARY SHEET CERTIFICATE HOLDERS' DATA REPORT As Required by the Provisions of the ASME Code Section III, Division I Certificate Holder's Serial Nos. GV/PI 291 Pa. 4 of 4

1. Manufactured and certified by FRAMATOME ANP - Usine de Chalon/Saint Marcel (Name and address of Certificate Holder)

Zone Industrielle et nortuaire sud-71380 SAINT MARCEL - FRANCE

2. Manufactured for NORTHERN STATES POWER COMPANY (Name and address of Purchaser) 1717 Wakonade Drive East - WELCH, MINNESOTA 55089 - USA

3. Location of Installation PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT I 1717 WAKONADE DRIVE EAST-WELCH, MINNESOTA 55089- USA (Name and address) EE-G-DB-0568-B

4. Type Vertical Heat Exchanger GV/PI 291 N/A EE-G-DB-0572-D 161 2004

, (horiz. or vert.) (tank. Jacketed. heat. ex.) (Cert. Holder serial n-) (CRN) (drawuig n') (Nar Bd.n) (year built) 17 - Nozzle inspection and safety valve opening Table 2- Nozzles and Access Openings Purpose Quantity Dia. or Size TYPe taoe Material Thickness R ateiril Location Pnmary 2 18" Integral Integral SA 50 Gr3 Cl 2 6.4" Integral Channel manways _________ ogd____________ head Primnary inlet 31.61" Integ-al Integral SASrrayne A508 182Gr3 Cl 2 and F3161.N 3S5112-3.3" Integral Channel

_____ head__

Primary outlet 1 31.61" Integral Integral SA 508 Gr3 Cl 2 and 3.5"112" Integral Channel

____forged SA 182 F316 LN 3.3" _____ head SFA-5.5 AWS Lower shell Handholes 6 8" Built up Welded SFA-E.23 AWS 5.25' Built up Intwnediae F9P4-EEF2N-F2N shell Instrumentation Full Lower shell t In..

15 0.72" Set on penetration SA 105 0.64' N/A and Nozzle

. comer weld . .I shell Instrumentation Full Upper shell taps 1' 3 0.91" Set on penetration SA 105 0.67" N/A and Nozzle comer weld shell Blowdown t Blowown 2 1.939" apsFull Set on penetration SA 105 0.78" N/A Tubesheet comer weld SecodaryFull Scanways 2 18" Set in penetration SA 508 Gr3 Cl 2 6.78" Integral Upper shell Feedwater 1 13.94" Set in penetration SA 508 Gr3 Cl 2 6.1"/1.6" Integral Nozzle shell butt weld Full Recirculation 1 2.63" Set in penetration SA 508 Gr3 Cl 2 1.9"/3.8" N/A Nozzle shell butt weld I Steam Outlet 1 32" Integral Integral SA 508 Gr3 Cl 2 2.2"/10.7" Integral Top head

____________________________ ______ forged _________ ____ _____

Date 9 ~t"%t' I Name _ FRAMATOME ANP Signed (Certificate Holder) (Authorized r rrsentatlve)

Date g M.o V 2 c:o4 Signed O&OsXWJ, Commissions A, Nt- N (I 22zn i-, ZIS (Authorized Nuclear Inslqtor) [Nat'l Board (Inc. Endorsements). State, Province and No]

i

-r FORM N-2 CERTIFICATE HOLDERS' DATA REPORT FOR IDENTICAL NUCLEAR PARTS AND APPURTENANCES*

As Required by the Provisions of the ASME Code,Section III Not to Exceed One Day's Production Pg. 1 of -2

1. Manufactured and certified by SGT Ltd. 400 South Tryon Charlotte NC 28285 Iname and addres of NPT Cenifc4ate Holder)

Manufactured for FRAMATOME ANP-Usine de Chalon St. Marcel Zone Industrielle et portuaire Sud - 71380 Saint Marcel - France inarna and address of purchaaer) 3.

Location of installation Prairie Island Nuclear Generating Plant Unit 1 17'17 Wakonade Drive East Welch, MN 55089 ER80S-D2 (name and address)

4. Typo BUMPP]INGV4020 E8018-NM2 90 ksi minimum NIA 2004 fdrawing no.) maftl. spec, no.) (tnsil*e strength) (C{N) (year built)

5. ASME Code. Section 111, Division 1: 1995 1996 1 N/A (edition) - addenda date) (cas Coda Caest no.1

6. Fabricated in accordance with.ConsL Spec- (Div. 2 only) N/A Revision Date Ino.)

7. Remarks: Site Girth weld between conical shell and nozzle shell -*

S. Norn. thickness (in.) 3.39 Min. design thickness fin.) 3.27 Dia. ID (ft & in.) 14'- 0 5/16" Length overall (ft &.in.) N/A

9. When applicable, Certificate Holders' Data Reports are attached for each htemrnof this report:

National National Pan or Appurtenance Board No. Part or Appurtenance Board No.

Serial Number in Numerical Order Serial Number in Numerical Order

.1) SG II-S/C006 N/A (26)

(2) (27)

(3) (28)

(4) 129)

(5) (30)

(6) (31)

(7) (32)

(8) (33)

(9) (34) 110) (35)

(11) (36)

(12) (37)

(13) (38)

(14) (39)

(15) (40)

(16) (41)

(17) (42)

(18) (43) 119) (44)

(20) 145)

(21) (46)

(22) (47)

(23) 148)

(24) (49)

(25) (50) 0

10. Design pressure 1085 psi. Temp. 600 F. Hydro.testpressure 1357 psi /70'F at temp. F "wen applicable)

Supplemental information in the form of lists, sketches. or drawings may be used provided 11)size is 81/2 x 11, (2)information in items 2 and 3 on this Data Report is included on each sheet, 3)each sheet is numbered and the number of sheets is recorded at the top of this form.

(198) This form (E00040) may be obtained from the Order Dept. ASME. 22 Law Drive, Box 2300, Fairfield. NJ 07007-2300.

FORM N-2 (Back - Pg 2 of l 2 .

Certificate Holder's Serial Nos. SG 11-SIC006 through CERTIFICATION OF DESIGN Design specifications certified by Joselito 0. Calle P.E. State Virginia Reg. no. 024373 Design report' certified by Harry T. Harrison P.E. State Virginia Reg. no. 040201255 twhen applicable)

CERTIFICATE OF COMPUANCE We certify that the statements made in this report are correct and that this 1+/-ihe,.) weld conforms to the rules of construction of the ASME Code, Section 111, Division 1.

NPT Certificate of Authorization No. N-3090-1 Expires May 31, 2005 Date _______ Name SGTLtd.

INPT Certificate Holder)

Signed A C _';J lmnhorized representmeaS);4)ft 1

CERTIFICATE OF INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel lnspectors and the State or Province of n-"tl'; andemployedb rI-orPO" -rseAhI]VJ'FJ2 ir-v 0i: (dAcUi4) of 1-1ttVfoltD

Cr havoinspectedtheseitemsdescribedinthisDataReporton ,and state thatto the best of my knowledge and belief, the Certificate Holder has fabricated these parts or appurtenances in accordance with the ASME Code, Section Ill, Division 1. Each part listed has been authorized for stamping on the date shown above.

By signing this certificate, neither the inspector nor his employer makes any warranty, expressed or impifed, concerning the equipment described in this Data Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

Date if/1/o Signed 1-7t (1.

(AUoW Ned MOWes Insepaoll Commissions Of J A,1 'Q./uvLtor-co Merl. M lincl. endorsements) and state or prov. Phd no.J

,4 V' r--

-41 PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-057 I

1. Owner Nuclear Management Company, LLC Date 12/16/2004

- Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name I -I . 1717 Wakonade Dr. E, Welch Minnesota 55089 - - 0310379. 0310472, 0310229, 0310231, DCP 03SGO1 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by SGT Ltd.

Type Code Symbol Stamp NPT Name 400 S. Tyron St. Suite 2100, Charlotte, NC 28285 Authorization N-3090-1 Address Expiration Date -* 6/4/07

4. Identification of System MS, SG . Code Class 2

5. (a)Applicable Construction Code ASME IiI I 1995 Edition Addenda 1996 Code Case N-416-2 (b) Applicable Edition of Section;XI Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xi Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name -Serial # Removed, or Code

, Installed Stamp Rigid Retraint MSH-1 Removed O Original Steam Generator Westinghouse 1102 68-25 134-012 Removed New Steam Generator Framatome GV/PI292 134-012 2003 Installed _

-1~ :

7. Description of Work Piping was removed and reinstalled in support of the installation of the secondary side of the replacement steam generator. The rigid restraint was modified to remove the rigid band. Weld build up in the counterbore was also performed.

8. Tests conducted: Hydrostatic L Pneumatic L Nominal Operating Pressure ] Exempt L Other LI Pressure

NOP psi Test Temp. NOT OF Other: n/a NOTE: Supplemental sheets in form of lists; sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

I I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-057

9. Remarks This work is in support of the Unit 1 Steam Generator Replacement. The N-2 Data Sheet for the upper part is attacnea to this NIS-2. The N-1 for the entire vessel is attached to NIS-2 for Item # 1-22-055 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp A//a Certificate of Authorization No 4//A* Expiration Date Signed , ASME Program Engineer Date _ _2_ _ __ _ _

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnpenta and employed byHsBR Insp and Ins Co of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period <M JuL04 to LJAAI Os , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

{US).

Go Commissions IB I A4 *

-TES MA 4i nspector's gnature National Board, Province and Endorsements Date Z A o , i4 K)

FORM N-2 CERTIFICATE HOLDERS' DATA REPORT FOR IDENTICAL NUCLEAR PARTS AND APPURTENANCES As Required by the Provisions of the ASME Code Section III Not to Exceed One Day's Production Pg. 1 of 5

1. Manufactured and certified by FRAMATOME ANP - Usine de Chalon/Saint Marcel (Name and address of Certificate Holder)

Zone Industrielle et portuaire sud - 71380 SAINT MARCEL - FRANCE

2. Manufactured for NORTHERN STATES POWER COMPANY (Name and address of Purchaser) 1717 Wakonade Drive East - WELCH, MINNESOTA 55089 - USA

3. Location of Installation PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT I (Name and address) 1717 Wakonade Drive East -WELCH. MINNESOTA 55089 - USA

4. Type See supplementary sheets N/A 2004 r (drawing no.) (maii spec no.) (tensile strength) (CRN) (year built) 5.ASMECodeSectionillDivision1 1995 1996 1 See remarks (edition) . (addenda) (class) (code case no.)

6. Fabricated In accordance with Const. Spec (Dlv 2 only) _ N/A Revision Date (no.)

7. Re'marks:

Code cases are: N-71-16, N 41 i

' he secondary side hydrotest is not completed

8. Nom. Thickness (in.) Supp. sheet Min. des thickness (in.) 3.27" Dia. ID (ft & In)See supplementary sheets Length overall (ft & In.) 24' 6.1"

9. When applicable, Certificate Holders' Data Reports are attached for each item on this report:

Part or Appurtenance National Part or Appurtenance National Serial Number Board No. Serial Number Board No.

In Numerical Order In Numerical Order GV1PI 292 (PSF) N/A ' . .

1. 19N__ _ _ __ _ __ _ _

2. . 20.'

3. , 21 .

4 __ _ _ _ _ _ _ _ _ _ _ _ 22. _ _ _ _ _ _ _ _ _ _ _ _

5. 23. 1,

6. _ _ _ _ _ _ _ _ _ _ _ 24. _ _ _ _ _ _ _ _ _ _ _

7 ._ __ _ __ _ __ _ __ _ 25. _ _ _ _ _ _ _ _ _ _ _ _

8. _ _ _ _ _ _ _ _ _ 26. _ _ _ _ _ _ _ _ _

i

9. . 27.

1L . : 29.

1. . . . .0 , ._.___._._. .. . 3...

13.p. _________ p e.F Pe ue / @31.

14. __ _ _ _ _ _ _ _ _ _ _ _ 32.

IS _ ____ ___ ____ ___ ____ ___ 33.

10. Design Pressure upp.set si Temp. Su___sheet Deg. F Hydro.Test Pressure 'N/A @ Temp Deg F

FORM N-2 (Back - Pg 2 of 5)

Certificate Holders' Serial Nos GV/PI 292 (PSF) through CERTIFICATION OF DESIGN Design Specifications Certified by Joselito O.CALLE P.E. StateNOrth Carolina Reg. No. 022219 Deign Report Certified by HarryT.HARRISON P.E.Slate Virginia Reg. No. 012551 CERTIFICATE OF COMPLIANCE We Certify that the statements made in this report are correct and that this (these)

STEAM GENERATOR UPPER PART conform to the rules of construction of the ASME Code.Section III Division 1 NPT Certification of authorization No. N - 2772 Expires: Jan 29. 2,006 Dato.2kJ 042 Name FRAMATOME ANP Signed C. -r ^t CERTIFICATE OF INSPECTION 1.the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NEW YORK and employed by ROYAL INSURANCE of CHARLOTTE, NORTH CAROLINA have Inspected these items described In this Data Report on 1 Q C b 1 And state that to the best of my knowledge and belief, the Certificate Holder has fabricated these parts or Appurtenances in accordance with the ASME Code, Section 1II,Division 1. Each Part has been authorized for stamping on the date shown above.

By signing this certificate; neither the Inspector nor his Employer makes any warranty expressed or Implied concerning the equipment described In this Data Report. Furthermore, neither the Inspector nor his Employer shall be liable for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

Dae1 Date( AP5 '4 Signed o Nudear Commissions A.NNY Board Ed58 S 5258 fAuthodized Nuclear Inspector) (Nall Board Endsmts. State or Prov, and no.)

CERTIFICATE HOLDERS' DATA REPORT SUPPLEMENTARY SHEET As Required by the Provisions of the ASME Code Section III

-CertificateHolder'sSerialNos.GV/PI292(PSF) Pg. 3 of 5

1. Manufactured and certified by FRAMATOME ANP - Usine de Chalon/Saint Marcel T an ddress oCertificate Holder)

Zone Industrielle et portuaire sud - 7 1 SAINT MARCEL - FRANCE

2. Manufactured for NORTHERN STATES POWER COMPANY (Name and address of Purchaser) 1717 Wakonade Drive East - WELCH, M1NNESOTA 55089 - USA

3. Location of Installation PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT I 1717 Wakonade Drive East - WELCH. MNNESOTA 55089 - USA

4. Component or Part STEAM GENERATOR UPPER PART

5. 2004 . N/A N/A (year built) (CRN) (Nan Board No.)

Data Items by Line No.

4 Drawinz N° REV BUMPPVNGV 2002 A BUEPPI/NGV 6105 K Materinl Snecification ASME Material Nozzle shell SA 508 Gr3 C12 Upper shell SA 508 Gr 3 C12 Elliptical head SA 508 Gr3 C12 Fcedwater nozzle SA 508 Gr3 C12 Recirculation nozzle SA 508 Gr3 C12 Secondary manway SA 508 Gr3 C12 Instrumentation tap 3/4" SA 105 Instrumentation tap 1" SA 105 Tensile strength (see note 1)

Nozzle shell 90 Ksi Upper shell 90 Ksi Elliptical head 90 Ksi ;..

Feedwater nozzle 90 Ksi Recirculation nozzle 90 Ksi I.

Secondary manway 90 Ksi Date 0 t4 1 I lo L Name. FRAMATOME ANP _Signed Gned o i Q

e (CertUicate oderj (Authorized repr-Date t tpt 4 Signed ( Commissions A JJ.r4o N (Authorized Nuclear Inspect - - [Narl Board (Inc. Endorsements), Stale. Province and No]

CERTIFICATE HOLDERS' DATA REPORT SUPPLEMENTARY SHEET As Required by the Provisions of the ASME Code Section III Certificate Holder's Serial Nos.GV/VI 292 (PSE) pg, of .5 I. Manufactured and certiried by FRAMATOME ANP -Usin de Chalorn/Saint Marcel (Name and address of Certificate Holder)

Zone Industrielle et portuajie sud- 71380 SAINT MARCEL.- FRANCE

2. Manufactured for NORTHERN STATES POWER COMPANY (Name and address of Purchaser) 1717 Wakonade Drive East - WELCH, MINNESOTA 55089 -USA

3. Location of Installation PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT I 1717 Wakonade Drive East - WELCH, MINNESOTA 55089 - USA ItI

4. Component or PartSTEAM GENERATOR UPPER PART

5. 2004 N/A N/A r (year built) (CRN) (Natl Board No.)

i -

Data Items by Line No.

Instrumentation tap 'A" 70 J(i

_____Instrumentation tap I" 70 KCni

_________Note I : tensile strength value Su from ASME code, Section 11I, Appendice 1, Table 1.1.0 which refers to Section IL.Part D. Suboart 1. Table U 8 Nominal thickness (in)

Nozzle shell 3.39" Upper shell 3.39" Elliptical head 3.54."

Feedwater nozzle 3.52" Recirculation nozzle 3.52" Secondary mtanway 3.46"1 Instrumentation tap V/4' 0.64" Instrumentation tap 1" 0.67"

. II

______Dia ID. (ft &in.) r-,

______Nozzle shell 14' 0.32" I

______Upper shell 14' 0.32" Elliptical head 14' 0.32" Date 0k I .:s.I o(j Name_-

FRAMATOME ANP .Signed CZ R- rr (Certificate Holder) (Authorized rp i Date ... ,. A p tf.LJi2'fL Signed Q 9 - t Commissions[Ni A., Ai. r--I s"2.!(

(Authorized Nuclear Inspector) (NnBoard (Inc Endorsements). State. Province and No)

CERTIFICATE HOLDERS' DATA REPORT SUPPLEMENTARY SHEET As Required by the Provisions of the ASME Code Section III N=

Certificate Holder's Serial Nos. GV/PI 292 (PSF) pg. 5. of S I. Manufactured and certified by FRAMATOME ANP-Usine de Chalon/Saint MarceI (Name and address of Certificate Holder)

Zone Industrielle ct portuaire sud - 71380 SAINT MARCEL- FRANCE

2. Manufactured for NORTHERN STATES POWER COMPANY (Name and address of Purchaser) 1717 Wakonade Drive East - WELCH, MINNESOTA 55089 - USA

3. Location of Installation PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT I 1717 Wakonade Drive East - WELCH, MINNESOTA 55089 - USA

4. Component or Part STEAM GENERATOR UPPER PART Ii

5. 2004 NIA N/A i-(year built) (CRN) (Nanl Board No.)

7, Data Items by Line No.

8 Feedwatcr nozzle 13.94" Recirculation nozzle 2.63" Secondary manway It 6" Instrumentation tap 3/4" 0.72" Instrumentation tap I" 0.91 "

10 Design pressure and temperature Secondary side: 1085 psi / 600 'F

_ _ _ __ _ I

'I-

4. L 4.

+

k.

+

Signed C.Or1Cr Date 0 l4 12!. lo 4 Name_ FRAMATOME ANP .

(Certificate Holder) (AthriedrepS*

Date 2, Ape, I o4-Commissions A /A' M"I 6- c*i Signed ao k (Authorized Nuclear Inspewbr) RNarl Board (Inc. Endorsements), State. Province and No)

-MM I FORM NIS-2 OWNER'S REPORT PRAIRIE ISLAND NUCLEAR GENERATING PLANT i

FOR. REPAIR/ REPLACEMENT ACTIVITY

. ITEM 1-22-058-I

1. Owner Nuclear Management Company, LLC Date 12/16/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 - -- 0310375, 0310471, 0310229, 0310231, DCP 03SG01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by SGT Ltd.

Type Code Symbol Stamp NPT Name 400 S. Tyron St. Suite 2100, Charlotte, NC 28285 Authorization N-3090-1

--- Address --- - Expiration Date 6/4/07

4. Identification of System MS, SG Code Class 2

5. (a)Applicable Construction Code ASME IlIl 1995 Edition Addenda 1996 Code Case N-416-2 (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial# Removed, or Code Installed Stamp Rigid Retraint MSH-11 Removed _I Original Steam Generator Westinghouse 1101 68-24 134-011 Removed i; New Steam Generator Framatome GVIPI291 134-011 2003 Installed

,. ... : . - . .. ; . , - ~N-

7. Description of Work Piping was removed and reinstalled In support of the installation of the secondary side of the replacement steam generator. The rigid restraint was modified to remove the rigid band.

8. Tests conducted: Hydrostatic 1 Pneumatic L Nominal Operating Pressure i Exempt LI Other n Pressure NOP psi Test Temp. NOT 0 F

Other: n/a I - - -

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 )2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

I I.

FR PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY

9. Remarks ITEM 1-22-058 This work is insupport of the Unit 1 Steam Generator Replacement. The N-2 Data Sheet for the upper part is aaacneo to I

this NIS-2. The N-1 for the entire vessel is attached to NIS-2 for Item # 1-22-056.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp vi/A Certificate of AuthoraUe)No. Expiration Date Signed ( C. ASMEProgram Engineer Date /__//_ _ __ _y Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnqentn and employed byHsBlnsp IndIns Co of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period doJuLo'/ to

___J______ , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions omssln. As hJ aL3I9a (t(inspector'sjnature National Board, Province and Endorsements Date ,;

(j / K - J-Mu

-at,

I-FORM N-2 CERTIFICATE HOLDERS' DATA REPORT FOR IDENTICAL NUCLEAR PARTS AND APPURTENANCES As Required by the Provisions of the ASME Code Section III Not to Exceed One Day's Production Pg. 1 of 5

1. Manufactured and certified by FRAMATOME ANP - Usine de Chalon/Saint Marcel (Name and address of Certificate Holder)

Zone Industrielle et portuaire sud - 71380 SATNT MARCEL - FRANCE

2. Manufactured for NORTHERN STATES POWER COMPANY (Name and address of Purciaser) 1717 Wakonade Drive East - WELCH, MINNESOTA 55089 - USA 3.Location of Installation PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT I (Name and address) 1717 Wakonade Drive East- WELCH. MINNESOTA 55089 - USA r

!I

4. Type See supplementary sheets (drawing no.) (marl spec no.) (tensile srcenglh)

N/A (CRN) 2004 (year built) r

5. ASME Code, Section 111. Division 1 1995 1996 1 See remarks .

tedition) (addenda) (class) (code case no.)

N/A

6. Fabricated in accordance with Const. Spec. (Div 2 only) _ _ _ Revision Date (no.)

7. Remarks:

Code cases are: N-71-16, N 411-1 The secondary side hydrotest is not completed

8. Nom. Thickness (in.) Supp. slhet Min. des thickness (in.) 3.27" DIa.ID(ft&In) SeesuPplmentarysheets Length overall (ft & in.) 24' 6.1"

9. When applicable, Certificate Holders' Data Reports are attached for each item on this report-Part or Appurtenance National Part or Appurtenance National Serial Number Board No. Serial Number Board No..

In Numerical Order In Numerical Order

1. GV/P1291 (PSF) N/A 19

2. __ _ _ _ _ _ _ _ _ _ _ _ _ 20.

3. __ _ _ _ _ _ _ _ _ _ _ _ 21 4 22.

5. 23.

6. . . . . 24.

7. 25.

8. __ _ _ _ _ _ _ _ _ _ _ _ _ _ 26. _ _ _ _ _ _ _ _ _ _ _ _ _ _ t-

9. __ _ _ _ _ _ _ _ _ _ _ _ _ 27. _ _ _ _ _ _ _ _ _ _ _ _ _

to. __ _ _ _ _ _ _ _ _ _ _ _ _ _ 28. _ _ _ _ _ _ _ _ _ _ _ _ _ _

-29.

12. 30.

13. 31. '

14. shts______________ shet_ eg32. ure__________

__________Pes g 15 __ _ _ _ _ _ _ _ _ _ _ _ _ _ 33. _ _ _ _ _ _ _ _ _ _ _ _ _ _

16. _ _ _ _ _ _ __ _ _ _ _ _ _ 34. _ _ _ _ _ _ _ _ _ _ _ _ _ _

10. Design Pressure Suppsheet psi Temp. _________et Deg. F Hydro.Test Pressure N/A @ Temp Deg F

FORM N-2 (Back - Pg 2 of 5)

Certificate Holders' Serial Nos GVWPl 291 (PSF) through CERTIFICATION OF DESIGN Design Specifications Certified by Joselito O.CALLE P.E. StateNorth Carolina Reg. No. 022219 Deign Report Certified by Harry T.HARRISON P.E. State Virginia Reg. No. 012551 CERTIFICATE OF COMPLIANCE We Certify that the statements made In this report are correct and that this (these)

STEAM GENERATOR UPPER PART conform to the rules of construction of the ASME Code,Section III Division 1 r

NPT Certification of authorization No. N - 2772 Expires: Tan 29. 2006 Date 4 Lft Name FRAMATOME ANP Signed IF.Pa o -r I. E G

CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boner and Pressure Vessel Inspectors and the State or Province of NEW YORK and employed by ROYAL INSURANCE of CHARLOTTE, NORTH CAROLINA have Inspected these items described Inthis Data Report on V: F{ii20oo04 And state that to the best of my knowledge and belief, the Certificate Holder has fabricated these parts or Appurtenances in accordance with the ASME Code. Section 1II,Division 1. Each Part has been authorized for stamping on the date shown above.

By signing this certificate, neither the Inspector nor his Employer makes any warranty expressed or implied concerning the equipment described In this Data Report. Furthermore, neither the Inspector nor his Employer shall be liable for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

Date A2Lp@ 2 +/-/OT°Signed ( Commissions A.N NY 5258 (Authorized Nuclear Inspector) (Nant Board Endsmts, State or Prov. and no.)

- I CERTIFICATE HOLDERS' DATA REPORT SUPPLEMENTARY SHEET As Required by the Provisions of the ASME Code Section III Certificate Holder's Serial Nos.GVIPl 291 (PSF) Pg. 3 of 5

1. Manufactured and certified by FRAMATOME ANP - Usine de Chalon/Saint Marcel (Name and address of Certificate Holder)

Zone Industrielle etportuaire sud- 71380 SAINT MARCEL- FRANCE

2. Manufactured for NORTHERN STATES POWER COMPANY (Name and address of Purchaser) 1717 Wakonade Drive East - WELCH, MINNESOTA 55089 - USA

3. Location of Installation PRAIRIE ISLAND NUCLEAR GE}NERATING PLANT UNIT I 1717 Wakonade Drive East -WELCH. MINNESOTA 55089 - USA

4. Component or Part STEAM GENERATOR UPPER PART i

5. 2004 N/A N/A (year built) (CRN) (Narl Qoard No.)

Data Items by Une No.

4 -Drawint! N° REV

. BUMPPI/NGV 2001 C BUEPPI/NGV 6105 K Material Snecification .ASME Material Nozzle shell SA 508 Gr3 C12 Upper shell SA 508 Gr 3 C12 Elliptical head SA 508 Gr3 C12 Feedwater nozzle SA 508 Gr3 C12 Recirculation nozzle SA 508 Gr3 C12 Secondary manway SA 508 Gr3 C12 Instrumentation tap 3/4" SA 105 Instrumentation tap I" SA 105 Tensile strength (see note 1)

Nozzle shell 90 Ksi Upper shell 90 Ksi Elliptical head 90 Ksi Feedwater nozzle 90 Ksi r Recirculation nozzle 90 Ksi Secondary manway 90 Ksi Date L2 I1 °4 Name- :FRAMATOME ANP Signed G. F R° s r <- z .

(Certificate Holder) (Authorized e Date 2iAo vlo4A Signed Commissions A .ro .

(Authorized Nuclear Inspecor) INat1 1oard (Inc. Endorsements). State, Province and No)

I .

CERTIFICATE HOLDERS' DATA REPORT SUPPLEMENTARY SHEET As Required by the Provisions of the ASME Code Section III Certificate Holders Serial Nos.GV/P! 291 (PSF) pg. 4 of 5

1. Manufactured and certified by FRAMATOME ANP - Usine de Chalon/Saint Marcel (Name and address of Certificate Holder)

Zone Industrielle et portuaire sud - 71380 SAINT MARCEL - FRANCE

2. Manufactured for NORTHERN STATES POWER COMPANY (Name and address of Purchaser) 1717 Wakonade Drive East - WELCH, MINNESOTA 55089 - USA

3. Location of Installation PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT I 1717 Wakonade Drive East - WELCH, MINNESOTA 55089 - USA

4. Component or Part STEAM GENERATOR UPPER PART r-

5. 2004 N/A N/A (year built) (CRN) (Nanl Doard No.)

Data Items by Une No.

4 Instrumentation tap %/" 70 Kqi Instrumentation tap 1" 70 K-i Note 1: tensile strength value Su from ASME code,Section III, Appendice 1, Table 1-1.0 which refers to Section 11. Part D. SubDart 1. Table U 8 Nominal thickness (in)

Nozzle shell 3.39" Upper shell 3.39" Elliptical head 3.54" Feedwater nozzle 3.52" Recirculation nozzle 3.52" Secondary manway 3.46" Instrumentation tap 3/'" 0.64" Instrumentation tap 1" 0.67" t

Dia ID. (ft & in.)

Nozzle shell 14' 0.32" Upper shell 14' 0.32" Elliptical head 14' 0.32" Date o La I4xt IlDj Name FRAMATOME ANP Signed 6 F Rh, am tF e 5-(Certificate Holder) (AuthorizedtR Date 2t l 'lo4-i'lp Signed (a tkl-L> LL Q. Commissions A. M *z?

(Authorized Nuclear Inspecidr) [Natn Board (Inc. Endorsements), State, Province and No]

- I -- 1 CERTIFICATE HOLDERS' DATA REPORT SUPPLEMENTARY SHEET As Required by the Provisions of the ASME Code Section III Certificate Holder's Serial Nos.GV/PI 291 (PSF) pg. 5 of 5

1. Manufactured and certified by FRAMATOME ANP -Usine de Chalon/Saint Marcel (Name and address of Certificate Holder)

Zone Industrielle et portuaire sud - 71380 SAINT MARCEL - FRANCE

2. Manufactured for NORTHERN STATES POWER COMPANY (Name and address of Purchaser) 1717 Wakonade Drive East - WELCH, MINNESOTA 55089 - USA

3. Location of Installation PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT I 1717 Wakonade Drive East - WELCH. MINNESOTA 55089 - USA

4. Component or Part STEAM GENERATOR UPPER PART V

5. 2004 N/A N/A II (year bullt) (CRN) (Naril Board No.)

Data Items I..

by Line No.

8 Feedwater nozzle 13.94" Recirculation nozzle 2.63" Secondary manway V' 6" Instrumentation tap 3/4" 0.72" Instrunentation tap 1" 0.91" 10 Design pressure and temperature Secondary side: 1085 psi /600 "F

+

.1.

I-4-

+

4-XI 4-i 4-Date IJ lIt IlO Name FRAMATOMEANP Signed C( ZF -W ie,;

(Certificate Holder) (Authorized reE9 Date Qi' Ae el O 4-Signed , e- Commissions A. M). M' l<2 < f';'

(Authorized Nuclear Ir ~clor) [Narl Board (Inc. Endorsements). State. Province and No]

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT.FOR REPAIR/ REPLACEMENT ACTIVITY I \ 1 - I'ITEM

1-22-059 I

1. Owner Nuclear Management Company, LLC Date 12/16/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 'of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0310381, 3010474, 0310228, DCP 03SG01

- - Address Repair Organization P.O. No., Job No., etc

3. Work Performed by SGT Ltd.

Type Code Symbol Stamp NPT Name 400 S. Tyron St. Suite 2100, Charlotte, NC 28285 Authorization N-3090-1 Expiration Date 6/4/07 - - I Address -- I;

4. Identification of System AF, FW Code Class 2

5. (a) Applicable Construction Code ASME IlIl 1995 Edition Addenda 1996 Code C;ase (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Aux. Feed line 3-AF-1 1 Removed O Aux. Feed line 3-AF-1 1 Installed L Feed Water line 16-FW-13 Removed L Feed Waterline 16-FW-13 Installed l.

7. Description of Work Piping was removed and replaced in support of the installation of the secondary side of the replacement steam generator. . . i_

8. Tests conducted: Hydrostatic i Pneumatic Nominal Operating Pressure L Exempt E]

Other; Pressure '1362 psi Test Temp. 84 0F Other: This work includes a contingency cut and weld in the Aux. Feed system downstream of the isolation and check valves. If contingency is necessary, this weld will be pressure tested In accordance with Code Case N-416-2.

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is Included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY

9. Remarks This work is in support of the Unit 1 Steam Generator Replacement.

ITEM 1-22-059 I

CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp ,J//

Certificate of AuthoriyinNo. AIIA Expiration Date Signed . . ASME Program Engineer Date 12/'/6/6y I Owner or Owner's Designee. Title CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minn0mtg and employed byHsR lnsp and Ins Co of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 74JW.o'f4 to c4JA4 OS ,and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

4-;. oQ ___ Commissions AS lqzs t44 Mrnjh2q IntCr's Signature National Board, Province and Endorsements Date _ v a,.

I J

K)i

I I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY i : ! s ITEM 1-22-060

1. Owner Nuclear Management Company, LLC Date I - 4.-Q615 Name

2. Plant* Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E. Welch Minnesota 55089 - 0310383, 3010477, 0310228, DCP 03SG01 Address .- Repair Organization P.O. No., Job No., etc

3. Work Performed by SGT Ltd.

Type Code Symbol Stamp NPT Name . .. .

Authorization N-3090-1 400 S. Tyron St. Suite 2100, Charlotte, NC 28285

-- - - Expiration Date 6/7/04 Address

4. Identification of System AF, FW Code Class 2

6. (a) Applicable Constructlon Code ASME IlIl , 1995 Edition Addenda 1996 Code Case (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases N-416-2

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name - - Serial # - - - Removed, or Code Installed Stamp Aux. Feed line 3-AF-12 Removed D Aux. Feed line 3-AF-12 . Installed - I Feed Water line 16-FW-16 Removed LI Feed Waterline 16-FW-16 Installed _

7. Description of Work Piping was removed and reinstalled In support of the installation of the secondary side of the replacement steam generator.

nu t . [

8. Tests conducted: Hydrostatic I Pneumatic -E Nominal Operating Pressure R Exempt 'l 0

Other i - Pressure psi Test Temp. F Other:

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

IN PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-060

9. Remarks This work is in support of the Unit 1 Steam Generator Replacement. A system leakage test was peformed on FW-3, as it was isolated during the hydrostatic test (ref. CAP 04148, SGT NCR 237 ). This weld will be VT-2 examined during a containment enby under W0O0306142.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp Certificate of Auth o o//. Expiration Date Signed , ASME Program Engineer Date / As______

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnpqntq and employed byHSR lnsp snd Ins Co of Connecticiit of Hartford Conn. have inspected the components described in this Owner's Report during the period IGJUL64 to t6J]A4oS , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

(Pn Inter's Sinatur a z Commissions - £ I&wa I IflAJo/9lY National Board, Province and Endorsements Date __a_ a_ , _as

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR! REPLACEMENT ACTIVITY

- ITEM 1-22-061 I

1. Owner Nuclear Management Company, LLC Date 12/14/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 - -- - ~0310360, 0310433, DCP 03RC02 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by SGT Ltd. Type Code Symbol Stamp NPT Name 400 S. Tyron St. Suite 2100, Charlotte, NC 28285 Authorization N-3090-1 Address - Expiration Date 6/4/07

4. Identification of System SG - -Code Class

5. (a) Applicable Construction Code AISC 9th Edition, ASME 1995 Edition Vill Addenda 96 Code Case (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Column 1 H-13 Corrected L Column 2 H-14 Corrected O Column 3 H-15 Corrected El Column 4 H-16 Corrected - LI

7. Description of Work Modified the support column swivel adapter and bumper blocks.

8. Tests conducted: Hydrostatic .,,Pneumatic L Nominal Operating Pressure 2 Exempt i Other Pressure psi Test Temp. * ° . F Other: n/a .-

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet Is numbered and number of sheets is recorded at the top of this form.

I -

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FO RM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-061

9. Remarks These activities are in support of the Unit 1 Steam Generator Replacement Project.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp 411,4 Certificate of Authorization No. Expiration Date Signed ASME Program Engineer Date _ _ _ ___

__/ _

Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnp-nti and employed byHSRFlnsp and Ins Co of Connecticut of Hartford Conn. have inspected the components described in this Owners Report during the period ainMAj OL. to oJA4I as , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xi.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owners Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

)) Commissions J ,oSS ' AdI mJi 9 zy National Board, Province and Endorsements I.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-062

1. Owner Nuclear Management Company, LLC Date 1211412004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 ' of 2 '

Name 1717 Wakonade Dr. E.'Welch Minnesota 55089 - 0310363, 0310435, DCP 03RC02 -

Address - - Repair Organization P.O. No., Job No., etc

3. Work Performed by SGT Ltd. Type Code Symbol Stamp NPT Name 400 S. Tyron St. Suite 2100, Charlotte, NC 28285 Authorization N-3090-1 Address Expiration Date 614/07

4. Identification of System SG Code Class 1

5. (a) Applicable Construction Code AISC 9th Edition, ASME , 1995 , Edition Addenda, 96 Code Case (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name . Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code

- Installed Stamp Column 1 H-13 Corrected L Column 2 H-14 Corrected El Column 3 H-15 Corrected H Column 4 H-16 Corrected _

7. Description of Work Modified the support column swivel adapter and bumper blocks.

8. Tests conducted: Hydrostatic LI Pneumatic EI Nominal Operating Pressure J Exempt 2J Other Pressure psi Test Temp. °F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet Is numbered and number of sheets is recorded at the top of this form.

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY

9. Remarks These activities are in support of the Unit 1 Steam Generator Replacement Project.

ITEM 1-22-062 I

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp 41// 4 Certificate of Authorization No. Expiration Date Signed B y ? < , ASME Program Engineer Date _ _ _ _ _'I_

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of MinnPsnti and employed byHsBlnsp and Ins co of ConnPrtictit of Hartford Conn. have inspected the components described in this Owner's Report during the period mAU.4 to 0%4 Joel 6s , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

E(4>G~C)

In ctor's Signitire Commissions tIAl t k¶ 5AI A IV rJKl q2H National Board, Province and Endorsements Date AULLLA it A. so

PRAIRIE ISLAND NUCLEAR GENERATING R N2 O ' .. OR- RI M

FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY R

PLANT C

.- ITEM ACTIV 1-22-063 I

1. Owner Nuclear Management Company, LLC Date 12/312004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 -. of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0309712. EEC-1359 Address Repair Organization P.O. No., Job No., etc

- 3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A

,~ f .I Address, .. ,Ala ul d:am

4. Identification of System RH Code Class 2

5. (a) Applicable Construction Code ASA 300 Edition.

Addenda Code Case '

(b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 12 RHR Discharge Pump Line Crane

RH-2-1 Corrected _I valve

!A_-.

7. Description of Work Replaced body to bonnet fasteners.

8. Tests conducted: Hydrostatic ] PneumatcL Nominal Operating Pressure R Exemptr1 P NOP psi T Other LI .Pressure NOP psi Test Temp. NOT °F Other:

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 112 in. x 11 in., (2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form. . ?i

I9. Remarks PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-063 I

M CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp Al/a-Certificate of Authorization No. I// Expiration Date Signed _ ASME Program Engineer Date _ _?/_

_ _A_

_ _ Y _

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnc;nt; and employed byHsR Insp ;nd Ins- Co of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period M8JULCoq to 19J4AI. , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owners Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

,#/Nj&ej /2 o Commissions I &.7.5 Au/ MJ0192W Uspector's Sig suture National Board, Province and Endorsements Date I , DALM&U 19 , 4061c; K-)

PRAIRIE ISLAND NUCLEAR GENERATING .PLANT . - - -

-. * - , ,. ; . . , . * ' . . . , - . I FORM NIS-2 OWNER'S REPORT FOR REPAIRI REPLACEMENT ACTIVITY ITEM 1-22-064

1. Owner Nuclear Management Company, LLC Date 11/30/2004 Name

2. Plant - Praire Island Nuclear Generating Plant -- Sheet - 1 of 2 Name . . . . .

1717 Wakonade Dr. E, Welch Minnesota 55089 0209698, EEC-1359 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner ....- .- -- .

Type Code Symbol Stamp N/A

- - - - - ~Name .- _ --

Same - Authorization NA Address - Expiration Date N/A

4. Identification of System RH Code Class , 2 S. (a)Applicable Construction Code ASA 300 : , Edition

'Addenda Code Case (b) Applicable Edition of Section Xl Utilized for RepairlReplacement Activity 1989 With No Addenda

(c) Applicable Section Xl Code Cases None

6. Identification of Components l Component Name l Manufacturer Manufacturer I Nat'l Bd # Other ID lYr Built Corrected, lASME l I1 RHR HX Tube Inlet

7. Description of Work Replaced body to bonnet fasteners.

8. Tests conducted: Hydrostatic E PneumatlcE] Nominal Operating Pressure i ExemptR]

Other Pressure NOP psi Test Temp. NOT OF Other:

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1)size is 8 1 /2 In.x 11 in., (2) information initems I through 6 on this report is included on each sheet, and (3)each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY i

ITEM 1-22-064

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp Certificate of Authorization No. 1//4 Expiration Date Signed , ASME Program Engineer Date _ _ _ _ _ __ _

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnfntn - and employed byHs Rlnsp ;nd Ins Cn of Connerticut of Hartford Conn. have inspected the components described in this Owner's Report during the period owvJot4 to

/qj ,4A 4 C6 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Lu2 Commissions 4I$qc&5 A.iJ91 Insp ts Signatur National Board, Province and Endorsements Date t,

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY 1.I .- Ia I

. T,EM ITEM 2 1-22-065 I

1. Owner Nuclear Management Company, LLC Date 1/10/2005 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 - 0304370, EEC-1310 - --

Address - - V -Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization- N/A - --

- - Expiration Date - N/A -

Address

4. Identification of System VC - Code Class 2

5. (a) Applicable Construction Code ASME VIII 2001 Editi on Addenda 2003 Code C.3se (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name

.Name __

Manufacturer NS.

-- _- Manufacturer Serial_# - - -

r -, -

Nat'l Bd #

Other ID Yr Built Corrected, ASME Removed, or Code Installed or ao 11/12 RC PMP Dch relief valve Crosby VC-25-1 1968 Removed 11112 RC PMP Dch relief valve Crosby - 08975 - VC-25-1 . 2003 Installed _

7. Description of Work Replaced relief valve for IST testing.

8. Tests conducted: Hydrostatic M Pneumatic LI Nominal Operating Pressure Cl Exempt E; Other Pressure - - . psi . TestTemp.

Other: The replacement valve was subjected to a functional test at the factory. -

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet Is numbered and number of sheets is recorded at the top of this form.

. - . .:. , 1 .

p PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-065 I

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp Certificate of Authorization No. Expiration Date Signed ASME Program Engineer Date _________

Owner or Owners Designee. Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnpcntn and employed byHSR ln;p sn Ilns Co of Connecticuit of Hartford Conn. have inspected the components described in this Owner's Report during the period O6AL ot to

______S , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions I.I &TS E M'" 1J2y (LInspector's.SWgrature National Board, Province and Endorsements Date aLi 'e /0 9/40S

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-066 I

1. Owner Nuclear Management Company, LLC Date 10/11/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet I of - - 2

- .Name-1717 Wakonade Dr. E, Welch Minnesota 55089 0309378 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same - Authorization N/A Address Expiration Date NIA

4. Identification of System SG Code Class 2

5. (a) Applicable Construction Code B31.1 1-967 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None

6. Identification of Components Mauacue atd#. Ote ID YrBit Crrce, AM Nam Copnn Component Name Manufacturer Manufacturer Nat'l Bd # - I Other.ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp SG Snubber Block Valve McDowell Welman 72218-000-04 1 12 SIG e4 11969 Removed El SG Snubber Block Valve McDowell Welman 72218-000-018 I .I . Ir i 2 SIG-0 j1969 III Installed J E

. Ar ,

. I 1. .

. a .1V, Vx- C4

7. Description of Work Replaced valve block.

8. Tests conducted: Hydrostatic E] Pneumatic - Nominal Operating Pressure Li ExemptR Other El Pressure psi Test Temp.

" . -, . . I.- - 1 .' .1 . I Other: n/a - :

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1)size Is 8 1/2 in. x 11 In., (2) information in items 1 through 6 on this report is Included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-066

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code.Section XI.

Type Code Symbol Stamp It Certificate of Authorization No. a/ Expiration Date Signed L ASME Program Engineer Date /o/k//hy _

Owner or Owne's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of MinnPcfrn and employed byHs.lr-- p Ins Co of Connecticut Ind of Hartford Conn. have inspected the components described in this Owner's Report during the period )8Jo o4 to III cIcoun , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

GD ;Q Commissions 4aBqo0IS AtI ffiJ i9.2q Inspector's Si ature National Board, Province and Endorsements Date ve1i ,? , ,

- - - 2 I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FR I R FORM NIS-2,OWNER'S -REPORT FOR REPAIR/ REPLACEMENT ACTIVITY

.. - F .. R R A ITEM 1-22-067 T

I

1. Owner Nuclear Management Company, LIC Date 10/11/2004 Name

2. Plant Praire Island Nuclear Generating Plant . - . .S- Sheet -- 1-- of - 2

- - .. .Name _- ..

1717 Wakonade Dr. E, Welch Minnesota 55089 0309311 Address Repair Organization P.O. No., Job No., etc 3.' Work Performed by Owner - . .

Type Code Symbol Stamp N/A Name .....

Same . Authorization N/A Address Expiration Date N/A

4. Identification of System SG Code Class 2

5. (a)Applicable Construction Code B31.1 1967 .

Edition Addenda n/a . Code Case n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp SG Snubber Block Valve McDowell Welman 72218-000-20 11 S/G01 1969 Removed l SG Snubber Block Valve McDowell Welman 72218-000-15 11 S/G 01 1969 Installed [

7. Description of Work Replaced valve block.

8. Tests conducted: Hydrostatic [3 Pneum tic[] Nominal Operating Pressure [3 Exempti Other Ej Pressure psi Test Temp. -. - F 1 , I 1 .. , , ._

Other: -n/a - - - - - -- - - - -.. .-- }

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 In. x 11 in., (2) information in items I through 6 on this report is Included on each sheet, and (3) each sheet is numbered and number of sheets -

is recorded at the top of this form.

-s.,*:

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-067

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp Certificate of Authon Expiration Date

-+/-/

Signed . ASME Program Engineer Date _ _ __ _ _

Owner or Ownees Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of MinnPcnt;; and employed byHSR Insp and Iln Co of Cnnnerticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 8 JULO4 to Is________and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions J43 eo1S5 Q1 my ^xaq

r In ec or's Signature National Board, Province and Endorsements Date r" , Am

./d 1

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT-FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-068

1. Owner Nuclear Management Company, LLC Date 11/30/2004 Name

2. Plant Praire Island Nuclear Generating Plant - - Sheet 1 of 2

- Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0309476. 0309477. DCP03SGO5 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System SG Code Class 2

5. (a) Applicable Construction Code B31.1 , 1967 Edition

- Addenda Code Case (b) Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Steam Gen. 3" external recirc. - = = Installed Line

7. Description of Work Install external recirc. piping and valve.

8. Tests conducted: HydrostaticEZ Pneumatic Nominal Operating Pressure LI Exemptn Other , Pressure 1360 psi Test Temp. 84 F Other:

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet Is numbered and number of sheets.

is recorded at the top of this form.

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-068 I

9. Remarks This work is part of the replacement of the Unit 1 Steam Generators.

CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp Certificate of Authoriz a Expiration Date Signed ASME Program Engineer Date _______

Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnp-qtn and employed byHSR lnsp and Ins Co of Connpcticrit of Hartford Conn. have inspected the components described in this Owner's Report during the period Z3JtLxo to

/2 Jo4A/OS , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

el!<er' Sgal:

P. ) Commissions L 1q 6,sM A.,. -

National Board, Province and Endorsements Date I YAR ,

A) ,Oos

<A I Ye C/

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY -

ITEM 1-22-069

1. Owner Nuclear Management Company, LLC Date 11130/2004 Name

2. Plant Praire Island Nuclear Generating Plant - - - Sheet 1 . . of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0309476, 0309478, DCP03SGO5 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner -. ~#~

Type Code Symbol Stamp N/A

- . - Name . -

Same -Authorization N/A Address Expiration Date N/A

4. Identification of System SG Code Class 2

5. (a) Applicable Construction Code B31.1 , 1967 Edition Addenda . Code Case (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer, - Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Steam Gen. 3" external recirc. . . . . Installed _

Line

7. Description of Work Install external recirc. piping and valve.

8. Tests conducted: Hydrostatic

Pneumatic : Nominal Operating Pressure LI Exempts

-Other Pressure 1360 psi Test Temp. 84 F Other: .

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3)each sheet is numbered and number of sheets is recorded at the top of this form.

F

9. Remarks PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY -

This work is part of the replacement of the Unit 1 Steam Generators.

ITEM 1-22-069 CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp Certificate of Authorization m/> Expiration Date Signed ,ASME Program Engineer Date _ _ _ _ __ _

Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnp<qtn and employed byHSR lnsp snd Ins (Do of Connpcticut of Hartford Conn. have inspected the components described in this Owner's Report during the period .23JoLto to 12JAdits , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owners Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

diuIn pectors Sigdature . Commissions So_I&ES m MA21qlq National Board. Province and Endorsements Date - Araaa i2Qob-K- J

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S -REPORT FOR-REPAIR/ REPLACEMENT ACTIVITY-ITEM 1-22-070

1. Owner Nuclear Management Company, LLC Date 11/1/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 - of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 030971 1, EEC-1505 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A

- Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System RH Code Class 2

5. (a) Applicable Construction Code ASA 300 - . Edition Addenda Code Case (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xi Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 12 RHR Crossover Inlet valve Crane 1968 Corrected

7. Description of Work Replaced body to bonnet fasteners.

8. Tests conducted: Hydrostatics Pneumatic -'.Nominal Operating Pressure E ExemptR Other E Pressure

psi Test Temp. 0 F

Other:

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 12 in. x 11 in., (2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

.1 - -

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY I

ITEM 1-22-070

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp A //4 Certificate of io o. // Expiration Date Signed . . ASME Proqram Enqineer Date _ _ _ __ _

Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed byHSR lnsp and Ins Co of Connectiutit of Hartford Conn. have inspected the components described in this Owners Report during the period .2JUL04 to 01 N104 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions Ci mssnH 1om r4aiq-L4 Pnsj5ectors Signat National Board, Province and Endorsements

%--1 Date t-/'1ftJkLA CS( _ .

L2

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORTL FOR REPAI REPLACEMENT ACTIVITY ITEM 1-22-071

1. Owner Nuclear Management Company, LLC Date 10/17/2004 Name

2. Plant Praire Island Nuclear Generating Plant - - Sheet I - of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0310190, EEC-1505 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner - -- -

Type Code Symbol Stamp N/A

-- Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System RH Code Class 2

5. (a)Applicable Construction Code ASA 300 - - Edition

.. '.t .Addenda ___________ . Code Case (b) Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacurer I NatVl Bd # Other ID Yr Built I Corrected, ASME

.7. Description of Work Replaced body to bonnet fasteners.

8. Tests conducted: . HydrostaticE] PneumaticE '.Nominal Operating Pressure ,1 Exemptj OtherD- Pressure Psi Test Temp. . F

,Other:

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 Id.x 11 in., (2) information In Items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form. - -j

- I PRAIRIE SLAND NUCLEAR GENERATING PLANT FORM NIS-2'OWNER'S R1EPORT FOR R'EPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-071

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp ,A/,4 Certificate of Authorization No. Expiration Date Signed ASME Program Engineer Date /d / 7 .

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnimrt- and employed byHsB lnp I nsInd Co of Connecticut of Hartford Conn: have inspected the components described in this Owner's Report during the period 4BJULOq to

__ __ro _ , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

.___CIO_. Commissions i's _ 4A/1

__Qos

191 Insp__cto__ SignatuCpm m n National Board, Province and Endorsements C-:#/ \

Date

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-72 OWNER'S REPORT FOR REPAIR/ REPLACEMENT-ACTIVITY ITEM 1-22-072

1. Owner Nuclear Management Company, LLC Date 1118/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet I of 2 Name .

1717 Wakonade Dr. E, Welch Minnesota 55089 0302035 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name - -

Same Authorization N/A Address Expiration Date N/A

4. Identification of System AF Code Class 3

5. (a) Applicable Construction Code B16.34 , . Edition Addenda Code Case (b) Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID. Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 12 MD AFW PMP Suct. Valve Velan . MV-32335 Corrected El

7. Description of Work Replaced body to bonnet fasteners.

8. Tests conducted: Hydrostatics PneumaticFi Nominal Operating Pressure LI Exempti Other LI Pressure psi Test Temp. OF Other:

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-072

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp a/a4 Certificate of Aution No. 82// Expiration Date Signed (9 e , ASME Program Engineer Date //_/__/_ _

Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnp-,nt- and employed byHSR Insp ;nr Ins CQo of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period a24IX74 to It,.zvoL4 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions J q 1&S5 WI Mi'-t 3PZ1 I .

'j (9ector's Signatbre

^ x National Board, Province and Endorsements Date vuldw I q , qol

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-073

1. Owner Nuclear Management Company, LLC Date 1112/2005

-- Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2

--- Name - - -

1717 Wakonade Dr. E, Welch Minnesota 55089 0309410, 0309412, 0306712 Address Repair Organization P.O. No., Job No., etc.

3. Work Performed by Owner Type Code Symbol Stamp N/A Name -

Same Authorization N/A Address Expiration Date NMA

4. Identification of System CC Code Class 3

5. (a) Applicable Construction Code ASME 1ll, Class C - 1968 Edition Addenda - Code Cases _ _._.

- N (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1989 With No Addenda .

(c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer. NatVI Bd # Other ID Yr Built Corrected, ASME Name Serial # - Removed, or Code Installed Stamp 11 CC Heat Exchanger Yuba 69G229-1A 1890 135-031 1969 Corrected _

7. Description of Work Replaced end flanges and covers; attached lifiting lugs to the end covers, and performed shell weld repairs as necessary to remove pitting of internal surfaces.

8. Tests conducted: Hydrostaticg -PneumatIcZ "Nominal Operating Pressure [2 Exempt F P r e s s r . e. T T . .N Other F1 Pressure - 165 - psi Test Temp. . NOT ° F' Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in tems 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM, NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-073

9. Remarks n/a CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp ///11 Certificate of Authorization N . 4//4 Expiration Date Signed , ASME Program Engineer Date 1/121/a___

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owners Report during the period 2LJOL O4 to rZJ<,J 0s , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owners Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

4

0afii;), Commissions o5 W'AS PA. mdal Inspector's S!nature National Board, Province and Endorsements Date 2^- .. UA4 4/ , XS j kV

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT

. FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-074

1. Owner Nuclear Management Company, LLC Date 1/21/2005

- I Name -

2. Plant Praire Island Nuclear Generating Plant - - Sheet 1 of . 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0309418 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name - - --

Same Authorization N/A Address Expiration Date N/A

4. Identification of System CC Code Class 3

5. (a) Applicable Construction Code ASME IlIl, Class C - 1968 Edition Addenda - Code Cases (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components

7. -,Description of Work Attached lifting lugs to the end covers that will be installed at the next refueling outage.

8. Tests conducted: Hydrostatic 2 PneumaticE Nominal Operating Pressure n Exempt i Other I Pressure psi Test Temp. 0F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

I. . . . .....

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY; ITEM 1-22-074

9. Remarks n/a CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp /I//z Certificate of A rzan Expiration Date Signed . ASME Program Engineer Date /____

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 4'JULCy to a'JAAIoS , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

(>ad d)Of Commissions R Imps Apl rJ -01M I spector's Si ature National Board, Province and Endorsements Date .

1101,.J 4 , gta LI d

j FPRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'SREPORTIFOR REPAIR/-REPLACEMENT -ACTIVITY ITEM 1-22-075

_ . ., . _ h .

1. Owner Nuclear Management Company, LLC Date 11/1212004 Name

- 2. Plant Praire Island Nuclear Generating Plant - Sheet 1 - of 2

-Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0403586 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner -

Type Code Symbol Stamp N/A

- Name Same . * - Authorization N/A

- Address - - . ... Expiration Date N/A

4. Identification of System CL Code Class 3

5. (a)ApplicableConstructionCode B31.1 ' , - 1967 ; Edition Addenda . Code Case (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda

(c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 12 Containment FCU Westinghouse - 174-012 Corrected El

7. Description of Work Replaced flange fasteners..

8. Tests conducted: Hydrostatic - Pneumatic ;Nominal Operating Pressure LI Exempti Other LI - Pressure - Psi Test Temp. - 0F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

'1 I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-075

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp A////

Certificate of Authorization No. ,i//;z Expiration Date Signed 6 2 , ASME Program Engineer Date __________

Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnpiont;- and employed byHsR Insp and In- to of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 93 lu-J o4 to I____OV_04 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xi.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

,,> )Ciu

~

'LUfpector's Sigrature Commissions Se 1bi5 aA J 192I National Board, Province and Endorsements Date Dat 'l#d W4 LI

PRAIRIE ISLAND NUCLEAR GENERATING PLANT . .07- E FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT-ACTIVITY ITEM 1-22-076

1. Owner Nuclear Management Company, LLC Date 10/15/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 . of - 2 Name ._..

1717 Wakonade Dr. E, Welch Minnesota 55089 0300316. EEC-1196 Address Repair Organization P.O. No., Job No., etc

3. -Work Performed by Owner - - - - -

Type Code Symbol Stamp N/A

- .- Name Same Authorization N-ANA Address Expiration Date N/A

4. Identification of System VC Code Class ..

5. (a)Applicable Construction Code ASME : .I1968 l Edition Addenda . . Code Case (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xi Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME

7. Description of Work Replaced flange to head fasteners.

8. Tests conducted: Hydrostatics Pneumatico Nominal Operating Pressure ExemptR]

- Other Pressure . Psi Test Temp. OF Other: n/a NOTE: Supplemental sheets In form of lists; sketches.:or drawings may be used, provided (1) size is 8 1 /2 in. x 11in., (2)>

Information In items 1 through 6 on this report Is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY

9. Remarks ITEM 1-22-076 I

11 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp //14 Certificate of Authorization No. A/dA Expiration Date Signed _ . ASMErProgram Engineer Date _ ______ __ _____

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnrpgntp and employed byHSR lnsp and Ins Co of ConnPcticiAt of Hartford Conn. have inspected the components described in this Owners Report during the period 9JULO4 to 1serc/r , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neitherthe Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

I ,,/Inspector's Unature

_ Commissions LA AT"' f~171 National Board, Province and Endorsements Date /7Z- I- ,A 5 .. atn

PRAIRIE ISLAND NUCLEAR GENERATING PLANT--

FORM NIS-2 OWNER'S REPORT, FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-077

1. Owner Nuclear Management Company, LLC Date 7/13/2004 Name -

2. Plant Praire Island Nuclear Generating Plant . Sheet . 1 of 2 N~ampe 1717 Wakonade Dr. E, Welch Minnesota 55089 0300828 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Same Authorization N/A Address . .. Expiration Date N/A

4. Identification of System ZH Code Class . 3

5. (a) Applicable Construction Code B31.1 _ .. 1967 Edition Addenda Code Case (b) Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name I Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME

7. Description of Work Replaced discharge flange fasteners.'

8. Tests conducted: Hydrostatic LI Pneumatics Nominal Operating Pressure L Exempt i Other E Pressure psi Test Temp. .F Other: -. * . . . ,

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x I1in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form. _ * . . .

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY

9. Remarks ITEM 1-22-077 I

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp A///A Certificate of Authorization No. W/O Expiration Date Signed _? H' ASME Program Engineer Owner or Owner's Designee, Title Date _ _ _ _ _ _ I __

CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnmcnt: and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period I., 1108LA to 13 3UL O4 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

/J--,1ni r.A0 -- )o Commissions hg&SSt Ac rnjA .19)M

) Inspector's Sgnature National Board, Province and Endorsements Dat )\. p. 4 . -. a j P

PRAIRIE ISLAND NUCLEAR GENERATING PLANT: -

FORM NIS-2 OWNER'S REPORT, FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-078 1

1. Owner Nuclear Management Company, LLC Date 1/12/2005 Name

2. Plant * - Praire Island Nuclear Generating Plant Sheet 1 of 2

- . Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0303945, 0303946. 0303949, DCP03CS02 Address Repair Organization P.O. No., Job No., etc

3. Work Owner Type Code Symbol Stamp N/A Performed by .- Name Authorization N/A Same -Expiration Date NIA Address Code Class 2

4. Identification of System CS

5. (a) Applicable Construction Code B31.1 1989 - Edition Addenda- Code Case (b) Applicable Edition of Section Xl Utilized for Repair/Replace ment Activity 1989 With No Addenda (c) Applicable Section XI Code Cases N-416-2

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 11 CS PMP Test Dsch. 2nd Isol. CS-26-3 Installed 11 CS PMP Test suct. Isol. CS-26-5 Installed - O 12 CS PMP Test Dsch.1 st Isol. l CS-26-2 Installed L 12 CS PMP Test Dsch. 2nd Isol. CS-26-4 Installed El 12 CS PMP Test suct. Isol. CS-26-6 Installed' .

6" Containment Spray Piping 6-CS-32 Installed L 6".Containment Spray Piping - , ; 6-CS-35 Installed , a CS System Hanger - . - . . 1-CSH-2 Removed L 8" Containment Spray Pipe -. - 8-CS4 Removed - L 8x8x6 Tee Containment Spray . 8-CS-4 Installed L line l l 1 l 11 CS PMVP Test Dsch. 1st Isol. CS-26-1 Installed L

7. Description of Work Added recirculation lines to Containment Spray piping. Removed piping support. Replaced support bolting on 11 & 12 CS pumps. _

8. Tests conducted: Hydrostatic- Pneumatic F .Nominal Operating Pressure i; Exempt n Other l Pressure NOP psi Test Temp. NOT 0 F Other: nla NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report Is included on each sheet, and (3)each sheet Is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-078

9. Remarks n/a CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp Aged Certificate of Authorizatio No. A//A Expiration Date Signed , ASMEProgram Engineer Date ///A '/>

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period ckAL6-4 to IVA14 Os , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xi.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

mS(D.CO Commissions SU I'M5 A1 alAC2 U nspector's Si ature National Board, Province and Endorsements Date D1 fIA ,& 5 U)j~J

I PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT'FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-079

1. Owner Nuclear Management Company, LLC Date 11/1/2004 Name

2. Plant Praire Island Nuclear Generating Plant

Sheet I of 2 -

Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0403587. EEC-1 096 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner - - -

- Type Code Symbol Stamp N/A

- - ~~Name . .

Same - Authorization N/A Address Expiration Date - N/A

4. Identification of System MS Code Class .. 2

5. (a)Applicable Construction Code B31.1 1967 - Edition Addenda . Code Case (b) Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID' Yr Built Corrected, ASME Name Serial #Removed, or Code

_ Installed Stamp 11 SG MS HDR Relief Valve Consolidated RS-21-3 . Corrected - [

11 SG MS HDR Relief Valve Consolidated RS-21-5 Corrected _

7. Description of Work Replace flange fasteners.

8. Tests conducted: Hydrostatic - Pneumatics Nominal, Operating Pressure. j Exempt i O h. .e -,

Other 0 Pressure Ipsi Test Temp. °F

.. I,

, ., I . *- ,. I I .

Other: . . - .

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

I:PRAIRIE I

ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-079

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp A//4 Certificate of Authorization No. Al Expiration Date Signed ASME Program Engineer Date ////ah Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnpcnti and employed byHsR Insp snd Ing Co of Cronnrcrtirtit of Hartford Conn. have inspected the components described in this Owner's Report during the period rRsEP6i to 6u AoV 04 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owners Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions Commission C.ss AdJ, Inspecte Ssignaturellj National Board, Province and Endorsements Date Date bin fL , n,g &aoI

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/IREPLACEMENT ACTIVITY

;ITEM 1-22-080 .

1. Owner Nuclear Management Company, LLC Date 11712005 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 - 0301139 Address - - -- -Repair Organization P.O. No., Job No., etc -

3. Work Performed by Owner Type Code Symbol Stamp NMA Name Same -- - - ----- Authorization --- NIA Expiration Date . NIA Address

4. Identification of System CS Code Class 2 r5 (al Annfie-ahip Cnn_~tnjnrtinn CnrIl. n/a Edition Addenda Code Case (b) Applicable Edition of Section Xl Utilized for RepairlReplacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components

7. Description of Work Replaced mechanical seal Icluding gland plate.

8. Tests conducted: Hydrostatic E Pneumatic E Nominal Operating Pressure D Exempt i .

Other El Pressure psi Test Temp. 0 F Other: nla NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

AH, X .

I I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-080

9. Remarks n/a CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp ,la Certificate of Authorization No. _ _ _ _ _ Expiration Date Signed _ , ASME Program Engineer Date _/_/______

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnpcnti and employed byHsR lnsp ;nd Ilns Co of Connerticut of Hartford Conn. have inspected the components described in this Owner's Report during the period ns Ao& o4 to

__J___OS_- , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions C omisi15 onsA rtnlJv{i

'(_jpector's Sigdature National Board, Province and Endorsements Date 1/ 10 I qoas

-PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR! REPLACEMENT ACTIVITY:

ITEM 1-22-081

1. Owner Nuclear Management Company, LLC Date 1012612004 Name - - .

2. Plant Praire Island Nuclear Generating Plant . . Sheet . - 1 . of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0407196, SPCE-ME-0453 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name .......

Same - Name . Authorization NMA Address Expiration Date N/A

4. Identification of System VC Code Class . . 2

5. (a) Applicable Construction Code n/a n/a , . Edition

. Addenda n/a Code Case n/a (b) Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID . Yr Built Corrected, ASME Name Serial# Removed, or Code Installed Stamp 12 BATP Goulds . . 792A190-2 ; . 145-612 . Corrected E]

7. Description of Work Replaced the mechanical seal gland plate.

8. Tests conducted: Hydrostatic El Pneumatic *- Nominal Operating Pressure E] Exempt R Other E - Pressure - - psi Test Temp. . OF Other: n/a NOTE: Supplemental sheets In form oflists, sketches, or drawings may be used, provided (1) size Is 8 1 12 in. x 11 in., (2) information In items 1 through 6 on this report Is Included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

i

9. Remarks n/a PRAIRIE ISLAND NUCLEAR GENERATING PLANT

FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-081 I

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code.Section XI.

Type Code Symbol Stamp ,4/.

Certificate of Author ,. IV! Expiration Date Signed , ASME Program Engineer Date _ _ _ _ _ _ _

Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnpcrst; and employed by HSR8lnsp and ins Co of Qonnprtiriut of Hartford Conn. have inspected the components described in this Owner's Report during the period IZ5EPoq to 80crOa* e, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions .A alq"t AH., m"J~,'9124 I / nnspector's Si nature National Board, Province and Endorsements Date 7 4p, e4 8 , -

FOR N PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FORREPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-082

1. Owner Nuclear Management Company, LLC Date 11/11/2004 Name

2. Plant Praire Island Nuclear Generating Plant - Sheet I of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0407276 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name Type Code Symbol Stamp N/A Same Authorization N/A

.ynirntinn Date F.MA

. -. ~~Address. -- r-

4. Identification of System MS Code Class

2

5. (a)Applicable Construction Code B16.5 XH-1112 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 11 MSIV Shutte & Koerting n/a CV-31098 1970 Corrected

7. Description of Work Replaced disc.

8. Tests conducted: Hydrostatic L Pneumatic .,Nominal Operating Pressure Exempt E Other Pressure psi Test Temp. OF Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 In.x 11 in., (2)

Information in items 1 through 6 on this report is included on each sheet, and (3)each sheet Is numbered and number of sheets is recorded at the top of this form.

I I I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-082

9. Remarks None.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp Certificate of Authorization No. Expiration Date Signed ASME Program Engineer Date _ _ _ __ _

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of MinnAgntn and employed byHsR Insp ;nd In, Co of Connecticiit of Hartford Conn. have inspected the components described in this Owner's Report during the period GSFPo0. to 03IA w , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

lq2\ an ow Commissions 4laioss 44 i 1d"i9z lnspectors Shnature ~ National Board, Province and Endorsements L-0 ,

Date 7

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT. FOR-REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-085

1. Owner Nuclear Management Company, LLC Date 111912004 Name -

2. Plant Praire Island Nuclear Generating Plant Sheet 1. of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0407291 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner - -

Type Code Symbol Stamp N/A

- Name Same - Authorization N/A Address Expiration Date N/A

4. Identification of System AF Code Class 2

5. (a) Applicable Construction Code B31.1 1967 Edition

'Addenda Code Case (b) Applicable Edition of Section Xl Utilized for RepairlReplacement Activity 1989 With No Addenda (c) Applicable Section Xi Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Spring Hanger Basic Engineers . 1-AFWH-88 Corrected O

7. Description of Work Reassembled spring hanger.

8. Tests conducted: Hydrostatic Pneumatico Nominal Operating Pressure Exempti Other 0 Pressure psi. Test Temp. F Other: VT-3 NOTE: Supplemental sheets in form of lits,'sketches, or drawings may be used, provided (1) size is 8 1 i2 in. x 11 in., (2) information In Items 1 through 6 on this report is included on each sheet, and (3)each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-085

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp t//.

m NO.

Certificate of Authorization 1A/Z Expiration Date_ _

Signed ASME Program Engineer Date ///

Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnp-,ntn and employed byHSR lnsp and Ins Co of Connnrtirut of Hartford Conn. have inspected the components described in this Owner's Report during the period PotA to it Moven , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

sector's Signatae S

CMQ Commissions o( I-90sr A41 njI 19q4 National Board, Province and Endorsements Date G il '2 , i20a

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-086

1. Owner Nuclear Management Company, LLC Date 12/3/2004 Name

2. - Plant Praire Island Nuclear Generating Plant Sheet - 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0407778 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner

- amee-Nam - -Type Code Symbol Stamp NMA Same Authorization N/A Address Expiration Date N/A

4. Identification of System RH Code Class 2

5. (a) Applicable Construction Code ASME ll, 1968 Edition Addenda Code Case (b) Applicable Edition of Section XI Utilized for RepairlReplacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 11 RHR Heat Exchanger Joseph Oats 1817-1A : 340 135-051.* 1968 Corrected

7. Description of Work Replaced flange fasteners.

8. Tests conducted: Hydrostatics E PneumatlcF1" - INominal Operating Pressure ExemptrJ Other Pressure NOP. - PSI Test Temp. NOT OF Other:

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 in. x 11 in., (2) :2 information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.. . .

PRAIRIE ISLAND NUCLEAR GENERATING PLANTI F FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY

9. Remarks ITEM 1-22-086 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp Certificate of Au tiNo. $/4 Expiration Date Signed ASME Program Engineer Date /2k/d Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minn-,ot;; and employed byHsR Insp and Ins Co of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period ./Swoi to

__D___co_ ,and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

C;6- I Q-2 C*jpector's S'lghiature Commissions 4 BJ10S As.55 M,,7lq921 National Board, Province and Endorsements Date .- q

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S.REPORTFOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-087

1. Owner Nuclear Management Company, LLC Date 11130/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2

- Name 1717 Wakonade Dr. E. Welch Minnesota 55089 0407227 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner -.

Type Code Symbol Stamp N/A Name - -

Same Authorization - N/A Address Expiration Date N/A

4. Identification of System RH Code Class 1

5. (a)Applicable Construction Code B16.34 , - - Edition Addenda . Code Case (b) Applicable Edition of Section XI Utilized for RepairlReplacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp RCS Lp B hot leg RHR Sup. Velan MV32231 Corrected -

7. Description of Work Replaced body to bonnet fasteners.

8. Tests conducted: Hydrostatics Pneumaticjj Nominal Operating Pressure Exempt L Other Pressure -NOP psi TestTemp.* NOT :F Other:

NOTE: Supplemental sheets In form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2)-

information in items I through 6 on this report is Included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY

9. Remarks ITEM 1-22-087 I

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp Certificate of Auth o 5No. , // Expiration Date Signed ASME Program Engineer Date _ _ _ _& __ _

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of MinnPontn and employed byHCR ln,;p and Ins Co of Connpnticut of Hartford Conn. have inspected the components described in this Owner's Report during the period .29 SepoV to

_______E__4 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions sf.Idos AAi, M41T9V4 I~yclor's Signatiure National Board, Province and Endorsements Date lt!9L -Q tm~l ~8 q00%4

. PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT.FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-088

1. Owner Nuclear Management Company, LIC Date 11/1512004 Name -

2. Plant Praire Island Nuclear Generating Plant _ Sheet - - '- - of -- 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0401076 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name . -- - -

Same -- ;:-,Authorization NM Address Expiration Date N/A

4. Identification of System VC Code Class . 2

5. (a) Applicable Construction Code n/a - , n/a Edition

- -.Addenda n/a Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xi Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer l NatI Bd # Other ID - Yr Built Corrected, ASME

7. Description of Work Replaced charging pump packing assemblies.

8. Tests conducted: Hydrostatic,0 Pneumatic . Nominal Operating Pressure f-

ExemptW Other E] Pressure -*. Psi Test Temp. OF

- . ; ' - l1 Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 In. x 11 in.; (2) information in items 1through 6 on this report is Included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-~2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-088

9. Remarks n/a CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp Certificate ofAutheori o. .No.Expiration Date Signed ASME Program Engineer Date y _____/__

Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION I; the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minningti and employed byHts lnsp and Ins Co of Connecticrtt of Hartford Conn. have inspected the components described in this Owner's Report during the period Ae S°oo:4 to

/9 A16V o0 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owners Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions AfS *1Wt MJe,91 Ipector's Sig ure National Board, Province and Endorsements Date L'ui /q , __aw _

7

FOR N- -PRAIRIE ISLAND NUCLEAR GENERATING PLANT.

FORM NGS-2 OWNER'S -REPORT FOR REPAIR/ REPLACEMENIT ACTIVITY2 U . - ITEM 1-22-089

1. Owner Nuclear Management Company, LLC Date 10/2912004

' Name

2. Plant Praire Island Nuclear Generating Plant - Sheet - 1 of . 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0407257 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name -

Same . Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code n/a n/a K' Edition -

Addenda n/a Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer I Nat'l Bd # Other ID Yr Built Corrected, ASME

'7. Description of Work Replaced the mechanical seal gland plate and 1 casing fastener assembly.

8. Tests conducted: Hydrostatic O PneumaticF . Nominal Operating Pressure Exempt E Other LI Pressure psi Test Temp. F Other n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 In.x 1 in., (2) information in items 1 through 6 on this report is Included on each sheet, and (3)each sheet is numbered and number of sheets is recorded at the top of this form.

I' I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-089

9. Remarks n/a CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp A1/a Certificate of Authoi 4/ Expiration Date Signed ASME Program Engineer Date Id/__ a __ _

Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnpqnta and employed byHsR Insp -nd Ing Co of Connecticut of Hartford Conn, have inspected the components described in this Owner's Report during the period OsE?6 to oIA/oV oq , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xi.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

62?<4V2 O0-f Commissions Ia /oAs iI/ II 1W

&sp'ector's Signao~re National Board, Province and Endorsements Date -7/~Ildl&4 i

PRAIRIE ISLAND NUCLEAR GENERATING PLANT.

FORM NIS-2 OWNER'S.REPORT FOR REPAIR/ REPLACEMENTACTIVITY ITEM 1-22-090

1. Owner Nuclear Management Company, LLC Date 11130/2004 Name

2. -Plant Praire Island Nuclear Generating Plant .Sheet I of - -2

- .-* -Name. : .

1717 Wakonade Dr. E, Welch Minnesota 55089 0407376 Address Repair Organization P.O. No., Job No., etc

-3. Work Performed by Owner - ---

Type Code Symbol Stamp N/A

- -Name - ----

Same - - , Authorization N/A

-Address -Expiration Date .N/A

4. Identification of System AF Code Class 3

5. (a) Applicable Construction Code B31.1 _ : - - 1967 - Edition

'.,Addenda Code Case (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases N.416-2

6. Identification of Components Component Name Manufacturer - Manufacturer - Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial# Removed, or Code Installed Smp AF piping -- . . . -

6-MS-8 Corrected _ J

7. Description of Work Corrected piping configuration for rupture disc holding flanges.

8. Tests conducted: - Hydrostatic PneumaticE - Nominal Operating Pressure E -Exempt

-

Otherf- Pressure -NOP . Psi . TestTemp. - NOT OF Other:

NOTE: Supplemrnetal sheets in form of lists, sketches, or drawings may be used, provided (1) size Is 8 112 in. x 11 in'. (2) information in Items 1 through 6 on this report is included on each sheet, and (3)each sheet is numbered and number of sheets is recorded at the top of this form.

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY

9. Remarks ITEM 1-22-090 I

CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp //4-Certificate of Authorization No Expiration Date Signed , ASME Program Engineer Date /1/3(1/y Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of MinnPcznt- and employed byHSB Insp and In- (Cn of Connectictit of Hartford Conn. have inspected the components described in this Owner's Report during the period Of OCr 04 to dQ 8&e o- , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions

.s Signature National Board, Province and Endorsements L " "9, n, L,

PRAIRIE ISLAND NUCLEAR GENERATING PLANT, FORM NIS-2:OWNER'S REPORT FOR-REPAIR/-REPLACEMENT ACTIVITY- .

ITEM 1-22-091

1. Owner Nuclear Management Company, LLC Date 12/1/2004 Name

2. Plant Praire island Nuclear Generating Plant --Sheet I of 2

- - Name- -

1717 Wakonade Dr. E, Welch Minnesota 55089 0305017 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner -

Type Code Symbol Stamp N/A

- - - - - ~Name- - -

Same - Authorization N/A Address Expiration Date N/A

4. Identification of System RC Code Class I

5. (a) Applicable Construction Code B31.1 . , 1967 . Edition Addenda Code Case (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases N-416-2

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Charging line isolation valve Rockwell Edwards 501148 RC-1--18 Removed - e Charging line isolation valve Rockwell Edwards RC-1-18 Installed _

7. Description of Work Replaced valve.

8. Tests conducted: Hydrostatic ,P eumatic Nominal Operating Pressure Exempto Other U Pressure NOP psi Test Temp. NOT F Other: .7 NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1)size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is Included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR] REPLACEMENT ACTIVITY I

ITEM 1-22-091

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp 4114 Certificate of Authorization N o. A4 Expiration Date .

Signed ASME Program Engineer Date /___ yI _ _

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION l, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minntc-,ntn and employed b yHsR lnsp and lns. Co of Connectirut of Hartford Conn. have inspected the components described in this Owner's Report during the period 04it'ioL to cY? ieco'4 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

eL It O-f) nP 2pector's Sigr3Ature Commissions National Board, Province and Endorsements Date/ zl afe -C;, Law

l PRAIRIE ISLAND NUCLEAR GENERATING PLANT lFORM NIS-2 OWNER'S REPORT-FOR bREPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-093

1. Owner Nuclear Management Company, LLC Date 111212004 Name

2. Plant Praire Island Nuclear Generating Plant - Sheet - 1 of 2

.- Name. . .

1717 Wakonade Dr. E, Welch Minnesota 55089 WO-0407875 Address Repair Organization P.O. No., Job No., etc

-3. Work Performed by Owner - -- - - - --- .. - - -

Name Type Code Symbol Stamp NMA Same Authorization NMA Address - . Expiration Date N/A

4. Identification of System MS Code Class 2

5. (a) Applicable Constructon Code B31.1 1967 ,Edition

.,Addenda - . Code Case (b) Applicable Edition of Section Xl Utilized for RepalrlReplacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components XComponent Name M . Manufacturer Natl Bd # l Other D Yr Built Corrected, l ASME l Serial # I I

7. Description of Work Weld build up of eroded area.

8. Tests conducted: Hydrostaticn. PneumaticE]- .Nominal Operating Pressure E Exempt Other D Pressure psi Test Temp. - F Other:

NOTE: Supplemental sheets in form of iists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in Items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-093

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code.Section XI.

Type Code Symbol Stamp Certificate of Authoriz ,- Expiration Date_ _ _ _ _

Signed ASME Program Engineer Date 1/4/9/2/y Owner or Ownees Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of MinnAgntn and employed byHSR InSp and Ins Co of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period Zsocr6c4i to

____d_ _t_ , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or -

implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions a6 iQos 1i, "IA Inspector's Ui nature National Board, Province and Endorsements Date u dge ol, n 2o I

FOR N- PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT- FOR REPAIRI REPLACEMENT ACTIVITY ITEM 1-22-094

1. Owner Nuclear Management Company, LLC Date 11/212004 Name

2. Plant Praire Island Nuclear Generating Plant - Sheet 1 of 2 Name 1717 Wakonade Dr. E. Welch Minnesota 55089 WO-0407874 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner - -

Type Code Symbol Stamp N/A Name -

Same Authorization N/A Address Expiration Date NMA

4. Identification of System MS Code Class 2

5. (a)Applicable Construction Code B31.1 ! 1967 , - Edition Addenda Code Case (b) Applicable Edition of Section Xl Utilized for RepalrlReplacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components lComponent Name lManufacturer-, lManufacturer I Natl d# Other ID Yr Built I Corrected, IASME

7. Description of Work Weld build up of eroded area.

8. Tests conducted: . Hydrostaticfl Pneumatico - Nominal Operating Pressure g .. Exemptj Other 0 Pressure - psI Psi Test Temp. °F

, . , , -I Other:

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size Is 8 1 /2 in. x 11 In., (2) information in items 1 through 6 on this report is included on each sheet, and (3)each sheet Is numbered and number of sheets is recorded at the top of this form.

H PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORMINIS-2 OWNER'S REPORT FOR RE PAIR/ REPL-ACEMVENTIACdTIVITY l ITEM 1-22-094

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp A//p Certificate of Authoin No. V// Expiration Date Signed . ASME Program Engineer Date _ ______ ___

Owner or Owner's Designee. Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of MinnPtntq and employed byHIsR InSp and Ing Co of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period os 6rrog to or.doy ov , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the.

requirements of the ASME Code, Section Xi.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

QO I spector's Inature Commissions AlaB ioYs .44' ml alt90q National Board, Province and Endorsements Date ,,e10mb o0 . font

(

PRAIRIE ISLAND NUCLEAR GENERATING PLANT.

FORM NIS-2 OWNER'S -REPORT FOR REPAIR/ REPLACEMENT ACTIVITY, ITEM 1-22-095

1. Owner Nuclear Management Company, LLC Date 11/30/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet - 1 of 2 Name .

1717 Wakonade Dr. E, Welch Minnesota 55089 0400020 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner N Type Code Symbol Stamp N/A

- --- -- Name ------

Same Authorization NMA Address Expiration Date NIA

4. Identification of System VC Code Class 2

5. (a)Applicable Construction Code B16.34 . : . Edition Addenda . Code Case (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer -; Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp RCP Seal Rtrn. Isolation Valve, Aloyco MV-32199 Corrected _

7. Description of Work Replaced body to bonnet fastener.

8. Tests conducted: Hydrostatic - Pneumaticjl Nominal Operating Pressure ExemptW

- Other Pressure T psi Test Temp. - F Other:

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x i1 in, (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

F

9. Remarks PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-095 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp ,/1 Certificate of Authorization No. /u Expiration Date Signed , ASME Proqram Engineer Date 1113_

/____ _ I _

Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnpvt:f and employed byHl,4sBnsp mnd In; Co of Connncticit of Hartford Conn. have inspected the components described in this Owner's Report during the period os ocr o4 to 4'1 L!Yc04 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

)51 Go/n Commissions A/ /fops A"i/ (/4JC/92Y 61 )Inspector's Sig4Ape National Board, Province and Endorsements Date ,v.4 - Z.. !1i ,,, __4

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY I ITEM 1-22-096 I

1. Owner Nuclear Management Company, LLC Date 12114/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 - . 0407857 Address . -.. Repair Organization P.O. No.,-Job No., etc

3. Work Performed by.. SGT Ltd. .

- Type Code Symbol Stamp NPT Name 400 S. Tyron St.. Suite 2100, Charlotte. NC 28285 Authorization N-3090-1 Address - - Expiration Date 6/4/07

4. Identification of System CL ' Code Class 3

5. (a)Appiicable Construction Code B31.1 , 1967 , N i. Edition Addenda Code Case !

(b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases N.416-2

6. Identification of Components

7. Description of Work Replaced Fan Coil Unit piping spooi piece with new pipe and fittings.

8. Tests conducted: Hydrostatic n Pneumatic E J Nominal Operating Pressure i Exempt . I Other f1 Pressure NOP psi Test Temp. NOT

F Other:

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY I

2 ITEM 1-22-096

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp A114 Certificate of Authorization No. _ _//, _ Expiration Date Signed ASME Program Engineer Date //,4 By _

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnocntn and employed byHSR Insp and Ins Co of Connertictit of Hartford Conn. have inspected the components described in this Owner's Report during the period 6?c'roq to t USA 6s , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

I Commissions l rB

/2015 44^1 MJnylas Il jpctor's Signat re National Board, Province and Endorsements Date AIMA fk-i AJ 6r~s J

K)

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-21OWNER'S REPORT.fOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-097

1. Owner Nuclear Management Company, LLC Date 11/30/2004 -

Name

2. Plant Praire Island Nuclear Generating Plant Sheet I --- of - 2 -

-Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0407938, EEC-1546 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner -

Type Code Symbol Stamp N/A

-Name Same Authorization - N/A Address -.

Expiration Date N/A

4. Identification of System Si Code Class 1

5. (a)Applicable Construction Code B16.34 _ - Edition.

KAddenda Code Case (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer ; Manufacturer. Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Hi/Lo Head SIS to 12 RX Vessel Velan = S1-9-5 Corrected _

Nozzle Check Valve

7. Description of Work Replaced the disc assembly.

8. Tests conducted: Hydrostatic E] PneumaticFi Nominal Operating Pressure Li . Exempt W Other Pressure psi Test Temp. F Other: Full open test will be conducted under SP 1092D, The closed test will be conducted during SP 1070. -

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 ln. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3)each sheet is numbered and number of sheets is recorded at the top of this form.

F PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY

9. Remarks ITEM 1-22-097 I

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp Alla Certificate of AAlU o Expiration Date Signed ASME Program Engineer Date '///&1d /dq I Owner or Ownees Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of hAinnintg and employed byH5;R lnp and Ins Co of Connecticut of Hartford Conn. have inspected the components described in this Owners Report during the period og nao' to o3JA4os , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions l QO Mi I 1i5Ai n 19A4 ln'Ve 9or's Signa'i&e National Board, Province and Endorsements Date Date A9-AAALIAnu

-Ii fu CA

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR! REPLACEMENT ACTIVITY

. IE .22 I 1 -0

, . .; . . :. ITEM 1-22-099 -

1. Owner Nuclear Management Company, LLC Date 11312005

- IName

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E. Welch Minnesota 55089 . 0408070 Address - - ~Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner

. Type Code Symbol Stamp NIA Name Same Authorization -- N/A - -

Address Expiration Date I N/A

4. Identification of System VC Code Class 1

5. (a) Applicable Construction Code B16.34 .' Edition Addenda Code Case (b) Applicable Edition of Section Xi Utilized for RepairlReplacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases N416-2

6. Identification of Components Component Name Manufacturer Manufacturer Natl Bd # Other ID Yr Built Corrected, ASME

-. Name - Serial # Removed, or Code

_ _ _ _ Installed Stamp 11 Seal Wtr Injection Check (2") Vogt

VC-8-5 Removed O I11 Seal Wtr Injection Check (2") Vogt 670106990100 VC-8-5 2000 Installed El

7. Description of Work Reolaced Check Valve;

.. . . 1 . . . . . . - -

8. Tests conducted: Hydrostatic El Pneumatic DI Nominal Operating Pressure . _ Exempt E Other n - Pressure . NOP psi Test Temp. . NOT °F Other:

NOTE: Supplemental sheets In form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is Included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

--- - - 0

9. Remarks PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-099 I

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp ad,/,,

Certificate of Aut -rrv Expiration Date Signed . , ASME Program Engineer Date I _____

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnpqntq and employed byHSB Insp and Ins Co of Connecticrit of Hartford Conn. have inspected the components described in this Owner's Report during the period IL0erot4 to

<tS be. oq , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

.. nr0 Commissions a.q"CS MAt M A°ck1 On pector's Signa'ture National Board, Province and Endorsements Date vC -. I I

.I U'

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S -REPORT FOR -REPAI/ REPLACEMENT ACTIVITY ITEM 1-22-101

1. Owner Nuclear Management Company, LLC Date 10/2912004 Name

2. Plant Praire Island Nuclear Generating Plant - - - . Sheet - I of 2 Name - - - -

1717 Wakonade Dr. E, Welch Minnesota 55089 0408126, EEC-1554 e .N.

Address Repair Organization P.O. No., J Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A

- - Name -

Same Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code - B16.34 - Edition Addenda_ - Code Cases -

(b) Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components l Component Name l Manufacturer , Manufacturer I Nat'l Bd # l Other ID l Yr Built I Co 11 Seal Water HX Inlet Grinnel l l VC-6-3 Corrected Li

7. Description of Work Replaced the valve bonnet and fasteners.

8. Tests conducted: Hydrostatics PneumaticL- NominalOperating Pressure , Exempt Wj Other El Pressure . psi Test Temp. °F Other:

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. xI1 in., (2) information in items 1 through 6 on this report is Included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

I " 1.

H PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-101

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp J/4 Certificate of Authorize /14I Expiration Date Signed 67 ASME Program Engineer Date i oh f/c _ _

Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 21ocro'4 to A/ /Jv cc, , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

0J)g~g7 Commissions aiI s5 i, w,92 spe tor's Signatur National Board, Province and Endorsements Date < c I r1 ,

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT.

FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-102

1. Owner Nuclear Management Company, LLC Date 1/13/2005 Name

2. Plant Praire Island Nuclear Generating Plant Sheet .. 1 .of 2 Name - .

1717 Wakonade Dr. E, Welch Minnesota 55089 0408112 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type C ode Symbol Stamp N/A Name Same Authoriization N/A Address Expirat ion Date N/A

4. Identification of System VC Code Class 1

5. (a)Applicable Construction Code B31.1 -1967 Edition

- . Addenda -

Code Cases.

(b) Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial #-Removed, or Code

.Installed Stamp VC System Hanger 1-RCVCH- Corrected

7. Description of Work Repair of weld on integral attachment.

8. Tests conducted: HydrostaticD Pneumatico .Nominal Operating Pressure ] Exempt :

Other Pressure psi TestTemp. - F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-102

9. Remarks n/a CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp IV14 Certificate of Authorizatigfo. _ 1//4 Expiration Date Signed , ASME Program Engineer Date / //2/_ _

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 31 WrfOi to I3JM'5 .. , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

G11' (7:)Commissions a 19%S a I A1:924 IO nector's Sign re National Board, Province and Endorsements Date 4 UA 13 , oo 0 t

R N- PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT-FOR REPAIR/ REPLACEMENTEACTIVITY ITEM 1-22-1 03

1. Owner Nuclear Management Company, LLC Date 11/1812004

'Name -

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name -

1717 Wakonade Dr. E, Welch Minnesota 55089 0408118 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner -

Type Code Symbol Stamp N/A

- - Name.

Same - . Authorization N/A Address Expiration Date NIA

4. Identification of System Si Code Class , 2.

5. (a) Applicable Construction Code B31.1 . 1967 Edition Addenda . . - Code Case !_._'.

(b) Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components l Component Name i Manufacturer l Manufacturer l Nat'l Bd # Other ID l Yr Built I Corrected, l ASME

7. Description of Work Repaired box support.'

8. Tests conducted: Hydrostatic , PneumatIcFj NominalOperatingPressure Exempti Other ' Pressure - . psi -TestTemp.-. OF Other:

.,, \.' -.. . ....

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size Is 8 1 /2 In. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR'REPAIRI REPLACEMENT ACTIVITY

9. Remarks ITEM 1-22-103 I

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp A.//4 Certificate of Authorization No. -Expiration Date Signed P Engineer Date ///a /°I_

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnpqnta and employed byHsR Insp and Ins Co of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period -it xCro to I?Aqod v , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owners Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

,A~f Q~OP Commissions ,/8 iTS AdJI /dA/J/72Y Insp s Sitna)MWr National Board, Province and Endorsements e~l's Date _eJ9 , chao

(

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-104 1

1. Owner Nuclear Management Company, LLC Date 1/13/2005

- -Name -

2. Plant Praire Island Nuclear Generating Plant - - - - - 1 .-- -

of 2

.- -- - - - - Name -.- - .

1717 Wakonade Dr. E, Welch Minnesota 55089 Work Address Repair Organization P.O. No., Job No., etc -

3. WorkPerformed by Owner Type Code Symbol Stamp N/A

- - Name Same - Authorization N/A

- Address Expiration Date N/A

4. Identification of System Si Code Class 1

5. (a) Applicable Construction Code B31.1 1967 Edition

- .. Addenda Code Cases .

(b) Applicable Edition of Section Xi Utilized for Rep air/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components

.. . .-- -. 7 . - . . - : , . . . .. I

7. Description of Work Repair of weld on integral attachment.

8. Tests conducted: HydrostaticM PneumaticE Nominal Operating Pressure ] Exempt i Other [ Pressure ; psi Test Temp. : F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8.1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets Is recorded at the top of this form.

. ...- - I I . 1. , , .. . ' -

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-104

9. Remarks n/a CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp o/14 Certificate of Authoriz >ia). } Expiration Date Signed , ASME Program Engineer Date ___3____

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB lnsp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owners Report during the period 1fl OCT04 to i3Jm bS , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owners Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Q.0 U nspector's Signature Commissions 4saq 5s WI ( 1 National Board, Province and Endorsements Date __ ,

K?

PRAIRIE ISLAND -~ ~NUCLEAR GENERATING

. I .

PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-105

1. Owner Nuclear Management Company, LLC Date 11/8/2004 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0408152, SPCE-ME-0453 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by* Owner Name - Type Code Symbol Stamp N/A Same Authorization NMA Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code n/a n/a ; Edition

.Addenda n/a Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components lComponent Name Manufacturer Manufacturer I Natl Bd# Other ID Yr Built. Corrected, TASME l Name Serial #

12 BATP Goulds 792A1 90-2

7. Description of Work Replaced the mechanical seal gland plate.

8. Tests conducted: -Hydrostaticj Pneumatic[] Nominal Operating Pressure E Exempts Other E Pressure . - : psi Test Temp. F Other: n/a NOTE: Supplemental sheets In form of lists, sketches.-or drawings may be used, provided (1) size is 8 1 12 in. x 11in., (2) information in items I through 6 on this report Is included on each sheet, and (3) each sheet Is numbered and number of sheets is recorded at the top of this form. -

I

9. Remarks n/a PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIRI REPLACEMENT ACTIVITY ITEM 1-22-105 I

E CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code. Section Xi.

Type Code Symbol Stamp A///4 Certificate of Authorization No. A'A4 Expiration Date Signed . ASME Proram Engineer Date / I Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnpc-t- and employed byHSR lncp and Ing Co of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 22ccro'1 to

________ , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective mebsure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

d4xoWQ~C:W Commissions & 19nss PA, MA.IVg~z

'(jn' pector's Sign.iture National Board, Province and Endorsements Date 146,1L4 I9

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT.FOR REPAIR/ REPLACEMENT ACTIVITY M Nm PA RITEM 1-22-107

1. Owner Nuclear Management Company, LLC Date 1/111/2005 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 - 0408547

- - Address - - _.- - - Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner

- - - Type Code Symbol Stamp . -NA Name

- _ Same -- -I --Authorization -- N/A

- - - I Address _. Expiration Date N/A -

4. Identification of System VC

I - - Code Class 2

5. (a)Applicable Construction Code n/a n/a . Edition Addenda n/a - - Code Case n/a (b) Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components

7. Description of Work Replaced assemblies 19, 20, 21 with rebuilt assemblies 7, 8, and 9.

,4: . : , ,:

8. Tests conducted: Hydrostatic a Pneumatic Nomninal Operating Pressure LI Exempt id OtherF Pressure psi Test Temp.- -_° F Other: A non-code leakage exam will be performed.

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x -1 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

.. I

I

9. Remarks PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-107 I

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp ,

Certificate of Authoriza no. _ _ __ __ _ Expiration Date Signed _. ASME Program Engineer Date _/__/_I Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnpc-nt; and employed byHSR ln;p nnd Ins Co of Connfctict of Hartford Conn. have inspected the components described in this Owner's Report during the period i510oq to IlJAOS , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xi.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owners Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions SSIQSS A4i M21W IrVPctor's Signatire National Board, Province and Endorsements Date Date - I1-I I 1lo5 (JY-2

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2-OWNER'S REPORT, FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-108

1. Owner Nuclear Management Company, LLC Date 1113/2005

- Name

2. Plant Praire Island Nuclear Generating Plant - --- Sheet 1 of 2

-- Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0408797 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A

- Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System RV Code Class 1

5. (a)Applicable Construction Code ASME IlIl 1965 - Edition Addenda - Code Cases (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial# Removed, or Code Installed Stamp Rx Head Conoseal #34 Corrected L Rx Head Conoseal #35 Corrected l Rx Head Conoseal #37 Corrected El

7. Description of Work Replaced Marmon Clamp, Fasteners, and Male Flange, and Jackscrews.

8. Tests conducted: Hydrostatic[ Pneumatico Nominal Operating Pressure n Exempt Ed; Other L Pressure psi Test Temp. F Other: Replaced components will be visually inspected for leakage at normal operating pressure and temperature.

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-108 9.Remarks n/a CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp A/14 Certificate oA rz 464$ Expiration Date .

Signed ASME Program Engineer Date Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period r7 ag4e to I3JAA ES , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xi.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

A-,, QC)^

InspectorCs gnature Commissions OR Iles A MdaWILA c0 2 National Board, Province and Endorsements Date rL4CUAA t , Gus (U)1

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT. FORREPAIR! . ...... ...... ..... REPLACEMENT

.... . ACTIVITY

- ITEM 1-22-110

1. Owner Nuclear Management Company, LLC Date 1/21/2005 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 - -0408838 Address - -Repair - Organization P.O. No., Job No., etc

3. Work Performed by Owner

- "Type Code Symbol Stamp N/A Name Same -Authorization N/A Address .--. Expiration Date N/A

4. Identification of System RC 'Code Class 1

5. (a)Applicable Construction Code B16.34 Edition Addenda Code Case (b) Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xi Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # - -. . Removed, or Code

. . Installed Stamp 1 Pressureizer PORV control Copes Vulcan CV-31231 Corrected El valve lI I 2 l C c R a be .

7. Description of Work Replaced plug and body to bonnet fasteners.

8. Tests conducted: Hydrostatic 2 Pneumatic D Nominal Operating Pressure Exempt ., ,

Other Pressure psi Test Temp.

Other: Exercise test. . I. - < 1 -- . .. . - .

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

- ~ ~~~ .,; ;I.. :

no;- hi hi

I I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-110

9. Remarks n/a CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp A//

Certificate of Authori p. Al 4 Expiration Date Signed . , ASME Program Engineer Date _______

Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnpcntf and employed byHsR Insp and Ins (o of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period /9wa6lay to Age4Mdos , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

t7%'X diD I OI Commissions Ig lA a"T AIl J/92g Inst*ctor's Signature' National Board, Province and Endorsements Date f A IT I I"

U§

PRAIRIE ISLAND NUCLEAR GENERATING PLANT -: --:l FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 1-22-111

1. Owner Nuclear Management Company. LLC Date 112112005 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1. of 2 -

1717 Wakonade Dr. E. Welch Minnesota 55089 0408894. ECN 03RC02-ECN-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same N Authorization NA Address Expiration Date N/A

4. Identification of System RC Code Class 1

5. (a) Applicable Construction Code ASME Vill 1968 Edition Addenda W68 Code Cases (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components

7. Description of Work Tack welded shims In place.

8. Tests conducted: Hydrostatic F Pneumaticl Nominal Operating Pressure E Exempt ;

Other [ - Pressure psi Test Temp. °F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3)each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY' ITEM 1-22-111

9. Remarks n/a CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp 1 Certificate of Authorization - 2,/4 Expiration Date Signed 1, ASME Program Engineer Date _ _ _ _ __ _ _

Owner or Owner's Designee. Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period /9A/o/of to

________ , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Oa Commissions I 9 s

61 Af.,t iJ ,1/?2'f

' Ispector's S ature National Board, Province and Endorsements Date <"go , )C. s

{ i/ J U~

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIRI REPLACEMENT ACTIVITY I.:.

'. - I IITEM 1 11 2

1. Owner Nuclear Management Company, LLC Date 1/10/2005 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0309936, EEC-1096 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Name Name Type Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date N/A

4. Identification of System MS Code Class 2

5. (a) Applicable Construction Code B31.1 1967 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Sectiorn Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed,-or Code Installed Stamp MS Safety Valve Dresser BR-06306 RS-21-1 Corrected II MS Safety Valve Dresser BM-09538 RS-21-7 Corrected

7. Description of Work Replaced studs and installed Superbolt nuts.

8. Tests conducted: Hydrostatic L Pneumatic E] Nominal Operating Pressure U Exempt i Other L Pressure psi Test Temp. .O Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 12 in. x 11 in., (2) information in Items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR! REPLACEMENT ACTIVITY ITEM 1-22-112

9. Remarks nia CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp Certificate of Auh . A11.4 Expiration Date Signed Program Engineer ASME Date ____ ___

Owner or Owner's Designee. Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding avalid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of MinnpstS and employed byHsR Insp and Ins Co of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 1o0/Alos . to

/odA4 o4 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owners Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

car Ispector's Sature Commissions $1faogs AdI MJ:2(gy National Board, Province and Endorsements Date a , /&uis

\1J

v t e Letter Sequence Request
TAC:MC6261, (Open)
Initiation Request Acceptance... Administration Questions Answers 22 August 2005 Results Approval... Other: ML052710295
MONTHYEAR2005-02-22 [Table View]

L-PI-05-013, Inservice Inspection Summary Report, Interval 3, Period 3, Refueling Outage Dates 09-10-04 Fuel Cycle 22: 12-7-2002 to 11-23-04

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L-PI-05-013, Inservice Inspection Summary Report, Interval 3, Period 3, Refueling Outage Dates 09-10-04 Fuel Cycle 22: 12-7-2002 to 11-23-04

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SUMMARY

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1.0 INTRODUCTION

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